TITLE 25.HEALTH SERVICES

Part 1. TEXAS DEPARTMENT OF HEALTH

Chapter 289. RADIATION CONTROL

The Texas Department of Health (department) proposes the repeal of §289.119 and new §289.229, concerning radiation safety requirements for accelerators, therapeutic radiation machines, and simulators.

Government Code §2001.039 requires that each state agency review and consider for readoption each rule adopted by that agency pursuant to the Government Code, Chapter 2001 (Administrative Procedure Act). Section 289.119 has been reviewed and the department has determined that the reasons for adopting the section continue to exist; however revisions to the rule are necessary.

The section proposed for repeal adopts by reference Part 35, titled "Radiation Safety Requirements for Particle Accelerators" of the Texas Regulations for Control of Radiation . The proposed new section incorporates language from Part 35 that has been rewritten into Texas Register format and includes addition and revision of subsections of the section. The repeal and new section are part of the renumbering phase in the process of rewriting the department's radiation rules in the Texas Register format. The new section reflects the renumbering.

Definitions that apply to therapeutic radiation machines and radiation therapy simulation systems (simulators) are added. Language is added to the section to incorporate radiation safety requirements for therapeutic radiation machines and simulators that were previously included in other sections of this chapter. References to other sections of this chapter are clarified to reflect the Texas Register format. Grammatical changes are made to the section for clarification. This section is also part of the department's continuing effort to update, clarify, and simplify its rules regarding the control of radiation based upon technological changes, public concerns, legislative directives, or other factors.

The department published a Notice of Intention to Review for §289.119 as required by Government Code §2001.039 in the Texas Register (25 TexReg 219) on January 7, 2000. No comments were received by the department on this section.

Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, has determined that for each year of the first five years the sections will be in effect, there will be no fiscal implications for state or local government as a result of enforcing or administering the sections as proposed.

Mrs. McBurney has also determined that for each year of the first five years the proposed sections will be in effect, the public benefit anticipated as a result of enforcing the sections will be to ensure that registrants comply with radiation safety requirements for accelerators, therapeutic radiation machines, and therapy simulations systems (simulators) and that equipment is properly used and maintained, ensuring the safety of workers and the public is protected from unnecessary exposure to radiation. There will be no effect on micro businesses or small businesses. There are no anticipated economic costs to persons who are required to comply with the sections as proposed. There is no anticipated impact on local employment. The new rule primarily reformats, clarifies, and consolidates existing requirements. It imposes no additional requirements such as record keeping, procedures, or processes. Therefore, there are no economic effects associated with the section as proposed.

Comments on the proposal may be submitted to Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, Texas Department of Health, 1100 West 49th Street, Austin, Texas 78756-3189, (512) 834-6688 or electronic mail at Ruth.McBurney@tdh.state.tx.us. Public comments will be accepted for 30 days following publication of this proposal in the Texas Register . In addition, a public meeting to accept oral comments will be held at 1:30 p.m., Tuesday, June 20, 2000, in Conference Room N218, Texas Department of Health, Bureau of Radiation Control, located at the Exchange Building, 8407 Wall Street, Austin, Texas.

Subchapter C. TEXAS REGULATIONS FOR CONTROL OF RADIATION

25 TAC §289.119

(Editor's note: The text of the following section proposed for repeal will not be published. The section may be examined in the offices of the Texas Department of Health or in the Texas Register office, Room 245, James Earl Rudder Building, 1019 Brazos Street, Austin.)

The repeal is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with the authority to adopt rules for the performance of each duty imposed by law on the board, the department, and the commissioner of health.

The repeal affects Health and Safety Code, Chapter 401; the Health and Safety Code, Chapter 12; and Government Code §2001.039.

§289.119.Radiation Safety Requirements for Particle Accelerators.

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003515

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


Subchapter E. REGISTRATION REGULATIONS

25 TAC §289.229

The new section is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with the authority to adopt rules for the performance of each duty imposed by law on the board, the department, and the commissioner of health.

The new section affects Health and Safety Code, Chapter 401; the Health and Safety Code, Chapter 12; and Government Code §2001.039.

§289.229.Radiation Safety Requirements for Accelerators, Therapeutic Radiation Machines, and Simulators.

(a)

Purpose. This section establishes radiation safety requirements for the use of accelerators, therapeutic radiation machines, and radiation therapy simulation systems (simulators). No person shall possess, use, transfer, or acquire an accelerator, a therapeutic radiation machine, or a radiation therapy simulation system (simulator) except as authorized in a certificate of registration issued in accordance with §289.226 of this title (relating to Registration of Radiation Machine Use and Services) or as otherwise provided for in this chapter.

(b)

Scope.

(1)

This section applies to persons who receive, possess, use or transfer accelerators used in industrial operations and research and development, and therapeutic radiation machines and radiation therapy simulation systems (simulators) used in the healing arts and veterinary medicine. Use of therapeutic radiation machines in the healing arts or veterinary medicine under this section shall be made by or under the supervision of a practitioner of the healing arts or a veterinarian. The registrant shall be responsible for the administrative control and for directing the use of the accelerators, other therapeutic radiation machines, or simulators.

(2)

The requirements of this section are in addition to and not in substitution for other applicable requirements of §289.203 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections), §289.204 of this title (relating to Fees for Certificates of Registration, Radioactive Material Licenses, Emergency Planning and Implementation, and Other Regulatory Services), §289.205 of this title (relating to Hearing and Enforcement Procedures), §289.226 of this title, and §289.231 of this title (relating to General Provisions and Standards for Protection Against Machine-Produced Radiation).

(3)

Registrants engaged in industrial radiographic operations are subject to the requirements of §289.255 of this title (relating to Radiation Safety Requirements and Licensing and Registration Procedures for Industrial Radiography).

(c)

Prohibitions.

(1)

The agency may prohibit use of accelerators, therapeutic radiation machines, and simulators that pose significant threat or endanger public health and safety, in accordance with §289.205 of this title and §289.231 of this title.

(2)

Individuals shall not be exposed to the useful beam except for healing arts purposes and unless such exposure has been authorized by a licensed practitioner of the healing arts. This provision specifically prohibits deliberate exposure of an individual for training, demonstration, or other non-healing arts purposes.

(3)

No research and/or development using radiation machines on humans shall be conducted unless approved by an Institutional Review Board (IRB) as required by Title 45, Code of Federal Regulations (CFR) Part 46 and Title 21, CFR Part 56. The IRB must include at least one practitioner of the healing arts to direct any use of radiation in accordance with §289.231(b) of this title.

(d)

Exemptions.

(1)

Veterinary facilities are exempt from the aural communication requirements for radiation therapy systems and radiation therapy simulators in subsection (h)(2)(B)(i), (h)(3)(B)(v), or (h)(4)(A)(iv) of this section.

(2)

Individuals who are sole practitioners and sole operators and the only occupationally exposed individual are exempt from the following requirements:

(A)

§289.203(b) of this title; and

(B)

subsection (h)(1)(D) of this section.

(e)

Definitions. The following words and terms when used in this section shall have the following meaning unless the context clearly indicates otherwise.

(1)

Aluminum equivalent - The thickness of type 1100 aluminum alloy affording the same attenuation, under specified conditions, as the material in question. The nominal chemical composition of type 1100 aluminum alloy is 99% minimum aluminum, 0.12% copper.

(2)

Attenuate - To reduce the exposure rate upon passage of radiation through matter.

(3)

Automatic exposure control (AEC) - A device that automatically controls one or more technique factors in order to obtain a required quantity of radiation at preselected locations (See definition for phototimer).

(4)

Automatic exposure rate control (AERC) - A device that automatically controls one or more technique factors in order to obtain a required quantity of radiation per unit time at preselected locations.

(5)

Barrier (See definition for protective barrier).

(6)

Beam axis - A line from the source through the centers of the x-ray field.

(7)

Beam-flattening filter - A filter used to provide dose uniformity over the area of a useful x-ray beam at a specified depth.

(8)

Beam-limiting device - A device that provides a means to restrict the dimensions of the x-ray field.

(9)

Beam quality - A term that describes the penetrating power of the x-ray beam. This is identified numerically by half-value layer and is influenced by kilovolt peak (kVp) and filtration.

(10)

Beam quality (accelerator) - A term that describes the type and penetrating power of the ionizing radiation produced for certain machine settings.

(11)

Beam monitoring system - A dosimetry system designed to detect and measure the radiation present in the useful beam.

(12)

Beam scattering foil - A foil used to scatter a beam of electrons.

(13)

Calibration of machines - The measurement and specification of absorbed dose to a medium, or exposure in air, at a defined point in a radiation beam.

(14)

Central axis of the beam - An imaginary line passing through the center of the useful beam and the center of the plane figure formed by the edge of the first beam-limiting device.

(15)

Coefficient of variation or C - The ratio of the standard deviation to the mean value of a population of observations. It is estimated using the following equation:

Figure: 25 TAC §289.229(e)(15)

(16)

Collimator - A device or mechanism by which the x-ray beam is restricted in size.

(17)

Computed tomography (CT) - The production of a tomogram by the acquisition and computer processing of x-ray transmission data.

(18)

Continuous pressure type switch - A switch so constructed that a circuit closing contact can be maintained only by continuous pressure on the switch by the operator.

(19)

Control panel - The part of the radiation machine where the switches, knobs, push buttons, and other hardware necessary for manually setting the technique factors are located.

(20)

CT conditions of operation - All selectable parameters governing the operation of a CT x-ray system including, but not limited to, nominal tomographic section thickness, filtration, and the technique factors as defined in this subsection.

(21)

CT gantry - The tube housing assemblies, beam-limiting devices, detectors, and the supporting structures and frames that hold these components.

(22)

Diagnostic x-ray system - An x-ray system designed for irradiation of any part of the human body or any animal for the purpose of diagnosis or visualization.

(23)

Diaphragm - A device or mechanism by which the x-ray beam is restricted in size.

(24)

Dose monitoring system - A system of devices for the detection, measurement, and display of quantities of radiation.

(25)

Dose monitor unit - A unit response from the dose monitoring system from which the absorbed dose can be calculated.

(26)

Existing equipment - Therapy systems subject to subsections (h)(2) and (h)(3) of this section that were manufactured on or before March 1, 1989.

(27)

Field size - The dimensions along the major axes of an area in a plane perpendicular to the central axis of the beam at the normal treatment or examination source to image distance and defined by the intersection of the major axes and the 50% isodose line.

(28)

Filter - Material placed in the useful beam to preferentially absorb selected radiations.

(29)

Focal spot - The area projected on the anode of the x-ray tube that is bombarded by the electrons accelerated from the cathode and from which the useful beam originates.

(30)

Gantry - That part of the system supporting and allowing possible movement of the radiation source.

(31)

Half-value layer (HVL) - The thickness of a specified material that attenuates the beam of radiation to an extent such that the exposure rate is reduced to one-half of its original value.

(32)

Healing arts - Any treatment, operation, diagnosis, prescription, or practice for the ascertainment, cure, relief, palliation, adjustment, or correction of any human disease, ailment, deformity, injury, or unhealthy or abnormal physical or mental condition.

(33)

Image intensifier - A device, installed in its housing, that instantaneously converts an x-ray pattern into a corresponding light image of higher energy density.

(34)

Image receptor - Any device, such as a fluorescent screen or radiographic film, that transforms incident x-ray photons either into a visible image or into another form that can be made into a visible image by further transformations.

(35)

Inherent filtration - The filtration of the useful beam provided by the permanently installed components of the x-ray tube housing assembly.

(36)

Institutional Review Board (IRB) - Any board, committee, or other group formally designated by an institution to review, approve the initiation of, and conduct periodic review of biomedical research involving human subjects.

(37)

Interlock - A device preventing the start or continued operation of equipment unless certain predetermined conditions prevail.

(38)

Interruption of irradiation - The stopping of irradiation with the possibility of continuing irradiation without resetting of operating conditions at the control panel.

(39)

Isocenter - A fixed point in space located at the center of the smallest sphere through which the central axis of the beam passes in all conditions.

(40)

Kilovolt - kV (See definition for peak tube potential).

(41)

Kilovolt peak - kVp (See definition for peak tube potential).

(42)

Lead equivalent - The thickness of lead affording the same attenuation, under specified conditions, as the material in question.

(43)

Leakage radiation - Radiation emanating from the source(s) assembly except for the useful beam and radiation produced when the exposure switch or timer is not activated.

(44)

Leakage technique factors - The technique factors associated with the source assembly that is used in measuring leakage radiation.

(45)

Licensed medical physicist - An individual holding a current Texas license under the Medical Physics Practice Act, Texas Civil Statutes, Article 4512n.

(46)

Medical research - The investigation of various health risks and diseases using radiation machines as part of the evaluation process.

(47)

Moving beam radiation therapy - Radiation therapy with any planned displacement of radiation field or with any planned change of absorbed dose distribution.

(48)

New equipment - Systems subject to subsections (h)(2) and (h)(3) of this section that were manufactured after March 1, 1989.

(49)

Nominal treatment distance - The following treatment distances shall apply.

(A)

For electron irradiation, the distance from the scattering foil or exit window of the electron beam to the surface along the central axis of the useful beam, as specified by the manufacturer.

(B)

For x-ray irradiation, the distance from the target along the central axis of the useful beam to the isocenter. For non-isocentric equipment, this distance shall be that specified by the manufacturer.

(50)

Peak tube potential - The maximum value of the potential difference (in kilovolts) across the x-ray tube during an exposure.

(51)

Phototimer - A method for controlling radiation exposures to image receptors by the amount of radiation that reaches a radiation monitoring device. The radiation monitoring device is part of an electronic circuit that controls the duration of time the tube is activated (See definition for automatic exposure control).

(52)

Port film - An x-ray exposure made with a therapy system to visualize a patient's treatment area using radiographic film.

(53)

Practitioner of the healing arts (practitioner) - A person licensed to practice healing arts by either the Texas State Board of Medical Examiners as a physician, the Texas State Board of Dental Examiners, the Texas Board of Chiropractic Examiners, or the Texas State Board of Podiatry Examiners.

(54)

Primary dose monitoring system - A system that will monitor the useful beam during irradiation and that will terminate irradiation when a preselected number of dose monitor units have been acquired.

(55)

Primary protective barrier - (See definition for protective barrier).

(56)

Protective apron - An apron made of radiation absorbing materials used to reduce radiation exposure.

(57)

Protective barrier - A barrier of radiation absorbing materials used to reduce radiation exposure. The types of protective barriers are as follows:

(A)

primary protective barrier - A barrier sufficient to attenuate the useful beam to the required degree.

(B)

secondary protective barrier - A barrier sufficient to attenuate the stray radiation to the required degree.

(58)

Protective glove - A glove made of radiation absorbing materials used to reduce radiation exposure.

(59)

Radiation oncologist - A practitioner with a specialty in radiation therapy.

(60)

Radiation therapy simulation system (simulator) - An x-ray system intended for localizing and confirming the volume to be irradiated during radiation treatment and confirming the position and size of the therapeutic irradiation field.

(61)

Scan - The complete process of collecting x-ray transmission data for the production of a tomogram. Data can be collected simultaneously during a single scan for the production of one or more tomograms.

(62)

Scan increment - The amount of relative displacement of the patient with respect to the CT x-ray system between successive scans measured along the direction of such displacement.

(63)

Scan sequence - A preselected set of two or more scans performed consecutively under preselected CT conditions of operation.

(64)

Scan time - The period of time between the beginning and end of x-ray transmission data accumulation for a single scan.

(65)

Scattered radiation - Radiation that has been deviated in direction during passage through matter.

(66)

Secondary dose monitoring system - A system that will terminate irradiation in the event of failure of the primary system.

(67)

Secondary protective barrier (See definition for protective barrier).

(68)

Shutter - A device attached to the tube housing assembly that can totally intercept the useful beam and that has a lead equivalency not less than that of the tube housing assembly.

(69)

Source-to-image receptor distance (SID) - The distance from the source to the center of the input surface of the image receptor.

(70)

Source-to-skin distance (SSD) - The distance from the source to the skin of the patient.

(71)

Spot check - Those tests and analyses performed at specified intervals for the purpose of verifying the consistent operation of radiation equipment.

(72)

Stationary beam therapy - Radiation therapy without relative displacement of the useful beam.

(73)

Supervision - The delegating of the task of applying radiation in accordance with this section to persons not licensed in the healing arts or veterinary medicine, who provide services under the practitioner's control. The licensed practitioner or veterinarian assumes full responsibility for these tasks and must assure that the tasks will be administered correctly.

(74)

Termination of irradiation - The stopping of irradiation in a fashion that will not permit continuance of irradiation without the resetting of operating conditions at the control panel.

(75)

Therapy system - An x-ray system that utilizes prescribed doses of ionizing radiation for treatment.

(76)

Traceable to a national standard - This indicates that a quantity or a measurement has been compared to a national standard, for example, National Institute of Standards and Technology, directly or indirectly through one or more intermediate steps and that all comparisons have been documented.

(77)

Useful beam - Radiation that passes through the window, aperture, cone, or other collimating device of the source housing. Also referred to as the primary beam.

(78)

Veterinarian - An individual licensed by the Texas Board of Veterinary Medical Examiners.

(79)

Wedge filter - An added filter effecting continuous progressive attenuation on all or part of the useful beam.

(f)

Accelerators used for research and development and industrial operations.

(1)

Registration. Each person possessing an accelerator shall apply for and receive a certificate of registration in accordance with §289.226(j) of this title before activation of the accelerator, including acceptance testing.

(2)

Facility requirements.

(A)

Each accelerator facility shall be provided with primary and/or secondary barriers as are necessary to assure compliance with §289.231(m) and (o) of this title.

(B)

A radiation survey shall be conducted when the accelerator is registered and is capable of producing radiation to determine compliance with §289.231(m) and (o) of this title.

(C)

Initial surveys shall be performed as follows.

(i)

All new and existing facilities not previously surveyed shall have a survey made by a physicist, who shall provide a written report of the survey to the registrant.

(ii)

The survey report shall include, but not be limited to, the following:

(I)

a diagram of the facility that details building structures and the position of the accelerator, control panel, and associated equipment;

(II)

a description of the accelerator including the manufacturer, model and serial number, beam type, and beam energy;

(III)

a description of the instrumentation used to determine radiation measurements, including the date and source of the most recent calibration for each instrument used;

(IV)

conditions under which radiation measurements were taken; and

(V)

survey data including:

(-a-)

projected annual total effective dose equivalent (TEDE) in areas adjacent to the accelerator; and

(-b-)

a description of workload, use, and occupancy factors employed in determining the projected annual TEDE.

(iii)

The registrant shall maintain a copy of the survey report for inspection by the agency in accordance with subsection (k) of this section.

(iv)

The survey report shall include documentation of all instances where the facility is in violation of applicable requirements of this chapter. Any deficiencies detected during the survey shall be corrected prior to using the accelerator.

(3)

Safety requirements.

(A)

Interlock systems shall comply with the following requirements.

(i)

Instrumentation, readouts, and controls in the accelerator console shall be clearly identified.

(ii)

Each entrance into a target room or other high radiation area shall be provided with a safety interlock that shuts down the machine under conditions of barrier penetration.

(iii)

When the production of radiation has been interrupted, it shall only be possible to resume operation of the accelerator by manually resetting the console.

(iv)

Each safety interlock shall be on an electrical circuit that allows the interlock to operate independently of all other safety interlocks.

(v)

All safety interlocks shall be designed so that any defect or component failure in the interlock system prevents operation of the accelerator.

(vi)

A scram button or other emergency power cut-off switches shall be labeled. The scram button or cut-off switches shall include a manual reset so that the accelerator cannot be restarted from the accelerator console without resetting the cut-off switch.

(vii)

The safety interlock system shall have a visible or audible alarm that will indicate when any interlock has been activated.

(viii)

All interlocks and visible or audible alarms shall be tested for proper operation at intervals not to exceed three months.

(ix)

If an interlock or alarm is operating improperly, it shall be immediately labeled as defective and repaired within seven calendar days.

(x)

Records of tests and repairs required by this paragraph shall be made and maintained in accordance with subsection (k) of this section for inspection by the agency.

(B)

Each registrant shall develop and implement written operating and safety procedures. The procedures shall include, but may not be limited to, the following:

(i)

methods used to secure the accelerator from unauthorized use;

(ii)

methods of testing and training operators in accordance with subsection (f)(4) of this section;

(iii)

procedures for notifying the proper personnel in the event of an accident;

(iv)

posting requirements;

(v)

procedures for testing interlocks, entrance controls, and alarm systems;

(vi)

personnel monitoring;

(vii)

maintenance of records; and

(viii)

procedures for necessary area surveys and time intervals.

(C)

There shall be available at each accelerator facility, appropriate portable monitoring equipment that is operable and has been calibrated for the appropriate radiations being produced at the facility. The equipment shall be calibrated in accordance with §289.231(s)(2) of this title.

(D)

A radiation protection survey shall be performed and the results recorded when changes have been made in shielding, operation, equipment, or occupancy of adjacent areas.

(E)

For portable or mobile accelerators, such as neutron generators that are used at temporary job sites where permanent shielding is not available, radiation protection shall be provided by temporary shielding or by providing an adequate exclusion area around the accelerator while it is in use.

(F)

Records of calibration and survey results made in accordance with subparagraphs (C) and (D) of this paragraph shall be maintained in accordance with subsection (k) of this section.

(4)

Training requirements for operators.

(A)

No person shall be permitted to operate an accelerator unless such person has received instruction in and demonstrated competence with the following:

(i)

operating and safety procedures in accordance with paragraph (3)(B);

(ii)

radiation warning and safety devices incorporated into the equipment and in the room;

(iii)

identification of radiation hazards associated with the use of the equipment; and

(iv)

procedures for reporting an actual or suspected exposure.

(B)

Records of the training specified in subparagraph (A) of this paragraph shall be made and maintained for agency inspection in accordance with subsection (k) of this section.

(5)

Records/documents.

(A)

The registrant shall maintain copies of the following records/documents at authorized use locations in accordance with subsection (k) of this section:

(i)

current applicable sections of this chapter as listed on the certificate of registration;

(ii)

current certificate of registration;

(iii)

surveys of radiation levels in unrestricted areas in accordance with paragraph (2)(B) of this subsection;

(iv)

personnel monitoring records of occupationally exposed individuals in accordance with §289.231(f) and (r) of this title, as applicable;

(v)

current operating and safety procedures in accordance with paragraph (3)(B) of this subsection or §289.255 of this title, as applicable;

(vi)

operator training in accordance with paragraph (4)(B) of this subsection;

(vii)

notice of violation from last inspection, if applicable, and documentation of corrections of violations;

(viii)

receipt, transfer, and disposal of accelerators including the date, the manufacturer name, any model and serial number from the control panel or console of the radiation machine, and identification of the person making the record;

(ix)

latest calibrations for each survey instrument in use at the authorized use location in accordance with paragraph (3)(F) of this subsection;

(x)

interlock and alarm tests in accordance with paragraph (3)(A)(x) of this subsection; and

(xi)

latest radiation survey records in accordance with paragraphs (2)(C)(iii) or (3)(F) of this subsection.

(B)

Records specified in subparagraph (A) of this paragraph may be maintained in electronic format.

(g)

Requirements for accelerator(s) used in industrial radiography. In addition to the requirements in subsections (f)(1), (2), (3)(C)-(F), and (5) of this section, accelerators used for industrial radiography shall meet the applicable requirements of §289.255 of this title.

(h)

Therapeutic radiation machines and simulators used in the healing arts and veterinary medicine.

(1)

General requirements.

(A)

Each person possessing a therapeutic radiation machine capable of operating at or above 1 million electron volts (MeV) shall apply for and receive a certificate of registration from the agency before activation of the radiation machine, including acceptance testing.

(B)

Each person possessing a simulator and/or a therapeutic radiation machine capable of operating below 1 MeV shall apply for a certificate of registration within 30 days after energizing the equipment.

(C)

Individuals who operate radiation machines for human use shall meet the appropriate credentialing requirements issued in accordance with the Medical Radiologic Technologist Act, Texas Civil Statutes, Article 4512m. Copies of the credentialing document shall be maintained at the locations(s) where the individual is working.

(D)

Each registrant shall develop and implement written operating and safety procedures. These procedures shall be made available to each individual operating radiation machines and simulators, including any restrictions of the operating technique required for the safe operation of the particular therapeutic radiation system. These procedures shall include, but are not limited to the following:

(i)

use of a technique chart in accordance with paragraph (4)(A)(i) of this subsection;

(ii)

radiation dose requirements in accordance with §289.231(m) and (o) of this title;

(iii)

personnel monitoring requirements in accordance with §289.231(n) of this title;

(iv)

use of protective devices in accordance with paragraph (4)(A)(iii) of this subsection;

(v)

credentialing requirements for individuals operating radiation machines in accordance with subparagraph (C) of this paragraph;

(vi)

exposure of individuals other than the patient in accordance with paragraphs (2)(D)(iv)(IV), and (3)(C)(v)(I) of this subsection;

(vii)

film processing program in accordance with paragraph (4)(A)(vi) and (vii) of this subsection;

(viii)

procedures for restriction and alignment of beam in accordance with paragraph (4)(B)(iii) of this subsection;

(ix)

posting notices to workers in accordance with §289.203(b) of this title;

(x)

instructions to workers in accordance with §289.203(c) of this title;

(xi)

notifications and reports to individuals in accordance with §289.203(d) of this title; and

(xii)

posting of a radiation area in accordance with §289.231(x) and (y) of this title.

(E)

Registrants with equipment that has been issued variances by the United States Food and Drug Administration (FDA) to Title 21, CFR Part 1020 shall maintain copies of those variances at authorized use locations in accordance with subsection (k) of this section.

(2)

Therapeutic radiation machines capable of operating at energies below 1 MeV.

(A)

Equipment requirements.

(i)

When the tube is operated at its leakage technique factors, the leakage radiation shall not exceed the values specified at the distance stated for the classification of that radiation machine system shown in the following Table I. The leakage technique factors are the maximum-rated peak tube potential and the maximum-rated continuous tube current for the maximum-rated peak tube potential.

Figure: 25 TAC §289.229(h)(2)(A)(i)

(ii)

Permanent fixed diaphragms or cones used for limiting the useful beam shall provide the same or a higher degree of protection as required for the tube housing assembly.

(iii)

Removable and adjustable beam-limiting devices shall meet the following requirements.

(I)

Removable beam-limiting devices shall, for the portion of the useful beam to be blocked by these devices, transmit not more than 1.0% of the useful beam at the maximum kVp and maximum treatment filter. This requirement does not apply to auxiliary blocks or materials placed in the x-ray field to shape the useful beam to the individual patient.

(II)

Adjustable beam-limiting devices installed before March 1, 1989, shall, for the portion of the x-ray beam to be blocked by these devices, transmit not more than 5.0% of the useful beam at the maximum kVp and maximum treatment filter.

(III)

Adjustable beam-limiting devices installed after March 1, 1989, shall meet the requirements of subclause (I) of this clause.

(iv)

The filter system shall be so designed that:

(I)

the filters cannot be accidentally displaced at any possible tube orientation;

(II)

for equipment installed after March 1, 1989, an interlock system prevents irradiation if the proper filter is not in place;

(III)

the radiation at 5 centimeters (cm) from the filter insertion slot opening does not exceed 30 roentgens per hour (R/hr) under any operating conditions; and

(IV)

each filter is marked as to its material of construction and its thickness. For wedge filters, the wedge angle shall appear on the wedge or wedge tray.

(v)

The tube housing assembly shall be capable of being immobilized for stationary treatments.

(vi)

The tube housing assembly shall be so marked that it is possible to determine the location of the focal spot to within 5 millimeters (mm), and such marking shall be readily accessible for use during calibration procedures.

(vii)

Contact therapy tube housing assemblies shall have a removable shield of at least 0.5 mm lead equivalency at 100 kVp that can be positioned over the entire useful beam exit port during periods when the beam is not in use.

(viii)

The timer shall:

(I)

have a display provided at the treatment control panel and a pre-set time selector;

(II)

activate with the production of radiation and retain its reading after irradiation is interrupted. After irradiation is terminated and before irradiation can be reinitiated, it shall be necessary to reset the elapsed time indicator to zero;

(III)

terminate irradiation when a pre-selected time has elapsed, if any dose monitoring system present has not previously terminated irradiation;

(IV)

permit selection of exposure times as short as one second;

(V)

not permit an exposure if set at zero;

(VI)

not activate until the shutter is opened when irradiation is controlled by a shutter mechanism unless calibration includes a timer factor to compensate for mechanical lag; and

(VII)

be accurate to within 1.0% of the selected value or one second, whichever is greater.

(ix)

The control panel, in addition to the displays required in clause (viii)(I) of this subparagraph, shall have the following:

(I)

an indication of whether electrical power is available at the control panel and if activation of the x-ray tube is possible;

(II)

an indication of whether x rays are being produced;

(III)

means for indicating x-ray tube potential and current;

(IV)

means for terminating an exposure at any time;

(V)

a locking device that will prevent unauthorized use of the therapeutic radiation system (a computerized pass-word system would also constitute a locking device);

(VI)

for therapeutic radiation systems manufactured after March 1, 1989, a positive display of specific filters in the beam; and

(VII)

emergency buttons/switches that shall be clearly labeled as to their functions.

(x)

There shall be means of determining initially the SSD to within 1 cm and of reproducing this measurement to within 2 mm thereafter.

(xi)

Unless it is possible to bring the radiation output to the prescribed exposure parameters within five seconds, the beam shall be attenuated by a shutter having a lead equivalency not less than that of the tube housing assembly. After the unit is at operating parameters, the shutter shall be controlled electrically by the operator from the control panel. An indication of shutter position shall appear at the control panel.

(xii)

Each therapeutic radiation system equipped with a beryllium or other low-filtration window shall be clearly labeled as such upon the tube housing assembly and at the control panel.

(B)

Facility requirements for therapeutic radiation systems capable of operating above 50 kVp.

(i)

Provision shall be made for two-way aural communication between the patient and the operator at the control panel.

(ii)

Windows, mirrors, closed-circuit television, or an equivalent system shall be provided to permit continuous observation of the patient during irradiation and shall be so located that the operator can observe the patient from the control panel.

(I)

When the primary viewing system is by electronic means, an alternate viewing system, which may be electronic, shall be available for use in the event of failure of the primary viewing system.

(II)

Should both systems described in subclause (I) of this clause fail or be inoperative, treatment shall not be performed with the unit until one of the systems is restored.

(C)

Additional facility requirements for therapeutic radiation systems capable of operation above 150 kVp.

(i)

Each installation shall be provided with primary and/or secondary barriers as are necessary to assure compliance with §289.231(m) and (o) of this title. All protective barriers shall be fixed except for entrance doors or beam interceptors.

(ii)

The control panel shall be located outside the treatment room or in an enclosed booth inside the room.

(iii)

Interlocks shall be provided such that all entrance doors must be closed, including doors to any interior booths, before treatment can be initiated or continued. If the radiation beam is interrupted by any door opening, it shall not be possible to restore the machine to operation without closing the door and reinitiating irradiation by manual action at the control panel. When any door is opened while the x-ray tube is activated, the exposure at a distance of 1 meter (m) from the source shall be reduced to less than 100 mR/hr.

(D)

Surveys, calibrations, spot checks, and additional operating procedures.

(i)

Surveys shall be performed as follows.

(I)

All new and existing facilities not previously surveyed shall have a survey made by a licensed medical physicist with a specialty in therapeutic radiological physics or medical health physics, who shall provide a written report of the survey to the registrant. Additional surveys shall be done after any change in the facility, facility design, or equipment that might cause a significant increase in radiation hazard.

(II)

The registrant shall maintain a copy of the initial survey report and all subsequent survey reports required by subclause (I) of this clause in accordance with subsection (k) of this section for inspection by the agency.

(III)

The survey report shall indicate all instances where the installation is in violation of applicable requirements of this chapter.

(ii)

Calibrations shall be performed as follows.

(I)

The calibration of a therapeutic radiation system shall be performed at intervals not to exceed one year and after any change or replacement of components that could cause a change in the radiation output. The calibrations shall be such that the dose at a reference point in a water or plastic phantom can be calculated to within an uncertainty of 5.0%.

(II)

The calibration of the radiation output of the therapeutic radiation system shall be performed by a licensed medical physicist with a specialty in therapeutic radiological physics who is physically present at the facility during such calibration.

(III)

The calibration of the therapeutic radiation system shall include, but not be limited to, the following determinations:

(-a-)

verification that the therapy system is operating in compliance with the design specifications;

(-b-)

HVL for each kV setting and filter combination used;

(-c-)

the exposure rates as a function of field size, technique factors, filter, and treatment distance used; and

(-d-)

the degree of congruence between the radiation field and the field indicated by the localizing device, if such device is present, shall be within 5 mm for any field edge.

(IV)

Calibration of the radiation output of a therapeutic radiation system shall be performed with a calibrated dosimetry system. The dosimetry system shall be calibrated within the previous 24 months and shall be traceable to a national standard. During the calendar year in which the dosimetry system is not calibrated, an intercomparison to a system calibrated within the previous 12 months shall be performed.

(V)

Records of calibration measurements specified in clause (ii) of this subparagraph shall be made and maintained by the registrant in accordance with subsection (k) of this section for inspection by the agency.

(VI)

A copy of the latest calibrated absorbed dose rate measured on a particular therapeutic radiation system shall be available at a designated area within the therapy facility housing that therapeutic radiation system.

(iii)

Spot checks shall be performed on therapeutic radiation systems capable of operation at greater than 150 kVp. Such measurements shall meet the following requirements.

(I)

The spot check procedures shall be in writing and shall have been developed by a licensed medical physicist with a specialty in therapeutic radiological physics.

(II)

If a licensed medical physicist does not perform the spot check measurements, the results of the spot check measurements shall be reviewed by a licensed medical physicist with a specialty in therapeutic radiological physics within five treatment days and a record made of the review. If the output varies by more than 5.0% from the expected value, a licensed medical physicist shall be notified immediately.

(III)

The written spot check procedures shall specify the frequency that tests or measurements are to be performed and that the spot check shall be performed during the calibration specified in clause (ii) of this subparagraph. The acceptable tolerance for each parameter measured when compared to the value for that parameter determined in the calibration specified in clause (ii) of this subparagraph shall be stated.

(IV)

The written spot check procedures shall include special operating instructions that shall be carried out whenever a parameter in subclause (III) of this clause exceeds an acceptable tolerance.

(V)

Whenever a spot check indicates a significant change in the operating characteristics of a system, as specified in the procedures, the system shall be recalibrated, as required in clause (ii) of this subparagraph.

(VI)

Records of written spot checks and any necessary corrective actions shall be maintained by the registrant in accordance with subsection (k) of this section for inspection by the agency. A copy of the most recent spot check shall be available at a designated area within the therapy facility housing of that therapeutic radiation system.

(VII)

When a spot check involves a radiation measurement, such measurement shall be obtained using a system satisfying the requirements of clause (ii)(IV) of this subparagraph or that has been intercompared with a system meeting those requirements within the previous year.

(iv)

In addition to the items listed in paragraph (1)(D) of this subsection, operating and safety procedures shall also include procedures to ensure the following requirements are met.

(I)

Therapeutic radiation systems shall not be left unattended unless the system is secured against unauthorized use.

(II)

Restraining or mechanical supporting devices shall be used when a patient or port film must be immobilized in position for radiation therapy.

(III)

The tube housing assembly shall not be held by hand during operation unless the system is designed to require such holding and the peak tube potential of the system does not exceed 50 kVp. In such cases, the holder shall wear protective gloves and apron of not less than 0.5 mm lead equivalency at 100 kVp.

(IV)

For therapeutic radiation systems operating at or below 150 kVp, no individual other than the patient shall be in the treatment room unless such individual is protected by a barrier sufficient to meet the requirements of §289.231(o) of this title. No individual other than the patient shall be in the treatment room during exposures from therapeutic radiation systems operating above 150 kVp.

(V)

The therapeutic radiation system shall not be used in the administration of radiation therapy unless the requirements of clauses (ii) and (iii)(V) of this subparagraph have been met.

(3)

Therapeutic radiation machines capable of operating at energies of 1 MeV and above.

(A)

Equipment requirements.

(i)

For operating conditions producing maximum leakage radiation, the absorbed dose in rads due to leakage radiation, including x rays, electrons, and neutrons, at any point in a circular plane of 2 m radius centered on and perpendicular to the central axis of the beam at the isocenter or normal treatment distance and outside the maximum useful beam size shall not exceed 0.1% of the maximum absorbed dose in rads of the unattenuated useful beam measured at the point of intersection of the central axis of the beam and the plane surface. Measurements excluding those for neutrons shall be averaged over an area up to, but not exceeding, 100 square centimeters (cm 2 ) at the positions specified. Measurements of the portion of the leakage radiation dose contributed by neutrons shall be averaged over an area up to, but not exceeding, 200 cm 2 . For each system, the registrant shall determine or obtain from the manufacturer the leakage radiation existing at the positions specified for the specified operating conditions. Records on leakage radiation measurements shall be made and maintained in accordance with subsection (k) of this section for inspection by the agency.

(ii)

Each wedge filter that is removable from the system shall be clearly marked with an identification number. Documentation available at the control panel shall contain a description of the filter. The wedge angle shall appear on the wedge or wedge tray (if permanently mounted to the tray). If the wedge tray is damaged, the wedge transmission factor shall be redetermined. New equipment shall meet the following requirements.

(I)

Irradiation shall not be possible until a selection of a filter or a positive selection to use "no filter" has been made at the treatment control panel, either manually or automatically.

(II)

An interlock system shall be provided to prevent irradiation if the filter selected is not in the correct position.

(III)

A display shall be provided at the treatment control panel showing the beam quality in use.

(IV)

An interlock shall be provided to prevent irradiation if any filter selection operation carried out in the treatment room does not agree with the filter selection operation carried out at the treatment control panel.

(iii)

The registrant shall determine data sufficient to assure that the following beam quality requirements in tissue equivalent material are met.

(I)

The absorbed dose resulting from x rays in a useful electron beam at a point on the central axis of the beam 10 cm greater than the practical range of the electrons shall not exceed the values stated in the following Table II. Linear interpolation shall be used for values not stated.

Figure: 25 TAC §289.229(h)(3)(A)(iii)(I)

(II)

Compliance with subclause (I) of this clause shall be determined using:

(-a-)

a measurement within a tissue equivalent phantom with the incident surface of the phantom at the normal treatment distance and normal to the central axis of the beam;

(-b-)

a field size of 10 cm by 10 cm; and

(-c-)

a phantom whose cross-sectional dimensions exceed the measurement radiation field by at least 5 cm and whose depth is sufficient to perform the required measurement.

(III)

The absorbed dose at a surface located at the normal treatment distance, at the point of intersection of that surface with the central axis of the useful beam during x-ray irradiation, shall not exceed the limits stated in the following Table III. Linear interpolation shall be used for values not stated.

Figure: 25 TAC §289.229(h)(3)(A)(iii)(III)

(IV)

Compliance with subclause (III) of this clause shall be determined by measurements made as follows:

(-a-)

within a tissue equivalent phantom using an instrument that will allow extrapolation to the surface absorbed dose;

(-b-)

using a phantom whose size and placement meet the requirements of subclause (II) of this clause;

(-c-)

after removal of all beam modifying devices that can be removed without the use of tools, except for beam scattering or beam-flattening filters; and

(-d-)

using the largest field size available that does not exceed 15 cm by 15 cm.

(iv)

All therapeutic radiation systems shall be provided with radiation detectors in the radiation head. These shall include the following, as appropriate.

(I)

New equipment shall be provided with at least two independent radiation detectors. The detectors shall be incorporated into two independent dose monitoring systems.

(II)

Existing equipment shall be provided with at least one radiation detector. This detector shall be incorporated into a primary dose monitoring system.

(III)

The detector and the system into which that detector is incorporated shall meet the following requirements.

(-a-)

Each detector shall be removable only with tools and shall be interlocked to prevent incorrect positioning.

(-b-)

Each detector shall form part of a dose monitoring system from whose readings in dose monitor units the absorbed dose at a reference point in the treatment volume can be calculated.

(-c-)

Each dose monitoring system shall be capable of independently monitoring, interrupting, and terminating irradiation.

(-d-)

For new equipment, the design of the dose monitoring systems shall assure that the malfunctioning of one system shall not affect the correct functioning of the secondary system; and failure of any element common to both systems that could affect the correct function of both systems shall terminate irradiation.

(-e-)

Each dose monitoring system shall have a legible display at the treatment control panel. For new equipment, each display shall:

(-1-)

maintain a reading until intentionally reset to zero;

(-2-)

have only one scale and no scale multiplying factors;

(-3-)

utilize a design such that increasing dose is displayed by increasing numbers and shall be so designed that, in the event of an overdosage of radiation, the absorbed dose may be accurately determined; and

(-4-)

retain the dose monitoring information in at least one system for a 20-minute period of time in the event of a power failure.

(v)

In new equipment inherently capable of producing useful beams with unintentional asymmetry exceeding 5.0%, the asymmetry of the radiation beam in two orthogonal directions shall be monitored before the beam passes through the beam-limiting device. If the difference in dose rate between one region and another region symmetrically displaced from the central axis of the beam exceeds 5.0% of the central axis dose rate, indication of this condition shall be at the control panel; and if this difference exceeds 10% of the central axis dose rate, the irradiation shall be terminated.

(vi)

Selection and display of dose monitor units shall meet the following requirements.

(I)

Irradiation shall not be possible until a selection of a number of dose monitor units has been made at the treatment control panel.

(II)

The preselected number of dose monitor units shall be displayed at the treatment control panel until reset manually for the next irradiation.

(III)

After termination of irradiation, it shall be necessary to reset the dosimeter display to zero before subsequent treatment can be initiated.

(IV)

For new equipment, after termination of irradiation, it shall be necessary to manually reset the preselected dose monitor units before irradiation can be initiated.

(vii)

Termination of irradiation by the dose monitoring system or systems during stationary beam therapy shall meet the following requirements.

(I)

Each primary system shall terminate irradiation when the preselected number of dose monitor units has been detected by the system.

(II)

If original design of the equipment includes a secondary dose monitoring system, that system shall be capable of terminating irradiation when not more than 15% or 40 dose monitor units, whichever is smaller, above the preselected number of dose monitor units set at the control panel has been detected by the secondary dose monitoring system.

(III)

For new equipment, a secondary dose monitoring system shall be present. That system shall be capable of terminating irradiation when not more than 10% or 25 dose monitoring units, whichever is smaller, above the preselected number of dose monitor units set at the control panel has been detected by the secondary dose monitoring system.

(IV)

For new equipment, an indicator on the control panel shall show which dose monitoring system has terminated irradiation.

(viii)

A locking device shall be provided in the system to prevent unauthorized use of the x-ray system. A computerized password system would also constitute a locking device.

(ix)

It shall be possible to interrupt irradiation and equipment movements at any time from the operator's position at the treatment control panel. Following an interruption, it shall be possible to restart irradiation by operator action without any reselection of operating conditions. If any change is made of a preselected value during an interruption, irradiation and equipment movements shall be automatically terminated.

(x)

It shall be possible to terminate irradiation and equipment movements or go from an interruption condition to termination conditions at any time from the operator's position at the treatment control panel.

(xi)

Timers shall meet the following requirements.

(I)

A timer that has a display shall be provided at the treatment control panel. The timer shall have a preset time selector and an elapsed time indicator.

(II)

The timer shall be a cumulative timer that activates with the production of radiation and retains its reading after irradiation is interrupted or terminated. After irradiation is terminated and before irradiation can be reinitiated, it shall be necessary to reset the elapsed time indicator to zero.

(III)

For new equipment, after termination of irradiation and before irradiation can be reinitiated, it shall be necessary to manually reset the preset time selector.

(IV)

The timer shall terminate irradiation when a preselected time has elapsed if the dose monitoring systems have not previously terminated irradiation.

(xii)

Equipment capable of producing more than one radiation type shall meet the following additional requirements.

(I)

Irradiation shall not be possible until a selection of radiation type has been made at the treatment control panel.

(II)

An interlock system shall be provided to:

(-a-)

ensure that the equipment can emit only the radiation type that has been selected;

(-b-)

prevent irradiation if any selected operations carried out in the treatment room do not agree with the selected operations carried out at the treatment control panel;

(-c-)

prevent irradiation with x-rays except to obtain a port film when electron applicators are fitted; and

(-d-)

prevent irradiation with electrons when accessories specific for x-ray therapy are fitted.

(III)

The radiation type selected shall be displayed at the treatment control panel before and during irradiation.

(xiii)

Equipment capable of generating radiation beams of different energies shall meet the following requirements.

(I)

Irradiation shall not be possible until a selection of energy has been made at the treatment control panel.

(II)

An interlock system shall be provided to prevent irradiation if any selected operations carried out in the treatment room do not agree with the selected operations carried out at the treatment control panel.

(III)

The nominal energy value selected shall be displayed at the treatment control panel before and during irradiation.

(xiv)

Equipment capable of both stationary beam therapy and moving beam therapy shall meet the following requirements.

(I)

Irradiation shall not be possible until a selection of stationary beam therapy or moving beam therapy has been made at the treatment control panel.

(II)

An interlock system shall be provided to prevent irradiation if any selected operations carried out in the treatment room do not agree with the selected operations carried out at the treatment control panel.

(III)

The selection of stationary or moving beam shall be displayed at the treatment control panel. An interlock system shall be provided to ensure that the equipment can only operate in the mode that has been selected.

(IV)

For new equipment, an interlock system shall be provided to terminate irradiation if movement of the gantry occurs during stationary beam therapy or stops during moving beam therapy unless such stoppage is a preplanned function.

(V)

Moving beam therapy shall be controlled to obtain the selected relationships between incremental dose monitor units and incremental angle of movement.

(-a-)

For new equipment, an interlock system shall be provided to terminate irradiation if the number of dose monitor units delivered in any 10 degrees of arc differs by more than 20% from the selected value.

(-b-)

For new equipment, where gantry angle terminates the irradiation in arc therapy, the dose monitor units shall differ by less than 5.0% from the value calculated from the absorbed dose per unit angle relationship.

(VI)

Where the dose monitor system terminates the irradiation in moving beam therapy, the termination of irradiation shall be as required by clause (vii) of this subparagraph.

(xv)

For new equipment, a system shall be provided from whose readings the absorbed dose rate at a reference point in the treatment volume can be calculated. The radiation detectors specified in subparagraph (iv) of this paragraph may form part of this system. In addition, the dose monitor unit rate shall be displayed at the treatment control panel. If the equipment can deliver under any conditions an absorbed dose rate at the normal treatment distance more than twice the maximum value specified by the manufacturer for any machine parameters utilized, a device shall be provided that terminates irradiation when the absorbed dose rate exceeds a value twice the specified maximum. The dose rate at which the irradiation will be terminated shall be in a record maintained by the registrant in accordance with subsection (k) of this section for agency inspection.

(xvi)

The registrant shall determine, or obtain from the manufacturer, the location with reference to an accessible point on the radiation head of the x-ray target or the virtual source of x-rays and the electron window or the virtual source of electrons if the system has electron beam capabilities.

(xvii)

Capabilities shall be provided so that all radiation safety interlocks can be checked for correct operation.

(B)

Facility and shielding requirements.

(i)

Each installation shall be provided with primary and/or secondary barriers as are necessary to assure compliance with §289.231(m) and (o) of this title.

(ii)

All protective barriers shall be fixed except for entrance doors or beam interceptors.

(iii)

The control panel shall be located outside the treatment room and all emergency buttons/switches shall be clearly labeled as to their functions.

(iv)

Windows, mirrors, closed-circuit television, or an equivalent system shall be provided to permit continuous observation of the patient following positioning and during irradiation and shall be so located that the operator may observe the patient from the control panel. When the primary viewing system is by electronic means, an alternate viewing system, which may be electronic, shall be available for use in the event of failure of the primary viewing system.

(v)

Provision shall be made for continuous two-way aural communication between the patient and the operator at the control panel independent of the particle accelerator. However, where excessive noise levels or treatment requirements make aural communication impractical, other methods of communication shall be used. When this is the case, a description of the alternate method shall be submitted to and approved by the agency.

(vi)

Treatment room entrances shall be provided with a warning light in a readily observable position near the outside of all access doors to indicate when the useful beam is "on".

(vii)

Interlocks shall be provided such that all entrance doors must be closed before treatment can be initiated or continued. If the radiation beam is interrupted by any door opening, it shall not be possible to restore the machine to operation without closing the door and reinitiating irradiation by manual action at the control panel.

(C)

Surveys, calibrations, spot checks, operational requirements, and additional operating procedures.

(i)

Surveys shall be performed as follows.

(I)

All new and existing facilities not previously surveyed shall have a survey made by a licensed medical physicist with a specialty in therapeutic radiological physics or medical health physics, who shall provide a written report of the survey to the registrant. The physicist who performs the survey shall be a person who did not consult in the design of the therapeutic radiation machine installation and is not employed by or within any corporation or partnership with the person who consulted in the design of the installation. In addition, such surveys shall be done after any change in the facility or equipment that might cause a significant increase in radiation hazard.

(II)

The survey report shall include, but not be limited to the following:

(-a-)

a diagram of the facility that details building structures and the position of the control panel, therapeutic radiation machine, and associated equipment;

(-b-)

a description of the therapeutic radiation system, including the manufacturer, model and serial number, beam type, and beam energy;

(-c-)

a description of the instrumentation used to determine radiation measurements, including the date and source of the most recent calibration for each instrument used;

(-d-)

conditions under which radiation measurements were taken; and

(-e-)

survey data including:

(-1-)

projected annual TEDE in areas adjacent to the therapy room; and

(-2-)

a description of workload, use, and occupancy factors employed in determining the projected annual TEDE.

(III)

The registrant shall maintain a copy of the survey report and a copy of the survey report shall be provided to the agency within 30 days of completion of the survey. Records of survey report shall be maintained in accordance with subsection (k) of this section for inspection by the agency.

(IV)

The survey report shall include documentation of all instances where the installation is in violation of applicable regulations. Any deficiencies detected during the survey shall be corrected prior to using the machine.

(ii)

Calibrations of therapeutic systems shall be performed as follows.

(I)

The calibration of systems subject to this subsection shall be performed in accordance with an established calibration protocol before the system is first used for irradiation of a patient and thereafter at time intervals that do not exceed 12 months and after any change that might significantly alter the calibration, spatial distribution, or other characteristics of the therapy beam. The calibration procedures shall be in writing, and shall have been developed by a licensed medical physicist with a specialty in therapeutic radiological physics. The calibration protocol entitled, "Protocol for Clinical Reference Dosimetry of High-Energy Photon and Electron Beams," Task Group 51, Radiation Therapy Committee, American Association of Physicists in Medicine, Medical Physics 26(9): 1847-1870, September 1999, is accepted as an established protocol. If Task Group 51 protocol for calibration is not used, at a minimum the calibration protocol shall include items in subclauses (III)-(V) of this clause below.

(II)

The calibration shall be performed by a licensed medical physicist with a specialty in therapeutic radiological physics who is physically present at the facility during the calibration.

(III)

Calibration radiation measurements required by subclause (I) of this clause shall be performed using a dosimetry system:

(-a-)

having a calibration factor for cobalt-60 gamma rays traceable to a national standard;

(-b-)

that has been calibrated within the previous 24 months and after any servicing that may have affected its calibration. During the calendar years in which the dosimetry system is not calibrated, an intercomparison to a system calibrated within the previous 12 months shall be performed;

(-c-)

that has been calibrated in such a fashion that an uncertainty can be stated for the radiation quantities monitored by the system; and

(-d-)

that has had constancy checks performed on the system as specified by the licensed medical physicist with a specialty in therapeutic radiological physics.

(IV)

Calibrations shall be in sufficient detail that the dose at a reference point in a tissue equivalent phantom can be calculated to within an uncertainty of 5.0%.

(V)

The calibration of the therapy unit shall include, but not be limited to, the following determinations.

(-a-)

Verification that the equipment is operating in compliance with the design specifications concerning the light field, patient positioning lasers, and back-pointer lights with the isocenter when applicable, variation in the axis of rotation for the table, gantry, and collimator system, and beam flatness and symmetry at the specified depth.

(-b-)

The absorbed dose rate at various depths in a tissue equivalent phantom for the range of field sizes used, for each effective energy, that will verify the accuracy of the dosimetry of all therapy procedures utilized with that therapy beam.

(-c-)

The uniformity of the radiation field to include symmetry, flatness, and dependence on gantry angle.

(-d-)

Verification that existing isodose charts applicable to the specific machine continue to be valid or are updated to existing machine conditions.

(-e-)

Verification of transmission factors for all accessories such as wedges, block trays, and/or universal and custom made beam modifying devices.

(VI)

Records of calibration measurements specified in subclause (I) of this clause and dosimetry system calibrations specified in subclause (III) of this clause shall be maintained by the registrant in accordance with subsection (k) of this section for inspection by the agency.

(VII)

A copy of the latest calibrated absorbed dose rate measured in accordance with subclause (I) of this clause shall be available at a designated area within the facility housing that therapy system.

(iii)

Spot checks shall be performed on systems subject to this paragraph during calibrations and thereafter at weekly intervals with the period between spot checks not to exceed five treatment days. Such radiation output measurements shall meet the following requirements.

(I)

The spot check procedures shall be performed in accordance with established protocol, shall be in writing, and shall have been developed by a licensed medical physicist with a specialty in therapeutic radiological physics. The spot check protocol entitled, "Comprehensive QA for Radiation Oncology," Task Group 40, Radiation Therapy Committee, American Association of Physicists in Medicine, Medical Physics 21(4): 581- 618, April, 1994, is accepted as an established protocol. If Task Group 40 protocol for spot checks is not used, at a minimum, the spot check protocol shall include items in subclauses (III)-(VI) of this clause below.

(II)

If a licensed medical physicist does not perform the spot check measurements, the results of the spot check measurements shall be reviewed by a licensed medical physicist at a frequency not to exceed five treatment days and a record kept of the review. If the output varies by more than 3.0% from the expected value, a licensed medical physicist shall be notified immediately.

(III)

The written spot check procedures shall specify the frequency at which tests or measurements are to be performed and the acceptable tolerance for each parameter measured in the spot check when compared to the value for that parameter determined in the calibration.

(IV)

Where a system has built-in devices that provide a measurement of any parameter during irradiation, such measurement shall not be utilized as a spot check measurement.

(V)

A parameter exceeding a tolerance set by a licensed medical physicist shall be corrected before the system is used for patient irradiation.

(VI)

Whenever a spot check indicates a significant change in the operating characteristics of a system, as specified in a licensed medical physicist's written procedures, the system shall be recalibrated, as required in this clause of this subparagraph.

(VII)

Records of spot check measurements and any necessary corrective actions shall be maintained by the registrant in accordance with subsection (k) of this section for inspection by the agency.

(VIII)

When a spot check involves a radiation measurement, such measurement shall be obtained using a system satisfying the requirements of subclause (III) of this clause or that has been intercompared with a system meeting those requirements within the previous year.

(iv)

Facilities with therapeutic radiation machines with energies of 1 MeV and above shall procure the services of a licensed medical physicist with a specialty in therapeutic radiological physics.

(I)

The physicist shall be responsible for:

(-a-)

calibration of radiation machines;

(-b-)

supervision and review of beam and clinical dosimetry;

(-c-)

measurement, analysis, and tabulation of beam data;

(-d-)

establishment of quality assurance procedures and performance of spot check review; and

(-e-)

review of absorbed doses delivered to patients.

(II)

The licensed medical physicist described in subclause (I) of this clause shall also be available and responsive to immediate problems or emergencies.

(v)

In addition to the items listed in paragraph (1)(D) of this subsection, operating and safety procedures shall also include procedures to ensure the following requirements are met.

(I)

No individual other than the patient shall be in the treatment room during treatment of a patient.

(II)

Restraining or mechanical supporting devices shall be used if a patient or port film must be immobilized in position during treatment.

(III)

The therapeutic system shall not be used in the administration of radiation therapy unless the requirements of clauses (i)-(v) of this subparagraph have been met.

(4)

Radiation therapy simulators.

(A)

General requirements. In addition to the general requirements in subsections (h)(1)(B)-(E) of this section, radiation therapy simulators shall comply with the following:

(i)

Technique chart. A technique chart relevant to the particular radiation machine shall be provided or electronically displayed in the vicinity of the control panel and used by all operators.

(ii)

Operating and safety procedures. Each registrant shall have and implement written operating and safety procedures in accordance with subsection (h)(1)(D) of this section.

(iii)

Protective devices. When utilized, protective devices shall meet the following requirements.

(I)

Protective devices shall be made of no less than 0.25 millimeter (mm) lead equivalent material.

(II)

Protective devices, including aprons, gloves, and shields shall be checked annually for defects, such as holes, cracks, and tears. These checks may be performed by the registrant by visual, tactile, or x-ray imaging. If a defect is found, equipment shall be replaced or removed from service until repaired. A record of this test shall be made and maintained by the registrant in accordance with subsection (k) of this section for inspection by the agency.

(iv)

Viewing system. Windows, mirrors, closed circuit television, or an equivalent system shall be provided to permit the operator to continuously observe the patient during irradiation. The operator shall be able to maintain verbal, visual, and aural contact with the patient.

(v)

Operator position. The operator's position during the exposure shall be such that the operator's exposure is as low as reasonably achievable (ALARA) and/or protected by an apron, gloves, or other shielding having a minimum of 0.25 mm lead equivalent material.

(vi)

No individuals other than the patient and the operator(s) shall be in the treatment room during operation of the simulator.

(vii)

Film processing.

(I)

Films shall be developed in accordance with the time- temperature relationships recommended by the film manufacturer. The specified developer temperature for automatic processing and the time-temperature chart for manual processing shall be posted in the darkroom. If the registrant determines an alternate time-temperature relationship is more appropriate for a specific facility, that time-temperature relationship shall be documented and posted.

(II)

Chemicals shall be replaced according to the chemical manufacturer's or supplier's recommendations or at an interval not to exceed three months.

(III)

Darkroom light leak tests shall be performed and any light leaks corrected at intervals not to exceed six months.

(IV)

Lighting in the film processing/loading area shall be maintained with the filter, bulb wattage, and distances recommended by the film manufacturer for that film emulsion or with products that provide an equivalent level of protection against fogging.

(V)

Corrections or repairs of the light leaks or other deficiencies in subclauses (II), (III), and (IV) of this clause shall be initiated within 72 hours of discovery and completed no longer than 15 days from detection of the deficiency unless a longer time is authorized by the agency. Records of the correction or repairs shall include the date and initials of the individual performing these functions and shall be maintained in accordance with subsection (k) of this section for inspection by the agency.

(VI)

Documentation of the items in subclauses (II), (III), and (IV) of this clause shall be maintained at the site where performed and shall include the date and initials of the individual completing these items. These records shall be kept in accordance with subsection (k) of this section for inspection by the agency.

(viii)

Alternative processing systems. Users of daylight processing systems, laser processors, self-processing film units, or other alternative processing systems shall follow manufacturer's recommendations for image processing.

(B)

Additional requirements for radiation therapy simulators used in the general radiographic mode of operation.

(i)

Beam quality (HVL). The half-value layer of the useful beam for a given x-ray tube potential shall not be less than the values shown in the following Table IV. If it is necessary to determine such half-value layer at an x-ray tube potential that is not listed in Table IV, linear interpolation may be made.

Figure: 25 TAC §289.229(h)(4)(B)(i)

(ii)

Technique and exposure indicators.

(I)

The technique factors to be used during an exposure shall be indicated before the exposure begins except when automatic exposure controls are used, in which case the technique factors that are set prior to the exposure shall be indicated.

(II)

The indicated technique factors shall be accurate to within manufacturer's specifications. If these specifications are not available from the manufacturer, the factors shall be accurate to within ±10% of the indicated setting.

(iii)

Beam limitation.

(I)

The beam limiting device (collimator) shall restrict the useful beam to the area of clinical interest.

(II)

A method shall be provided to visually define the center (cross-hair centering) of the x-ray field to within a 2 mm diameter.

(III)

A method shall be provided to accurately indicate the distance to within 2 mm.

(IV)

The delineator wires shall be accurate with the indicated setting within 2 mm.

(V)

The x-ray field shall be congruent with the light field within 2 mm.

(iv)

Timers. Means shall be provided to terminate the exposure at a preset time interval, a preset product of current and time, a preset number of pulses, or a preset radiation exposure to the image receptor. In addition, it shall not be possible to make an exposure when the timer is set to a "zero" or "off" position if either position is provided and a visual and/or audible signal shall indicate when an exposure has been terminated.

(v)

AEC. When an AEC is provided, an indication shall be made on the control panel when this mode of operation is selected.

(vi)

Timer reproducibility. When all technique factors are held constant, including control panel selections associated with AEC systems, the coefficient of variation of exposure interval for both manual and AEC systems shall not exceed 0.05. This requirement applies to clinically used techniques.

(vii)

Exposure reproducibility. When all technique factors are held constant, including control panel selections associated with AEC systems, the coefficient of variation of exposure for both manual and AEC systems shall not exceed 0.05. This requirement applies to clinically used techniques.

(viii)

Linearity.

Figure: 25 TAC §289.229(h)(4)(B)(viii)

(C)

Additional requirements for radiation therapy simulators utilizing fluoroscopic capabilities.

(i)

X-ray production in the fluoroscopic mode shall be controlled by a device that requires continuous pressure by the fluoroscopist for the entire time of the exposure (continuous pressure type switch).

(ii)

During fluoroscopy and cinefluorography, the kV and the mA shall be continuously indicated at the control panel and/or the fluoroscopist's position.

(iii)

The SSD shall not be less than the 20 cm for image-intensified fluoroscopes used for examinations as specified in the registrant's operating and safety procedures. The written operating and safety procedures shall provide precautionary measures to be adhered to during the use of this device. The procedures must provide information on the means to restore the unit to a 30 cm SSD when the unit is returned to general service.

(iv)

Fluoroscopic timers shall meet the following requirements.

(I)

Means shall be provided to preset the cumulative on-time of the fluoroscopic x-ray tube. The maximum cumulative time of the timing device shall not exceed five minutes without resetting.

(II)

A signal audible to the fluoroscopist shall indicate the completion of any preset cumulative on-time. Such signal shall continue to sound while x-rays are produced until the timing device is reset. In lieu of such signal, the timer shall terminate the beam after the preset cumulative on-time is completed.

(v)

The exposure foot switch shall be permanently mounted in the control booth to ensure that the operator cannot enter the simulator room while the fluoroscope is activated.

(vi)

Simulators must duplicate the geometric conditions of the radiation therapy equipment plan and therefore spot checks regarding geometric conditions shall be performed in accordance with subsection (h)(3)(C)(iii)(I) of this section.

(D)

Additional requirements for radiation therapy simulators utilizing CT capabilities. CT simulators producing digital images only are exempt from the requirements of this subparagraph and paragraph (h)(4)(A)(i), (vii), and (viii) of this subsection.

(i)

Equipment requirements.

(I)

Tomographic systems shall meet the following requirements.

(-a-)

For any single tomogram system, means shall be provided to permit visual determination of the tomographic plane or a reference plane offset from the tomographic plane.

(-b-)

For any multiple tomogram system, means shall be provided to permit visual determination of the tomographic plane or a reference plane offset from the tomographic plane.

(-c-)

If a device using a light source is used to satisfy the requirements of item (-a-) or (-b-) of this subclause, the light source shall provide illumination levels sufficient to permit visual determination of the location of the tomographic plane or reference plane under ambient light conditions of up to 500 lux.

(II)

The CT x-ray system shall be designed such that the CT conditions of operation to be used during a scan or a scan sequence are indicated prior to the initiation of a scan or a scan sequence. On equipment having all or some of these conditions of operation at fixed values, this requirement may be met by permanent markings. Indication of CT conditions shall be visible from any position from which scan initiation is possible.

(III)

The x-ray control and gantry shall provide visual indication whenever x rays are produced and, if applicable, whether the shutter is open or closed.

(IV)

Means shall be provided to require operator initiation of each individual scan or series of scans.

(V)

All emergency buttons/switches shall be clearly labeled as to their functions.

(VI)

Termination of exposure shall be as follows.

(-a-)

Means shall be provided to terminate the x-ray exposure automatically by either de-energizing the x-ray source or shuttering the x-ray beam in the event of equipment failure affecting data collection. Such termination shall occur within an interval that limits the total scan time to no more than 110% of its preset value through the use of either a backup timer or devices that monitor equipment function.

(-b-)

A signal visible to the operator shall indicate when the x-ray exposure has been terminated through the means required by item (-a-) of this subclause.

(-c-)

The operator shall be able to terminate the x-ray exposure at any time during a scan or series of scans under CT x-ray system control, of greater than 0.5 second duration. Termination of the x-ray exposure shall necessitate resetting of the CT conditions of operation prior to initiation of another scan.

(VII)

CT x-ray systems containing a gantry manufactured after September 3, 1985 shall meet the following requirements.

(-a-)

The total error in the indicated location of the tomographic plane or reference plane shall not exceed 5 mm.

(-b-)

If the x-ray production period is less than 0.5 second, the indication of x-ray production shall be actuated for at least 0.5 second. Indicators at or near the gantry shall be discernible from any point external to the patient opening where insertion of any part of the human body into the primary beam is possible.

(-c-)

The deviation of indicated scan increment versus actual increment shall not exceed ±1 mm with any mass from 0 to 100 kilograms (kg) resting on the support device. The patient support device shall be incremented from a typical starting position to the maximum incremented distance or 30 cm, whichever is less, and then returned to the starting position. Measurement of actual versus indicated scan increment can be taken anywhere along this travel.

(ii)

Facility design requirements.

(I)

Provision shall be made for two-way aural communication between the patient and the operator at the control panel.

(II)

Windows, mirrors, closed-circuit television, or an equivalent shall be provided to permit continuous observation of the patient during irradiation and shall be so located that the operator can observe the patient from the control panel. When the primary viewing system is by electronic means, an alternate viewing system, which may be electronic, shall be available for use in the event of failure of the primary viewing system.

(iii)

Dose measurements of the radiation output of the CT x-ray system.

(I)

Dose measurements of the radiation output of the CT x-ray system shall be performed by a licensed medical physicist with a specialty in diagnostic radiological physics. The measurements shall be performed as follows:

(-a-)

at intervals not to exceed 12 months;

(-b-)

when major maintenance, except x-ray tube replacement, that could affect radiation output is performed; or

(-c-)

when a major change in equipment operation (e.g. introduction of a new software package) is accomplished.

(II)

Measurements of the radiation output of a CT x-ray system shall be performed with a calibrated dosimetry system. The dosimetry system shall have been calibrated within the preceding 24 months and shall be traceable to a national standard. During the calendar year in which the dosimetry system is not calibrated, an intercomparison to a system calibrated within the previous 12 months shall be performed.

(III)

Records of dose measurements shall be maintained by the registrant in accordance with subsection (k) of this section.

(iv)

A maintenance schedule shall be developed in accordance with the manufacturer's United States Department of Health and Human Services maintenance schedule. The schedule shall include, but need not be limited to the following:

(I)

dose measurements required by clause (iii)(I) of this subparagraph; and

(II)

acquisition of images obtained with phantoms using the same processing mode and CT conditions of operation as are used to perform dose measurements required by clause (iii)(I) of this subparagraph. The registrant shall retain either of the following in accordance with subsection (k) of this section for inspection by the agency:

(-a-)

photographic copies of the images obtained from the image display device; or

(-b-)

images stored in digital form.

(5)

Records/documents.

(A)

The registrant shall maintain copies of the following records/documents at authorized use locations in accordance with subsection (k) of this section for inspection by the agency:

(i)

current applicable sections of this chapter as listed on the certificate of registration;

(ii)

current certificate of registration;

(iii)

current operating and safety procedures in accordance with subsection (h)(1)(D) of this section;

(iv)

receipt, transfer, disposal, surveys, and calibrations of radiation machines specific to that location including the date, the manufacturer name, model and serial number from the control panel or console of the radiation machine and identification of the person making the record;

(v)

credentials of operators of radiation machines operating at that location in accordance with subsection (h)(1)(D) of this section;

(vi)

film processing records for that location in accordance with subsection (h)(4)(A)(vii) of this section, as applicable;

(vii)

FDA variances of machines at that location in accordance with subsection (h)(1) of this section;

(viii)

CT dose measurements and CT quality control films or images at that location in accordance with subsection (h)(4)(D)(iii)(I) and (II) of this section;

(ix)

therapy (below 1 MeV) surveys and calibrations of equipment at that location in accordance with subsection (h)(2)(D)(i) and (ii) of this section;

(x)

therapy (1 MeV and above) surveys and calibrations of equipment at that location in accordance with subsection (h)(3)(C)(i) and (ii) of this section;

(xi)

records, notices, and reports of therapy events in accordance with subsection (j) of this section; and

(xii)

notice of violations from last inspection, if applicable, and documentation of corrections of any violations.

(B)

Records specified in subparagraph (A) may be maintained in electronic format.

(i)

Therapy events (misadministrations).

(1)

Therapy events involving equipment operating at energies below 1 MeV shall be reported when:

(A)

the event involves the wrong individual, or wrong treatment site;

(B)

the treatment consists of three or fewer fractions and the calculated total administered dose differs form the total prescribed dose by more than 10% of the total prescribed dose; or

(C)

the calculated total administered dose differs from the total prescribed dose by more than 20% of the total prescribed dose.

(2)

Therapy events involving equipment operating with energies of 1 MeV and above shall be reported when:

(A)

the event involves the wrong individual, wrong type of radiation, wrong energy, or wrong treatment site;

(B)

the treatment consists of three or fewer fractions and the calculated total administered dose differs from the total prescribed dose by more than 10% of the total prescribed dose; or

(C)

the calculated total administered dose differs from the total prescribed dose by more than 20% of the total prescribed dose.

(j)

Reports of therapy events (misadministrations).

(1)

For a therapy event, a registrant shall do the following:

(A)

notify the agency by telephone no later than 24 hours after discovery of the event;

(B)

notify the referring physician and also notify the patient of the event no later than 24 hours after its discovery, unless the referring physician personally informs the registrant either that he or she will inform the patient or that, based on medical judgement, telling the patient would be harmful. The registrant is not required to notify the patient without first consulting the referring physician. If the referring physician or patient cannot be reached within 24 hours, the registrant shall notify the patient as soon as possible thereafter. The registrant may not delay any appropriate medical care for the patient, including any necessary remedial care as a result of the event, because of any delay in notification;

(C)

submit a written report to the agency within 15 days after the discovery of the event. The report must not include the patient's name or other information that could lead to identification of the patient. The written report must include the following:

(i)

registrant's name and certificate of registration number;

(ii)

prescribing physician's name;

(iii)

a brief description of the event;

(iv)

why the event occurred;

(v)

the effect on the patient;

(vi)

what improvements are needed to prevent recurrence;

(vii)

actions taken to prevent recurrence;

(viii)

whether the registrant notified the patient, or the patient's responsible relative or guardian (this person will be subsequently referred to as "the patient"); and if not, why not; and

(ix)

if the patient was notified, what information was provided to the patient; and

(D)

furnish the following to the patient within 15 days after discovery of the event if the patient was notified:

(i)

a copy of the report that was submitted to the agency; or

(ii)

a brief description of both the event and the consequences, as they may affect the patient, provided a statement is included that the report submitted to the agency can be obtained from the registrant.

(2)

Each registrant shall retain a record of each event in accordance with subsection (k) of this section for inspection by the agency. The record shall contain the following:

(A)

the names of all individuals involved (including the prescribing physician, allied health personnel, the patient, and the patient's referring physician);

(B)

the patient's identification number;

(C)

a brief description of the event;

(D)

why it occurred;

(E)

the effect on the patient;

(F)

what improvements are needed to prevent recurrence; and

(G)

the actions taken to prevent recurrence.

(3)

Aside from the notification requirement, nothing in subsection (i) of this section and paragraphs (1) and (2) of this subsection shall affect any rights or duties of registrants, and physicians in relation to each other, patients, or the patient's responsible relatives or guardians.

(k)

Records/documents for agency inspection. Each registrant shall make the following records/documents available to the agency for inspection, upon reasonable notice.

Figure: 25 TAC §289.229(k)

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003516

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


25 TAC §289.226

The Texas Department of Health (department) proposes an amendment to §289.226, concerning the registration of radiation machine use and services.

The amendment clarifies when the use of accelerators and therapy radiation machines must be registered. Requirements for radiation safety officers for dental facilities are deleted because these requirements have been incorporated in another section. Requirements concerning the approval of a healing arts screening program are deleted from another section and more appropriately incorporated in this section. Requirements for providers of equipment and for persons who sell, lease, loan, install, assemble, and transfer radiation machines are added to formalize in rule what is currently required by certificate of registration condition. References are updated and minor clarifying language is added throughout the rule. This amendment is part of the department's continuing effort to update, clarify, and simplify its rules regarding the control of radiation based upon technological advances, public concerns, legislative directives, or other factors.

Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, has determined that for each year of the first five years the section will be in effect, there will be no fiscal implications for state or local government as a result of enforcing or administering the section as proposed.

Mrs. McBurney has also determined that for each year of the first five years the proposed section will be in effect, the public benefit anticipated as a result of enforcing the section will be to ensure continued protection of the public and workers from unnecessary exposure to radiation by ensuring requirements are in place for registering all types of radiation machines. There will be no effect on micro businesses or small businesses. There are no anticipated economic costs to persons who are required to comply with the section as proposed. There is no anticipated impact on local employment. The amendment clarifies the registration requirements for accelerators, deletes requirements incorporated in another section, and incorporates requirements that are deleted from another section and more appropriately placed in this section. Because the amendment imposes no additional requirements such as record keeping, regulatory limits, procedures, or processes, there are no economic effects associated with the section as proposed.

Comments on the proposal may be presented to Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, Texas Department of Health, 1100 West 49th Street, Austin, Texas 78756-3189, Telephone (512) 834- 6688 or electronic mail at Ruth.Mcburney@tdh.state.tx.us. Public comments will be accepted for 30 days following publication of this proposal in the Texas Register . In addition, a public meeting to accept oral comments will be held at 10:00 a.m., Thursday, June 15, 2000, in Conference Room N218, Texas Department of Health, Bureau of Radiation Control, located at the Exchange Building, 8407 Wall Street, Austin, Texas.

The amendment is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with the authority to adopt rules for the performance of each duty imposed by law on the board, the department, and the commissioner of health.

The amendment affects Health and Safety Code, Chapter 401 and Chapter 12.

§289.226. Registration of Radiation Machine Use and Services.

(a)

Purpose. [ Scope and purpose. ]

[ (1) ]

This section provides for the registration of persons using radiation machines and persons who are in the business of providing radiation machine installation or radiation services. No person shall use radiation machines or perform radiation services except as authorized in a certificate of registration issued by the agency in accordance with the requirements of this section. A person who receives, possesses, uses, owns, or acquires radiation machines [ has made application for registration in accordance with this section and is using a radiation machine ] prior to receiving a certificate of registration is subject to the requirements of this chapter.

(b)

Scope.

(1)

[ (2) ] In addition to the requirements of this section, all registrants are subject to the requirements of §289.203 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections), §289.204 of this title (relating to Fees for Certificates of Registration, Radioactive Material Licenses, Emergency Planning and Implementation, and Other Regulatory Services), §289.205 of this title (relating to Hearing and Enforcement Procedures), and §289.231 of this title (relating to General Provisions and Standards for Protection Against Machine-Produced Radiation). [ §289.112 of this title (relating to Hearing and Enforcement Procedures), §289.114 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections), §289.201 of this title (relating to General Provisions), §289.202 of this title (relating to Standards for Protection Against Radiation), and §289.204 of this title (relating to Fees for Certificates of Registration, Radioactive Material(s) Licenses, Emergency Planning and Implementation, and Other Regulatory Services). Registrants using radiation machines in industrial radiographic operations are subject to the requirements of §289.115 of this title (relating to Radiation Safety Requirements and Licensing and Registration Procedures for Industrial Radiography); registrants using machines in the healing arts and veterinary medicine are subject to the requirements of §289.227 of this title (relating to Use of Radiation Machines in the Healing Arts and Veterinary Medicine); registrants using mammography x-ray equipment are subject to the requirements of §289.230 of this title (relating to Certification of Mammography Systems); registrants using analytical x-ray equipment are subject to the requirements of §289.118 of this title (relating to Radiation Safety Requirements for Analytical X-Ray Equipment); and registrants using particle accelerators are subject to the requirements of §289.119 of this title (relating to Radiation Safety Requirements for Particle Accelerators). If an accelerator is used to produce radioactive materials, a license issued in accordance with §289.252 of this title (relating to Licensing of Radioactive Material) is required. Services listed in subsection (a)(3) of this section may constitute the practice of medical physics and, therefore, require a license from the Texas Board of Licensure for Professional Medical Physicists in accordance with the Medical Physics Practice Act, Texas Civil Statutes, Article 4512n. ]

(2)

Registrants using radiation machines in the healing arts and veterinary medicine are subject to the requirements of §289.227 of this title (relating to Use of Radiation Machines in the Healing Arts and Veterinary Medicine).

(3)

Registrants using analytical and other industrial radiation machines, such as x-ray equipment used for cathodoluminescence, ion implantation, gauging, or electron beam welding, are subject to the requirements of §289.228 of this title (relating to Radiation Safety Requirements for Analytical and Other Industrial Radiation Machines).

(4)

Registrants using accelerators, therapeutic radiation machines, and simulators are subject to the requirements of §289.229 of this title (relating to Radiation Safety Requirements for Accelerators, Therapeutic Radiation Machines, and Simulators).

(5)

Registrants using mammography radiation machines are subject to the requirements of §289.230 of this title (relating to Certification of Mammography Systems and Accreditation of Mammography Facilities).

(6)

Registrants using radiation machines in industrial radiographic operations are subject to the requirements of §289.255 of this title (relating to Radiation Safety Requirements and Licensing and Registration Procedures for Industrial Radiography).

(7)

Services listed in paragraph (8) of this subsection may constitute the practice of medical physics and, therefore, may require individuals performing those services to have a license from the Texas Board of Licensure for Professional Medical Physicists in accordance with the Medical Physics Practice Act, Texas Civil Statutes, Article 4512n.

(8)

[ (3) ] For the purposes of this section, radiation services shall include, but may not be limited to the following:

(A)

provision of radiation protection or health physics consultations or surveys that require the consultant to operate or cause a radiation machine to be operated in order to make measurements or gather data;

(B)

presentation of agency-accepted training courses that are specifically required by this chapter ;

(C)

calibration of radiation machine output;

(D)

calibration of survey and measurement instruments;

(E)

demonstration and sales of radiation machines that require the individual to operate or cause a radiation machine to be operated in order to demonstrate or sell;

(F)

assembly , installation or repair [ (i.e., installation, repair, or maintenance) ];

(G)

provision of personnel monitoring services;

(H)

performance of equipment performance evaluations on radiation machines; or

(I)

provision of radiation machines on a routine basis to a facility for limited time periods. For purposes of this section, a person providing the services described in this subparagraph is a provider of equipment. For healing arts facilities, the use of radiation machines shall be directed by a licensed practitioner employed by the contracting facility.

(9)

[ (4) ] For purposes of this section, a practitioner of the healing arts is a person licensed to practice healing arts by either the Texas State Board of Medical Examiners as a physician, [ the Texas State Board of Dental Examiners, ] the Texas Board of Chiropractic Examiners, or the Texas State Board of Podiatry Examiners.

(c)

[ (5) ] Prohibition. Exposure of an individual for training, demonstration, or other non-healing arts purposes is prohibited.

(d)

[ (b) ] Exemptions.

(1)

Electronic equipment that produces radiation incidental to its operation for other purposes is exempt from the registration and notification requirements of this section, provided that the dose equivalent rate averaged over an area of 10 square centimeters (cm 2 ) does not exceed 0.5 millirem per hour (mrem/hr) at 5 centimeters (cm) from any accessible surface of such equipment. The production, testing, or factory servicing of such equipment shall not be exempt.

(2)

Radiation machines in transit or in storage incident to transit are exempt from the requirements of this section. This exemption does not apply to the providers of radiation machines for mobile services. Facilities that have placed all radiation machines in storage, including on-site storage , [ in place, ] and have notified the agency in writing, are exempt from the requirements of this section. This exemption is void if any radiation machine is energized resulting in the production of radiation.

(3)

Domestic television receivers and video display terminals, including the servicing of such devices, are exempt from the requirements of this section.

(4)

Inoperable radiation machines are exempt from the requirements of this section. For the purposes of this section, an inoperable radiation machine means a radiation machine that cannot be energized when connected to a power supply without repair or modification.

(5)

Financial institutions that take possession of radiation machines as the result of foreclosure, bankruptcy, or other default of payment are exempt from the requirements in this section to the extent that they demonstrate that the unit is operable for the sole purpose of selling, leasing, or transferring.

(6)

Facilities, including academic institutions and research and/or development facilities, registered for the use of radiation machines are exempt from the registration requirements of subsections (g) and (l) [ subsection (e) of this section and subsection (i) ] of this section to the extent that their personnel perform radiation services only for the facility by whom they are employed.

(e)

[ (c) ] Application for registration.

(1)

Application for registration shall be completed on forms prescribed by the agency and shall contain all the information required by the form and accompanying instructions.

(2)

A radiation safety officer (RSO) shall be designated on each application form. The qualifications of that individual shall be submitted to the agency with the application. The RSO shall meet the applicable requirements of subsection (w)(1) [ (s)(1) ] of this section and carry out the responsibilities of subsection (w)(2) [ (s)(2) ] of this section.

(3)

The agency may at any time after the filing of the original application, require further statements in order to enable the agency to determine whether the certificate of registration should be issued or [ , ] denied . [ , modified, or revoked. ]

(4)

An application for a certificate of registration may include a request for a certificate of registration authorizing one or more activities. Applications for certification of mammography systems must be made separately.

(5)

Applications and documents submitted to the agency may be made available for public inspection except that the agency may withhold any document or part thereof from public inspection in accordance with §289.231(aa) [ §289.201(n) ] of this title.

(6)

Each application for a certificate of registration shall be accompanied by the fee prescribed in §289.204 of this title.

(7)

BRC Form 226-1 (Franchise Tax Form) shall be submitted with the application to confirm that no tax owed to the state under Tax Code, Chapter 171, is delinquent.

(f)

[ (d) ] Application for registration for human or veterinary use of radiation machines. In addition to the requirements of subsection (e) [ (c) ] of this section, each applicant shall comply with the following.

(1)

Each person having a radiation machine used in healing arts or veterinary medicine shall apply for registration with the agency within 30 days after beginning use of [ following the commencement of the operation of ] the radiation machine, except for mobile services that shall be registered in accordance with subsection (i) [ (g) ] of this section, [ clinical trial evaluations that shall be registered in accordance with subsection (m)(2)(B) of this section, ] and healing arts screening programs that shall be approved in accordance with subsection (j) of this section. [ (f)(1) of §289.227 of this title. ]

(2)

Each person having an accelerator or therapeutic radiation machine at or above 1 million electron volts (MeV) for human use shall apply for and receive a certificate of registration from the agency before activation, including acceptance testing, of the accelerator.

(3)

Each person having a simulator and/or therapeutic radiation machine below 1 MeV for human use shall apply for registration with the agency within 30 days of energizing the equipment.

(4)

[ (3) ] The applicant shall be qualified by reason of training and experience to use the radiation machine [ machine(s) ] for the purpose requested in accordance with this section in such a manner as to minimize danger to occupational and public health and safety.

(5)

[ (4) ] The applicant's proposed equipment, facilities, and operating and safety procedures shall be adequate to minimize danger to occupational and public health and safety.

(6)

[ (5) ] An application for healing arts must be signed by a licensed practitioner and an application for veterinary medicine must be signed by a licensed veterinarian. The signature of the administrator, president, or chief executive officer will be accepted in lieu of a licensed practitioner's signature if the facility has more than one licensed practitioner who may direct the operation of radiation machines. [ is a licensed hospital or a medical facility with more than ten radiation machines. ] The application shall also be signed by the RSO if the RSO is someone other than the licensed practitioner or licensed veterinarian.

(7)

[ (6) ] An application for accelerators or therapeutic radiation machines for human use must be signed by a practitioner licensed by the Texas State Board of Medical Examiners. The signature of the administrator, president, or chief executive officer will be accepted in lieu of a licensed practitioner's signature if the facility has more than one licensed practitioner who may direct the operation of radiation machines. [ is a licensed hospital or a medical facility with more than ten radiation machines. ] The application shall also be signed by the RSO if the RSO is someone other than the licensed practitioner. Each applicant shall submit operating and safety procedures as described in §289.229(h)(1)(D) of this title and a description of the proposed facilities in accordance with the following:

(A)

§289.229(h)(2)(B) and (C) of this title for equipment with energies below 1 MeV; and

(B)

§289.229(h)(3)(B) of this title for equipment with energies above 1 MeV. [ 35.3 and 35.10 of Texas Regulations for Control of Radiation (TRCR) Part 35 as adopted by reference in §289.119 of this title, and a description of the proposed facilities in accordance with 35.7-35.9 and 35.12 of TRCR Part 35 as adopted by reference in §289.119 of this title. ]

(g)

[ (e) ] Application for registration of radiation machine assembly, installation, calibration, or repair, consultants, providers of equipment, and radiation services other than providers of personnel monitoring service, agency-accepted training courses, and calibration of survey and measurement instruments. In addition to the requirements of subsection (e) [ (c) ] of this section, each applicant shall comply with the following.

(1)

Each person who intends to engage in the business of providing radiation services described in subsection (b)(8) [ (a)(3) ] of this section shall apply for and receive a certificate of registration from the agency before providing such service.

(2)

An application for radiation services shall be signed by the applicant or registrant or a person duly authorized to act for and on the applicant's or registrant's behalf. The application shall also be signed by the RSO if the RSO is someone other than the applicant or registrant.

(3)

The applicant shall submit to the agency written documentation of the specific training and experience that qualifies each individual to discharge the duties of this service. Documentation of each individual's training shall be maintained for inspection by the agency. As a minimum, each applicant shall submit the following:

(A)

for assembler and/or calibration of radiation machines [ x-ray ] equipment, the qualifications listed in subsection (w)(3) [ (s)(3) ] of this section;

(B)

for all other services, the qualifications listed in subsection (w)(1)(A) [ (s)(1)(A) ] of this section.

(4)

No person shall perform services specified in this subsection that are not specifically authorized by the agency.

(5)

No person shall perform these machine services, other than initial installation of the first machine on the premises, for an individual who cannot produce evidence of registration with the agency authorizing the possession and use of the machines in question.

(6)

The applicant shall submit the interval to be followed to calibrate electronic equipment used in radiation machine servicing , for example, kVp meters and voltmeters [ (e.g., kVp meters, voltmeters) ].

(7)

Each applicant for providers of equipment shall submit the following:

(A)

an established main location where the machines, [ machine, ] records, etc. will be maintained for inspection. This must be a street address, not a post office box number;

(B)

evidence that the healing arts facility responsible for administering or supervising the administering of radiation is registered in accordance with the requirements [ rules ] in this section; and

(C)

a current copy of the applicant's operating and safety procedures is required when personnel is also provided. [ ; and ]

[ (D)

a list of facilities where equipment will be provided. ]

(h)

[ (f) ] Application for registration for provider of personnel monitoring services. In addition to the requirements of subsection (e) [ (c) ] of this section, each applicant shall comply with the following.

(1)

Each person who intends to provide personnel monitoring services shall apply for and receive a certificate of registration from the agency before providing such services.

(2)

An application for personnel monitoring services shall be signed by the applicant or registrant or a person duly authorized to act for and on the applicant's or registrant's behalf. The application shall also be signed by the RSO if the RSO is someone other than the applicant or registrant.

(3)

The applicant shall submit documentation that the facility has been accredited by the National Voluntary Laboratory Accreditation for Personnel Dosimetry Processors of the National Institute of Science and Technology in accordance with accreditation criteria established in Title 15 , Code of Federal Regulations (CFR) , Part 7b, as amended.

(4)

The maximum allowable time delay between the end date of the monitoring period and the date at which processing will not be performed shall be stated.

(5)

The maximum time between processing and reporting results shall be stated.

(i)

[ (g) ] Application for registration of mobile services used in the healing arts and veterinary medicine. In addition to the requirements of subsections (e) and (f) [ (c) and (d) ] of this section or §289.230(f) of this title, as applicable, each applicant shall apply for and receive authorization for mobile services before beginning mobile service operation. The following shall be submitted : [ . ]

(1)

an [ An ] established main location where the machine(s), [ machine, ] records, etc. will be maintained for inspection. This must be a street address, not a post office box number ; [ . ]

(2)

a [ A ] sketch or description of the normal configuration of each radiation machine's [ x-ray unit's ] use, including the operator's position and any ancillary personnel's location during exposures. If a mobile van is used with a fixed unit inside, furnish the floor plan indicating protective shielding and the operator's location ; and [ . ]

(3)

for [ For ] mobile services used in the healing arts, a current copy of the applicant's operating and safety procedures regarding radiological practices for protection of patients, operators, employees, and the general public.

(j)

Application for registration of healing arts screening and medical research.

(1)

In addition to the requirements of subsections (e) and (f) of this section or §289.230(f) of this title, as applicable, each applicant shall apply for and receive authorization for healing arts screening before initiating a screening program. The information and evaluation in subsection (w)(4) of this section shall be submitted with the application.

(2)

In addition to the requirements of subsections (e) and (f) of this section, any research using radiation machines on humans must receive prior approval from the agency and must be approved by an Institutional Review Board (IRB) as required by Title 45, CFR Part 46 and Title 21, CFR, Part 56. The IRB must include at least one practitioner of the healing arts to direct any use of radiation in accordance with §289.231(b)(1) of this title.

(k)

[ (h) ] Application for registration of radiation machines for non-human use other than veterinary medicine. [ Application for registration for use of radiation machines in industrial radiography, analytical equipment, accelerators for non-human use, and academic and/or research and development facilities. ] In addition to the requirements of subsection (e) [ (c) ] of this section, each applicant shall comply with the following.

(1)

Each person having an accelerator for non-human use shall apply for and receive a certificate of registration from the agency before beginning use of the accelerator.

(2)

Each person having an accelerator for non-human use shall submit the following:

(A)

operating and safety procedures as described in §289.229(f)(3)(C) of this title; and

(B)

a description of the applicant's proposed facilities in accordance with §289.229(f)(2) and (f)(3)(A), (B), and (D) of this title.

(3)

Each person having a radiation machine for non- human use other than veterinary medicine shall apply for registration with the agency within 30 days after beginning use of the machine.

(4)

Each applicant for industrial radiographic operations shall submit the information required in §289.255(u)(7) of this title.

(5)

An application for the uses specified in this subsection shall be signed by the applicant or registrant or a person duly authorized to act for and on the applicant's or registrant's behalf. The application shall also be signed by the RSO if the RSO is someone other than the applicant or registrant.

[ (1)

Each person having analytical equipment or radiation machines in an academic institution and/or research and development facility, shall apply for registration with the agency within 30 days following the commencement of the operation of the radiation machines. ]

[ (2)

Each person having an accelerator for non-human use or a radiation machine used in industrial radiographic operations shall apply for and receive a certificate of registration from the agency before beginning use of the accelerator or radiation machine. ]

[ (3)

An application for industrial radiographic operations, analytical x-ray, accelerators for non-human use and radiation machines in academic institutions and/or research and development facilities shall be signed by the applicant or registrant or a person duly authorized to act for and on the applicant's or registrant's behalf. The application shall also be signed by the RSO if the RSO is someone other than the applicant or registrant. ]

[ (4)

Each applicant for industrial radiographic operations shall submit the information required in 31.46 of TRCR Part 31 as adopted by reference in §289.115 of this title. ]

[ (5)

Each applicant for accelerators for non-human use shall submit the following: ]

[ (A)

operating and safety procedures as described in 35.3 and 35.10 of TRCR Part 35 as adopted by reference in §289.119 of this title; and ]

[ (B)

a description of the applicant's proposed facilities in accordance with 35.7-35.9, and 35.12 of TRCR Part 35 as adopted by reference in §289.119 of this title. ]

(l)

[ (i) ] Application for registration of calibration of survey and measurement instruments. In addition to the requirements of subsection (e) [ (c) ] of this section, each applicant shall comply with the following.

(1)

Each person who intends to engage in the business of providing calibration of survey and measurement instruments shall apply for and receive a certificate of registration from the agency before providing services.

(2)

An application for calibration of survey and measurement instruments shall be signed by the applicant or registrant or a person duly authorized to act for and on the applicant's or registrant's behalf. The application shall also be signed by the RSO if the RSO is someone other than the applicant or registrant.

(3)

Each applicant shall submit the following:

(A)

procedures for calibration;

(B)

qualifications of personnel performing the calibration;

(C)

a copy of the calibration certificate to be used; and

(D)

a copy of the expiration sticker to be used.

(m)

[ (j) ] Application for registration of agency-accepted training courses specifically required by this chapter . In addition to the requirements of subsection (e) [ (c) ] of this section, each applicant shall comply with the following.

(1)

Each person who intends to engage in the business of providing agency-accepted training courses specifically required by this chapter shall apply for and receive a certificate of registration from the agency before providing training.

(2)

An application for agency-accepted training courses shall be signed by the applicant or registrant or a person duly authorized to act for and on the applicant's or registrant's behalf. The application shall also be signed by the RSO if the RSO is someone other than the applicant or registrant.

(3)

Each applicant shall submit the following:

(A)

a course syllabus;

(B)

the number of instructional hours for each subject;

(C)

a list of training resources , for example, reference books, texts, workbooks, physical facilities, etc. [ (e.g., reference books, texts, workbooks, physical facilities, etc.) ];

(D)

all test questions and corresponding answers; and

(E)

resumes containing the radiation safety training, education, and experience of each instructor.

(n)

[ (k) ] Issuance of certificate of registration.

(1)

Upon a determination that an application meets the requirements of the Texas Radiation Control Act (Act) and the requirements of the agency, the agency may issue a certificate of registration authorizing the proposed activity in such form and containing such conditions and limitations as it deems appropriate or necessary.

(2)

The agency may incorporate in the certificate of registration at the time of issuance, or thereafter by amendment, such additional requirements and conditions with respect to the registrant's possession, use, and transfer of radiation machines subject to this chapter [ part ] as it deems appropriate or necessary in order to:

(A)

minimize danger to occupational and public health and safety;

(B)

require such reports and the keeping of such records, and to provide for such inspections of activities under the registration as may be appropriate or necessary; and

(C)

prevent loss or theft of radiation machines subject to this section.

(o)

[ (l) ] Specific terms and conditions of certificates of registration.

(1)

Each certificate of registration issued in accordance with this section shall be subject to the applicable provisions of the Act, now or hereafter in effect, and to the applicable rules [ requirements ] and orders of the agency.

(2)

No certificate of registration issued or granted under this section shall be transferred, assigned, or in any manner disposed of, either voluntarily or involuntarily, to any person unless the agency authorizes the transfer in writing.

(3)

Each person registered by the agency for radiation machine use in accordance with this section shall confine use and possession of the radiation machine registered to the locations and purposes authorized in the certificate of registration.

(p)

[ (m) ] Responsibilities of registrant.

(1)

The registrant shall notify the agency in writing of any changes that would render the information contained in the application for registration and/or the certificate of registration inaccurate.

(A)

Notification is required within 30 days of any change of radiation machine inventory. This includes installation or removal and the disposition of any machine disposed of or transferred. The assembler's notification of installation may be accepted in lieu of notification by the registrant with the exception of mammographic x-ray units. This does not relieve the registrant of the responsibility to assure that proper notification has been made.

(B)

Notification is required within 30 days of the following changes:

(i)

name and mailing address;

(ii)

street address where machine [ machine(s) ] will be used;

(iii)

RSO [ radiation safety officer ];

(iv)

type of servicing and/or services provided; or

(v)

name of facility contracted for "provider of equipment."

(C)

Notification is required prior to any changes that would render the information contained in the application or the certification of mammography systems inaccurate.

(2)

The following criteria applies to radiation machines used for clinical trial evaluations and loaner or demonstration radiation machines. [ units and units used for clinical trial evaluations. ]

(A)

Radiation machines used for clinical trial evaluations and loaner or demonstration radiation machines [ units ] may be used for up to 60 days without adding the radiation machine [ unit ] to an existing certificate of registration. [ The facility is required to notify the agency in writing of the period of use. ] If the use period will exceed 60 days, the facility will be required to add the radiation machine [ unit ] to their certificate of registration and a fee will be assessed. Radiation machines shall be registered in accordance with subsection (f)(1) of this section.

[ (B)

Facilities who do not have existing certificates of registration may not evaluate radiation machines unless an application for a certificate of registration has been submitted to the agency along with the appropriate fees prior to beginning use of the unit ].

(B)

No fees will be assessed for the operation of radiation machines for clinical trial evaluations or loaner or demonstration radiation machines used for a period of 60 days or less at a facility with a current certificate of registration.

[ (C)

No fees will be assessed for the operation of loaner units or evaluation periods of 60 days or less unless the loaner units or evaluation periods are in a facility described in subparagraph (B) of this paragraph. ]

(3)

No registrant shall engage any person for services described in subsection (g) [ (e) ] of this section until such person provides evidence of registration with the agency.

(4)

Records of training and experience required by this section shall be maintained for review until disposal is authorized by the agency.

(5)

The following applies to voluntary or involuntary petitions for bankruptcy.

(A)

Each registrant shall notify the agency, in writing, immediately following the filing of a voluntary or involuntary petition for bankruptcy. This notification must include:

(i)

the bankruptcy court in which the petition for bankruptcy was filed; and

(ii)

the date of the filing of the petition.

(B)

A copy of the "petition for bankruptcy" shall be submitted to the agency along with the written notification.

[ (A)

Each registrant shall notify the agency, in writing, immediately following the filing of a voluntary or involuntary petition for bankruptcy under any Chapters of Title 11 (Bankruptcy) of the United States Code (11 USC) by or against: ]

[ (i)

a registrant; ]

[ (ii)

an entity (as that term is defined in 11 U.S.C. 101(14)) controlling a registrant or listing the certificate of registration or registrant as property of the estate; or ]

[ (iii)

an affiliate (as that term is defined in 11 U.S.C. 101(2)) of the registrant. ]

[ (B)

This notification must include: ]

[ (i)

the bankruptcy court in which the petition for bankruptcy was filed; and ]

[ (ii)

the date of the filing of the petition. ]

[ (C)

A copy of the "petition for bankruptcy" shall be submitted to the agency along with the written notification. ]

(6)

The registrant is responsible for complying with this chapter and the conditions of the certificate of registration.

(7)

No person shall use radiation machines or perform services that are not authorized in the certificate of registration issued by the agency.

(8)

Assembler [ and/or transferor ] obligations are as follows.

(A)

No person shall transfer a radiation machine to or install for, other than initial installation of the first machine on the premises, any person who does not possess a current certificate of registration issued by the agency in accordance with this section.

(B)

Any person who sells, leases, lends, disposes, assembles, installs, or otherwise transfers radiation machines in the state shall notify the agency of the following information within 30 [ 15 ] days of such action:

(i)

the name, address, and certificate of registration number, except in the case of initial machine installation, of persons who have received such machines;

(ii)

the type of radiation machine, the manufacturer's name [ manufacturer ], model number , and control panel serial number of each radiation machine; and

(iii)

the date of transfer or disposal of each radiation machine.

(C)

In the case of diagnostic x-ray systems that contain certified components, a copy of the assembler's report on United States Food and Drug Administration (FDA) form 2579, prepared in compliance with requirements of the federal diagnostic x-ray standard [ standards ] ( Title 21 , CFR , § 1020.30(d)), shall be submitted to the agency within 15 days following completion of the assembly. Such report shall suffice in lieu of any other assembly report submitted by the assembler to the agency.

(D)

No person shall make, sell, lease, transfer, lend, assemble, or install radiation machines or the components of such machines unless such machines and equipment, when properly placed in operation and used, meet the applicable requirements of this chapter.

(9)

Providers of equipment shall keep a log of radiation machines provided in Texas. The record shall be maintained for inspection by the agency and shall list the following current information:

(A)

date machine is provided; and

(B)

name of customer and customer's certificate of registration number.

(q)

Sale, lease, loan, installation, assembly, disposal, and transfer of radiation machines.

(1)

No person shall transfer a radiation machine to or install for, other than initial installation of the first machine on the premises, any person who does not possess a current certificate of registration issued by the agency in accordance with this section.

(2)

Any person who sells, leases, lends, disposes, assembles, installs, or otherwise transfers radiation machines in the state shall notify the agency of the following information within 30 days of such action:

(A)

the name, address, and certificate of registration number, except in the case of initial machine installation, of persons who have received such machines;

(B)

the type of radiation machine, the manufacturer's name, model number, and control panel serial number of each radiation machine; and

(C)

the date of transfer or disposal of each radiation machine.

(3)

No person shall make, sell, lease, transfer, lend, assemble, or install radiation machines or the components of such machines unless such machines and equipment, when properly placed in operation and used, meet the applicable requirements of this chapter.

(r)

[ (n) ] Expiration of certificates of registration.

(1)

Except as provided by subsection (t) [ (p) ] of this section, each certificate of registration that specifies an expiration date expires at the end of the day on that date. Expiration of the certificate of registration does not relieve the registrant of the requirements of this chapter.

(2)

If a registrant does not submit an application for renewal of the certificate of registration under subsection (t) [ (p) ] of this section, as applicable, the registrant shall on or before the expiration date specified in the certificate of registration:

(A)

terminate use of all radiation machines and/or terminate radiation machine servicing or radiation services;

(B)

submit a record of the disposition of the radiation machines; [ x-ray units; ] and

(C)

pay any outstanding fees in accordance with §289.204 of this title.

(s)

[ (o) ] Termination of certificates of registration. When a registrant decides to terminate all activities involving radiation machines or services authorized under the certificate of registration, the registrant shall notify the agency immediately and do the following :

(1)

request termination of the certificate of registration in writing;

(2)

submit a record of the disposition of the radiation machines; [ x-ray units; ] and

(3)

pay any outstanding fees in accordance with §289.204 of this title.

(t)

[ (p) ] Renewal of certificate of registration.

(1)

Application for renewal of registration shall be filed in accordance with subsection (e)(1)-(5) [ (c)(1)-(5) ] of this section, [ and ] applicable paragraphs of subsections (f)-(h) and (k)-(m) [ (d)-(f) ] of this section [ and subsections (h)-(j) of this section ], and §289.230(f) of this title , as applicable.

(2)

If a registrant files an application in proper form before the existing certificate of registration expires, such existing certificate of registration shall not expire until the application status has been determined by the agency.

(u)

[ (q) ] Modification and revocation of certificates of registration.

(1)

The terms and conditions of all certificates of registration shall be subject to amendment, revision, or modification. A certificate of registration may be suspended or revoked by reason of amendments to the Act, or by reason of rules in this chapter and orders issued by the agency.

(2)

Any certificate of registration may be revoked, suspended, or modified, in whole or in part, for any of the following:

(A)

any material false statement in the application or any statement of fact required under provisions of the Act;

(B)

conditions revealed by such application or statement of fact or any report, record, or inspection, or other means that would warrant the agency to refuse to grant a certificate of registration on an original application; or

(C)

violation of, or failure to observe any of the terms and conditions of the Act, this chapter, or of the certificate of registration, or order of the agency.

(3)

Each certificate of registration revoked by the agency ends at the end of the day on the date of the agency's final determination to revoke the certificate of registration, or on the revocation date stated in the determination, or as otherwise provided by the agency order.

(4)

[ (3) ] Except in cases of willfulness or those in which the occupational and public health, interest or safety requires otherwise, no certificate of registration shall be modified, suspended, or revoked unless, prior to the institution of proceedings therefore, facts or conduct that may warrant such action shall have been called to the attention of the registrant in writing and the registrant shall have been afforded an opportunity to demonstrate or achieve compliance with all lawful requirements.

(v)

[ (r) ] Reciprocal recognition of out-of-state certificates of registration.

(1)

Whenever any radiation machine is to be brought into the state for any temporary use, the person proposing to bring such machine into the state shall file written notice with the agency at least three working days before such machine is to be used in the state. The notice shall include:

(A)

the number and type of radiation machine; [ the number(s) and type(s) of radiation machine(s); ]

(B)

the nature, start date, duration, and scope of use;

(C)

the exact location where the radiation machine is to be used; [ the exact location(s) where the radiation machine(s) is(are) to be used; ]

(D)

the name [ name(s) ] of the Texas licensed practitioner [ practitioner(s) ] if the machines are used to irradiate human beings;

(E)

a copy of the person's operating and safety procedures; and

(F)

the name and address where the machine user can be reached while in the state. [ the name(s) and address(es) where the machine user(s) can be reached while in the state. ]

(2)

If, for a specific case, the three-day period would impose an undue hardship on the person, he/she may, at the determination of the agency, obtain permission to proceed sooner.

(3)

The out-of-state person shall provide a copy of their certificate of registration or equivalent document. If the state from which the machine is [ machines are ] proposed to be brought does not issue certificates of registration or equivalent documents, a certificate of registration shall [ must ] be obtained from the agency in accordance with the provisions of this section.

(4)

In addition, the out-of-state person shall:

(A)

submit an annual fee as specified in §289.204(e) [ §289.204(e)(7) ] of this title;

(B)

comply with all applicable requirements of the agency; and

(C)

supply the agency with such other information as the agency may reasonably request.

(5)

The agency may withdraw, limit, or qualify its acceptance of any certificate of registration or equivalent document issued by another agency upon determining that such action is necessary in order to prevent undue hazard to public health and safety or property.

(6)

Whenever radiation services are to be provided by a person from out-of-state for any temporary use, that person shall apply for and receive a certificate of registration from the agency before providing services. The application shall be filed in accordance with subsections (e), (g)-(h), and (k)-(m) of this section, [ subsection (c) of this section and subsections (e)-(f) of this section and subsections (i)-(j) of this section ] as applicable.

(w)

[ (s) ] Appendices.

(1)

Requirements for RSOs for registrants.

(A)

All RSOs shall meet the following general requirements in addition to requirements in specific categories , except for industrial radiography RSOs:

(i)

educational courses related to ionizing radiation safety or a radiation safety officer course;

(ii)

experience in the use and familiarity of the type of equipment used; and

(iii)

knowledge of potential radiation hazards or emergency precautions.

(B)

Specific requirements for RSOs by facility are as follows . [ : ]

(i)

Healing [ healing ] arts facilities shall have:

(I)

licensed practitioner RSOs with documentation of licensing board number; or

(II)

non-practitioner RSOs with the following:

(-a-)

evidence of a valid general certificate issued under the Medical Radiologic Technologist Certification Act, Texas Civil Statutes, Article 4512m, and at least two years of supervised use of radiation machines;

(-b-)

evidence of a valid limited general certificate issued under the Medical Radiologic Technologist Certification Act, Texas Civil Statutes, Article 4512m, and at least four years of supervised use of radiation machines;

(-c-)

evidence of registry by the American Registry of Radiologic Technologists (ARRT) or the American Registry of Clinical Radiologic Technologists (ARCRT) and at least two years of supervised use of radiation machines;

(-d-)

evidence of associate degree in radiologic technology, health physics, or nuclear technology, and at least two years of supervised use of radiation machines;

(-e-)

evidence of registration with the Board of Nurse Examiners as a Registered Nurse or a Registered Nurse with an extended scope of practice (Nurse Practitioner) performing radiologic procedures, and at least two years of supervised use of radiation machines in the respective practitioners' specialty;

(-f-)

evidence of registration with the Texas State Board of Physician Assistant Examiners, and at least two years of supervised use of radiation machines in the respective practitioners' specialty;

(-g-)

evidence of:

(-1-)

registration with the Texas State Board of Medical Examiners performing radiologic procedures under a physician's instruction and direction;

[ (-2-)

registration with the Texas State Board of Dental Examiners performing radiologic procedures under a dentist's instruction and direction or evidence of a valid certificate as a registered dental hygienist; ]

(-2-)

[ (-3-) ] registration with the Texas State Board of Chiropractic Examiners performing radiologic procedures under a chiropractor's instruction and direction; or

(-3-)

[ (-4-) ] registration with the Texas State Board of Podiatry Examiners performing radiologic procedures under a podiatrist's instruction and direction; and

(-4-)

[ (-5-) ] at least four years of supervised use of radiation machines in the respective practitioners' specialty;

(-h-)

for radiotherapy facilities, evidence of registry by the ARRT or ARCRT and at least four years of supervised experience in radiotherapy;

(-i-)

evidence of bachelor's (or higher) degree in a natural or physical science, health physics, radiological science, nuclear medicine, or nuclear engineering; or

(-j-)

evidence of a current Texas license under the Medical Physics Practice Act, Texas Civil Statutes, Article 4512n, in one or more of the following appropriate specialties:

(-1-)

medical health physics, diagnostic radiological physics, or medical nuclear physics for diagnostic x-ray facilities; or

(-2-)

medical health physics or therapeutic radiological physics for radiotherapy facilities.

(ii)

Veterinary facilities shall have:

(I)

veterinarian RSOs with documentation of veterinary license board number; or

(II)

non-veterinarian RSOs with two years minimum experience in the use of radiation machines in veterinary medicine under the supervision of a licensed veterinarian.

(iii)

Academic institutions and/or research and development facilities shall have RSOs who are faculty or staff members in radiation protection, radiation engineering, or related disciplines. (This individual may also serve as the RSO over the healing arts section of the facility . ) [ . ]

(iv)

Industrial radiography operations shall have RSOs who meet the requirements of §289.225(m)(4)(B) of this title. [ 31.23 of TRCR Part 31 as adopted by reference in §289.115 of this title. ]

(C)

Exemptions. The RSO identified on a certificate of registration issued before September 1, 1993, need not comply with the training requirements in this subsection.

(2)

Responsibilities of RSOs [ radiation safety officers for ] certificates of registration. Specific duties of the RSO include, but are not limited to, the following:

(A)

establishing and overseeing operating and safety procedures that maintain radiation exposures as low as reasonably achievable (ALARA), and to review them regularly to ensure that the procedures are current and conform with this chapter;

(B)

ensuring that individual [ personnel ] monitoring devices are properly used by occupationally-exposed personnel, that records are kept of the monitoring results, and that timely notifications are made as required by §289.203 [ §289.114 ] of this title;

(C)

investigating and reporting to the agency each known or suspected case of radiation exposure to an individual or radiation level detected in excess of limits established by this chapter and each theft or loss of source(s) of radiation, determining the cause, and taking steps to prevent its recurrence;

(D)

having a thorough knowledge of management policies and administrative procedures of the registrant and keeping management informed on a periodic basis of the performance of the registrant's radiation protection program , if applicable ;

(E)

assuming control and having the authority to institute corrective actions including shut-down of operations when necessary in emergency situations or unsafe conditions;

(F)

maintaining records as required by this chapter;

(G)

ensuring that personnel are adequately trained and complying with this chapter, the conditions of the certificate of registration, and the operating and safety procedures of the registrant.

(3)

Minimum education and training for persons performing radiation machine assembly, installation or [ maintenance, and ] repair. All persons performing radiation machine assembly, installation or [ maintenance, and ] repair shall meet the general requirements in subparagraph (A) of this paragraph and one or more of the specialized requirements in subparagraph (B) of this paragraph.

(A)

General requirements include:

(i)

experience or education providing familiarity with the type(s) of equipment to be serviced to include radiation safety;

(ii)

knowledge of protective measures to reduce potentially hazardous conditions; and

(iii)

six months of supervised assembly and repair of the type(s) of equipment to be serviced.

(B)

Specialized requirements include:

(i)

one year of formal training (may be satisfied by factory school, military technical training school, or other courses in radiation machine assembly, installation or [ maintenance, and ] repair techniques) or an associate's degree in biomedical equipment repair;

(ii)

a bachelor's degree in electrical engineering with specialized training in radiation producing devices; or

(iii)

a combination of training and experience equal to clause (i) of this subparagraph.

(C)

Exemptions. A registrant holding a valid certificate of registration who has hired individuals to perform services before September 1, 1993, need not comply with the education and training requirements in this paragraph. Individuals hired after September 1, 1993, must comply with the education and training requirements in this paragraph.

(4)

Information to be submitted by persons proposing to conduct healing arts screening. Persons requesting that the agency approve a healing arts screening program shall submit the following information and evaluation.

(A)

Administrative controls to include the following:

(i)

the name and address of the applicant and, where applicable, the names and addresses of agents within Texas;

(ii)

the diseases or conditions for which the x-ray examinations are to be used in diagnoses;

(iii)

a detailed description of the x-ray examinations proposed in the screening program;

(iv)

a description of the population to be examined in the screening program, for example, age, sex, physical condition, and other appropriate information; and

(v)

an evaluation of any known alternate methods not involving ionizing radiation that could achieve the goals of the screening program and why these methods are not used instead of the x-ray examination.

(B)

Operating procedures for all x-ray systems (except bone densitometers) to include the following:

(i)

an evaluation of the x-ray systems to be used in the screening program. The evaluation shall be performed by a licensed medical physicist with a specialty in diagnostic radiological physics. The evaluation shall show that such systems do satisfy all requirements of this section;

(ii)

a description of the diagnostic film quality control program; and

(iii)

a copy of the technique chart for the x-ray examination procedures to be used.

(C)

Operating procedures for bone densitometers to include the manufacturer's evaluation of the system to be used in the screening program. The evaluation shall show that such systems satisfy all requirements of this section.

(D)

Training data to include the following:

(i)

the qualifications of each individual who will be operating the x-ray systems;

(ii)

the qualifications of the individual who will be supervising the operators of the x-ray systems. The extent of supervision and the method of work performance evaluation shall be specified; and

(iii)

the name and address of the practitioner who will interpret the radiographs.

(E)

Records to include the following:

(i)

a description of the procedures to be used in advising the individuals screened, and their private practitioners of the healing arts, of the results of the screening procedure and any further medical needs indicated; and

(ii)

a description of the procedures for the retention or disposition of the radiographs and other records pertaining to the x-ray examinations.

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003595

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


25 TAC §289.227

The Texas Department of Health (department) proposes the repeal of §289.227 and new §289.227, concerning the use of radiation machines in the healing arts and veterinary medicine.

The proposed section deletes the requirements for therapeutic radiation machines, simulators, and therapy misadministrations. These requirements are incorporated in a separate section, §289.229 (concerning Radiation Safety Requirements for Accelerators, Therapeutic Radiation Machines, and Simulators). In addition, the requirements for dental facilities are deleted and incorporated in a separate section, §289.232 (concerning Radiation Control Regulations for Dentists Using Radiation Machines). Requirements for calibration of equipment used to measure dose rate for fluoroscopy and computed tomography are updated. The proposed section will enable a registrant to calibrate the dosimetry system every two years instead of annually, with an intercomparison of the dosimetry system required in the year in which the calibration of the system is not traceable to a national standard. The remaining subsections of the rule are rearranged for clarity, references are updated, and clarifying language is added to the technical standards throughout the rule. The proposed new section is part of the department's continuing effort to update, clarify, and simplify its rules regarding the control of radiation based upon technological advances, public concerns, or other factors.

Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, has determined that for each year of the first five years the sections will be in effect, there will be no fiscal implications for state or local government as a result of enforcing or administering the sections as proposed.

Mrs. McBurney has also determined that for each year of the first five years the proposed sections will be in effect, the public benefit anticipated as a result of enforcing the sections will be to ensure that registrants comply with the use of radiation machines in the healing arts and veterinary medicine, ensuring the safety of workers and that the public is protected from unnecessary exposure to radiation. The updated calibration requirements will reduce the cost to calibrate dosimetry systems because the required interval for calibration is changed from annually to once every two years. Micro businesses, small businesses, and persons required to comply with the sections as proposed will have a savings every other year ranging from $550 to $700. There are no anticipated increased economic costs to micro businesses, small businesses, or persons who are required to comply with the sections as proposed. There is no anticipated impact on local employment.

Comments on the proposal may be submitted to Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, Texas Department of Health, 1100 West 49th Street, Austin, Texas 78756-3189, (512) 834-6688 or electronic mail at Ruth.Mcburney@tdh.state.tx.us. Public comments will be accepted for 30 days following publication of this proposal in the Texas Register . In addition, a public meeting to accept oral comments will be held at 2:00 p.m., Thursday, June 15, 2000, in Conference Room N218, Texas Department of Health, Bureau of Radiation Control, located at the Exchange Building, 8407 Wall Street, Austin, Texas.

(Editor's note: The text of the following section proposed for repeal will not be published. The section may be examined in the offices of the Texas Department of Health or in the Texas Register office, Room 245, James Earl Rudder Building, 1019 Brazos Street, Austin.)

The repeal is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with the authority to adopt rules for the performance of each duty imposed by law on the board, the department, and the commissioner of health.

The repeal affects Health and Safety Code, Chapter 401 and Chapter 12.

§289.227.Use of Radiation Machines in the Healing Arts and Veterinary Medicine.

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003517

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


The new section is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with the authority to adopt rules for the performance of each duty imposed by law on the board, the department, and the commissioner of health.

The new section affects Health and Safety Code, Chapter 401 and Chapter 12.

§289.227.Use of Radiation Machines in the Healing Arts and Veterinary Medicine.

(a)

Purpose. This section establishes requirements for the use of radiation machines in the healing arts and in veterinary medicine. All usage of such machines under this section shall be made by or under the supervision of a practitioner of the healing arts for human use or licensed veterinarian for veterinary use. The use of mammography radiation machines is exempt from this section and is covered in §289.230 of this title (relating to Certification of Mammography Systems and Accreditation of Mammography Facilities), with the exceptions listed in §289.230(e)(1) and (2) of this title. The use of dental radiation machines is exempt from this section and is covered in §289.232 of this title (relating to Radiation Control Regulations for Dentists Using Radiation Machines).

(b)

Scope.

(1)

The registrant shall be responsible for directing the operation of the radiation machines under the administrative control of the registrant. The registrant shall assure that the requirements of this section are met in the operation of such radiation machines.

(2)

In addition to the requirements of this section, all registrants, unless otherwise specified, are subject to the requirements of §289.203 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections), §289.204 of this title (relating to Fees for Certificates of Registration, Radioactive Material Licenses, Emergency Planning and Implementation, and Other Regulatory Services), §289.205 of this title (relating to Hearing and Enforcement Procedures), §289.226 of this title (relating to Registration of Radiation Machine Use and Services), and §289.231 of this title (relating to General Provisions and Standards for Protection Against Machine Produced Radiation).

(c)

Prohibitions.

(1)

The agency may prohibit use of radiation machines that pose significant threat or endanger occupational and public health and safety, in accordance with §289.205 of this title and §289.231 of this title.

(2)

Individuals shall not be exposed to the useful beam except for healing arts purposes and unless such exposure has been authorized by a licensed practitioner of the healing arts. This provision specifically prohibits deliberate exposure for the following purposes:

(A)

exposure of an individual for training, demonstration, or other non-healing arts purposes;

(B)

exposure of an individual for the purpose of healing arts screening, except as authorized by §289.226(j)(1) of this title; and

(C)

exposure of an individual for the purpose of research, except as authorized by §289.226(j)(2) of this title.

(3)

Non-image-intensified fluoroscopic equipment shall not be used.

(d)

Exemptions.

(1)

Portable radiation machines designed to be hand-held are exempt from the requirements of subsection (i)(11) of this section. The portable radiation machine must be held by the tube housing support or handle.

(2)

Veterinary facilities are exempt from the aural communication requirements for computed tomography (CT) in subsection (p)(2)(A) of this section.

(3)

Individuals who are sole practitioners and sole operators and the only occupationally exposed individual are exempt from the following requirements:

(A)

§289.203(b) of this title; and

(B)

operating and safety procedures in accordance with subsection (i)(2) of this section.

(4)

Registrants are exempt from the posting of the radiation area requirements in §289.231(x)(1) of this title provided that the operator has continuous surveillance and access control of the radiation area.

(e)

Definitions. The following words and terms when used in this section shall have the following meaning unless the context clearly indicates otherwise.

(1)

Accessible surface - The external surface of the enclosure or housing provided by the manufacturer.

(2)

Aluminum equivalent - The thickness of type 1100 aluminum alloy affording the same attenuation, under specified conditions, as the material in question. The nominal chemical composition of type 1100 aluminum alloy is 99% minimum aluminum, 0.12% copper.

(3)

Attenuate -To reduce the exposure rate upon passage of radiation through matter.

(4)

Attenuation block - A block or stack, having dimensions 20 centimeters (cm) by 20 cm by 3.8 cm, of type 1100 aluminum alloy or other materials having equivalent attenuation. The nominal chemical composition of type 1100 aluminum alloy is 99% minimum aluminum, 0.12% copper.

(5)

Automatic exposure control (AEC) - A device that automatically controls one or more technique factors in order to obtain a required quantity of radiation at preselected locations (See definition for phototimer).

(6)

Automatic exposure rate control (AERC) - A device that automatically controls one or more technique factors in order to obtain a required quantity of radiation per unit time at preselected locations.

(7)

Barrier (See definition for protective barrier).

(8)

Beam axis - A line from the source through the centers of the x-ray fields.

(9)

Beam-limiting device - A device that provides a means to restrict the dimensions of the x-ray field.

(10)

Beam quality (diagnostic x-ray) - A term that describes the penetrating power of the x-ray beam. This is identified numerically by half-value layer and is influenced by kilovolt peak (kVp) and filtration.

(11)

Bone densitometer - A device intended for medical purposes to measure bone density and mineral content by x-ray transmission measurements through the bone and adjacent tissues.

(12)

Calibration of instruments - The comparative response or reading of an instrument relative to a series of known radiation values over the range of the instrument.

(13)

Calibration of machines - The measurement and specification of absorbed dose to a medium, or exposure in air, at a defined point in a radiation beam.

(14)

Central axis of the beam - A line passing through the virtual source and the center of the plane figure formed by the edge of the first beam-limiting device.

(15)

Certified equipment - Equipment that has been certified in accordance with Title 21, Code of Federal Regulations (CFR).

(16)

Coefficient of variation or C - The ratio of the standard deviation to the mean value of a population of observations. It is estimated using the following equation:

Figure: 25 TAC §289.227(e)(16)

(17)

Collimator - A device or mechanism by which the x-ray beam is restricted in size.

(18)

Computed tomography (CT) - The production of a tomogram by the acquisition and computer processing of x-ray transmission data.

(19)

Continuous pressure type switch - A switch so constructed that a circuit closing contact can be maintained only by continuous pressure on the switch by the operator.

(20)

Contrast scale (CS) - The change in the linear attenuation coefficient per CT number (CTN) relative to water; that is:

Figure: 25 TAC §289.227(e)(20)

(21)

Control panel - The part of the radiation machine control upon which are mounted the switches, knobs, push buttons, and other hardware necessary for manually setting the technique factors.

(22)

CT conditions of operation - All selectable parameters governing the operation of a CT x-ray system including, but not limited to, nominal tomographic section thickness, filtration, and the technique factors as defined in this subsection.

(23)

CT gantry - The tube housing assemblies, beam-limiting devices, detectors, and the supporting structures and frames that hold these components.

(24)

CT number (CTN) - The number used to represent the x-ray attenuation associated with each elemental area of the CT image, that is:

Figure: 25 TAC §289.227(e)(24)

(25)

Diagnostic source assembly - The tube housing assembly with a beam-limiting device attached.

(26)

Diagnostic x-ray system - An x-ray system designed for irradiation of any part of the human body or any animal for the purpose of diagnosis or visualization.

(27)

Diaphragm - A device or mechanism by which the x-ray beam is restricted in size.

(28)

Entrance exposure - The exposure expressed in roentgens (R), measured in air with the specified technique, calculated or adjusted to represent the exposure at the point where the center of the useful beam enters the patient.

(29)

Entrance exposure rate - The exposure per unit time at the point where the center of the useful beam enters the patient.

(30)

Field emission equipment - Equipment that uses an x-ray tube in which electron emission from the cathode is due solely to the action of an electric field.

(31)

Field size - The dimensions along the major axes of an area in a plane perpendicular to the central axis of the beam at the normal treatment or examination source to image distance and defined by the intersection of the major axes and the 50% isodose line.

(32)

Filter - Material placed in the useful beam to preferentially absorb selected radiations.

(33)

Fluoroscopic imaging assembly - A subsystem in which x-ray photons produce a fluoroscopic image. It includes the image receptors such as the image intensifier and spot-film device, electrical interlocks, if any, and structural material providing linkage between the image receptor and diagnostic source assembly.

(34)

Focal spot - The area projected on the anode of the x-ray tube bombarded by the electrons accelerated from the cathode and from which the useful beam originates.

(35)

Gantry - That part of the system supporting and allowing possible movement of the radiation source.

(36)

General purpose x-ray system - Any radiographic x-ray system that is not limited by design to radiographic examinations of specific anatomical regions.

(37)

Gonadal shield - A protective barrier for the testes or ovaries.

(38)

Half-value layer (HVL) - The thickness of a specified material that attenuates the beam of radiation to an extent such that the exposure rate is reduced to one-half of its original value.

(39)

Healing art - Any system, treatment, operation, diagnosis, prescription, or practice for the ascertainment, cure, relief, palliation, adjustment, or correction of any human disease, ailment, deformity, injury, or unhealthy or abnormal physical or mental condition.

(40)

Healing arts screening - The testing of asymptomatic human beings using radiation machines for the detection or evaluation of health indications when such tests are not specifically and individually ordered by a licensed practitioner of the healing arts legally authorized to prescribe such x-ray tests for the purpose of diagnosis or treatment.

(41)

High level control for fluoroscopy - Any selected mode having an entrance exposure rate above 10 roentgens per minute (R/min). This mode must meet the high level requirements in subsection (o)(3)(A)(i)(II), (ii)(II), or (iii)(II) of this section.

(42)

Image intensifier - A device, installed in its housing, that instantaneously converts an x-ray pattern into a corresponding light image of higher energy density.

(43)

Image receptor - Any device, such as a fluorescent screen or radiographic film, that transforms incident x-ray photons either into a visible image or into another form that can be made into a visible image by further transformations.

(44)

Irradiation - The exposure of matter to ionizing radiation.

(45)

kV - Kilovolt.

(46)

kVp - Kilovolt peak (See definition for peak tube potential).

(47)

kWs - Kilowatt-second. It is equivalent to 10 E 3 watt-second, where 1 watt-second =1 kV x 1milliampere (mA) x 1 second.

(48)

Lead equivalent - The thickness of lead affording the same attenuation, under specified conditions, as the material in question.

(49)

Leakage radiation - Radiation emanating from the diagnostic or therapeutic source assembly except for the useful beam and radiation produced when the exposure switch or timer is not activated.

(50)

Leakage technique factors - The technique factors associated with the diagnostic source assembly that are used in measuring leakage radiation. They are defined as follows:

(A)

for diagnostic source assemblies intended for capacitor energy storage equipment, the maximum-rated peak tube potential and the maximum-rated number of exposures in an hour for operation at the maximum-rated peak tube potential with the quantity of charge per exposure being 10 millicoulombs (10 milliampere-second (mAs)) or the minimum obtainable from the unit, whichever is larger;

(B)

for diagnostic source assemblies intended for field emission equipment rated for pulsed operation, the maximum-rated peak tube potential and the maximum-rated number of x-ray pulses in an hour for operation at the maximum-rated peak tube potential; or

(C)

for all other diagnostic source assemblies, the maximum-rated peak tube potential and the continuous tube current for the maximum-rated peak tube potential.

(51)

Licensed medical physicist - An individual holding a current Texas license under the Medical Physics Practice Act, Texas Civil Statutes, Article 4512n.

(52)

Linear attenuation coefficient (u) - The quotient of dN/N by dl when dN/N is the fraction of uncharged ionizing radiation that experiences interactions in traversing a distance dl in a specified material.

(53)

mA - Milliampere.

(54)

mAs - Milliampere-second.

(55)

Medical research - The investigation of various health risks and diseases using radiation machines as part of the evaluation process.

(56)

Mobile services - The utilization of radiation machines in temporary locations for limited time periods. The radiation machines may be fixed inside a mobile van or transported to temporary locations.

(57)

Mobile x-ray equipment - (See definition for x-ray equipment).

(58)

Multiple tomogram system - A computed tomography x-ray system that obtains x-ray transmission data simultaneously during a single scan to produce more than one tomogram.

(59)

Nominal tomographic section thickness - The full-width at half-maximum of the sensitivity profile taken at the center of the cross sectional volume over which x-ray transmission data are collected.

(60)

Non-certified equipment - Equipment manufactured and assembled prior to certification requirements of Title 21, CFR, effective as specified in Title 21, CFR, Part 1020.30(a).

(61)

Patient - An individual subjected to healing arts examination, diagnosis, or treatment.

(62)

Peak tube potential - The maximum value of the potential difference in kilovolts across the x-ray tube during an exposure.

(63)

Phantom - A volume of material behaving in a manner that can be related to tissue with respect to the attenuation and scattering of radiation.

(64)

Phototimer - A method for controlling exposures to image receptors by the amount of radiation that reaches a radiation monitoring device. The radiation monitoring device is part of an electronic circuit that controls the duration of time the tube is activated (See definition for automatic exposure control).

(65)

Portable x-ray equipment (See definition for x-ray equipment).

(66)

Practitioner of the healing arts (practitioner) - A person licensed to practice healing arts by either the Texas State Board of Medical Examiners as a physician, the Texas Board of Chiropractic Examiners, or the Texas State Board of Podiatry Examiners.

(67)

Primary protective barrier - (See definition for protective barrier).

(68)

Protective apron - An apron made of radiation absorbing materials used to reduce radiation exposure.

(69)

Protective barrier - A barrier of radiation absorbing materials used to reduce radiation exposure. The types of protective barriers are as follows:

(A)

primary protective barrier -A barrier sufficient to attenuate the useful beam to the required degree.

(B)

secondary protective barrier - A barrier sufficient to attenuate the stray radiation to the required degree.

(70)

Protective glove - A glove made of radiation absorbing materials used to reduce radiation exposure.

(71)

Radiograph - An image receptor on which the image is created directly or indirectly by an x-ray exposure and results in a permanent record.

(72)

Reference plane - A plane that is displaced from and parallel to the tomographic plane.

(73)

Scan - The complete process of collecting x-ray transmission data for the production of a tomogram. Data can be collected simultaneously during a single scan for the production of one or more tomograms.

(74)

Scan increment - The amount of relative displacement of the patient with respect to the CT x-ray system between successive scans measured along the direction of such displacement.

(75)

Scan sequence - A preselected set of two or more scans performed consecutively under preselected CT conditions of operation.

(76)

Scan time - The period of time between the beginning and end of x-ray transmission data accumulation for a single scan.

(77)

Scattered radiation - radiation that has been deviated in direction during passage through matter.

(78)

Secondary protective barrier (See definition for protective barrier).

(79)

Shutter - A device attached to the tube housing assembly that can totally intercept the useful beam and that has a lead equivalency not less than that of the tube housing assembly.

(80)

Single tomogram system - CT x-ray system that obtains x-ray transmission data during a scan to produce a single tomogram .

(81)

Source - The focal spot of the x-ray tube.

(82)

Source-to-image receptor distance (SID) - The distance from the source to the center of the input surface of the image receptor.

(83)

Source-to-skin distance (SSD) - The distance from the source to the skin of the patient.

(84)

Spacer - A device designed to limit the target to skin distance.

(85)

Special purpose x-ray system - Any radiographic x-ray system that is limited by design to radiographic examinations of specific anatomical regions. Special purpose x-ray systems include, but are not limited to, dedicated chest units, cystography units, and head and skull units.

(86)

Special procedures - The application of special x-ray equipment and specialized techniques to obtain required diagnostic information. This usually provides enhanced detail of a given anatomical structure but with reduced visualization of others. Special procedures include, but are not limited to, angiography, cardiac catheterization, myelogram, and surgery.

(87)

Spot film - A radiograph that is made during a fluoroscopic examination to permanently record conditions that exist during that fluoroscopic procedure.

(88)

Spot film device - A device intended to transport and/or position a radiographic image receptor between the x-ray source and fluoroscopic image receptor. It includes a device intended to hold a cassette over the input end of an image intensifier for the purpose of making a radiograph.

(89)

Stationary x-ray equipment - (See definition for x-ray equipment).

(90)

Stray radiation - The sum of leakage and scattered radiation.

(91)

Supervision - The delegating of the task of applying radiation in accordance with this section to persons not licensed in the healing arts or veterinary medicine, who provide services under the practitioner's control. The licensed practitioner or veterinarian assumes full responsibility for these tasks and must assure that the tasks will be administered correctly.

(92)

Target - The part of a radiation head that by design intercepts a beam of accelerated particles with subsequent emission of other radiation.

(93)

Technique chart - A chart that provides all necessary generator control settings and geometry needed to make clinical radiographs when the radiography system is in manual mode.

(94)

Technique factors - The conditions of operation that are specified as follows:

(A)

for capacitor energy storage equipment, peak tube potential in kV and quantity of charge in mAs;

(B)

for field emission equipment rated for pulsed operation, peak tube potential in kV and number of x-ray pulses;

(C)

for CT equipment designed for pulsed operations, peak tube potential in kV, scan time in seconds, and either tube current in mA, x-ray pulse width in seconds, and the number of x-ray pulses per scan or the product of tube current, x-ray pulse width, and the number of x-ray pulses in mAs;

(D)

for CT equipment not designed for pulsed operation, peak tube potential in kV, and either tube current in mA and scan time in seconds or the product of tube current and exposure time in mAs when the scan time and exposure time are equivalent; and

(E)

for all other equipment, peak tube potential in kV and either tube current in mA and exposure time in seconds or the product of tube current and exposure time in mAs.

(95)

Tomogram - The depiction of the x-ray attenuation properties of a section through the body.

(96)

Tomographic plane - The geometric plane that is identified as corresponding to the output.

(97)

Tomographic section - The volume of an object whose x-ray attenuation properties are imaged in a tomogram.

(98)

Traceable to a national standard - This indicates that a quantity or a measurement has been compared to a national standard, for example, the National Institute of Standards and Technology, directly or indirectly through one or more intermediate steps and that all comparisons have been documented.

(99)

Tube - An x-ray tube, unless otherwise specified.

(100)

Tube housing assembly - The tube housing with tube installed. It includes high-voltage and/or filament transformers and other appropriate elements when such are contained within the tube housing.

(101)

Useful beam - Radiation that passes through the window, aperture, cone, or other collimating device of the source housing. Also referred to as the primary beam.

(102)

Veterinarian - An individual licensed by the Texas Board of Veterinary Medical Examiners.

(103)

X-ray control - A device that controls input power to the x-ray high-voltage generator and/or the x-ray tube. It includes equipment such as timers, phototimers, automatic brightness stabilizers, and similar devices that control the technique factors of an x-ray exposure.

(104)

X-ray equipment - An x-ray system, subsystem, or component thereof. Types of x-ray equipment are as follows:

(A)

mobile x-ray equipment - x-ray equipment mounted on a permanent base with wheels and/or casters for moving while completely assembled;

(B)

portable x-ray equipment - x-ray equipment designed to be hand-carried; or

(C)

stationary x-ray equipment - x-ray equipment that is installed in a fixed location.

(105)

X-ray field - That area of the intersection of the useful beam and any one of the set of planes parallel to and including the plane of the image receptor, whose perimeter is the locus of points at which the exposure rate is one-fourth of the maximum in the intersection.

(106)

X-ray high-voltage generator - A device that transforms electrical energy from the potential supplied by the x-ray control to the tube operating potential. The device may also include means for transforming alternating current to direct current, filament transformers for the x-ray tubes, high-voltage switches, electrical protective devices, and other appropriate elements.

(107)

X-ray system - An assemblage of components for the controlled production of x rays. It includes minimally an x-ray high-voltage generator, an x-ray control, a tube housing assembly, a beam-limiting device, and the necessary supporting structures. Additional components that function with the system are considered integral parts of the system.

(108)

X-ray subsystem - Any combination of two or more components of an x-ray system.

(109)

X-ray tube - Any electron tube that is designed to be used primarily for the production of x rays.

(f)

Educational facilities. Facilities conducting training using non-humans shall comply with all the requirements of this section except for subsection (i)(5) of this section concerning operator credentialing, subsection (k) of this section concerning radiographic entrance exposure limits, subsections (r) and (s) of this section concerning film processing, and subsection (q) of this section concerning equipment performance evaluation.

(g)

Requirements for bone densitometers. Bone densitometers shall be exempt from this chapter except for the following:

(1)

§289.203 of this title, §289.204 of this title, §289.205 of this title, §289.231 of this title, and §289.226 of this title;

(2)

healing arts screening and medical research in accordance with §289.226(j) of this title;

(3)

purpose and scope in accordance with subsections (a) and (b) of this section;

(4)

prohibitions in accordance with subsection (c)(1) and (2) of this section;

(5)

exemptions in accordance with subsection (d)(1),(3), and (4) of this section;

(6)

definitions in accordance with subsection (e) of this section, as applicable;

(7)

operating and safety procedures in accordance with subsection (i)(2) of this section;

(8)

operator credentialing in accordance with subsection (i)(5) of this section;

(9)

gonadal shielding in accordance with subsection (j)(3) of this section;

(10)

warning labels in accordance with subsection (l)(1) of this section;

(11)

records in accordance with subsection (t) of this section;

(12)

record requirements for authorized use locations and authorized records locations for mobile services in accordance with subsection (t)(1)-(3) of this section; and

(13)

record requirements for mobile services in accordance with subsection (t)(3) of this section;

(h)

Certified equipment for chiropractic, medical, and podiatric facilities. This subsection does not apply to veterinary facilities. In addition to the requirements of this chapter, the registrant shall not make, nor cause to be made, any modification of components or installations of components certified in accordance with the United States Food and Drug Administration (FDA) Title 21, CFR, Part 1020, "Performance Standards for Ionizing Radiation Emitting Products," as amended, in any manner that could cause the installations or the components to fail to meet the requirements of the applicable parts of the standards specified in 21 CFR, Part 1020, except where a variance has been granted by the Director, Center for Devices and Radiological Health, FDA. A copy of the variance shall be maintained by the registrant in accordance with subsection (t)(1) of this section for inspection by the agency.

(i)

General requirements for chiropractic, medical, podiatric, and veterinary facilities.

(1)

Technique chart. A technique chart relevant to the particular radiation machine shall be provided or electronically displayed in the vicinity of the control panel and used by all operators.

(2)

Operating and safety procedures. Each registrant shall have and implement written operating and safety procedures. These procedures shall be made available to each individual operating a radiation machine, including any restrictions of the operating technique required for the safe operation of the particular x-ray system. These procedures shall include, but are not limited to, the items in subsection (u) of this section.

(3)

Occupational dose limits and personnel monitoring. Except as otherwise exempted, all individuals who are associated with the operation of a radiation machine are subject to the occupational dose limits of §289.231(m) of this title regarding dose limits to individuals, and the personnel monitoring requirements of §289.231(n) of this title.

(4)

Protective devices. Protective devices shall be utilized when required, as in subsection (i)(8)(B) and (D), (i)(10), and (o)(8) of this section.

(A)

Protective devices shall be made of no less than 0.25 millimeter (mm) lead equivalent material.

(B)

Protective devices, including aprons, gloves, and shields shall be checked annually for defects such as holes, cracks, and tears. These checks may be performed by the registrant by visual or tactile means, or x-ray imaging. If a defect is found, protective devices shall be replaced or removed from service until repaired. A record of this test shall be made and maintained by the registrant in accordance with subsection (t)(1) of this section for inspection by the agency.

(5)

Operator credentialing. Individuals who operate radiation machines shall meet the appropriate credentialing requirements of rules issued in accordance with the Medical Radiologic Technologist Act, Texas Civil Statutes, Article 4512m. Copies of the credentialing document shall be maintained at the locations(s) where the individual is working.

(6)

Practice of Medical Physics. Surveys, tests, or evaluations required by this section may constitute the practice of medical physics and, therefore, require a license from the Texas Board of Licensure for Professional Medical Physicists in accordance with the Medical Physics Practice Act, Texas Civil Statutes, Article 4512n.

(7)

Exposure of individuals other than the patient. No individual other than a patient, operator, and ancillary personnel shall be in the x-ray room or area while exposures are being made unless such individual's assistance is required.

(8)

Holding of patient or film (image receptor).

(A)

When a patient or film (image receptor) must be held in position during radiography, mechanical supporting or restraining devices shall be used when the exam permits.

(B)

If a patient or film (image receptor) must be held by an individual during an exposure, that individual shall be protected with appropriate shielding devices described in paragraph (4) of this subsection.

(C)

The registrant's written operating and safety procedures required by paragraph (2) of this subsection shall include the following:

(i)

a list of circumstances in which mechanical holding devices cannot be routinely utilized; and

(ii)

a procedure used for selecting an individual to hold or support the patient or film (image receptor).

(D)

In those cases where the patient must hold the film (image receptor), any portion of the body other than the area of clinical interest struck by the useful beam shall be protected by not less than 0.25 mm lead equivalent material.

(9)

Viewing system. Windows, mirrors, closed circuit television, or a method shall be provided to permit the operator to continuously observe the patient during irradiation.

(10)

Operator position. The operator position during the exposure shall be such that the operator's exposure is as low as reasonably achievable (ALARA) and the operator is a minimum of six feet from the source of radiation or protected by an apron, gloves, or other shielding having a minimum of 0.25 lead equivalent material.

(11)

Holding of tube. In no case shall an individual hold the tube or tube housing assembly supports during any radiographic exposure.

(j)

Requirements specifically for chiropractic, medical, and podiatric facilities.

(1)

Patient protection. Notwithstanding the provisions of subsection (i)(7) of this section, other patients who are in line with the primary beam and who cannot be removed from the room shall be protected by whole body protective barriers of a minimum of 0.25 mm lead equivalent material or so positioned that the nearest portion of their body is at least six feet from both the tube head and the nearest edge of the image receptor.

(2)

Contact with the patient. The operator shall be able to maintain verbal, visual, and aural contact with the patient.

(3)

Gonadal shielding. Gonadal shielding shall be used on patients when the gonads are in or within 5 cm of the useful beam. This requirement does not apply if the shielding will interfere with the diagnostic procedure. Gonadal shielding shall be of at least 0.5 mm lead equivalent material.

(k)

Radiographic entrance exposure limits for chiropractic, medical, and podiatric facilities. This subsection does not apply to veterinary facilities. The in-air exposure determined for the technique used for the specified average human adult patient thickness for routine medical radiography shall not exceed the entrance exposure limits in the following Table I.

Figure: 25 TAC §289.227(k)

(l)

General requirements for all diagnostic x-ray systems for chiropractic, medical, podiatric, and veterinary facilities.

(1)

Warning label. The warning label will meet the requirements of §289.231(z) of this title.

(2)

Mechanical support of tube head. The tube housing assembly shall be adjusted to remain stable during an exposure unless tube housing movement is a designed function of the x-ray system.

(3)

Battery charge indicator. On battery-powered x-ray generators, visual means shall be provided on the control panel to indicate whether the battery is in a state of charge adequate for proper operation.

(4)

Radiation from components other than the diagnostic source assembly. The radiation emitted by a component other than the diagnostic source assembly shall not exceed 2 milliroentgens (mR) in one hour at 5 cm from any accessible surface of the component when it is operated in an assembled x-ray system under any conditions for which it was designed. Measurement is averaged over an area of 100 square centimeters (cm 2 ) with no linear dimension greater than 20 cm.

(5)

Beam quality. The following requirements apply to beam quality.

(A)

Half-value layer.

(i)

The half-value layer of the useful beam for a given x-ray tube potential shall not be less than the values shown in the following Table II. If it is necessary to determine such half-value layer at an x-ray tube potential that is not listed in Table II, linear interpolation may be made.

Figure: 25 TAC §289.227(l)(5)(A)(i)

(ii)

For capacitor energy storage equipment, compliance with the requirements of paragraph (5) of this subsection shall be determined with the maximum quantity of charge per exposure.

(B)

Filtration controls.

(i)

For x-ray systems that have variable kVp and variable filtration for the useful beam, a device shall link the kVp selector with the filters and shall prevent an exposure unless the minimum amount of filtration required by subparagraph (A) of this paragraph is in the useful beam for the given kVp that has been selected.

(ii)

Any other system having removable filters shall be required to have the minimum amount of filtration as required by subparagraph (A)(i) of this paragraph permanently located in the useful beam during each exposure.

(6)

Multiple tubes. Where two or more radiographic tubes are controlled by one exposure switch, the tube or tubes that have been selected shall be clearly indicated prior to initiation of the exposure. This indication shall be both on the x-ray control panel and at or near the tube housing assembly that has been selected.

(7)

Technique and exposure indicators.

(A)

The technique factors to be used during an exposure shall be indicated before the exposure begins except when automatic exposure controls are used, in which case the technique factors that are set prior to the exposure shall be indicated.

(B)

On equipment having fixed technique factors, the requirement of subparagraph (A) of this paragraph may be met by permanent markings.

(C)

The x-ray control shall provide visual indication of the production of x rays.

(D)

The indicated technique factors shall be accurate to meet manufacturer's specifications. If these specifications are not available from the manufacturer, the factors shall be accurate to within plus or minus 10% of the indicated setting.

(m)

Additional requirements specifically for chiropractic, medical, and podiatric x-ray systems. This subsection does not apply to fluoroscopic, veterinary, or CT x-ray systems.

(1)

Beam limitation. Beam limitation shall be as follows.

(A)

Stationary general purpose x-ray systems.

(i)

Beam-limiting devices shall restrict the useful beam to the area of clinical interest as follows:

(I)

the misalignment of the x-ray field for a manual rectangular collimator shall be within 2.0% of the SID for the length or width of the image receptor;

(II)

the x-ray field for a circular or polygon collimator shall not exceed the diagonal of the image receptor by more than 2.0% of the SID; or

(III)

the misalignment of the x-ray field for an automatic or semi-automatic collimator shall be within 3.0% of the SID for the length and width of the image receptor and must be within 4.0% of the SID, without regard to the sign, of the sum of the difference of the length and width of the image receptor.

(ii)

A method shall be provided for visually defining the perimeter of the x-ray field. The total misalignment of the edges of the visually defined field with the respective edges, either the length or width, of the x-ray field shall not exceed 2.0% of the SID.

(iii)

An SID indicator shall be present and shall be accurate to within 2.0% of the SID.

(iv)

The system shall indicate when the axis of the x-ray field is perpendicular to the plane of the image receptor.

(v)

The center of the x-ray field, when perpendicular to the image receptor, shall be accurate to within 2.0% of the SID with respect to the center of the image receptor.

(vi)

The beam-limiting device shall numerically indicate the field size in the plane of the image receptor.

(vii)

Indication of field size dimensions and SIDs shall be specified in inches and/or centimeters.

(viii)

The field size indicated on the beam-limiting device shall be within 2.0% of the SID along the width and length, separately, of the actual x-ray field size.

(B)

Mobile x-ray systems. Mobile x-ray systems shall comply with the requirements in subparagraph (A)(i)-(iii) of this paragraph.

(C)

Radiographic systems designed for one image receptor size. Radiographic equipment designed for only one image receptor size at a fixed SID shall provide a means to do the following:

(i)

limit the x-ray field to no greater than the dimensions of the image receptor at the SID, and to align the center of the x-ray field with the center of the image receptor to within 2.0% of the SID center; or

(ii)

align the x-ray field such that the x-ray field does not extend beyond any edge of the image receptor at the SID.

(D)

Special purpose x-ray systems.

(i)

When the x-ray beam is perpendicular to the plane of the image receptor, a means shall be provided to do the following:

(I)

limit the x-ray field such that the x-ray field does not exceed each dimension of the image receptor by more than 2.0% of the SID; and

(II)

align the center of the x-ray field with the center of the image receptor to within 2.0% of the SID.

(ii)

The requirements of clause (i) of this subparagraph may be met with a system that meets the requirements for a general purpose x-ray system as specified in subparagraphs (A)(i)-(iv) of this paragraph or, when alignment means are also provided, may be met with either of the following:

(I)

an assortment of removable, fixed-aperture, beam-limiting devices sufficient to meet the requirement for each combination of image receptor size and SID for which the unit is designed with each such device having clear and permanent markings to indicate the image receptor size and SID for which it is designed; or

(II)

a beam-limiting device having multiple fixed apertures sufficient to meet the requirement for each combination of image receptor size and SID for which the radiation machine is designed. Permanent, clearly legible markings shall indicate the image receptor size and SID for which each aperture is designed and shall indicate which aperture is in position for use.

(2)

Radiation exposure control devices. Radiation exposure control devices shall include the following:

(A)

X-ray control. An x-ray control shall be incorporated into each x-ray system such that an exposure can be terminated by the operator at any time except for an exposure of 0.5 seconds or less or during serial radiography when means shall be provided to permit completion of any single exposure of the series in process. The exposure switch shall be of the continuous pressure type.

(B)

Timers. Means shall be provided to terminate the exposure at a preset time interval, a preset product of current and time, a preset number of pulses, or a preset radiation exposure to the image receptor. In addition it shall not be possible to make an exposure when the timer is set to a "zero" or "off" position if either position is provided.

(C)

AEC. When an AEC is provided, the following shall occur.

(i)

Indication shall be made on the control panel when this mode of operation is selected.

(ii)

If the x-ray tube potential is equal to or greater than 50 kVp, the minimum exposure time for field emission equipment rated for pulsed operation shall be equal to or less than a time interval equivalent to two pulses.

(iii)

The minimum exposure time for all equipment other than that specified in clause (ii) of this subparagraph shall be equal to or less than 0.0167 second or a time interval required to deliver 5 mAs, whichever is greater.

(iv)

Either the product of peak x-ray tube potential, current, and exposure time shall be limited to not more than 60 kWs per exposure, or the product of x-ray tube current and exposure time shall be limited to not more than 600 mAs per exposure except that, when the x-ray tube potential is less than 50 kVp, the product of x-ray tube current and exposure time shall be limited to not more than 2,000 mAs per exposure.

(v)

A visible and/or audible signal shall indicate when an exposure has been terminated at the limits required by clause (iv) of this subparagraph, and manual resetting shall be required before further automatically timed exposures can be made.

(D)

Exposure interval reproducibility. When all technique factors are held constant, including control panel selections associated with AEC systems, the coefficient of variation of exposure interval for both manual and AEC systems shall not exceed 0.05. This requirement applies to clinically used techniques.

(3)

SSD. All mobile or portable radiographic systems shall be provided with means to limit the SSD to equal to or greater than 30 cm.

(4)

Exposure reproducibility. When all technique factors are held constant, including control panel selections associated with AEC systems, the coefficient of variation of exposure for both manual and AEC systems shall not exceed 0.05. This requirement applies to clinically used techniques.

(5)

Linearity.

Figure: 25 TAC §289.227(m)(5)

(6)

Radiation from capacitor energy storage equipment in standby status. Radiation emitted from the x-ray tube when the exposure switch or timer is not activated shall not exceed a rate of 2 milliroentgens per hour (mR/hr) at 5 cm from any accessible surface of the diagnostic source assembly, with the beam-limiting device fully open.

(n)

Additional requirements specifically for veterinary x-ray systems.

(1)

The x-ray control shall provide visual or audible indication of the production of x-rays observable at or from the operator's protected position whenever xrays are produced.

(2)

Beam limiting devices shall do the following:

(A)

provide the same degree of protection as is required of the housing;

(B)

restrict the useful beam to the area of clinical interest;

(C)

limit the x-ray field such that the x-ray field shall not exceed:

(i)

2.0% of the SID for the length or width of the rectangular image receptor; or

(ii)

2.0% of the SID for the diagonal of the image receptor for circular image receptors.

(3)

A means shall be provided to center the primary beam to the image receptor within 2.0% of the SID.

(4)

A means shall be provided to terminate the exposure at the following:

(A)

a preset time interval;

(B)

a preset product of current and time;

(C)

a preset number of pulses; or

(D)

a preset radiation exposure to the image receptor.

(5)

The radiation machine shall not be able to make an exposure when the timer is set to a "zero" or "off" position if either position is provided.

(6)

All stationary, mobile, or portable x-ray systems used for veterinary x rays shall be provided with the following:

(A)

a continuous pressure type exposure switch; and

(B)

either a six and one-half foot high protective barrier for operator protection during exposures; or

(C)

a means provided for the operator to be at least six feet from the tube housing assembly.

(7)

Operators using portable radiation machines designed to be hand-held are exempt from the requirements of paragraph (6) of this subsection. The hand-held portable radiation machine shall be held by the tube housing support or handle. The operator shall wear protective devices in accordance with subsection (i)(4) of this section.

(8)

When all technique factors are held constant, including control panel selections associated with AEC systems, the coefficient of variation of exposure for both manual and AEC systems shall not exceed 0.05. This requirement applies to clinically used techniques.

(9)

The technique factors to be used during an exposure shall be indicated before the exposure begins. If AECs are used, the technique factors that are set prior to the exposure shall be indicated.

(10)

For machines having fixed technique factors, the requirements of paragraph (9) of this subsection may be met by permanent markings on the equipment. Indication of technique factors shall be visible from the operator's position except in the case of spot films made by the fluoroscopist.

(11)

Fluoroscopic and CT units used in veterinary facilities shall meet the requirements of subsections (o) and (p) of this section. Therapy systems used in veterinary facilities shall meet the requirements of §289.229 of this title.

(12)

Portable machines shall be used in a manner that complies with this section.

(13)

All exams and retakes shall be ordered by the veterinarian.

(o)

Fluoroscopic x-ray systems and spot-film devices for all facilities.

(1)

Limitation of the useful beam. Limitation of the useful beam shall be as follows.

(A)

Primary barrier.

(i)

The fluoroscopic imaging assembly shall be provided with a primary protective barrier that intercepts the entire cross section of the useful beam at any SID.

(ii)

The x-ray tube used for fluoroscopy shall not produce x rays unless the barrier is in position to intercept the useful beam and the imaging device is in place and operable.

(iii)

The exposure rate due to transmission through the barrier with the attenuation block in the useful beam, combined with radiation through the image intensifier if provided, shall not exceed 3.34 x 10 -3 % of the entrance exposure rate at a distance of 10 cm from any accessible surface of the fluoroscopic imaging assembly beyond the plane of the image receptor.

(B)

Measuring compliance of barrier transmission.

(i)

The exposure rate due to transmission through the primary protective barrier combined with radiation through the image intensifier shall be determined by measurements averaged over an area of 100 cm 2 with no linear dimension greater than 20 cm.

(ii)

If the source is below the tabletop, the measurement shall be made with the input surface of the fluoroscopic imaging assembly positioned 30 cm above the tabletop.

(iii)

If the source is above the tabletop and the SID is variable, the measurement shall be made with the end of the beam-limiting device or spacer as close to the tabletop as it can be placed, provided that it shall not be closer than 30 cm.

(iv)

Movable grids and compression devices shall be removed from the useful beam during the measurement.

(v)

The attenuation block shall be positioned in the useful beam 10 cm from the point of measurement of entrance exposure rate and between this point and the input surface of the fluoroscopic imaging assembly.

(vi)

The collimator shall be fully open when the measurement is made.

(C)

X-ray field.

(i)

Compliance with clauses (ii)-(vii) of this subparagraph shall be determined with the beam axis perpendicular to the plane of the image receptor.

(ii)

Equipment with a fixed SID and the capability of a visible area of no greater than 300 cm 2 shall be provided with either stepless adjustment of the x-ray field or a means to further limit the x-ray field at the image receptor to 125 cm 2 or less. If the equipment is provided with stepless adjustment, the minimum x-ray field size at the maximum SID shall be less than or equal to 5 cm by 5 cm at the image receptor.

(iii)

Equipment with a variable SID or a fixed SID with the capability of a visible area of greater than 300 cm 2 shall be provided with stepless adjustment of the field size. The minimum x-ray field size at the maximum SID shall be less than or equal to 5 cm by 5 cm at the image receptor.

(iv)

Neither the length nor the width of the x-ray field in the plane of the image receptor shall exceed that of the visible area of the image receptor by more than 3.0% of the SID. The sum of the excess length and the excess width shall be no greater than 4.0% of the SID.

(v)

For rectangular x-ray fields used with circular image receptors, the error in alignment shall be determined along the length and width dimensions of the x-ray field that pass through the center of the visible area of the image receptor.

(vi)

For fluoroscopic equipment with only a manual mode of collimation, the x-ray field produced shall be limited to the area of the spot-film cassette at 16 inches above tabletop. Additionally, during fluoroscopy, the beam shall be restricted to the area of the input phosphor.

(vii)

Spot-film devices shall meet the following additional requirements.

(I)

Means shall be provided between the source and the patient for adjustment of the x-ray field size in the plane of the film to the size of that portion of the film that has been selected on the spot-film selector.

(-a-)

Such adjustment shall be automatically accomplished except when the x-ray field size in the plane of the film is smaller than that of the selected portion of the film.

(-b-)

The total misalignment of the edges of the x-ray field with the respective edges of the selected portion of the image receptor along the length or width dimensions of the x-ray field in the plane of the image receptor shall not exceed 3.0% of the SID when adjusted for full coverage of the selected portion of the image receptor.

(-c-)

The sum, without regard to sign of the misalignment along any two orthogonal dimensions, shall not exceed 4.0% of the SID.

(II)

The center of the x-ray field in the plane of the film shall be aligned with the center of the selected portion of the film to within 2.0% of the SID.

(2)

Activation of the fluoroscopic tube. X-ray production in the fluoroscopic mode shall be controlled by a device that requires continuous pressure by the fluoroscopist for the entire time of the exposure (continuous pressure type switch). When recording serial fluoroscopic images, the fluoroscopist shall be able to terminate the x-ray exposures at any time, but means may be provided to permit completion of any single exposure of the series in process.

(3)

Entrance exposure rate allowable limits.

(A)

The following requirements apply to fluoroscopic equipment manufactured prior to May 19, 1995.

(i)

Equipment with AERC. Fluoroscopic equipment that is provided with AERC shall not be operable at any combination of tube potential and current that will result in an exposure rate in excess of 2.58 x 10 -3 coulomb per kilogram per minute (C/kg/min) (10 roentgens per minute (10 R/min)) at the point where the center of the useful beam enters the patient, except:

(I)

during recording of fluoroscopic images, excluding last image hold; or

(II)

when an optional high-level control is provided. When so provided, the equipment shall not be operable at any combination of tube potential and current that will result in an exposure rate in excess of 1.29 x 10 -3 C/kg/min (5 R/min) at the point where the center of the useful beam enters the patient, unless the high-level control is activated. Special means of activation of high-level controls shall be required. The high- level control shall be operable only when continuous manual activation is provided by the operator. A continuous signal audible to the fluoroscopist shall indicate that the high-level control is being employed.

(ii)

Equipment without AERC (manual mode). Fluoroscopic equipment that is not provided with AERC shall not be operable at any combination of tube potential and current that will result in an exposure rate in excess of 1.29 x 10 -3 C/kg/min (5 R/min) at the point where the center of the useful beam enters the patient, except:

(I)

during recording of fluoroscopic images, excluding last image hold; or

(II)

when an optional high-level control is activated. Special means of activation of high-level controls shall be required. The high-level control shall be operable only when continuous manual activation is provided by the operator. A continuous signal audible to the fluoroscopist shall indicate that the high-level control is being employed.

(iii)

Equipment with both an AERC mode and a manual mode. Fluoroscopic equipment that is provided with both an AERC mode and a manual mode shall not be operable at any combination of tube potential and current that will result in an exposure rate in excess of 2.58 x 10 -3 C/kg/min (10 R/min) in either mode at the point where the center of the useful beam enters the patient except:

(I)

during recording of fluoroscopic images, excluding last image hold; or

(II)

when the mode or modes have an optional high-level control, in which case that mode or modes shall not be operable at any combination of tube potential and current that will result in an exposure rate in excess of 1.29 x 10 -3 C/kg/min (5 R/min) at the point where the center of the useful beam enters the patient, unless the high level control is activated. Special means of activation of high-level control shall be required. The high level control shall be operable only when continuous manual activation is provided by the operator. A continuous signal audible to the fluoroscopist shall indicate that the high-level is being employed.

(iv)

Measuring compliance. Compliance with subparagraph (A) of this paragraph shall be determined as follows.

(I)

If the source is below the x-ray table, the exposure rate shall be measured at 1 cm above the tabletop or cradle.

(II)

If the source is above the x-ray table, the exposure rate shall be measured at 30 cm above the tabletop with the end of the beam-limiting device or spacer positioned as closely as possible to the point of measurement.

(III)

In a C-arm type of fluoroscope, the exposure rate shall be measured at 30 cm from the input surface of the fluoroscopic imaging assembly provided that the end of the beam-limiting device or spacer is no closer than 30 cm from the input surface of the fluoroscopic imaging assembly. The applicable limit shall not be exceeded at any available SID.

(IV)

In a lateral (horizontal) type of fluoroscope, the exposure rate shall be measured at a point 15 cm from the centerline of the x-ray table and in the direction of the x-ray source with the end of the beam-limiting device or spacer positioned as closely as possible to the point of measurement. If the table top is movable, it shall be positioned as closely as possible to the lateral x-ray source, with the end of the beam-limiting device or spacer no closer than 15 cm to the centerline of the x-ray table.

(B)

The following requirements apply to fluoroscopic equipment manufactured on and after May 19, 1995.

(i)

Fluoroscopic equipment operable at any combination of tube potential and current that will result in an exposure rate greater than 1.29 x 10 -3 C/kg/min (5 R/min) at the point where the center of the useful beam enters the patient shall be equipped with AERC. Provision for manual selection of technique factors may be provided.

(ii)

Fluoroscopic equipment shall not be operable at any combination of tube potential and current that will result in an exposure rate in excess of 2.58 x 10 -3 C/kg/min (10 R/min) at the point where the center of the useful beam enters the patient except:

(I)

During the recording of images from an x-ray image- intensifier tube using photographic film or a video camera when the x-ray source is operated in a pulsed mode.

(II)

When the high-level control is activated, the equipment shall not be operable at any combination of tube potential and current that will result in an exposure rate in excess of 5.16 x 10 -3 C/kg/min (20 R/min) at the point where the center of the useful beam enters the patient. Special means of activation of high-level controls shall be required. The high-level control shall only be operable when continuous manual activation is provided by the operator. A continuous signal audible to the fluoroscopist shall indicate that the high-level control is being employed.

(iii)

Measuring compliance. Compliance with subparagraph (B) of this paragraph shall be determined as follows.

(I)

If the source is below the x-ray table, the exposure rate shall be measured at 1 cm above the tabletop or cradle.

(II)

If the source is above the x-ray table, the exposure rate shall be measured at 30 cm above the tabletop with the end of the beam-limiting device or spacer positioned as closely as possible to the point of measurement.

(III)

In a C-arm type of fluoroscope, the exposure rate shall be measured at 30 cm from the input surface of the fluoroscopic imaging assembly provided that the end of the beam-limiting device or spacer is no closer than 30 cm from the input surface of the fluoroscopic imaging assembly. The applicable limit shall not be exceeded at any available SID.

(IV)

In a lateral (horizontal) type of fluoroscope, the exposure rate shall be measured at a point 15 cm from the centerline of the x-ray table and in the direction of the x-ray source with the end of the beam-limiting device or spacer positioned as closely as possible to the point of measurement. If the table top is movable, it shall be positioned as closely as possible to the lateral x-ray source, with the end of the beam-limiting device or spacer no closer than 15 cm to the centerline of the x-ray table.

(C)

For hand-held fluoroscopes, the exposure rate shall be measured at the point closest to the source.

(D)

Periodic measurement of entrance exposure rate shall be performed as follows by a licensed medical physicist with a specialty in diagnostic radiological physics.

(i)

Such measurements shall be made within 30 days of installation, annually, and within 30 days after any maintenance of the system that might affect the exposure rate.

(ii)

Results of these measurements shall be posted where any fluoroscopist may have ready access to such results while using the fluoroscope and maintained in accordance with subsection (t)(1) of this section for inspection by the agency. The measurement results shall be stated in R/min and include the technique factors used in determining such results. The name of the person performing the measurements and the date the measurements were performed shall be included in the results.

(iii)

Conditions of periodic measurement of entrance exposure rate are as follows.

(I)

The measurement shall be made in accordance with subparagraph (A)(iv) or (B)(iii) of this paragraph, as applicable.

(II)

X-ray systems that do not incorporate an AERC shall utilize a milliamperage and kVp typical of the clinical use of the x-ray system. Materials should be placed in the useful beam between the detection and imaging systems when conducting these periodic measurements to protect the imaging system.

(III)

X-ray systems that do incorporate an AERC shall have sufficient material placed in the useful beam to produce a milliamperage and kVp typical of the clinical use of the x-ray system.

(4)

Measurements of the output rate. Measurements of the output rate of the fluoroscopic unit shall be performed with a calibrated dosimetry system. The dosimetry system shall have been calibrated within the preceding 24 months and the calibration shall be traceable to a national standard. During the calendar year in which the dosimetry system is not calibrated, an intercomparison to a system calibrated within the previous 12 months shall be performed.

(5)

Indication of potential and current. During fluoroscopy and cinefluorography, the kV and the mA shall be continuously indicated at the control panel and/or the fluoroscopist's position.

(6)

SSD. The SSD shall not be less than the following:

(A)

38 cm on stationary fluoroscopes installed after March 1, 1989;

(B)

35.5 cm on stationary fluoroscopes that were in operation prior to March 1, 1989;

(C)

30 cm on all mobile and portable fluoroscopes;

(D)

20 cm for image-intensified fluoroscopes used for examinations as specified in the registrant's operating and safety procedures. The written operating and safety procedures shall provide precautionary measures to be adhered to during the use of this device. The procedures must provide information on the means to restore the unit to a 30 cm SSD when the unit is returned to general service; and

(E)

the FDA approved variance for a specific manufacturer of a hand- held fluoroscope.

(7)

Fluoroscopic timer.

(A)

Means shall be provided to preset the cumulative on-time of the fluoroscopic x-ray tube. The maximum cumulative time of the timing device shall not exceed five minutes without resetting.

(B)

A signal audible to the fluoroscopist shall indicate the completion of any preset cumulative on-time. Such signal shall continue to sound while x rays are produced until the timing device is reset. In lieu of such signal, the timer shall terminate the beam after the preset cumulative on-time is completed.

(8)

Control of scattered radiation.

(A)

Fluoroscopic configuration, including fluoroscopic table designs, shall not permit any portion of any individual's body, except the head, neck, and extremities, to be exposed to scattered radiation emanating from above or below the tabletop unless the radiation has passed through not less than a total of 0.25 mm lead equivalent material. The material may be, but is not limited to, drapes, self-supporting curtains, or viewing shields, in addition to any lead equivalency provided by a protective apron.

(B)

Where sterile fields or special procedures prohibit the use of normal protective barriers or drapes, all of the following conditions shall be met.

(i)

All persons, except the patient, in the room where fluoroscopy is performed shall wear protective aprons that provide a shielding equivalent of 0.5 mm of lead.

(ii)

The fluoroscopic field size shall be reduced to the absolute minimum required for the procedure being performed (area of clinical interest).

(iii)

Operating and safety procedures shall reflect the above conditions, and fluoroscopy personnel shall exhibit awareness of situations requiring the use and/or nonuse of the protective drapes.

(C)

For image-intensified fluoroscopic equipment with only a manual mode of collimation, the x-ray field produced shall be limited to the area of the spot-film cassette at 16 inches above tabletop. Additionally, during fluoroscopy, the beam shall be restricted to the area of the input phosphor.

(p)

CT x-ray systems.

(1)

Equipment requirements shall include the following.

(A)

Tomographic plane indication and alignment.

(i)

For any single tomogram system, means shall be provided to permit visual determination of the tomographic plane or a reference plane offset from the tomographic plane.

(ii)

For any multiple tomogram system, means shall be provided to permit visual determination of the location of a reference plane. The reference plane can be offset from the location of the tomographic planes.

(iii)

If a device using a light source is used to satisfy the requirements of clause (i) or (ii) of this subparagraph, the light source shall provide illumination levels sufficient to permit visual determination of the location of the tomographic plane or reference plane under ambient light conditions of up to 500 lux.

(B)

Indication of CT conditions of operation. The CT x-ray system shall be designed such that the CT conditions of operation to be used during a scan or a scan sequence are indicated prior to the initiation of a scan or a scan sequence. On equipment having all or some of these conditions of operation at fixed values, this requirement may be met by permanent markings. Indication of CT conditions of operation shall be visible from any position from which scan initiation is possible.

(C)

Initiation of operation.

(i)

The x-ray control and gantry shall provide visual indication whenever x rays are produced and, if applicable, whether the shutter is open or closed.

(ii)

Means shall be provided to require operator initiation of each individual scan or series of scans.

(iii)

All emergency buttons/switches shall be clearly labeled as to their functions.

(D)

Termination of exposure.

(i)

Means shall be provided to terminate the x-ray exposure automatically by either de-energizing the x-ray source or shuttering the x-ray beam in the event of equipment failure affecting data collection. Such termination shall occur within an interval that limits the total scan time to no more than 110% of its preset value through the use of either a backup timer or devices that monitor equipment function.

(ii)

A signal visible to the operator shall indicate when the x-ray exposure has been terminated through the means required by clause (i) of this subparagraph.

(iii)

The operator shall be able to terminate the x-ray exposure at any time during a scan or series of scans under CT x-ray system control, of greater than 0.5 seconds duration. Termination of the x-ray exposure shall necessitate resetting of the CT conditions of operation prior to initiation of another scan.

(E)

Additional requirements applicable to CT x-ray systems. Additional requirements applicable to CT x-ray systems containing a gantry manufactured after September 3, 1985, are as follows.

(i)

The total error in the indicated location of the tomographic plane or reference plane shall not exceed 5 mm.

(ii)

If the x-ray production period is less than 0.5 seconds, the indication of x-ray production shall be actuated for at least 0.5 seconds. Indicators at or near the gantry shall be discernible from any point external to the patient opening where insertion of any part of the human body into the primary beam is possible.

(iii)

The deviation of indicated scan increment versus actual increment shall not exceed plus or minus 1 mm with any mass from 0 to 100 kilograms (kg) resting on the support device. The patient support device shall be incremented from a typical starting position to the maximum incremented distance or 30 cm, whichever is less, and then returned to the starting position. Measurement of actual versus indicated scan increment can be taken anywhere along this travel.

(2)

Facility design requirements shall include the following.

(A)

Provision shall be made for two-way aural communication between the patient and the operator at the control panel.

(B)

Windows, mirrors, closed-circuit television, or an equivalent shall be provided to permit continuous observation of the patient during irradiation and shall be so located that the operator can observe the patient from the control panel. When the primary viewing system is by electronic means, an alternate viewing system, which may be electronic, shall be available for use in the event of failure of the primary viewing system.

(3)

Dose measurements of the radiation output of the CT x-ray system shall be performed as follows by a licensed medical physicist with a specialty in diagnostic radiological physics.

(A)

Performance of the measurements shall be:

(i)

at intervals not to exceed 12 months;

(ii)

when major maintenance, except x-ray tube replacement, that could affect radiation output is performed; and

(iii)

when a major change in equipment operation is accomplished, for example, introduction of a new software package.

(B)

Measurements of the radiation output of a CT x-ray system shall be performed with a calibrated dosimetry system. The dosimetry system shall have been calibrated within the preceding 24 months and the calibration shall be traceable to a national standard. During the calendar year in which the dosimetry system is not calibrated, an intercomparison to a system calibrated within the previous 12 months shall be performed.

(C)

Records of dose measurements shall be maintained by the registrant in accordance with subsection (t)(1) of this section for inspection by the agency.

(4)

A maintenance schedule shall be developed. This schedule shall be included in the registrant's operating and safety procedures and shall include but may not be limited to the following:

(A)

dose measurements required by paragraph (3)(A) of this subsection; and

(B)

acquisition of images obtained with phantoms using the same processing mode and CT conditions of operation as are used to perform dose measurements required by paragraph (3)(A) of this subsection. The registrant shall maintain either of the following in accordance with subsection (t)(1) of this section for inspection by the agency:

(i)

photographic copies of the images obtained from the image display device; or

(ii)

images stored in digital form.

(q)

Equipment performance evaluation for chiropractic, medical, and podiatric facilities. This subsection does not apply to veterinary facilities.

(1)

For all x-ray systems listed in paragraphs (5)-(7) of this subsection, the registrant shall perform, or cause to be performed, tests necessary to assure proper function of equipment with the indicated standard for each item specified. Such tests shall be performed at the frequency listed in the following table.

Figure: 25 TAC §289.227(q)(1)

(2)

Records of the test results, including any numerical readings shall be maintained by the registrant in accordance with subsection (t)(1) of this section for inspection by the agency.

(3)

Any items not meeting the specifications of the tests shall be corrected or repaired. The correction or repair shall begin within 30 days following the check and shall be performed according to a plan designated by the registrant. Correction or repair shall be completed no longer than 90 days from discovery unless authorized by the agency. Records of corrections or repairs shall be maintained by the registrant in accordance with subsection (t)(1) of this section for inspection by the agency.

(4)

Measurements of the radiation output of an x-ray system shall be performed with a calibrated dosimetry system. The dosimetry system shall have been calibrated within the preceding 24 months and the calibration shall be traceable to a national standard. During the calendar year in which the dosimetry system is not calibrated, an intercomparison to a system calibrated within the previous 12 months shall be performed.

(5)

Radiographic x-ray equipment performance evaluation.

(A)

Timer. The accuracy of the timer shall meet the manufacturer's specifications. If the manufacturer's specifications are not obtainable, the timer accuracy shall be plus or minus 10% of the indicated time with testing performed at 0.5 second.

(B)

Exposure reproducibility. Exposure reproducibility shall meet the requirements of subsection (m)(4) of this section.

(C)

Linearity. mR/mAs stations shall meet the requirements of subsection (m)(5) of this section.

(D)

kVp. If the registrant possesses documentation of the appropriate manufacturer's kVp specifications, the radiation machine shall meet those specifications. If the registrant does not possess documentation of the appropriate manufacturer's kVp specifications, the indicated kVp shall be accurate to within plus or minus 10% of the indicated setting at no less than three points over the usual operating range of the machine.

(E)

Tube stability. The x-ray tube shall remain physically stable during exposures. In cases where tubes are designed to move during exposure, the registrant shall assure proper and free movement of the unit.

(F)

Collimation. The following items shall meet the requirements of subsection (m)(1) of this section:

(i)

numerical indicators of x-ray field size;

(ii)

light field versus x-ray field congruence;

(iii)

automatic and semi-automatic collimators unless disabled; and

(iv)

center of x-ray field alignment with center of image receptor.

(6)

Fluoroscopic x-ray systems and spot film devices equipment performance evaluation. Fluoroscopic equipment shall meet the requirements of subsection (o) of this section.

(7)

CT x-ray systems equipment performance evaluation. CT x-ray systems shall meet the requirements of subsection (p) of this section.

(r)

Automatic and manual film processing for chiropractic, medical, podiatric, and veterinary facilities and mobile services.

(1)

Films shall be developed in accordance with the time-temperature relationships recommended by the film manufacturer. The specified developer temperature for automatic processing and the time-temperature chart for manual processing shall be posted in the darkroom. If the registrant determines an alternate time-temperature relationship is more appropriate for a specific facility, that time-temperature relationship shall be documented and posted.

(2)

Chemicals shall be replaced according to the chemical manufacturer's or supplier's recommendations or at an interval not to exceed three months.

(3)

Darkroom light leak tests shall be performed and any light leaks corrected at intervals not to exceed six months.

(4)

Lighting in the film processing/loading area shall be maintained with the filter, bulb wattage, and distances recommended by the film manufacturer for that film emulsion or with products that provide an equivalent level of protection against fogging.

(5)

Corrections or repairs of the light leaks or other deficiencies in paragraphs (2)-(4) of this subsection shall be initiated within 72 hours of discovery and completed no longer than 15 days from detection of the deficiency unless a longer time is authorized by the agency. Records of the correction or repairs shall include the date and initials of the individual performing these functions and shall be maintained in accordance with subsection (t)(1) of this section for inspection by the agency.

(6)

Documentation of the items in paragraphs (2), (3), and (5) of this subsection shall be maintained at the site where performed and shall include the date and initials of the individual completing these items. These records shall be maintained in accordance with subsection (t)(1) of this section for inspection by the agency.

(s)

Alternative processing systems. Users of daylight processing systems, laser processors, self-processing film units, or other alternative processing systems shall follow manufacturer's recommendations for image processing. Documentation that the registrant is following manufacturer's recommendations shall include the date and initials of the individual completing the document and shall be maintained at the site where performed in accordance with subsection (t)(1) of this section for inspection by the agency.

(t)

Record/document requirements for mobile services and authorized use locations for chiropractic, medical, podiatric, and veterinary facilities.

(1)

Each registrant shall maintain the following records/documents at each site, including authorized records sites for mobile services, for inspection by the agency. The records may be maintained in electronic format.

Figure: 25 TAC §289.227(t)(1)

(2)

Records required in paragraph (1)(F), (Q), and (R) of this subsection shall include the following:

(A)

manufacturer's name, model and serial number from the control panel or console of the radiation machine or from the survey instrument;

(B)

dates of receipt, transfer, and disposal for records required by paragraph (1)(Q) of this subsection; and

(C)

name of the individual recording the information.

(3)

Copies of the records/documents in paragraph (1)(A)-(D), (H), (J), and (N)-(P) of this subsection shall be kept with radiation machines authorized to be used for mobile services. Mobile services with on-board film processors shall maintain the records in paragraph (1)(O) and/or (P) of this subsection as applicable with the processor for a period of no less than one year.

(u)

Appendices. The registrant's operating and safety procedures shall include, but are not limited to, the following procedures as applicable:

(1)

posting notices to workers in accordance with §289.203(b) of this title;

(2)

instructions to workers in accordance with §289.203(c) of this title;

(3)

notifications and reports to individuals in accordance with §289.203(d) of this title;

(4)

ordering x-ray exams in accordance with §289.231(b)(1) of this title;

(5)

occupational dose requirements in accordance with §289.231(m) of this title;

(6)

personnel monitoring requirements in accordance with §289.231(n), (q), and (s) of this title;

(7)

posting of a radiation area in accordance with §289.231(x) of this title;

(8)

use of a technique chart in accordance with subsection (i)(1) of this section;

(9)

use of protective devices in accordance with subsection (i)(4) of this section;

(10)

credentialing requirements for individuals operating radiation machines in accordance with subsection (i)(5) of this section;

(11)

exposure of individuals other than the patient in accordance with subsection (i)(7) of this section;

(12)

holding of patients or film (image receptors) in accordance with subsection (i)(8) of this section;

(13)

gonadal shielding in accordance with subsection (j)(3) of this section;

(14)

use of 20 cm SSD (spacers) in accordance with subsection (o)(6)(D) of this section;

(15)

control of scattered radiation in accordance with subsection (o)(8) of this section; and

(16)

film processing program in accordance with subsections (r) and (s) of this section.

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003518

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


Subchapter F. LICENSE REGULATIONS

25 TAC §289.251

The Texas Department of Health (department) proposes an amendment to §289.251, concerning exemptions, general licenses, and general license acknowledgements for radioactive material.

Government Code §2001.039 requires that each state agency review and consider for readoption each rule adopted by that agency pursuant to the Government Code, Chapter 2001 (Administrative Procedure Act). Section 289.251 has been reviewed and the department has determined that the reasons for adopting the section continue to exist; however revisions to the rule are necessary.

The amendment incorporates an exemption for capsules containing carbon-14 urea for "in vivo" diagnostic use in humans. This exemption is an item of compatibility with the United States Nuclear Regulatory Commission (NRC) and as an agreement state, Texas must adopt it. The amendment incorporates additional information required to be furnished by the holder of a general license acknowledgement concerning certain measuring, gauging, and controlling devices. Language was added regarding appointment by the general license acknowledgement holder of an individual responsible for having knowledge of the appropriate agency requirements and the authority for taking required actions to comply with agency requirements. In addition, the amendment clarifies requirements for reporting of changes of address (including change in the name of the holder of a general license acknowledgement) and adds a two-year storage restriction for devices that are not in use. The amendment reflects corrections of references to other sections of this chapter. This amendment is also part of the department's continuing effort to update, clarify, and simplify its rules regarding the control of radiation based upon technological advances, public concerns, legislative directives, compatibility with NRC, or other factors.

The department published a Notice of Intention to Review for §289.251 as required by Government Code §2001.039 in the Texas Register (25 TexReg 219) on January 7, 2000. No comments were received by the department on this section.

Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, has determined that for each year of the first five years the section will be in effect, there will be no fiscal implications for state or local government as a result of enforcing or administering the section as proposed.

Mrs. McBurney has also determined that for each year of the first five years the proposed section will be in effect, the public benefit anticipated as a result of enforcing the section will be to ensure continued protection of the public, workers, and the environment from unnecessary exposure to radiation and to provide greater accountability for devices containing radioactive material. There will be no effect on micro businesses or small businesses. There are no anticipated economic costs to persons who are required to comply with the section as proposed. There is no anticipated impact on local employment. Adding the exemption for capsules containing carbon-14 urea for "in vivo" diagnostic use incorporates in rule an exemption that is currently being handled on a case-by-case basis. The requirement for appointing a responsible individual does not cause the general license acknowledgement holder to obtain additional training or certification for that individual, simply a written acceptance of that responsibility. General licensees are currently required to properly dispose of devices containing radioactive material, but the current rule does not specify when disposition is appropriate. The proposed section specifies a time interval for appropriate disposition. Therefore, there are no economic effects associated with the section as proposed.

Comments on the proposal may be presented to Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, Texas Department of Health, 1100 West 49th Street, Austin, Texas 78756-3189, Telephone (512) 834- 6688 or electronic mail at Ruth.McBurney@tdh.state.tx.us. Public comments will be accepted for 30 days following publication of this proposal in the Texas Register . In addition, a public meeting to accept oral comments will be held at 9:00 a.m., Tuesday, June 13, 2000, in Conference Room N218, Texas Department of Health, Bureau of Radiation Control, located at the Exchange Building, 8407 Wall Street, Austin, Texas.

The amendment is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with the authority to adopt rules for the performance of each duty imposed by law on the board, the department, and the commissioner of health.

The amendment affects Health and Safety Code, Chapter 401 and Chapter 12, and Government Code §2001.039.

§289.251. Exemptions, General Licenses, and General License Acknowledgements.

(a)

Purpose [ Scope and purpose ]. This section provides for exemptions to licensing requirements, general licensing of radioactive material, and acknowledgement of general licenses.

(b)

Scope. Except as otherwise authorized, no person shall receive, possess, use, transfer, own, or acquire radioactive material except as authorized in a general license or general license acknowledgement issued in accordance with this section, or in a specific license issued in accordance with [ §289.115 of this title (relating to Radiation Safety Requirements and Licensing and Registration Procedures for Industrial Radiography), §289.127 of this title (relating to Licensing of Naturally Occurring Radioactive Material (NORM)), ] §289.252 of this title (relating to Licensing of Radioactive Material), [ or ] §289.254 of this title (relating to Licensing of Radioactive Waste Processing and Storage Facilities), §289.255 of this title (relating to Radiation Safety Requirements and Licensing and Registration Procedures for Industrial Radiography), or §289.259 of this title (relating to Licensing of Naturally Occurring Radioactive Material (NORM)).

(c)

[ (b) ] Definitions. The following terms when used in this chapter shall have the following meanings[ , ] unless the text clearly indicates otherwise.

(1)

General license - An authorization granted in accordance with this section. General licenses provided in this section are effective without the filing of applications with the agency or the issuance of licensing documents to the particular persons. The general licensee is subject to all other applicable portions of this chapter and any limitations of the general license.

(2)

General license acknowledgement - A written recognition of a general license issued in accordance with this section. General license acknowledgements require the submission of an application to the agency and the issuance of a written acknowledgement of a general license granted in accordance with this section. The holder of a general license acknowledgement is subject to all other applicable portions of this chapter as well as any limitations specified in the acknowledgement document.

(d)

[ (c) ] Exemptions for source material.

(1)

Any person is exempt from this section and §289.252 of this title if that person receives, possesses, uses, or transfers source material in any chemical mixture, compound, solution, or alloy in which the source material is by weight less than 1/20 of 1.0% (0.05%) of the mixture, compound, solution, or alloy.

(2)

Any person is exempt from this section and §289.252 of this title if that person receives, possesses, uses, or transfers unrefined and unprocessed ore containing source material; provided that, except as authorized in a specific license, such person shall not refine or process such ore. This exemption does not apply to the mining of ore containing source material.

(3)

Any person is exempt from this section and §289.252 of this title if that person receives, possesses, uses, or transfers:

(A)

any quantities of thorium contained in:

(i)

incandescent gas mantles;

(ii)

vacuum tubes;

(iii)

welding rods;

(iv)

electric lamps for illuminating purposes provided that each lamp does not contain more than 50 milligrams (mg) of thorium;

(v)

germicidal lamps, sunlamps, and lamps for outdoor or industrial lighting provided that each lamp does not contain more than two grams of thorium;

(vi)

rare earth metals and compounds, mixtures, and products containing not more than 0.25% by weight thorium, uranium, or any combination of these; or

(vii)

personnel neutron dosimeters, provided that each dosimeter does not contain more than 50 mg [ milligrams ] of thorium;

(B)

source material contained in the following products:

(i)

glazed ceramics, for example tableware, [ ceramic tableware, ] provided that the glaze contains not more than 20% by weight source material;

(ii)

glassware containing not more than 10% by weight source material, but not including commercially manufactured glass brick, pane glass, ceramic tile, or other glass or ceramic used in construction;

(iii)

glass enamel or glass enamel frit containing not more than 10% by weight source material imported or ordered for importation into the United States, or initially distributed by manufacturers in the United States, before July 25, 1983; or

(iv)

piezoelectric ceramic containing not more than 2.0% by weight source material;

(C)

photographic film, negatives, and prints containing uranium or thorium;

(D)

any finished product or part fabricated of, or containing, metal-thorium alloys, provided that the thorium content of the alloy does not exceed 4% by weight and that the exemption contained in this subparagraph shall not be deemed to authorize the chemical, physical, or metallurgical treatment or processing of any such product or part;

(E)

depleted uranium contained in counterweights installed in aircraft, rockets, projectiles, and missiles, or stored or handled in connection with installation or removal of such counterweights, provided that:

(i)

the counterweights are manufactured in accordance with a specific license issued by the United States Nuclear Regulatory Commission (NRC) [ commission ] authorizing distribution by the licensee in accordance with Title 10 , Code of Federal Regulations (CFR) , Part 40;

(ii)

each counterweight has been impressed with the following legend clearly legible through any plating or other covering: "DEPLETED URANIUM," (The requirements specified in this clause need not be met by counterweights manufactured prior to December 31, 1969, provided that such counterweights are impressed with the legend, "CAUTION - RADIOACTIVE MATERIAL - URANIUM," as previously required by this chapter);

(iii)

each counterweight is durably and legibly labeled or marked with the identification of the manufacturer and the statement: "UNAUTHORIZED ALTERATIONS PROHIBITED," (The requirements specified in this clause need not be met by counterweights manufactured prior to December 31, 1969, provided that such counterweights are impressed with the legend, "CAUTION - RADIOACTIVE MATERIAL - URANIUM," as previously required by this chapter); and

(iv)

the exemption contained in this subparagraph shall not be deemed to authorize the chemical, physical, or metallurgical treatment or processing of any such counterweights other than repair or restoration of any plating, covering, or labeling;

(F)

depleted uranium used as shielding constituting part of any shipping container, provided that:

(i)

the shipping container is conspicuously and legibly impressed with the legend "CAUTION - RADIOACTIVE SHIELDING - URANIUM;" and

(ii)

the uranium metal is encased in a one-eighth inch minimum wall thickness of mild steel or equally fire resistant material;

(G)

thorium contained in finished optical lenses, provided that each lens does not contain more than 30% by weight of thorium, and that the exemption contained in this subparagraph shall not be deemed to authorize either:

(i)

the shaping, grinding, or polishing of such lens or manufacturing processes other than the assembly of such lens into optical systems and devices without any alteration of the lens; or

(ii)

the receipt, possession, use, or transfer of thorium contained in contact lenses, or in spectacles, or in eyepieces in binoculars or in other optical instruments;

(H)

uranium contained in detector heads for use in fire detection units, provided that each detector head contains not more than 0.005 microcurie (µCi) of uranium; or

(I)

thorium contained in any finished aircraft engine part containing nickel-thoria alloy, provided that:

(i)

the thorium is dispersed in the nickel-thoria alloy in the form of finely divided thoria (thorium dioxide); and

(ii)

the thorium content in the nickel-thoria alloy does not exceed 4.0% by weight.

(4)

The exemptions in subsection (d)(3) of this section [ paragraph (3) of this subsection ] do not authorize the manufacture of any of the products described.

(e)

[ (d) ] Exemptions for radioactive material other than source material.

(1)

Exempt concentrations.

(A)

Except as provided in subparagraph (B) of this paragraph, any person is exempt from this section and §289.252 of this title if that person receives, possesses, uses, transfers, or acquires products or materials containing radioactive material in concentrations not in excess of those listed in subsection (q)(1) of this section.

(B)

No person may introduce radioactive material into a product or material, including waste, knowing or having reason to believe that it will be transferred to persons exempt in accordance with subparagraph (A) of this paragraph or equivalent regulations of the NRC [ commission ], any agreement state, or any licensing state, except in accordance with a specific license issued in accordance with §289.252 (i) [ (h)(1) ] of this title or the general license provided in §289.252 (ee) [ (s) ] of this title.

(2)

Exempt quantities.

(A)

Except as provided in subparagraph (C) of this paragraph, any person is exempt from these rules if that person receives, possesses, uses, transfers, or acquires radioactive material in individual quantities, each of which does not exceed the applicable quantity set forth in subsection (q)(2) of this section.

(B)

Any person who possesses radioactive material received or acquired, prior to September 25, 1971, in accordance with the general license provided in subsection (h)(1)(B) [ (g)(1)(B) ] of this section is exempt from the requirements for a license set forth in §289.252 of this title if that person possesses, uses, or transfers such radioactive material.

(C)

This paragraph does not authorize the production, packaging, or repackaging of radioactive material for purposes of commercial distribution, or the incorporation of radioactive material into products intended for commercial distribution.

(D)

No person may, for purposes of commercial distribution, transfer radioactive material in quantities greater than the individual quantities set forth in subsection (q)(2) of this section, knowing or having reason to believe that such quantities of radioactive material will be transferred to persons exempt in accordance with this paragraph or equivalent regulations of the NRC [ commission ], any agreement state, or any licensing state, except in accordance with a specific license issued by the NRC [ commission ] in accordance with Title 10 , CFR , § 32.18 or by the agency in accordance with §289.252 (j) [ (h)(2) ] of this title, which states that the radioactive material may be transferred by the licensee to persons exempt in accordance with this paragraph or the equivalent regulations of the NRC [ commission ], any agreement state, or any licensing state.

(E)

The schedule of quantities set forth in subsection (q)(2) of this section applies only to radioactive materials distributed as exempt quantities in accordance with a specific license issued by the agency, another licensing state, or the commission. Subsection (q)(2) of this section does not apply to radioactive materials that have decayed from quantities not originally exempt and does not make such material, or the sources or devices in which the material is contained, exempt from the licensing requirements in this section or §289.252 of this title.

(3)

Exempt items.

(A)

Certain items containing radioactive material.

(i)

Except for persons who apply radioactive material to, or persons who incorporate radioactive material into the following products, any person is exempt from this chapter if that person receives, possesses, uses, transfers, or acquires the following products:

(I)

timepieces, hands, or dials containing not more than the following specified quantities of radioactive material and not exceeding the following specified levels of radiation:

(-a-)

25 millicuries (mCi) of tritium per timepiece;

(-b-)

5 mCi [ millicuries ] of tritium per hand;

(-c-)

15 mCi [ millicuries ] of tritium per dial (bezels when used shall be considered as part of the dial);

(-d-)

100 µCi [ microcuries ] of promethium-147 per watch or 200 µCi [ microcuries ] of promethium-147 per any other timepiece;

(-e-)

20 µCi [ microcuries ] of promethium-147 per watch hand or 40 µCi [ microcuries ] of promethium-147 per other timepiece hand;

(-f-)

60 µCi [ microcuries ] of promethium-147 per watch dial or 120 µCi [ microcuries ] of promethium-147 per other timepiece dial (bezels when used shall be considered as part of the dial);

(-g-)

the levels of radiation from hands and dials containing promethium-147 will not exceed, when measured through 50 milligrams per square centimeter (mg/cm 2 ) of absorber:

(-1-)

for wrist watches, 0.1 millirad per hour (mrad/hr) at 10 [ ten ] centimeters (cm) from any surface;

(-2-)

for pocket watches, 0.1 mrad/hr [ millirad per hour ] at 1 cm [ one centimeter ] from any surface; and

(-3-)

for any other timepiece, 0.2 (mrad/hr) [ millirad per hour ] at 10 cm [ ten centimeters ] from any surface; or

(-h-)

1 µCi [ one microcurie ] of radium-226 per timepiece in timepieces, hands, or dials manufactured or initially distributed prior to January 1, 1986;

(II)

lock illuminators containing not more than 15 mCi [ millicuries ] of tritium or not more than 2 mCi [ millicuries ] of promethium-147 installed in automobile locks. The levels of radiation from each lock illuminator containing promethium-147 will not exceed 1 mrad/hr [ one millirad per hour ] at 1 cm [ one centimeter ] from any surface when measured through 50 mg/cm 2 [ milligrams per square centimeter ] of absorber;

(III)

balances of precision containing not more than 1 mCi [ one millicurie ] of tritium per balance or not more than 0.5 mCi [ millicurie ] of tritium per balance part;

(IV)

automobile shift quadrants containing not more than 25 mCi [ millicuries ] of tritium;

(V)

marine compasses containing not more than 750 mCi [ millicuries ] of tritium gas and other marine navigational instruments containing not more than 250 mCi [ millicuries ] of tritium gas;

(VI)

thermostat dials and pointers containing not more than 25 mCi [ millicuries ] of tritium per thermostat;

(VII)

electron tubes , [ ; ] provided that each tube does not contain more than one of the following specified quantities of radioactive material and that the levels of radiation from each electron tube containing byproduct material do not exceed 1 mrad/hr [ one millirad per hour ] at 1 cm [ one centimeter ] from any surface when measured through 7 mg/cm 2 [ seven milligrams per square centimeter ] of absorber[ : ] (For purposes of this clause, "electron tubes" include spark gap tubes, power tubes, gas tubes including glow lamps, receiving tubes, microwave tubes, indicator tubes, pick-up tubes, radiation detection tubes, and any other completely sealed tube designed to control electrical currents):

(-a-)

150 mCi [ millicuries ] of tritium per microwave receiver protector tube or 10 mCi [ ten millicuries ] of tritium per any other electron tube;

(-b-)

1 µCi [ one microcurie ] of cobalt-60;

(-c-)

5 µCi [ five microcuries ] of nickel-63;

(-d-)

30 µCi [ microcuries ] of krypton-85;

(-e-)

5 µCi [ five microcuries ] of cesium-137; or

(-f-)

30 µCi [ microcuries ] of promethium-147;

(VIII)

ionizing radiation measuring instruments containing, for purposes of internal calibration or standardization, a source of radioactive material not exceeding the applicable quantity set forth in subsection (q)(2) of this section or 0.05 µCi [ microcurie ] of americium-241; or

(IX)

spark gap irradiators containing not more than 1 µCi [ one microcurie ] of cobalt-60 per spark gap irradiator for use in electrically ignited fuel oil burners having a firing rate of at least 3 [ three ] gallons per hour.

(ii)

Authority to transfer possession or control by the manufacturer, processor, or producer of any equipment, device, commodity, or other product containing source material or byproduct material whose subsequent possession, use, transfer, and disposal by all other persons are exempted from regulatory requirements may be obtained only from the United States Nuclear Regulatory Commission, Washington, DC 20555.

(B)

Self-luminous products containing tritium, krypton-85, promethium-147, or radium-226.

(i)

Except for persons who manufacture, process, or produce self-luminous products containing tritium, krypton-85, or promethium-147, any person is exempt from this chapter if that person receives, possesses, uses, transfers, owns, or acquires tritium, krypton-85, or promethium-147 in self-luminous products manufactured, processed, produced, imported, or transferred in accordance with a specific license issued by the NRC [ commission ] in accordance with Title 10 , CFR , § 32.22, which authorizes the transfer of the product to persons who are exempt from regulatory requirements. The exemption in this subparagraph does not apply to tritium, krypton-85, or promethium-147 used in products for frivolous purposes or in toys or adornments.

(ii)

Any person is exempt from this chapter if that person receives, possesses, uses, transfers, or owns articles acquired prior to January 1, 1986, each of which contains less than 0.1 µCi [ microcurie ] of radium-226.

(C)

Gas and aerosol detectors containing radioactive material.

(i)

Except for persons who manufacture, process, or produce gas and aerosol detectors containing radioactive material, any person is exempt from this chapter if that person receives, possesses, uses, transfers, owns, or acquires radioactive material in gas and aerosol detectors designed to protect life or property from fires and airborne hazards provided that:

(I)

detectors containing radioactive material shall have been manufactured, imported, or transferred in accordance with a specific license issued by the NRC [ commission ] in accordance with Title 10 , CFR , § 32.26, or an agreement state or a licensing state in accordance with §289.252 (k) [ (h)(3) ] of this title; and

(II)

the specific license issued in accordance with §289.252 of this title authorizes the transfer of the detectors to persons who are exempt from regulatory requirements.

(ii)

Authority to transfer possession or control by the manufacturer, processor, or producer of any equipment, device, commodity, or other product containing source material or byproduct material whose subsequent possession, use, transfer, and disposal by all other persons are exempted from regulatory requirements may be obtained only from the United States Nuclear Regulatory Commission, Washington, DC 20555.

(iii)

Gas and aerosol detectors previously manufactured and distributed to general licensees in accordance with a specific license issued by an agreement state or a licensing state shall be considered exempt in accordance with clause (i) of this subparagraph, provided that the devices are labeled in accordance with the specific license authorizing distribution of the generally licensed device, and provided further that they meet the requirements of §289.252 of this title.

(D)

Resins containing scandium-46 and designed for sand consolidation in oil wells. Any person is exempt from this chapter if that person receives, possesses, uses, transfers, or acquires synthetic plastic resins containing scandium-46, which are designed for sand consolidation in oil wells. Such resins shall have been manufactured or imported in accordance with a specific license issued by the NRC [ commission ], or shall have been manufactured in accordance with the specifications contained in a specific license issued by the agency or any agreement state to the manufacturer of such resins in accordance with licensing requirements equivalent to those in Title 10 , CFR , § 32.16 and § 32.17. This exemption does not authorize the manufacture of any resins containing scandium-46.

(4)

Exemption for capsules containing carbon-14 urea for "in vivo" diagnostic use in humans.

(A)

Except as provided in subparagraphs (B) and (C) of this paragraph, a person is exempt from the requirements of this section and §289.256 of this title (relating to Medical and Veterinary Use of Radioactive Material) provided that such person receives, possesses, uses, transfers, owns, or acquires capsules containing 1µCi (37 kilobecquerels) or less of carbon-14 urea each (allowing for nominal variation that may occur during the manufacturing process), for "in vivo" diagnostic use in humans.

(B)

A person desiring to use the capsules for research involving human subjects shall apply for and receive a specific license in accordance with §289.256 of this title.

(C)

A person desiring to manufacture, prepare, process, produce, package, repackage, or transfer for commercial distribution such capsules shall apply for and receive a specific license in accordance with Title 10, CFR, §32.21.

(D)

Nothing in this subsection relieves a person from complying with applicable requirements of the United States Food and Drug Administration (FDA) and other federal and state requirements governing the receipt, administration, and use of drugs.

(f)

[ (e) ] General licenses. In addition to the requirements of this section, all general licenses, unless otherwise specified, are subject to the requirements of §289.201 of this title (relating to General Provisions for Radioactive Material), §289.202(ww) and (xx) of this title (relating to Standards for Protection Against Radiation from Radioactive Material), §289.204 of this title (relating to Fees for Certificates of Registration, Radioactive Material Licenses, Emergency Planning and Implementation, and Other Regulatory Services), §289.205 of this title (relating to Hearing and Enforcement Procedures), and §289.257 of this title (relating to Packaging and Transportation of Radioactive Material) [ §289.112 of this title (relating to Hearing and Enforcement Procedures), §289.126 of this title (relating to Fees for Certificates of Registration, Radioactive Material(s) Licenses, Emergency Planning and Implementation, and Other Regulatory Services), and §289.201 of this title (relating to General Provisions ] [ 21.1201(a), (b), (c), and (d) of Texas Regulations for Control of Radiation (TRCR) as adopted by reference in §289.113 of this title (relating to Standards for Protection Against Radiation), and §289.252(r) of this title ].

(g)

[ (f) ] General licenses for source material.

(1)

A general license is hereby issued authorizing commercial and industrial firms, research, educational and medical institutions, and state and local government agencies to use and transfer not more than 15 pounds of source material at any one time for research, development, educational, commercial, or operational purposes. A person authorized to use or transfer source material, in accordance with this general license, may not possess more than a total of 150 pounds of source material in any one calendar year.

(2)

Persons who receive, possess, use, or transfer source material in accordance with the general license in paragraph (1) of this subsection are prohibited from administering source material, or the radiation therefrom, either externally or internally, to humans except as may be authorized by the agency in a specific license.

(3)

A general license is hereby issued to own source material without regard to quantity. This general license does not authorize any person to receive, possess, use, or transfer source material.

(4)

A general license is hereby issued to mine, transport, and transfer ores containing source material without regard to quantity. In addition to [ Notwithstanding ] the provisions of subsection (f) [ (e) ] of this section, persons who mine, transport, and transfer ores containing source material in accordance with this section [ part ] shall [ also ] comply with the provisions of §289.202(n), (ff), and (gg) [ 21.301, 21.1001, and 21.1003 of TRCR Part 21 as adopted by reference in §289.113 ] of this title.

(5)

A general license is hereby issued to receive, acquire, possess, use, or transfer depleted uranium contained in products or devices for the purpose of providing shielding, including beam shaping and collimation, in accordance with the provisions of subparagraphs (A), (B), (C), and (D) of this paragraph.

(A)

The general license in this paragraph applies only to products or devices that have been manufactured either in accordance with a specific license issued by the agency to the manufacturer of the products or devices in accordance with §289.252 (s) [ (h)(12) ] of this title or in accordance with a specific license issued to the manufacturer by another agreement state or the NRC [ commission ] that authorizes manufacture of the products or devices for distribution to persons generally licensed by another agreement state or the NRC [ commission ].

(B)

Persons who receive, acquire, possess, or use depleted uranium in accordance with the general license in this paragraph shall notify the agency within 30 days after the first receipt of acquisition of such depleted uranium. The general licensee shall furnish the following information and such other information as may be required by the agency:

(i)

name and address of the general licensee;

(ii)

a statement that the general licensee has developed and will maintain procedures designed to establish physical control over the depleted uranium in accordance with this paragraph and designed to prevent transfer of such depleted uranium in any form, including metal scrap, to persons not authorized to receive the depleted uranium; and

(iii)

name and/or title, address, and telephone number of the individual duly authorized to act for and on behalf of the general licensee in supervising the procedures identified in clause (ii) of this subparagraph.

(C)

The general licensee possessing or using depleted uranium in accordance with the general license in this paragraph shall report in writing to the agency any changes in information furnished by the general licensee. The report shall be submitted within 30 days after the effective date of such change.

(D)

A person who receives, acquires, possesses, or uses depleted uranium in accordance with the general license in this paragraph:

(i)

shall not introduce such depleted uranium, in any form, into a chemical, physical, or metallurgical treatment or process, except a treatment or process for repair or restoration of any plating or other covering of the depleted uranium;

(ii)

shall not abandon such depleted uranium;

(iii)

shall transfer or dispose of such depleted uranium only in accordance with the provisions of §289.252 (cc) [ (p) ] of this title. In the case where the transferee receives the depleted uranium in accordance with the general license in this paragraph or equivalent rule of the NRC [ commission ] or an agreement state, the transferor shall furnish the transferee a copy of this paragraph;

(iv)

in each calendar quarter, shall report in writing to the agency the name and address of the person receiving the depleted uranium in accordance with such transfer; and

(v)

shall not export such depleted uranium except in accordance with a license issued by the NRC [ commission ] in accordance with Title 10 , CFR , Part 110.

(E)

Any person receiving, acquiring, possessing, using, or transferring depleted uranium in accordance with the general license in this paragraph is exempt from the requirements of §289.202 of this title and §289.203 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections) [ §289.113 of this title (relating to Standards for Protection Against Radiation) and §289.114 of this title ] with respect to the depleted uranium covered by that general license.

(h)

[ (g) ] General licenses for radioactive material other than source material.

(1)

Certain devices and equipment. A general license is hereby issued to transfer, receive, acquire, possess, and use radioactive material incorporated in the devices or equipment specified in the following subparagraphs (A) and (B) of this paragraph that have been manufactured, tested, and labeled by the manufacturer in accordance with a specific license issued to the manufacturer by the NRC [ commission ] authorizing distribution in accordance with this general license or its equivalent. A general license is hereby issued to transfer, receive, acquire, possess, and use radioactive material incorporated in the devices or equipment specified in the following subparagraph (C) of this paragraph that have been manufactured, tested, and labeled by the manufacturer in accordance with a specific license issued to the manufacturer by the NRC [ commission ], an agreement state, or a licensing state authorizing distribution in accordance with this general license or its equivalent. In addition to [ Notwithstanding ] the provisions of subsection (f) [ (e) ] of this section, this general license is subject to the provisions of subsection (e)(1)(B) [ (d)(1)(B) ] of this section[ , ] and §289.252 (cc) [ (p) and (t) ] of this title : [ . ]

(A)

static [ Static ] elimination devices designed for use as static eliminators that contain, as a sealed source or sources, radioactive material totaling not more than 500 µCi [ microcuries ] of polonium-210 per device ; [ . The general license in this subparagraph does not authorize the manufacture of devices containing radioactive material. ]

(B)

ion [ Ion ] generating tubes designed for ionization of air that contain, as a sealed source or sources, radioactive material totaling not more than 500 µCi [ microcuries ] of polonium-210 per device or a total of not more than 50 mCi [ millicuries ] of tritium per device ; or [ . ]

(C)

other [ Other ] devices designed and manufactured for the purpose of producing light or an ionized atmosphere. Any person who receives, possesses, uses, or transfers radioactive material in a device in accordance with the general license in this subparagraph:

(i)

shall assure that all labels bearing a statement that removal of the label is prohibited, are affixed to the device at the time of receipt, are maintained on the device and, are clearly visible and legible. [ affixed to the device at the time of receipt, and bearing a statement that removal of the label is prohibited, are maintained thereon, are clearly visible and legible, and ] The general licensee shall comply with all instructions and precautions provided by such labels;

(ii)

shall assure that the device is tested for leakage of radioactive material and proper operation of the "on-off" mechanism and indicator, if any, at no longer than six-month intervals or at such other intervals as specified in the label; however:

(I)

devices containing only krypton need not be tested for leakage of radioactive material; and

(II)

devices containing only tritium or not more than 100 µCi [ microcuries ] of other beta and/or gamma emitting material or 10 µCi [ ten microcuries ] of alpha emitting material and devices held in storage in the original shipping container prior to initial installation need not be tested for any purpose; provided that each source is tested for leakage within six months prior to being used or transferred;

(iii)

shall assure that the tests required by clause (ii) of this subparagraph and other testing, installation, servicing, and removal from location of installation involving the radioactive materials, shielding or containment, are performed:

(I)

in accordance with the instructions provided by the labels;

(II)

in accordance with written instructions provided by the manufacturer as specified in §289.252 (l)(3) [ (h)(4)(C) ] of this title; or

(III)

by a person holding a specific license from the agency, the NRC [ commission ], an agreement state, or a licensing state to perform such activities;

(iv)

shall maintain records showing compliance with the requirements of clauses (ii) and (iii) of this subparagraph. The records shall show the test results. The records also shall identify the device tested by manufacturer, model and [ number, ] serial number of the device , [ and ] serial number of the sealed source, and show the dates of performance and the names of persons performing testing, installation, servicing, and removal from location of installation, of the radioactive material, its shielding or containment;

(v)

upon the occurrence of failure or damage to, or any indication of a possible failure or damage to, the radioactive material shielding or the "on-off" mechanism, or upon the detection of 0.005 µCi [ microcuries ] or more of removable radioactive contamination, shall immediately suspend operation of the device until it has been repaired by the manufacturer or other person holding a specific license from the agency, the NRC [ commission ], an agreement state, or a licensing state to repair such devices, or disposed of by transfer to a person authorized by a specific license to receive the radioactive material contained in the device and, within 30 days, furnish the agency with a report containing a brief description of the event and the remedial action taken;

(vi)

shall not abandon the device containing radioactive material;

(vii)

except as provided in clause (viii) of this subparagraph, shall transfer or dispose of the device containing radioactive material only by transfer to a specific licensee of the agency, the NRC [ commission ], an agreement state, or a licensing state, whose specific license authorizes the receipt of the device, and within 30 days after transfer of a device to a specific licensee, shall furnish the agency with a report containing identification of the device by manufacturer's name, model and [ number, ] serial number of the device , [ and ] serial number of the sealed source, and address of the person receiving the device;

(viii)

shall transfer the device to another general license(e) only:

(I)

where the device remains in use at a particular location. In such case, the transferor shall give the transferee a copy of this rule and any safety documents identified in the label on the device and, within 30 days of the transfer, report to the agency the manufacturer's name and model number of device transferred, the serial number of the sealed source transferred, the name and address of the transferee, and the name and/or position of an individual who may constitute a point of contact between the agency and the transferee; or

(II)

where the device is stored in the original shipping container at its intended location of use prior to initial use by the holder of a general license acknowledgement; and

(ix)

shall submit the written instructions specified in clause (iii) (II) of this subparagraph [ subparagraph (C)(iii)(II) of this paragraph ] which shall be followed while performing the testing and shall be maintained for inspection by the agency.

(2)

Luminous safety devices for aircraft.

(A)

A general license is hereby issued to receive, acquire, possess, and use tritium or promethium-147 contained in luminous safety devices for use in aircraft, provided:

(i)

each device contains not more than 10 [ ten ] curies (Ci) of tritium or 300 mCi [ millicuries ] of promethium-147; and

(ii)

each device has been manufactured, assembled, or imported in accordance with a specific license issued by the NRC [ commission ], or each device has been manufactured or assembled in accordance with the specifications contained in a specific license issued by the agency or any agreement state to the manufacturer or assembler of such device in accordance with licensing requirements equivalent to those in Title 10 , CFR , § 32.53.

(B)

The general license in subparagraph (A) of this paragraph does not authorize the manufacture, assembly, or repair of luminous safety devices containing tritium or promethium-147.

(C)

The general license in subparagraph (A) of this paragraph does not authorize the receipt, acquisition, possession, or use of tritium or promethium-147 contained in instrument dials.

[ (D)

Notwithstanding the provisions of subsection (e) of this section, the general license in subparagraph (A) of this paragraph is subject to the provisions of §289.252(t) of this title. ]

(3)

Ownership of radioactive material. A general license is hereby issued to own radioactive material without regard to quantity. Notwithstanding any other provisions of this section, this general license does not authorize the manufacture, production, transfer, receipt, possession, or use of radioactive material.

(4)

Calibration, stabilization, and reference sources.

(A)

A general license is hereby issued to those persons listed below to receive, acquire, possess, use, and transfer, in accordance with the provisions of subparagraphs (B) and (C) of this paragraph, americium-241, plutonium, and/or radium-226, in the form of calibration, stabilization, or reference sources:

(i)

any person who holds a specific license issued by the agency that authorizes that person to receive, possess, use, and transfer radioactive material; and

(ii)

any person who holds a specific license issued by the NRC [ Commission ] that authorizes that person to receive, possess, use, and transfer radioactive material.

(B)

The general license in subparagraph (A) of this paragraph applies only to calibration, stabilization, or reference sources that have been manufactured in accordance with the specifications contained in a specific license issued to the manufacturer or importer of the sources by the NRC [ commission ] in accordance with Title 10 , CFR , § 32.57 or Title 10 , CFR , § 70.39 or that have been manufactured in accordance with the authorizations contained in a specific license issued to the manufacturer by the agency, any agreement state, or any licensing state, in accordance with licensing requirements equivalent to those contained in 10 CFR § 32.57 or 10 CFR § 70.39.

(C)

Persons [ Notwithstanding the provisions of subsection (e) of this section, the general license provided in subparagraph (A) of this paragraph is subject to the provisions of §289.252(t) of this title. In addition, persons ] who receive, acquire, possess, use, or transfer one or more calibration or reference sources in accordance with these general licenses:

(i)

shall not possess at any one time, at any one location of storage or use, more than 5 µCi [ microcuries ] each of americium-241, plutonium-238, plutonium-239, and radium-226 in such sources;

(ii)

shall not receive, possess, use, or transfer such source unless the source or the storage container bears a label that includes the following statements, or a substantially similar statement that contains the information in the following statements:

(I)

option 1, as appropriate:

Figure: 25 TAC §289.251(h)(4)(C)(ii)(I)

[ Figure: 25 TAC §289.251(g)(4)(C)(ii)(I) ]

(II)

option 2, as appropriate:

Figure: 25 TAC §289.251(h)(4)(C)(ii)(II)

[ Figure: 25 TAC §289.251(g)(4)(C)(ii)(II) ]

(iii)

shall not transfer, abandon, or dispose of such source except by transfer to a person authorized by a specific license from the agency, the NRC [ commission ], an agreement state, or a licensing state to receive the source;

(iv)

shall store such source, except when the source is being used, in a closed container designed and constructed to contain americium-241, plutonium-238, plutonium-239, or radium-226; and

(v)

shall not use such source for any purpose other than the calibration of radiation detectors or the standardization of other sources.

(D)

The general license in subparagraph (A) of this paragraph does not authorize the manufacture of calibration or reference sources containing americium-241, plutonium-238, plutonium-239, or radium-226.

(5)

Ice detection devices.

(A)

A general license is hereby issued to receive, acquire, possess, use, and transfer strontium-90 contained in ice detection devices, provided each device contains not more than 50 µCi [ microcuries ] of strontium-90 and each device has been manufactured or imported in accordance with a specific license issued by the NRC [ commission ] or each device has been manufactured in accordance with the authorizations contained in a specific license issued by the agency or any agreement state to the manufacturer of such device in accordance with licensing requirements equivalent to those in Title 10 , CFR , § 32.61.

(B)

Persons who receive, acquire, possess, use, or transfer strontium-90 contained in ice detection devices in accordance with the general license in subparagraph (A) of this paragraph:

(i)

shall, upon occurrence of visually observable damage, such as bend or crack or discoloration from overheating to the device, discontinue use of the device until it has been inspected, tested for leakage, and repaired by a person holding a specific license from the NRC [ commission ] or an agreement state to manufacture or service such devices; or shall dispose of the device by transfer to a person authorized by a specific license from the agency, the NRC [ commission ], or an agreement state; and

(ii)

shall assure that all labels affixed to the device at the time of receipt, and which bear a statement prohibiting removal of the labels, are maintained on the device [ thereon ].

(C)

The general license in subparagraph (A) of this paragraph does not authorize the manufacture, assembly, disassembly, or repair of strontium-90 in ice detection devices.

[ (D)

Notwithstanding the provisions of subsection (e) of this section, the general license in subparagraph (A) of this paragraph is subject to the provisions of §289.252(t) of this title. ]

(i)

[ (h) ] Intrastate transportation of radioactive material.

(1)

A general license is hereby issued to any common or contract carrier to transport and store radioactive material in the regular course of their carriage for another or storage incident to transport [ thereto ], provided the transportation and storage is in accordance with the applicable requirements of §289.257 of this title [ the regulations, appropriate to the mode of transport, of the United States Department of Transportation (DOT) ] insofar as such requirements [ regulations ] relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting. Any notification of incidents referred to in those requirements shall be filed with the agency and the United States Department of Transportation (DOT) [ DOT ]. Persons who transport and store radioactive material in accordance with the general license in this paragraph are exempt from the requirements of §289.202 and §289.203 of this title [ §289.113 of this title and §289.114 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections) ].

(2)

A general license is hereby issued to any private carrier to transport radioactive material, provided the transportation is in accordance with the applicable requirements [ of the regulations ], appropriate to the mode of transport, of the DOT insofar as such requirements [ regulations ] relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting. Any notification of incidents referred to in those requirements shall be filed with the agency and the DOT.

(j)

[ (i) ] General license acknowledgements. In addition to the requirements of this section, all general license acknowledgement holders, unless otherwise specified, are subject to the requirements of §§ 289.201, 289.202(ww) and (xx), 289.204, 289.205, and §289.257 [ 289.112, and 289.126, of this title, and 21.1201(a), (b), (c), and (d), 21.1202(a), (b), (c), and (d) of TRCR Part 21 as adopted by reference in §289.113 of this title, and §289.252(r) ] of this title.

(k)

[ (j) ] General license acknowledgements for radioactive material other than source material.

(1)

Certain measuring, gauging, and controlling devices.

(A)

A general license is hereby issued to commercial and industrial firms and to research, educational, and medical institutions, individuals in the conduct of their business, and state or local government agencies to receive, acquire, possess, use, or transfer in accordance with the provisions of subparagraphs (B)-(E) [ (B), (C), (D), and (E) ] of this paragraph, radioactive material, excluding special nuclear material, contained in devices designed and manufactured for the purpose of detecting, measuring, gauging or controlling thickness, density, level, interface location, radiation, leakage, or qualitative or quantitative chemical composition.

(B)

The general license in subparagraph (A) of this paragraph applies only to radioactive material contained in devices that have been manufactured and labeled in accordance with the authorizations contained in a specific license issued by the agency in accordance with §289.252 (l) [ (h)(4) ] of this title or in accordance with the authorizations contained in a specific license issued by the NRC [ commission ], an agreement state, or a licensing state, which authorizes distribution of devices to persons generally licensed by the NRC [ commission ], an agreement state, or a licensing state.

(C)

Within 30 days following the receipt, acquisition, or possession of radioactive material in a device, except for calibration, stabilization, [ and ] reference sources, electron capture detector cells, ion mobility spectrometers, beta backscatter gauges, and static meters issued in accordance with the general license in subparagraph (A) of this paragraph, the general licensee shall file an application for an acknowledgement on a form prescribed by the agency. The application shall be signed by the individual duly authorized to act for or on behalf of the general licensee. In filing the application for acknowledgement, the general licensee shall furnish the following information and any other information specifically requested by the agency.

(i)

Name and mailing address of the general licensee.

(ii)

Information about each device to include the manufacturer, model number, serial number of the device and sealed source, and the radioisotope and activity (as indicated on the label).

(iii)

Name and telephone number of the responsible person designated as a representative of the holder of a general licensee acknowledgement in accordance with subparagraph (E)(xii) of this paragraph.

(iv)

Address at which the device(s) are used and/or stored. For portable devices, the address of the primary place of storage.

(v)

Certification by the responsible representative of the general licensee that the information concerning the device(s) has been verified through a physical inventory and checking of label information.

(vi)

Certification by the responsible representative of the general licensee that they are aware of the requirements of this section.

(D)

Each application shall be accompanied by BRC Form 252-1, Business Information Form and the applicable fee as required by §289.204 of this title [ TRC Form 12-2 ].

(E)

Any person who receives, acquires, possesses, uses, or transfers radioactive material in a device in accordance with the general license in subparagraph (A) of this paragraph:

(i)

shall assure that all labels bearing a statement that removal of the label is prohibited, are affixed to the device at the time of receipt, are maintained on the device and, are clearly visible and legible. [ affixed to the device at the time of receipt, and bearing a statement that removal of the label is prohibited, are maintained thereon, are clearly visible and legible, and ] The general licensee shall comply with all instructions and precautions provided by such labels;

(ii)

shall assure that the device is tested for leakage of radioactive material and proper operation of the "on-off" mechanism and indicator, if any, at no longer than six-month intervals or at such other intervals as specified in the label; however:

(I)

devices containing only krypton need not be tested for leakage of radioactive material; and

(II)

devices containing only tritium or not more than 100 µCi [ microcuries ] of other beta and/or gamma emitting material or 10 µCi [ ten microcuries ] of alpha emitting material and devices held in storage in the original shipping container prior to initial installation need not be tested for any purpose, provided that each source is tested for leakage within six months prior to being used or transferred;

(iii)

shall assure that the tests required by clause (ii) of this subparagraph and other testing, installation (removal of the manufacturer's lock and initial alignment of the radiation beam), servicing, and removal from location of installation involving the radioactive materials, shielding or containment, are performed:

(I)

in accordance with the instructions provided by the labels;

(II)

in accordance with written instructions provided by the manufacturer as specified in §289.252 (l)(3) [ (h)(4)(C) ] of this title; or

(III)

by a person holding a specific license from the agency, the NRC [ commission ], an agreement state, or a licensing state to perform such activities;

(iv)

shall maintain records showing compliance with the requirements of clauses (ii) and (iii) of this subparagraph. The records shall show the test results. The records also shall identify the device tested by manufacturer, model and [ number, ] serial number of the device , [ and ] serial number of the sealed source, and show the dates of performance of and the names of persons performing testing, installation, servicing, and removal from location of installation, of the radioactive material, its shielding or containment;

(v)

shall maintain assignment records for portable or mobile devices for inspection by the agency at the location listed in the general license acknowledgement. These records shall include:

(I)

a unique identification (e.g. serial number) of each portable or mobile device;

(II)

the location(s) where each portable or mobile device is assigned; and

(III)

the date(s) each portable or mobile device is assigned to the location(s) in accordance with subclause (II) of this clause ; [ . ]

(vi)

shall maintain utilization records for each portable or mobile device used at the location(s) in accordance with clause (v)(II) of this subparagraph for inspection by the agency at that location(s);

(vii)

shall have a copy of the appropriate operating and instruction manual at each temporary site for agency inspection;

(viii)

upon the occurrence of failure or damage to, or any indication of a possible failure or damage to, the radioactive material shielding or the "on-off" mechanism, or upon the detection of 0.005 µCi [ microcuries ] or more of removable radioactive contamination, shall immediately suspend operation of the device until it has been repaired by the manufacturer or other person holding a specific license from the agency, the NRC [ commission ], an agreement state, or a licensing state to repair such devices, or disposed of by transfer to a person authorized by a specific license to receive the radioactive material contained in the device and, within 30 days, furnish the agency with a report containing a brief description of the event and the remedial action taken and in the case of detection of 0.005 µCi or more removable radioactive material or failure of or damage to a source likely to result in contamination of the premises or the environs, a plan for ensuring that the premises and environs are acceptable for unrestricted use. Under these circumstances, the requirements in §289.202(eee) of this title may be applicable, as determined by the agency on a case-by-case basis ;

(ix)

shall not abandon the device containing radioactive material;

(x)

except as provided in clause (xi) of this subparagraph, shall transfer or dispose of the device containing radioactive material only by transfer to a person holding a specific license issued by the agency in accordance with §289.252 (l) [ (h)(4) ] of this title, or an equivalent specific license issued by the NRC [ commission ], an agreement state, or a licensing state, whose specific license authorizes the receipt of the device, or as otherwise authorized by the agency in writing, and within 30 days after transfer of a device to a specific licensee, shall furnish the agency and agreement states with a report containing identification of the device by manufacturer's name, model and [ number, ] serial number of the device and serial number of the sealed source, [ and ] the name, address , and license number of the person receiving the device (except when the device is temporarily transferred to the specific licensee for repair of the device) , and the date of the transfer ; [ and ]

(xi)

shall transfer the device to another general license(e) only:

(I)

where the device remains in use at a particular location. In such case, the transferor shall give the transferee a copy of this rule and any safety documents identified in the label on the device and, within 30 days of the transfer, report to the agency the manufacturer's name , [ and ] the model and serial number of the device transferred, the serial number of the sealed source transferred, the name and address of the transferee, and the name and telephone number of the responsible individual identified by the transferee in accordance with clause (xii) of this subparagraph to have knowledge of and authority to take actions to ensure compliance with the appropriate agency requirements and/or position of an individual who may constitute a point of contact between the agency and the transferee, or

(II)

where the device is held in storage by an intermediate person [ stored ] in the original shipping container at its intended location of use prior to initial use by the holder of a general license acknowledgement ; [ . ]

(xii)

shall appoint an individual responsible for having knowledge of the appropriate agency requirements and the authority for taking required actions to comply with appropriate agency requirements. The general licensee, through this appointed individual, shall ensure the day-to-day compliance with appropriate agency requirements. This appointment does not relieve the general licensee of responsibility in this regard;

(xiii)

shall report changes of address (including change in the name of the holder of a general license acknowledgement) to the agency within 30 days of the effective date of the change. If it is a portable device, a report of address change is only required for a change in the device's primary place of storage; and

(xiv)

shall not hold devices that are not in use for longer than two years. If devices with shutters are not being used, the shutter must be locked in the closed position. The testing required by clause (ii) of this subparagraph need not be performed during the period of storage only. However, when devices are put back into service or transferred to another person, and have not been tested within the required test interval, they must be tested for leakage before use or transfer and the shutter tested before use.

(F)

The general license in subparagraph (A) of this paragraph does not authorize the manufacture of devices containing radioactive material.

(G)

The written instructions specified in subparagraph (E)(iii)(II) of this paragraph shall be followed while performing the testing and shall be maintained for inspection by the agency.

(2)

General license acknowledgements for use of radioactive material for certain in vitro clinical or laboratory testing , not to include research and development . (The New Drug provisions of the Federal Food, Drug, and Cosmetic Act also govern the availability and use of any specific diagnostic drugs in interstate commerce.)

(A)

A general license is hereby issued to any physician, veterinarian, clinical laboratory, or hospital to receive, acquire, possess, transfer, or use, for any of the following stated tests, in accordance with the provisions of subparagraphs (B), (C), and (D) of this paragraph, the following radioactive materials in prepackaged units:

(i)

iodine-125, in units not exceeding 10 µCi [ ten microcuries ] each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to humans or animals;

(ii)

iodine-131, in units not exceeding 10 µCi [ ten microcuries ] each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to humans or animals;

(iii)

carbon-14, in units not exceeding 10 µCi [ ten microcuries ] each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to humans or animals;

(iv)

hydrogen-3 (tritium), in units not exceeding 50 µCi [ microcuries ] each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to humans or animals;

(v)

iron-59, in units not exceeding 20 µCi [ microcuries ] each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to humans or animals;

(vi)

selenium-75, in units not to exceed 10 µCi [ ten microcuries ] each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to humans or animals;

(vii)

mock iodine-125 reference or calibration sources, in units not exceeding 0.05 µCi [ microcurie ] of iodine-129 and 0.005 µCi [ microcurie ] of americium-241 each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to humans or animals; or

(viii)

cobalt-57, in units not exceeding 10 µCi [ ten microcuries ] each for use in in vitro clinical or laboratory tests not involving internal or external administration of radioactive material, or the radiation therefrom, to humans or animals.

(B)

No person shall receive, acquire, possess, use, or transfer radioactive material in accordance with the general license in subparagraph (A) of this paragraph until that person has filed an application for an acknowledgement on a form prescribed by the agency and has received from the agency an acknowledgement with an assigned number. The applicant shall furnish the following information and such other information as may be required by the agency:

(i)

name and address of the physician, veterinarian, clinical laboratory, or hospital;

(ii)

the location of use;

(iii)

a statement that the physician, veterinarian, clinical laboratory, or hospital has appropriate radiation measuring instruments to carry out in vitro clinical or laboratory tests with radioactive material as authorized in accordance with the general license in subparagraph (A) of this paragraph, and that such tests will be performed only by personnel trained specifically in the use of such instruments and in the handling of the radioactive material;

(iv)

name, title, address, and telephone number of the individual duly authorized to act for and on behalf of the general licensee supervising the use of radioactive material authorized by subparagraph (A) of this paragraph; and

(v)

BRC Form 252-1, Business Information Form and the applicable fee as required by §289.204 of this title [ TRC Form 12-2 ].

(C)

A person who receives, acquires, possesses, or uses radioactive material in accordance with the general license in subparagraph (A) of this paragraph shall comply with the following.

(i)

The holder of the general license acknowledgement shall not possess at any one time, at any one location of storage or use, a total amount of iodine-125, iodine-131, selenium-75, iron-59, and/or cobalt- 57 in excess of 200 µCi [ microcuries ].

(ii)

The holder of the general license acknowledgement shall store the radioactive material in the original shipping container or in a container providing equivalent radiation protection and meeting the requirements of §289.202(cc) [ 21.904 of TRCR Part 21 as adopted by reference in §289.113 ] of this title until used.

(iii)

The holder of the general license acknowledgement shall use the radioactive material only for the uses authorized by subparagraph (A) of this paragraph.

(iv)

The holder of the general license acknowledgement shall not transfer the radioactive material to a person who is not authorized to receive it in accordance with a specific license issued by the agency, the NRC [ commission ], any agreement state, or any licensing state, nor transfer the radioactive material in any manner other than in the unopened, labeled shipping container as received from the supplier.

(v)

The holder of the general license acknowledgement shall dispose of the mock iodine-125 reference or calibration sources described in subparagraph (A)(vii) of this paragraph as required by §289.202(ff) [ 21.1001 of TRCR Part 21 as adopted by reference in §289.113 ] of this title.

(D)

The holder of the general license acknowledgement [ in accordance with the general license in subparagraph (A) of this paragraph ] shall not receive, acquire, possess, or use radioactive material in accordance with the general license in subparagraph (A) of this paragraph :

(i)

except as prepackaged units that are labeled in accordance with the provisions of an applicable specific license issued in accordance with §289.252 (p) [ (h)(8) ] of this title or in accordance with the provisions of a specific license issued by the NRC [ commission ], any agreement state, or any licensing state that authorizes the manufacture and distribution of iodine-125, iodine-131, carbon-14, hydrogen-3 (tritium), iron-59, selenium-75, cobalt-57, or mock iodine-125 to persons holding general license acknowledgements in accordance with this paragraph or its equivalent; and

(ii)

unless one of the statements in the following figures, as appropriate, or a substantially similar statement that contains the information called for in one of the following statements, appears on a label affixed to each prepackaged unit or appears in a leaflet or brochure that accompanies the package:

(I)

option 1, as appropriate: [ "This radioactive material shall be received, acquired, possessed, and used only by physicians, veterinarians, clinical laboratories, or hospitals and only for in vitro clinical or laboratory tests not involving internal or external administration of the material, or the radiation therefrom, to human beings or animals. Its receipt, acquisition, possession, use, and transfer are subject to the regulations and a general license of the commission or of a state with which the commission has entered into an agreement for the exercise of regulatory authority. __________ Name of Manufacturer"; or ]

Figure: 25 TAC §289.251(k)(2)(D)(ii)(I)

(II)

option 2, as appropriate: [ "This radioactive material shall be received, acquired, possessed, and used only by physicians, veterinarians, clinical laboratories, or hospitals and only for in vitro clinical or laboratory tests not involving internal or external administration of the material, or the radiation therefrom, to human beings or animals. Its receipt, acquisition, possession, use, and transfer are subject to the rules and a general license of a licensing state. __________ Name of Manufacturer." ]

Figure: 25 TAC §289.251(k)(2)(D)(ii)(II)

(l)

[ (k) ] Issuance of general license acknowledgements.

(1)

Upon a determination that the information submitted by the applicant meets the requirements of the Texas Radiation Control Act (Act) and the rules of the agency, the agency will issue a general license acknowledgement recognizing the proposed activity in such form and containing such conditions and limitations as it deems appropriate or necessary.

(2)

The agency may incorporate in any general license acknowledgement at the time of issuance, or thereafter by amendment, additional requirements and conditions governing the receipt, possession, use, transfer, and disposal of radioactive material subject to this section as it deems appropriate or necessary in order to:

(A)

minimize danger to occupational and public health and safety or the environment;

(B)

require such reports and the keeping of such records, and to provide for such inspections of activities in accordance with the license as may be appropriate or necessary; and

(C)

prevent loss or theft of material subject to this section.

(m)

[ (l) ] Specific terms and conditions.

(1)

Each general license acknowledgement issued in accordance with this section shall be subject to the applicable provisions of the Act, now or hereafter in effect, and to the applicable rules and orders of the agency.

(2)

Each person holding a general license acknowledgement issued by the agency in accordance with this section shall confine use and possession of the material licensed to the locations and purpose authorized in the general license acknowledgement.

(3)

Each holder of a general license acknowledgement shall notify the agency, in writing, immediately following the filing of a voluntary or involuntary petition for bankruptcy . [ in accordance with any Chapters of Title 11 (Bankruptcy) of the United States Code (11 U.S.C.) by or against: ]

[ (A)

a holder of a general license acknowledgement; ]

[ (B)

an entity (as that term is defined in 11 U.S.C. 101(14)) controlling the holder of a general license acknowledgement or listing the general license acknowledgement or the holder of the general license acknowledgement as property of the estate; or ]

[ (C)

an affiliate, (as that term is defined in 11 U.S.C. 101(2)) of the holder of a general license acknowledgement. ]

(4)

The notification in paragraph (3) of this subsection must include [ indicate ]:

(A)

the bankruptcy court in which the petition for bankruptcy was filed; and

(B)

the date of the filing of the petition.

(5)

A copy of the "Petition for Bankruptcy" shall be submitted to the agency with the written notification.

(n)

[ (m) ] Termination [ Expiration and termination ] of general license acknowledgements.

[ (1)

Each general license acknowledgement expires at the end of the day, in the month and year stated in the general license acknowledgement. ]

(1)

[ (2) ] Each holder of a general license acknowledgement shall notify the agency immediately, in writing, and request termination of the general license acknowledgement when the holder of the general license acknowledgement decides to terminate all activities involving materials specified in the general license acknowledgement.

[ (3)

No less than 30 days before the expiration date specified in a general license acknowledgement, the holder of the general license acknowledgement shall submit an application for general license acknowledgement renewal in accordance with subsection (n) of this section. ]

(2)

[ (4) ] Each holder of a general license acknowledgement shall, no less than 30 days before vacating or relinquishing possession of control of premises that have been used as a place of storage or use of radioactive material as a result of general licensed activities, notify the agency in writing of intent to vacate and do the following: [ . ]

(A)

terminate use of radioactive material; and

(B)

dispose of radioactive material in accordance with this section and/or §289.202(ff) of this title.

[ (5)

If a holder of a general license acknowledgement does not submit an application for renewal in accordance with subsection (n) of this section, such person shall on or before the expiration date specified in the general license acknowledgement: ]

[ (A)

terminate use of radioactive material; and ]

[ (B)

dispose of radioactive material in accordance with this section and/or 21.1001 of TRCR Part 21 as adopted by reference in §289.113 of this title. ]

[ (n)

Renewal of general license acknowledgements. ]

[ (1)

Applications for renewal of general license acknowledgements shall be filed in accordance with subsection (j)(1)(C) or (2)(B) of this section, as applicable. ]

[ (2)

If a holder of a general license acknowledgement has properly filed a renewal application for the same activities at least 30 days before the expiration of the existing general license acknowledgement in accordance with this section, such existing general license acknowledgement shall not expire until the application has been finally determined by the agency. ]

(o)

Amendment of general license acknowledgements.

(1)

The holder of the general license acknowledgement in accordance with the general license in subsections (k)(1)(A) [ (j)(1)(A) ] and (2)(A) of this section shall report in writing to the agency any changes in information furnished by the holder of the general license acknowledgement. The report shall be submitted within 30 days after the effective date of such change.

(2)

Applications for amendments of a general license acknowledgement shall be filed in accordance with subsection (k)(1)(C) [ (j)(1)(C) ] or (2)(B) of this section, as applicable, and shall specify the respects in which the holder of a general license acknowledgement desires a general license acknowledgement to be amended.

(p)

Modification and revocation of [ general licenses and ] general license acknowledgements.

(1)

The terms and conditions of all general license acknowledgements shall be subject to amendment, revision, or modification.

(2)

A general license acknowledgement may be suspended or revoked by reason of amendments to the Act, or by reason of rules in this chapter and orders issued by the agency. [ The agency may incorporate in the general license acknowledgement at the time of issuance or thereafter by appropriate rule, regulation, or order, such additional requirements and conditions with respect to the general license acknowledgement holder's possession, use, and transfer of radioactive material as it deems appropriate or necessary. ]

(3)

Any general license acknowledgement may be revoked, suspended, or modified, in whole or in part , for any of the following :

(A)

[ for ] any material false statement in the application or any statement of fact required in accordance with provisions of the Act;

[ (B)

because of the Act; ]

(B)

[ (C) ] [ because of ] conditions revealed by such application or statement of fact or any report, record, or inspection, or other means that would warrant the agency to refuse to grant a general license acknowledgement on an original application; or

(C)

[ (D) ] [ for ] violation of, or failure to observe, any of the terms and conditions of the Act , this chapter, or of the general license acknowledgement , or order of the agency. [ ; or ]

[ (E)

or of any rule or order of the agency. ]

(4)

Except in cases [ of willfulness or those ] in which the occupational and public health, interest, or safety requires otherwise, no general license acknowledgement shall be modified, suspended, or revoked unless, prior to the institution of proceedings therefore, facts or conduct that may warrant such action shall have been called to the attention of the holder of the general license acknowledgement in accordance with §289.205 [ §289.112 ] of this title and the holder of the general license acknowledgement shall have been accorded [ has ] an opportunity to demonstrate [ or achieve ] compliance with all lawful requirements in writing .

(q)

(No change.)

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003514

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


25 TAC §289.252

The Texas Department of Health (department) proposes the repeal of §289.252 and new §289.252, concerning licensing of radioactive material.

The new section adds self-guarantee as an approved method of financial assurance and clarifies financial assurance requirements for governmental entities. These requirements are items of compatibility with the United States Nuclear Regulatory Commission (NRC) and as an agreement state, Texas must adopt these requirements. The new section adds radiation safety officer (RSO) qualifications for licenses with broad scope authorization for research and development and duties and responsibilities for radiation safety committees (RSC). The requirement for a specific licensee who manufactures and distributes devices to general licensees to furnish information is clarified. The specific licensee must furnish such information prior to the transfer of devices to a general licensee. Requirements for sealed source and device evaluations have been revised to clarify what type of sealed sources and devices do not require a safety review. All requirements for medical licensing that are currently located in the proposed repeal of §289.252 will be transferred to §289.256 of this title (relating to Medical and Veterinary Use of Radioactive Material). This will provide clarification that §289.252 addresses licensing the use of radioactive material in industrial settings and the commercial manufacture and distribution of radioactive material. The new section is part of the department's continuing effort to update, clarify, and simplify its rules regarding the control of radiation based upon technological advances, public concerns, legislative directives, compatibility with NRC, or other factors.

Mrs. Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, has determined that for each year of the first five years the sections are in effect, there will be no fiscal implications for state or local government as a result of enforcing or administering the sections as proposed.

Mrs. McBurney has also determined that for each year of the first five years the sections are in effect, the public benefit anticipated as a result of enforcing the sections will be protection of the public and the environment from unnecessary exposure to radiation by ensuring that RSOs and RSCs are qualified to perform their duties and responsibilities and that general licensees are sufficiently made aware of their responsibilities with regard to devices containing radioactive material. There will be no effect on micro businesses or small businesses. There are no anticipated economic costs to persons who are required to comply with the sections as proposed. There is no anticipated impact on local employment. The addition of an option for complying with financial assurance requirements does not alleviate the requirement for financial assurance; it simply provides an additional method of compliance. The addition of specific RSO qualifications and RSC duties and responsibilities formalizes in rule current agency policy. The clarification of types of sealed sources and devices that do not require a safety review also formalizes in rule what is currently agency policy. Because the amendment is clarifying and does not impose any additional requirements such as record keeping, regulatory limits, procedures, or processes, there are no economic effects associated with the section as proposed.

Comments on the proposal may be presented to Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, Texas Department of Health, 1100 West 49th Street, Austin, Texas 78756-3189, Telephone (512) 834- 6688 or electronic mail at Ruth.Mcburney@tdh.state.tx.us. Public comments will be accepted for 30 days following publication of this proposal in the Texas Register . In addition, a public meeting to accept oral comments will be held at 10:00 a.m., Tuesday, June 13, 2000, in Conference Room N218, Texas Department of Health, Bureau of Radiation Control, located at the Exchange Building, 8407 Wall Street, Austin, Texas.

(Editor's note: The text of the following section proposed for repeal will not be published. The section may be examined in the offices of the Texas Department of Health or in the Texas Register office, Room 245, James Earl Rudder Building, 1019 Brazos Street, Austin.)

The repeal is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with authority to adopt rules for the performance of every duty imposed by law on the board, the department, and the commissioner of health.

The repeal affects Health and Safety Code, Chapter 401 and Chapter 12.

§289.252. Licensing of Radioactive Material.

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003512

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


The new section is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with authority to adopt rules for the performance of every duty imposed by law on the board, the department, and the commissioner of health.

The new section affects Health and Safety Code, Chapter 401 and Chapter 12.

§289.252. Licensing of Radioactive Material.

(a)

Purpose. The intent of this section is as follows.

(1)

This section provides for the specific licensing of radioactive material.

(2)

Unless otherwise exempted, no person shall receive, possess, use, transfer, own, or acquire radioactive material except as authorized by the following:

(A)

a specific license issued in accordance with this section and/or any of the following sections:

(i)

§289.254 of this title (relating to Licensing of Radioactive Waste Processing and Storage Facilities);

(ii)

§289.255 of this title (relating to Radiation Safety, Requirements and Licensing and Registration Procedures for Industrial Radiography);

(iii)

§289.256 of this title (relating to Medical and Veterinary Use of Radioactive Material);

(iv)

§289.258 of this title (relating to Licensing and Radiation Safety Requirements for Irradiators);

(v)

§289.259 of this title (relating to Licensing of Naturally Occurring Radioactive Material (NORM));

(vi)

§289.260 of this title (relating to Licensing of Uranium Recovery and Byproduct Material Disposal Facilities); or

(B)

a general license or general license acknowledgment issued in accordance with §289.251 of this title (relating to Exemptions, General Licenses, and General License Acknowledgements).

(3)

A person who receives, possesses, uses, transfers, owns, or acquires radioactive materials prior to receiving a license is subject to the requirements of this chapter.

(b)

Scope. In addition to the requirements of this section, the following additional requirements are applicable.

(1)

All licensees, unless otherwise specified, are subject to the requirements in the following sections:

(A)

§289.201 of this title (relating to General Provisions for Radioactive Material);

(B)

§289.202 of this title (relating to Standards for Protection Against Radiation from Radioactive Material);

(C)

§289.203 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections);

(D)

§289.204 of this title (relating to Fees for Certificates of Registration, Radioactive Material Licenses, Emergency Planning and Implementation, and Other Regulatory Services);

(E)

§289.205 of this title (relating to Hearing and Enforcement Procedures); and

(F)

§289.257 of this title (relating to Packaging and Transportation of Radioactive Material).

(2)

Licensees engaged in well logging service operations and tracer studies are subject to the requirements of §289.253 of this title (relating to Radiation Safety Requirements for Well Logging Service Operations and Tracer Studies).

(3)

Licensees engaged in radioactive waste processing and/or storage are subject to the requirements of §289.254 of this title.

(4)

Licensees engaged in industrial radiographic operations are subject to the requirements of §289.255 of this title.

(5)

Licensees using radioactive material for medical or veterinary use are subject to the requirements of §289.256 of this title.

(6)

Licensees using sealed sources in irradiators are subject to the requirements of §289.258 of this title.

(7)

Licensees possessing or using naturally occurring radioactive material are subject to the requirements of §289.259 of this title.

(8)

Licensees engaged in uranium recovery and byproduct material disposal are subject to the requirements of §289.260 of this title.

(c)

Types of licenses. Licenses for radioactive materials are of two types: general and specific.

(1)

General licenses provided in §289.251 and §289.259 of this title are effective without the filing of applications with the agency or the issuance of licensing documents to the particular persons, although the filing of an application for acknowledgement with the agency may be required for a particular general license. The general licensee is subject to any other applicable portions of this chapter and any limitations of the general license.

(2)

Specific licenses require the submission of an application to the agency and the issuance of a licensing document by the agency. The licensee is subject to all applicable portions of this chapter as well as any limitations specified in the licensing document.

(d)

Filing application for specific licenses. The agency may, at any time after the filing of the original application, require further statements in order to enable the agency to determine whether the application should be denied or the license should be issued.

(1)

Applications for specific licenses shall be filed in a manner prescribed by the agency.

(2)

Each application shall be signed by management.

(3)

An application for a license may include a request for a license authorizing one or more activities. The agency may require the issuance of separate specific licenses for those activities.

(4)

Each application for a specific license, other than a license exempted from §289.204 of this title, shall be accompanied by the fee prescribed in §289.204 of this title.

(5)

Each application shall be accompanied by a completed BRC Form 252-1 (Business Information Form).

(6)

Applications for licenses shall be processed in accordance with the following time periods.

(A)

The first period is the time from receipt of an application by the Division of Licensing, Registration and Standards to the date of issuance or denial of the license or a written notice outlining why the application is incomplete or unacceptable. This time period is 60 days.

(B)

The second period is the time from receipt of the last item necessary to complete the application to the date of issuance or denial of the license. This time period is 30 days.

(C)

These time periods are exclusive of any time period incident to hearings and post-hearing activities required by the Government Code, Chapters 2001.

(7)

Notwithstanding the provisions of §289.204(e)(1) of this title, reimbursement of application fees may be granted in the following manner.

(A)

In the event the application is not processed in the time periods as stated in paragraph (6) of this subsection, the applicant has the right to request of the director of the Radiation Control Program full reimbursement of all application fees paid in that particular application process. If the director does not agree that the established periods have been violated or finds that good cause existed for exceeding the established periods, the request will be denied.

(B)

Good cause for exceeding the period established is considered to exist if:

(i)

the number of applications for licenses to be processed exceeds by 15% or more the number processed in the same calendar quarter the preceding year;

(ii)

another public or private entity utilized in the application process caused the delay; or

(iii)

other conditions existed giving good cause for exceeding the established periods.

(C)

If the request for full reimbursement authorized by subparagraph (A) of this paragraph is denied, the applicant may then request a hearing by appeal to the Commissioner of Health for a resolution of the dispute. The appeal will be processed in accordance with the Formal Hearing Procedures, §§1.21-1.34 of this title (relating to the Texas Board of Health).

(8)

Applications for licenses may be denied for the following reasons:

(A)

any material false statement in the application or any statement of fact required under provisions of the Texas Radiation Control Act (Act); and

(B)

conditions revealed by the application or statement of fact or any report, record, or inspection, or other means that would warrant the agency to refuse to grant a license on an application.

(e)

General requirements for the issuance of specific licenses. A license application will be approved if the agency determines that:

(1)

the applicant and all personnel who will be handling the radioactive material are qualified by reason of training and experience to use the material in question for the purpose requested in accordance with this chapter in such a manner as to minimize danger to occupational and public health and safety or the environment;

(2)

the applicant's proposed equipment, facilities, and procedures are adequate to minimize danger to occupational and public health and safety or the environment;

(3)

the issuance of the license will not be inimical to the health and safety of the public;

(4)

the applicant satisfies any applicable special requirement in this section and other sections as specified in subsection (a)(2)(A) of this section;

(5)

the radiation safety information submitted for requested sealed source(s) or device(s) containing radioactive material is in accordance with subsection (v) of this section;

(6)

qualifications of the designated radiation safety officer (RSO) as specified in subsection (f) of this section are adequate for the purpose requested in the application;

(7)

the applicant submits an adequate operating, safety, and emergency procedures manual;

(8)

the applicant's permanent facility is located in Texas (if the applicant's permanent facility is not located in Texas, reciprocal recognition must be sought as required by subsection (ee) of this section); and

(9)

the owner of the property is aware that radioactive material is stored and/or used on the property, if the proposed storage facility is not owned by the applicant. The applicant shall provide a written statement from the owner indicating such.

(f)

Radiation safety officer.

(1)

An RSO shall be designated for every license issued by the agency.

(2)

The RSO's documented qualifications shall include as a minimum:

(A)

possession of a high school diploma or a certificate of high school equivalency based on the GED test;

(B)

completion of the training and testing requirements specified in this chapter for the activities for which the license application is submitted; and

(C)

training and experience necessary to supervise the radiation safety aspects of the licensed activity.

(3)

The specific duties of the RSO include, but are not limited to, the following:

(A)

to establish and oversee operating, safety, emergency, and as low as reasonably achievable (ALARA) procedures, and to review them at least annually to ensure that the procedures are current and conform with this chapter;

(B)

to oversee and approve all phases of the training program for operations and/or personnel so that appropriate and effective radiation protection practices are taught;

(C)

to ensure that required radiation surveys and leak tests are performed and documented in accordance with this chapter, including any corrective measures when levels of radiation exceed established limits;

(D)

to ensure that individual monitoring devices are used properly by occupationally-exposed personnel, that records are kept of the monitoring results, and that timely notifications are made in accordance with §289.203 of this title;

(E)

to investigate and cause a report to be submitted to the agency for each known or suspected case of radiation exposure to an individual or radiation level detected in excess of limits established by this chapter and each theft or loss of source(s) of radiation, to determine the cause(s), and to take steps to prevent a recurrence;

(F)

to investigate and cause a report to be submitted to the agency for each known or suspected case of release of radioactive material to the environment in excess of limits established by this chapter;

(G)

to have a thorough knowledge of management policies and administrative procedures of the licensee;

(H)

to assume control and have the authority to institute corrective actions, including shutdown of operations when necessary in emergency situations or unsafe conditions;

(I)

to ensure that records are maintained as required by this chapter;

(J)

to ensure the proper storing, labeling, transport, use and disposal of sources of radiation, storage, and/or transport containers;

(K)

to ensure that inventories are performed in accordance with the activities for which the license application is submitted;

(L)

to ensure that personnel are complying with this chapter, the conditions of the license, and the operating, safety, and emergency procedures of the licensee; and

(M)

to serve as the primary contact with the agency.

(4)

Requirements for RSOs for specific licenses for broad scope authorization for research and development. In addition to the requirements in paragraphs (1) and (3) of this subsection, the RSO's qualifications for specific licenses for broad scope authorization for research and development shall include evidence of the following:

(A)

a bachelor's degree in health physics, radiological health, physical science or a biological science with a physical science minor and four years of applied health physics experience in a program with radiation safety problems similar to those in the program to be managed;

(B)

a master's degree in health physics or radiological health and three years of applied health physics experience in a program with radiation safety problems similar to those in the program to be managed; or

(C)

two years of applied health physics experience in a program with radiation safety problems similar to those in the program to be managed and one of the following:

(i)

doctorate degree in health physics or radiological health;

(ii)

comprehensive certification by the American Board of Health Physics;

(iii)

certification by the American Board of Radiology in Medical Nuclear Physics;

(iv)

certification by the American Board of Science in Nuclear Medicine in Radiation Protection; or

(v)

certification by the American Board of Medical Physics in Medical Health Physics.

(5)

The qualifications in paragraph (4)(A)-(C) do not apply to RSOs on licenses issued prior to October 1, 2000.

(g)

The duties and responsibilities of the Radiation Safety Committee (RSC) include but are not limited to the following:

(1)

meeting as often as necessary to conduct business but not less than every three months;

(2)

reviewing personnel dosimetry data;

(3)

reviewing the results of required radiation safety surveys and any significant incidents, including spills, contamination, or medical events;

(4)

reviewing the results of inspections and taking appropriate action when noncompliance is identified;

(5)

reviewing the program for maintaining doses ALARA, and providing any necessary recommendations to ensure doses are ALARA;

(6)

reviewing the overall compliance status for authorized users;

(7)

sharing responsibility with the RSO to conduct periodic audits of the radiation safety program;

(8)

reviewing the audit of the radiation safety program and acting upon the findings;

(9)

developing criteria to evaluate training and experience of new authorized user applicants;

(10)

evaluating and approving authorized user applicants who request authorization to use radioactive material at the facility;

(11)

evaluating new uses of radioactive material; and

(12)

reviewing and approving permitted program and procedural changes prior to implementation.

(h)

Specific licenses for broad scope authorization for multiple quantities or types of radioactive material for use in research and development.

(1)

In addition to the requirements in subsection (e) of this section, a specific license for multiple quantities or types of radioactive material for use in research and development, not to include the internal or external administration of radiation or radioactive material to humans, will be issued if the agency approves the following information submitted by the applicant:

(A)

evidence that staff has substantial experience in the use of a variety of radioisotopes for a variety of research and development uses;

(B)

documentation of a full-time RSO meeting the requirements of subsection (f)(4) of this section;

(C)

evidence of an established RSC, including names and qualifications, with duties and responsibilities in accordance with subsection (g) of this section. The RSC shall be composed of an RSO, a representative of executive management, and one or more persons trained or experienced in the safe use of radioactive materials.

(2)

Unless specifically authorized, persons licensed according to paragraph (1) of this subsection shall not conduct tracer studies involving direct release of radioactive material to the environment.

(3)

Unless specifically authorized, in accordance with a separate license, persons licensed according to paragraph (1) of this subsection shall not:

(A)

receive, acquire, own, possess, use, or transfer devices containing 100,000 curies or more of radioactive material in sealed sources used for irradiation of materials;

(B)

conduct activities for which a specific license issued by the agency in accordance with subsections (i)-(u) of this section and §§289.254, 289.255, 289.256, and §289.259 of this title is required;

(C)

add or cause the addition of radioactive material to any food, beverage, cosmetic, drug, or other product designed for ingestion or inhalation by, or application to, a human being; or

(D)

commercially distribute radioactive material.

(i)

Specific licenses for introduction of radioactive material into products in exempt concentrations.

(1)

In addition to the requirements in subsection (e) of this section, a specific license authorizing the introduction of radioactive material into a product or material in the possession of the licensee or another to be transferred to persons exempt from this chapter in accordance with §289.251(e)(1)(A) of this title will be issued if the agency approves the following information submitted by the applicant:

(A)

a description of the product or material into which the radioactive material will be introduced;

(B)

intended use of the radioactive material and the product or material into which it is introduced;

(C)

method of introduction;

(D)

initial concentration of the radioactive material in the product or material;

(E)

control methods to assure that no more than the specified concentration is introduced into the product or material;

(F)

estimated time interval between introduction and transfer of the product or material;

(G)

estimated concentration of the radioactive material in the product or material at the time of transfer; and

(H)

procedures for disposition of unwanted or unused radioactive material; and

(2)

the applicant provides reasonable assurance that:

(A)

the concentrations of radioactive material at the time of transfer will not exceed the concentrations in §289.251(r)(1) of this title;

(B)

reconcentration of the radioactive material in concentrations exceeding those in §289.251(r)(1) of this title will not occur;

(C)

the use of lower concentrations is not feasible; and

(D)

the product or material is not to be incorporated in any food, beverage, cosmetic, drug, or other commodity or product designed for ingestion or inhalation by, or application to, a human.

(3)

Each person licensed in accordance with this subsection shall file an annual report with the agency and shall identify the type and quantity of each product or material into which radioactive material has been introduced during the reporting period. The report shall cover the year ending June 30, shall be filed within 30 days thereafter, and shall include the following:

(A)

name and address of the person who owned or possessed the product or material when the radioactive material was introduced;

(B)

the type and quantity of radionuclide introduced into each such product or material; and

(C)

the initial concentrations of the radionuclide in the product or material at time of transfer of the radioactive material by the licensee.

(4)

If no transfers of radioactive material have been made in accordance with this subsection during the reporting period, the report shall so indicate.

(j)

Specific licenses for commercial distribution of radioactive material in exempt quantities.

(1)

Authority to transfer possession or control by the manufacturer, processor, or producer of any equipment, device, commodity, or other product containing source material or byproduct material whose subsequent possession, use, transfer, and disposal by all other persons are exempted from regulatory requirements may be obtained only from the United States Nuclear Regulatory Commission, Washington, DC 20555.

(2)

In addition to the requirements in subsection (e) of this section, a specific license to distribute naturally occurring or accelerator-produced radioactive material (NARM) to persons exempt from this chapter in accordance with §289.251(e)(2) of this title will be issued if the agency approves the following information submitted by the applicant:

(A)

that the radioactive material is not contained in any food, beverage, cosmetic, drug, or other commodity designed for ingestion or inhalation by, or application to, a human;

(B)

that the radioactive material is in the form of processed chemical elements, compounds, or mixtures, tissue samples, bioassay samples, counting standards, plated or encapsulated sources, or similar substances, identified as radioactive and to be used for its radioactive properties, but is not incorporated into any manufactured or assembled commodity, product, or device intended for commercial distribution;

(C)

copies of prototype labels and brochures; and

(D)

procedures for disposition of unwanted or unused radioactive material.

(3)

The license issued in accordance with paragraph (2) of this subsection is subject to the following conditions.

(A)

No more than ten exempt quantities shall be sold or commercially distributed in any single transaction. However, an exempt quantity may be composed of fractional parts of one or more of the exempt quantities provided the sum of the fractions shall not exceed unity.

(B)

Each exempt quantity shall be separately and individually packaged. No more than 10 such packaged exempt quantities shall be contained in any other package for commercial distribution to persons exempt from this chapter in accordance with §289.251(e)(2) of this title. The outer package shall be such that the dose rate at the external surface of the package does not exceed 0.5 millirem per hour (mrem/hr).

(C)

The immediate container of each quantity or separately packaged fractional quantity of radioactive material shall bear a durable, legible label that:

(i)

identifies the radionuclide and the quantity of radioactivity; and

(ii)

bears the words "Radioactive Material."

(D)

In addition to the labeling information required by subparagraph (C) of this paragraph, the label affixed to the immediate container, or an accompanying brochure, shall:

(i)

state that the contents are exempt from the United States Nuclear Regulatory Commission (NRC), agreement state, or licensing state requirements;

(ii)

bear the words "Radioactive Material--Not for Human Use-- Introduction into Foods, Beverages, Cosmetics, Drugs, or Medicinals, or into Products Manufactured for Commercial Distribution is Prohibited--Exempt Quantities Should Not Be Combined"; and

(iii)

set forth appropriate additional radiation safety precautions and instructions relating to the handling, use, storage, and disposal of the radioactive material.

(4)

Each person licensed in accordance with this subsection shall maintain records identifying, by name and address, each person to whom radioactive material is commercially distributed for use in accordance with §289.251(e)(2) of this title or the equivalent regulations of an agreement state or a licensing state, and stating the kinds and quantities of radioactive material commercially distributed. An annual summary report stating the total quantity of each radionuclide commercially distributed in accordance with the specific license shall be filed with the agency. Each report shall cover the year ending June 30, and shall be filed within 30 days thereafter. If no commercial distributions of radioactive material have been made in accordance with this subsection during the reporting period, the report shall so indicate.

(5)

Licenses issued in accordance with this subsection do not authorize the following:

(A)

combining of exempt quantities of radioactive material in a single device;

(B)

any program advising persons to combine exempt quantity sources and providing devices for them to do so; and

(C)

the possession and use of combined exempt sources, in a single unregistered device, by persons exempt from licensing in accordance with §289.251(e)(2) of this title.

(k)

Specific licenses for incorporation of NARM into gas and aerosol detectors. In addition to the requirements in subsection (e) of this section, a specific license authorizing the incorporation of NARM into gas and aerosol detectors to be distributed to persons exempt from this chapter in accordance with §289.251(e)(3)(C) of this title will be issued if the agency approves the information submitted by the applicant. This information shall satisfy the requirements equivalent to those contained in Title 10, Code of Federal Regulations (CFR), 32.26.The maximum quantity of radium-226 in each device shall not exceed 0.1 µCi.

(l)

Specific licenses for the manufacture and commercial distribution of devices to persons generally licensed in accordance with §289.251(k)(1) of this title.

(1)

In addition to the requirements in subsection (e) of this section, a specific license to manufacture or commercially distribute devices containing radioactive material to persons generally licensed in accordance with §289.251(h)(1)(C) and (k)(1) of this title or equivalent requirements of the NRC, an agreement state, or a licensing state will be issued if the agency approves the following information submitted by the applicant:

(A)

the design, manufacture, prototype testing, quality control, labels, proposed uses, installation, servicing, leak testing, operating and safety instructions, and potential hazards of the device to provide reasonable assurance that:

(i)

the device can be safely operated by persons not having training in radiological protection;

(ii)

under ordinary conditions of handling, storage, and use of the device, the radioactive material contained in the device will not be released or inadvertently removed from the device, and it is unlikely that any person will receive in any period of one year a dose in excess of 10% of the limits specified in §289.202(f) of this title; and

(iii)

under accident conditions (such as fire and explosion) associated with handling, storage, and use of the device, it is unlikely that any person would receive an external radiation dose or dose commitment in excess of the following organ doses:

(I)

15 rems to the whole body; head and trunk; active blood-forming organs; gonads; or lens of eye;

(II)

200 rems to the hands and forearms; feet and ankles; localized areas of skin averaged over areas no larger than 1 square centimeter (cm 2 ); or

(III)

50 rems to other organs;

(B)

procedures for disposition of unused or unwanted radioactive material;

(C)

each device bears a durable, legible, clearly visible label or labels approved by the agency that contain the following in a clearly identified and separate statement:

(i)

instructions and precautions necessary to assure safe installation, operation, and servicing of the device (documents such as operating and service manuals may be identified in the label and used to provide this information);

(ii)

the requirement, or lack of requirement, for leak testing, or for testing any "on-off" mechanism and indicator, including the maximum time interval for such testing, and the identification of radioactive material by isotope, quantity of radioactivity, and date of determination of the quantity; and

(iii)

the information called for in one of the following statements, as appropriate, in the same or substantially similar form:

(I)

For radioactive materials other than NARM, the following statement is appropriate:

Figure: 25 TAC §289.252(l)(1)(C)(iii)(I)

(II)

For NARM, the following statement is appropriate:

Figure: 25 TAC §289.252(l)(1)(C)(iii)(II)

(III)

The model and serial number and name of manufacturer or distributor may be omitted from this label provided they are elsewhere stated in labeling affixed to the device.

(2)

In the event the applicant desires that the device be required to be tested at intervals longer than six months, either for proper operation of the "on-off" mechanism and indicator, if any, or for leakage of radioactive material, or for both, the applicant shall include in the application sufficient information to demonstrate that the longer interval is justified by performance characteristics of the device or similar devices and by design features that have a significant bearing on the probability or consequences of radioactive material leakage from the device or failure of the "on-off" mechanism and indicator. In determining the acceptable interval for the test for radioactive material leakage, the agency will consider information that includes, but is not limited to the following:

(A)

primary containment (sealed source capsule);

(B)

protection of primary containment;

(C)

method of sealing containment;

(D)

containment construction materials;

(E)

form of contained radioactive material;

(F)

maximum temperature withstood during prototype tests;

(G)

maximum pressure withstood during prototype tests;

(H)

maximum quantity of contained radioactive material;

(I)

radiotoxicity of contained radioactive material; and

(J)

operating experience with identical devices or similarly designed and constructed devices.

(3)

In the event the applicant desires that the general licensee in accordance with §289.251(h)(1)(C) and (k)(1) of this title or in accordance with equivalent regulations of the NRC, an agreement state, or a licensing state, be authorized to mount the device, collect the sample to be analyzed by a specific licensee for radioactive material leakage, perform maintenance of the device consisting of replacement of labels, rust and corrosion prevention, and for fixed gauges, repair and maintenance of sealed source holder mounting brackets, test the "on-off" mechanism and indicator, or remove the device from installation, the applicant shall include in the application written instructions to be followed by the general licensee, estimated annual doses associated with such activity or activities, and bases for such estimates. The submitted information shall demonstrate that performance of such activity or activities by an individual untrained in radiological protection, in addition to other handling, storage, and use of devices in accordance with the general license, is unlikely to cause that individual to receive an annual dose in excess of 10% of the limits specified in §289.202(f) of this title.

(4)

Before the device may be transferred, each person licensed in accordance with this subsection to commercially distribute devices to generally licensed persons shall furnish:

(A)

a copy of the general license in §289.251(h)(1)(C) and (k)(1) of this title to each person to whom the licensee directly commercially distributes radioactive material in a device for use in accordance with the general license in §289.251(h)(1)(C) and (k)(1) of this title;

(B)

a copy of the general license in the NRC's, agreement state's, or licensing state's regulation equivalent to §289.251(h)(1)(C) and (k)(1) of this title, or alternatively, a copy of the general license in §289.251(h)(1)(C) and (k)(1) of this title to each person to whom the licensee directly commercially distributes radioactive material in a device for use in accordance with the general license of the NRC, the agreement state, or the licensing state. If a copy of the general license in §289.251(h)(1)(C) and (k)(1) of this title is furnished to such a person, it shall be accompanied by an explanation that the use of the device is regulated by the NRC, agreement state, or licensing state in accordance with requirements substantially the same as those in §289.251(h)(1)(C) and (k)(1) of this title;

(C)

a copy of §289.251(h)(1)(C) and (k)(1) of this title;

(D)

a list of the services that can only be performed by a specific licensee;

(E)

information on acceptable disposal options including estimated costs of disposal; and

(F)

the name, address, and phone number of a contact person at the agency, an agreement state, or licensing state from which additional information may be obtained.

(5)

In the case of a transfer through an intermediate person, each licensee who commercially distributes radioactive material in a device for use in accordance with the general license in §289.251(h)(1)(C) and (k)(1) of this title, shall furnish the information in paragraph (4) of this subsection to the intended user prior to the initial transfer to the intermediate person.

(6)

Each person licensed in accordance with this subsection to commercially distribute devices to generally licensed persons shall:

(A)

report to the agency all commercial distributions of devices to persons for use in accordance with the general license in §289.251(h)(1)(C) and (k)(1) of this title.

(i)

The report shall cover each calendar quarter, shall be filed within 30 days thereafter, and shall include:

(I)

identity of each general licensee by name and address;

(II)

identity of an individual by name and/or position who may constitute a point of contact between the agency and the general licensee;

(III)

the type, model and serial number of device, and serial number of sealed source commercially distributed; and

(IV)

the quantity and type of radioactive material contained in the device.

(ii)

If one or more intermediate persons will temporarily possess the device at the intended place of use prior to its possession by the user, the report shall also include identification of each intermediate person by name, address, contact, and relationship to the intended user.

(iii)

If no commercial distributions have been made to persons generally licensed in accordance with §289.251(h)(1)(C) and (k)(1) of this title during the reporting period, the report shall so indicate.

(B)

report the following to the NRC to include covering each calendar quarter to be filed within 30 days thereafter:

(i)

all commercial distributions of such devices to persons for use in accordance with the NRC general license in Title 10, CFR, §31.5 including:

(I)

identity of each general licensee by name and address;

(II)

identity of an individual by name and/or position who may constitute a point of contact between the agency and the general licensee;

(III)

the type, model and serial number of device, and serial number of sealed source commercially distributed; and

(IV)

the quantity and type of radioactive material contained in the device; or

(ii)

if no commercial distributions have been made to the NRC licensees during the reporting period; the report shall so indicate; and

(C)

report to the appropriate agreement state or licensing state all transfers of devices manufactured and commercially distributed in accordance with this subsection for use in accordance with a general license in that state's requirements equivalent to §289.251(h)(1)(C) and (k)(1) of this title.

(i)

The report shall be submitted within 30 days after the end of each calendar quarter in which such a device is commercially distributed to the generally licensed person and shall include the following:

(I)

identity of each general licensee by name and address;

(II)

identity of an individual by name and/or position who may constitute a point of contact between the agency and the general licensee;

(III)

the type, model and serial number of the device, and serial number of sealed source commercially distributed; and

(IV)

the quantity and type of radioactive material contained in the device.

(ii)

If one or more intermediate persons will temporarily possess the device at the intended place of use prior to its possession by the user, the report shall also include identification of each intermediate person by name, address, contact, and relationship to the intended user; and

(D)

keep records showing the name, address, and the point of contact for each general licensee to whom the licensee directly or through an intermediate person commercially distributes radioactive material in devices for use in accordance with the general license provided in §289.251(h)(1)(C) and (k)(1) of this title, or equivalent requirements of the NRC, an agreement state, or a licensing state.

(i)

The records shall show the following:

(I)

date of each commercial distribution;

(II)

the isotope and the quantity of radioactivity in each device commercially distributed;

(III)

the identity of any intermediate person; and

(IV)

compliance with the reporting requirements of this subsection.

(ii)

If no commercial distributions have been made to persons generally licensed in accordance with §289.251(h)(1)(C) and (k)(1) of this title during the reporting period, the records shall so indicate.

(7)

If a notification of bankruptcy has been made in accordance with subsection (x)(4) of this section or the license is to be terminated, each person licensed under this subsection shall provide, upon request to the NRC and to any appropriate agreement state or licensing state, records of final disposition required under subsection (y)(14)(A) of this section.

(m)

Specific licenses for the manufacture, assembly, or repair of luminous safety devices for use in aircraft for commercial distribution to persons generally licensed in accordance with §289.251(h)(4) of this title. In addition to the requirements in subsection (e) of this section, a specific license to manufacture, assemble, or repair luminous safety devices containing tritium or promethium-147 for use in aircraft, for commercial distribution to persons generally licensed in accordance with §289.251(h)(4) of this title, will be issued if the agency approves the information submitted by the applicant. The information shall satisfy the requirements of Title 10, CFR, §§32.53, 32.54, 32.55, 32.56, and 32.101 or their equivalent.

(n)

Specific licenses for the manufacture of calibration sources containing americium-241, plutonium, or radium-226 for commercial distribution to persons generally licensed in accordance with §289.251(h)(6) of this title. In addition to the requirements in subsection (e) of this title, a specific license to manufacture calibration sources containing americium-241, plutonium, or radium-226 to persons generally licensed in accordance with §289.251(h)(6) of this title will be issued if the agency approves the information submitted by the applicant. The information shall satisfy the requirements of Title 10, CFR, §§32.57, 32.58, 32.59, and 32.102, and 10 CFR 70.39 or their equivalent.

(o)

Specific licenses for the manufacture and commercial distribution of sealed sources or devices containing radioactive material for medical use.

(1)

In addition to the requirements in subsection (e) of this section, a specific license to manufacture and commercially distribute sealed sources and devices containing radioactive material to persons licensed for use of sealed sources in the healing arts for use as a calibration or reference source will be issued if the agency approves the following information submitted by the applicant:

(A)

an evaluation of the radiation safety of each type of sealed source or device including the following:

(i)

the radioactive material contained, its chemical and physical form, and amount;

(ii)

details of design and construction of the sealed source or device;

(iii)

procedures for, and results of, prototype tests to demonstrate that the sealed source or device will maintain its integrity under stresses likely to be encountered in normal use and accidents;

(iv)

for devices containing radioactive material, the radiation profile of a prototype device;

(v)

details of quality control procedures to assure that production sources and devices meet the standards of the design and prototype tests;

(vi)

procedures and standards for calibrating sealed sources and devices;

(vii)

instructions for handling and storing the sealed source or device from the radiation safety standpoint. These instructions are to be included on a durable label attached to the sealed source or device or attached to a permanent storage container for the sealed source or device, provided that instructions that are too lengthy for the label may be summarized on the label and printed in detail on a brochure that is referenced on the label; and

(viii)

procedures for disposition of unwanted or unused radioactive material; and

(B)

documentation that the label affixed to the sealed source or device, or to the permanent storage container for the sealed source or device, contains information on the radionuclide, quantity, and date of assay, and a statement that the name of the sealed source or device is licensed by the agency for commercial distribution to persons licensed for use of sealed sources in the healing arts or by equivalent licenses of the NRC, an agreement state, or a licensing state, provided that the labeling for sealed sources that do not require long-term storage may be on a leaflet or brochure that accompanies the sealed source;

(C)

documentation that in the event the applicant desires that the sealed source or device be required to be tested for radioactive material leakage at intervals longer than six months, the applicant shall include in the application sufficient information to demonstrate that the longer interval is justified by performance characteristics of the sealed source or device or similar sources or devices and by design features that have a significant bearing on the probability or consequences of radioactive material leakage from the sealed source; and

(D)

documentation that in determining the acceptable interval for testing radioactive material leakage, information will be considered that includes, but is not limited to the following:

(i)

primary containment (sealed source capsule);

(ii)

protection of primary containment;

(iii)

method of sealing containment;

(iv)

containment construction materials;

(v)

form of contained radioactive material;

(vi)

maximum temperature withstood during prototype tests;

(vii)

maximum pressure withstood during prototype tests;

(viii)

maximum quantity of contained radioactive material;

(ix)

radiotoxicity of contained radioactive material; and

(x)

operating experience with identical sealed sources or devices or similarly designed and constructed sealed sources or devices.

(p)

Specific licenses for the manufacture and commercial distribution of radioactive material for certain in vitro clinical or laboratory testing in accordance with the general license. In addition to the requirements in subsection (e) of this section, a specific license to manufacture or commercially distribute radioactive material for use in accordance with the general license in §289.251(k)(2) of this title will be issued if the agency approves the following information submitted by the applicant:

(1)

that the radioactive material will be prepared for distribution in prepackaged units of:

(A)

iodine-125 in units not exceeding 10 microcuries (µCi) each;

(B)

iodine-131 in units not exceeding 10 µCi each;

(C)

carbon-14 in units not exceeding 10 µCi each;

(D)

hydrogen-3 (tritium) in units not exceeding 50 µCi each;

(E)

iron-59 in units not exceeding 20 µCi each;

(F)

cobalt-57 in units not exceeding 10 µCi each;

(G)

selenium-75 in units not exceeding 10 µCi each; or

(H)

mock iodine-125 in units not exceeding 0.05 µCi of iodine-129 and 0.005 µCi of americium-241 each;

(2)

that each prepackaged unit bears a durable, clearly visible label:

(A)

identifying the radioactive contents as to chemical form and radionuclide, and indicating that the amount of radioactivity does not exceed 10 µCi of iodine-125, iodine-131, carbon-14, cobalt-57, or selenium-75; 50 µCi of hydrogen-3 (tritium); 20 µCi of iron-59; or mock iodine-125 in units not exceeding 0.05 µCi of iodine-129 and 0.005 µCi of americium-241; and

(B)

displaying the radiation caution symbol in accordance with §289.202(z) of this title and the words, "CAUTION, RADIOACTIVE MATERIAL," and "Not for Internal or External Use in Humans or Animals";

(3)

that one of the following statements, as appropriate, or a substantially similar statement appears on a label affixed to each prepackaged unit or appears in a leaflet or brochure that accompanies the package:

(A)

option 1:

Figure: 25 TAC §289.252(p)(3)(A)

(B)

option 2:

Figure: 25 TAC §289.252(p)(3)(B)

(4)

that the label affixed to the unit, or the leaflet or brochure that accompanies the package, contains adequate information as to the precautions to be observed in handling and storing the radioactive material. In the case of a mock iodine-125 reference or calibration source, the information accompanying the source must also contain directions to the licensee regarding the waste disposal requirements of §289.202(ff) of this title.

(q)

Specific licenses for the manufacture and commercial distribution of ice detection devices. In addition to the requirements of subsection (e) of this section, a specific license to manufacture and commercially distribute ice detection devices to persons generally licensed in accordance with §289.251(h)(8) of this title will be issued if the agency approves the information submitted by the applicant. This information shall satisfy the requirements of Title 10, CFR, §§32.61, 32.62, and 32.103.

(r)

Specific licenses for the manufacture, preparation, or transfer for commercial distribution of radioactive drugs containing radioactive materials for medical use.

(1)

In addition to the requirements in subsection (e) of this section, a specific license to manufacture, prepare, or transfer for commercial distribution, radioactive drugs containing radioactive material for use by persons authorized in accordance with §289.256 of this title will be issued if the agency approves the following information submitted by the applicant:

(A)

evidence that the applicant is at least one of the following:

(i)

registered or licensed with the United States Food and Drug Administration (FDA) as a drug manufacturer;

(ii)

registered or licensed with a state agency as a drug manufacturer; or

(iii)

licensed as a pharmacy by the Texas State Board of Pharmacy; and

(B)

radionuclide data relating to the following:

(i)

chemical and physical form;

(ii)

maximum activity per vial, syringe, generator, or other container of the radioactive drug;

(iii)

shielding provided by the packaging to show it is appropriate for the safe handling and storage of the radioactive drugs by medical use licensees; and

(C)

labeling requirements including the following:

(i)

that each transport radiation shield, whether it is constructed of lead, glass, plastic, or other material, of a radioactive drug to be transferred for commercial distribution shall include the following:

(I)

radiation symbol and the words "CAUTION, RADIOACTIVE MATERIAL" or "DANGER, RADIOACTIVE MATERIAL;"

(II)

name of the radioactive drug or its abbreviation;

(III)

quantity of radioactivity at a specified date and time (the time may be omitted for radioactive drugs with a half life greater than 100 days); and

(ii)

that each syringe, vial, or other container used to hold a radioactive drug to be transferred for commercial distribution shall include the following:

(I)

radiation symbol and the words, "CAUTION, RADIOACTIVE MATERIAL" or "DANGER, RADIOACTIVE MATERIAL;"

(II)

name of the radioactive drug or its abbreviation;

(III)

quantity of radioactivity at a specified date and time (the time may be omitted for radioactive drugs with a half life greater than 100 days); or

(IV)

an identifier that ensures that the syringe, vial, or other container can be correlated with the information on the transport radiation shield.

(2)

A licensee shall possess and use instrumentation to measure the radioactivity of radioactive drugs and shall have procedures for the use of the instrumentation. The licensee shall measure, by direct measurement or by a combination of measurements and calculations, the amount of radioactivity in dosages of alpha, beta, or photon-emitting radioactive drugs prior to transfer for commercial distribution. In addition, the licensee shall:

(A)

perform tests before initial use, periodically, and following repair, on each instrument for accuracy, linearity, and geometry dependence, as appropriate for the use of the instrument; and make adjustments when necessary;

(B)

check each instrument for constancy and proper operation at the beginning of each day of use; and

(C)

maintain records of the tests and checks in this paragraph for a minimum of three years for inspection by the agency.

(3)

A licensee described in paragraph (1)(A)(iii) of this subsection shall do the following:

(A)

prepare radioactive drugs for medical use as described in §289.256 of this title, provided that the radioactive drugs are prepared by a nuclear pharmacist(s) designated in the application as the individual user(s) who has completed the training and experience requirements specified in the rules of the Texas State Board of Pharmacy, contained in Title 22, Texas Administrative Code, §291.52; and

(B)

provide to the agency a copy of each individual's certification by the Texas State Board of Pharmacy or the permit issued by a licensee of broad scope, and a copy of the state pharmacy license. If the licensee adds a nuclear pharmacist(s) to the license, this shall be completed no later than 30 days after the date that the licensee allows the individual(s) to work as a nuclear pharmacist.

(4)

Nothing in this subsection relieves the licensee from complying with applicable FDA, other federal, and state requirements governing radioactive drugs.

(s)

Specific licenses for the manufacture and commercial distribution of products containing depleted uranium for mass-volume applications.

(1)

In addition to the requirements in subsection (e) of this section, a specific license to manufacture products and devices containing depleted uranium for use in accordance with §289.251(g)(5) of this title or equivalent regulations of the NRC or an agreement state, will be issued if the agency approves the following information submitted by the applicant:

(A)

the design, manufacture, prototype testing, quality control procedures, labeling or marking, proposed uses, and potential hazards of the product or device to provide reasonable assurance that possession, use, or commercial distribution of the depleted uranium in the product or device is not likely to cause any individual to receive in any period of one year a radiation dose in excess of 10% of the limits specified in §289.202(f) of this title; and

(B)

reasonable assurance is provided that unique benefits will accrue to the public because of the usefulness of the product or device.

(2)

In the case of a product or device whose unique benefits are questionable, the agency will issue a specific license in accordance with paragraph (1) of this subsection only if the product or device is found to combine a high degree of utility and low probability of uncontrolled disposal and dispersal of significant quantities of depleted uranium into the environment.

(3)

The agency may deny any application for a specific license in accordance with this subsection if the end use(s) of the product or device cannot be reasonably foreseen.

(4)

Each person licensed in accordance with paragraph (1) of this subsection shall:

(A)

maintain the level of quality control required by the license in the manufacture of the product or device, and in the installation of the depleted uranium into the product or device;

(B)

label or mark each unit to:

(i)

identify the manufacturer of the product or device and the number of the license under which the product or device was manufactured, the fact that the product or device contains depleted uranium, and the quantity of depleted uranium in each product or device, and

(ii)

state that the receipt, possession, use, and commercial distribution of the product or device are subject to a general license or the equivalent and the requirements of the NRC or of an agreement state;

(C)

assure that before being installed in each product or device, the depleted uranium has been impressed with the following legend clearly legible through any plating or other covering: "Depleted Uranium";

(D)

furnish a copy of the following:

(i)

the general license in §289.251(g)(5) of this title to each person to whom the licensee commercially distributes depleted uranium in a product or device for use in accordance with the general license in §289.251(g)(5) of this title, or

(ii)

the NRC's or agreement state's requirements equivalent to the general license in §289.251(g)(5) of this title and a copy of the NRC's or agreement state's certificate;

(E)

report to the agency all commercial distributions of products or devices to persons for use in accordance with the general license in §289.251(g)(5) of this title.

(i)

The report shall be submitted within 30 days after the end of each calendar quarter in which such a product or device is commercially distributed to the generally licensed person and shall include the following:

(I)

identity of each general licensee by name and address;

(II)

identity of an individual by name and/or position who may constitute a point of contact between the agency and the general licensee;

(III)

the type and model number of devices commercially distributed; and

(IV)

the quantity of depleted uranium contained in the product or device.

(ii)

If no commercial distributions have been made to persons generally licensed in accordance with §289.251(g)(5) of this title during the reporting period, the report shall so indicate;

(F)

report to the NRC and each responsible agreement state agency all commercial distributions of industrial products or devices to persons for use in accordance with the general license in the NRC's or agreement state's equivalent requirements to §289.251(g)(5) of this title. The report shall meet the provisions of subparagraph (E)(i) and (ii) of this paragraph; and

(G)

keep records showing the name, address, and point of contact for each general licensee to whom the licensee commercially distributes depleted uranium in products or devices for use in accordance with the general license provided in §289.251(g)(5) of this title or equivalent requirements of the NRC or of an agreement state. The records shall be maintained for a period of two years for inspection by the agency and shall show the date of each commercial distribution, the quantity of depleted uranium in each product or device commercially distributed, and compliance with the report requirements of this section.

(t)

Specific licenses for the processing of loose radioactive material for manufacture and commercial distribution. In addition to the requirements in subsection (e) of this section, a license to process loose radioactive material for manufacture and commercial distribution of radioactive material to persons authorized to possess such radioactive material in accordance with this chapter will be issued if the agency approves the following information submitted by the applicant:

(1)

radionuclides to be used, including the chemical and/or physical form and the maximum activity of each radionuclide;

(2)

intended use of each radionuclide and the sealed sources and/or other products to be manufactured that includes:

(A)

receipt of radioactive material;

(B)

chemical or physical preparations;

(C)

sealed source construction;

(D)

final assembly or processing;

(E)

quality assurance testing;

(F)

quality control program;

(G)

leak testing;

(H)

American National Standards Institute (ANSI) testing procedures;

(I)

transportation containers;

(J)

shipping procedures; and

(K)

disposition of unwanted or unused radioactive material;

(3)

scaled drawings of the facility to include, but not be limited to:

(A)

air filtration;

(B)

ventilation system;

(C)

plumbing; and

(D)

radioactive material handling systems and, when applicable, remote handling hot cells;

(4)

details of the environmental monitoring program; and

(5)

documentation of training as specified in subsection (ii)(1) of this section for all personnel who will be handling radioactive materials.

(u)

Specific licenses for other manufacture and commercial distribution of radioactive material. In addition to the requirements in subsection (e) of this section, a license to manufacture and commercially distribute radioactive material to persons authorized to possess such radioactive material in accordance with these requirements will be issued if the agency approves the following information submitted by the applicant:

(1)

the radionuclides to be used, including the chemical and/or physical form and the maximum activity of each radionuclide;

(2)

the intended use of each radionuclide and the sealed sources and/or other products to be manufactured that includes:

(A)

receipt of radioactive material;

(B)

chemical or physical preparations;

(C)

sealed source construction;

(D)

final assembly or processing;

(E)

quality assurance testing;

(F)

quality control program;

(G)

leak testing;

(H)

ANSI testing procedures;

(I)

transportation containers;

(J)

shipping procedures; and

(K)

disposition of unwanted or unused radioactive material;

(3)

scaled drawings of radioactive material handling systems and;

(4)

documentation of training as specified in subsection (ii)(1) of this section for all personnel who will be handling radioactive material.

(v)

Sealed source or device evaluation. Except as provided in paragraphs (7) and (8) of this subsection, no sealed source or device containing radioactive material shall be authorized on a specific license or general license until radiation safety information for that sealed source or device has been evaluated by the agency, the NRC, another agreement state, or a licensing state.

(1)

An applicant shall submit a request to the agency for evaluation of radiation safety information about the sealed source or device containing a sealed source.

(2)

The request for review shall be submitted in duplicate accompanied by the appropriate fee in §289.204 of this title.

(3)

The request for review shall contain sufficient information about the sealed source or device to include the following:

(A)

the radioactive material contained, its chemical and physical form, and amount;

(B)

details of design and construction;

(C)

procedures for, and results of, prototype tests to demonstrate that the sealed source or device will maintain its integrity under stresses likely to be encountered in normal use and accidents;

(D)

details of quality control procedures to assure that production of sealed sources and devices meet the standards of the design and prototype tests;

(E)

labeling;

(F)

proposed uses; and

(G)

procedures for leak testing.

(4)

For a device containing radioactive material, the request shall also contain sufficient information about the device to include:

(A)

the radiation profile of a prototype device;

(B)

method of installation;

(C)

service and maintenance requirements; and

(D)

operating and safety instructions.

(5)

After review of the request, the agency may issue an evaluation documenting the information in paragraph (3) of this subsection for sealed sources and paragraph (4) of this subsection for devices containing radioactive material.

(6)

The applicant submitting the request for evaluation of the safety information about the product shall manufacture and distribute or cause the product to be manufactured or distributed in accordance with:

(A)

the statements and representations contained in the request;

(B)

documentation required to support the request; and

(C)

the provisions of the evaluation.

(7)

Sealed sources or devices that do not require radiation safety evaluations are as follows:

(A)

calibration and reference sources of 100 µCi or less for beta or gamma-emitting radionuclides and 10 µCi or less for alpha-emitting radionuclides; and

(B)

custom (one-of-a-kind) sources or devices used in research and development. If the same device is manufactured and transferred to a second licensee, it ceases to be custom. The licensee must be qualified by sufficient training and experience and have sufficient facilities and equipment to safely use the requested quantity of radioactive material in unsealed form.

(8)

Sealed sources or devices used in research and development that require modified safety evaluations.

(A)

For sealed sources or devices used in research and development, the following shall be submitted:

(i)

the radioactive material contained, its chemical and physical form, and amount;

(ii)

details of the design and construction sufficient to determine that no obvious mechanical flaws exist;

(iii)

information that demonstrates that sealed sources meet ANSI/HPS N43.6-1997 criteria for the particular category of use and that devices will maintain their integrity during normal use and accident conditions; and

(iv)

procedures for use that demonstrate a safe environment for users and others nearby.

(B)

A safety evaluation is not required if the licensee is qualified by sufficient training and experience and has sufficient facilities and equipment to safely use the requested quantity of radioactive material in unsealed form.

(w)

Issuance of specific licenses.

(1)

When the agency determines that an application meets the requirements of the Act and the rules of the agency, the agency will issue a specific license authorizing the proposed activity in such form and containing the conditions and limitations as it deems appropriate or necessary.

(2)

The agency may incorporate in any license at the time of issuance, or thereafter by amendment, additional requirements and conditions with respect to the licensee's receipt, possession, use, and transfer of radioactive material subject to this section as it deems appropriate or necessary in order to:

(A)

minimize danger to occupational and public health and safety or the environment;

(B)

require reports and the keeping of records, and to provide for inspections of activities in accordance with the license as may be appropriate or necessary; and

(C)

prevent loss or theft of radioactive material subject to this chapter.

(x)

Specific terms and conditions of licenses.

(1)

Each license issued in accordance with this section shall be subject to the applicable provisions of the Act and to applicable rules, now or hereafter in effect, and orders of the agency.

(2)

No license issued or granted in accordance with this section and no right to possess or utilize radioactive material granted by any license issued in accordance with this section shall be transferred, assigned, or in any manner disposed of, either voluntarily or involuntarily, directly or indirectly, through transfer of control of any license to any person unless the agency shall, after securing full information, find that the transfer is in accordance with the provisions of the Act and to applicable rules, now or hereafter in effect, and orders of the agency, and shall give its consent in writing.

(3)

Each person licensed by the agency in accordance with this section shall confine use and possession of the radioactive material licensed to the locations and purposes authorized in the license.

(4)

Each licensee shall notify the agency, in writing, immediately following the filing of a voluntary or involuntary petition for bankruptcy.

(5)

The notification in paragraph (4) of this subsection must include:

(A)

the bankruptcy court in which the petition for bankruptcy was filed; and

(B)

the date of the filing of the petition.

(6)

A copy of the petition for bankruptcy shall be submitted to the agency along with the written notification.

(y)

Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas.

(1)

Except as provided in paragraph (2) of this subsection and subsection (z)(2) of this section, each specific license expires at the end of the day, in the month and year stated in the license.

(2)

All license provisions continue, in effect, beyond the expiration date, with respect to possession of radioactive material until the agency notifies the former licensee in writing that the provisions of the license are no longer binding. During this time, the former licensee shall:

(A)

be limited to actions involving radioactive material that are related to decommissioning; and

(B)

continue to control entry to restricted areas until the location(s) is suitable for release for unrestricted use in accordance with the requirements in §289.202(ddd) of this title.

(3)

Within 60 days of the occurrence of any of the following, each licensee shall provide notification to the agency in writing and either begin decommissioning its site, or any separate building or outdoor area that contains residual radioactivity, so that the building and/or outdoor area is suitable for release in accordance with §289.202(eee) of this title, or submit within 12 months of notification a decommissioning plan, if required by paragraph (6) of this subsection, and begin decommissioning upon approval of that plan:

(A)

the license has expired in accordance with this subsection or subsection (dd)(3) of this section; or

(B)

the licensee has decided to permanently cease principal activities, as defined in §289.201(b) of this title, at the entire site or in any separate building or outdoor area; or

(C)

no principal activities under the license have been conducted for a period of 24 months; or

(D)

no principal activities have been conducted for a period of 24 months in any separate building or outdoor area that contains residual radioactivity such that the building or outdoor area is unsuitable for release in accordance with §289.202(eee) of this title.

(4)

Coincident with the notification required by paragraph (3) of this subsection, the licensee shall maintain in effect all decommissioning financial assurances established by the licensee in accordance with subsection (gg) of this section in conjunction with a license issuance or renewal or as required by this section. The amount of the financial assurance must be increased, or may be decreased, as appropriate, to cover the detailed cost estimate for decommissioning established in accordance with paragraph (9)(E) of this subsection.

(A)

Any licensee who has not provided financial assurance to cover the detailed cost estimate submitted with the decommissioning plan shall do so by March 1, 1998.

(B)

Following approval of the decommissioning plan, a licensee may reduce the amount of the financial assurance as decommissioning proceeds and radiological contamination is reduced at the site with the approval of the agency.

(5)

The agency may grant a request to delay or postpone initiation of the decommissioning process if the agency determines that such relief is not detrimental to the occupational and public health and safety and is otherwise in the public interest. The request must be submitted no later than 30 days before notification in accordance with paragraph (3) of this subsection. The schedule for decommissioning set forth in paragraph (3) of this subsection may not commence until the agency has made a determination on the request.

(6)

A decommissioning plan must be submitted if required by license condition or if the procedures and activities necessary to carry out decommissioning of the site or separate building or outdoor area have not been previously approved by the agency and these procedures could increase potential health and safety impacts to workers or to the public, such as in any of the following cases:

(A)

procedures would involve techniques not applied routinely during cleanup or maintenance operations;

(B)

workers would be entering areas not normally occupied where surface contamination and radiation levels are significantly higher than routinely encountered during operation;

(C)

procedures could result in significantly greater airborne concentrations of radioactive materials than are present during operation; or

(D)

procedures could result in significantly greater releases of radioactive material to the environment than those associated with operation.

(7)

The agency may approve an alternate schedule for submittal of a decommissioning plan required in accordance with paragraph (3) of this subsection if the agency determines that the alternative schedule is necessary to the effective conduct of decommissioning operations and presents no undue risk from radiation to the occupational and public health and safety and is otherwise in the public interest.

(8)

The procedures listed in paragraph (6) of this subsection may not be carried out prior to approval of the decommissioning plan.

(9)

The proposed decommissioning plan for the site or separate building or outdoor area must include the following:

(A)

a description of the conditions of the site or separate building or outdoor area sufficient to evaluate the acceptability of the plan;

(B)

a description of planned decommissioning activities;

(C)

a description of methods used to ensure protection of workers and the environment against radiation hazards during decommissioning;

(D)

a description of the planned final radiation survey;

(E)

an updated detailed cost estimate for decommissioning, comparison of that estimate with present funds set aside for decommissioning, and a plan for assuring the availability of adequate funds for completion of decommissioning; and

(F)

for decommissioning plans calling for completion of decommissioning later than 24 months after plan approval, a justification for the delay based on the criteria in paragraph (13) of this subsection.

(10)

The proposed decommissioning plan will be approved by the agency if the information in the plan demonstrates that the decommissioning will be completed as soon as practicable and that the health and safety of workers and the public will be adequately protected.

(11)

Except as provided in paragraph (13) of this subsection, licensees shall complete decommissioning of the site or separate building or outdoor areas as soon as practicable but no later than 24 months following the initiation of decommissioning.

(12)

Except as provided in paragraph (13) of this subsection, when decommissioning involves the entire site, the licensee shall request license termination as soon as practicable but no later than 24 months following the initiation of decommissioning.

(13)

The agency may approve a request for an alternate schedule for completion of decommissioning of the site or separate building or outdoor area, and license termination if appropriate, if the agency determines that the alternative is warranted by consideration of the following:

(A)

whether it is technically feasible to complete decommissioning within the allotted 24 month period;

(B)

whether sufficient waste disposal capacity is available to allow completion of decommissioning within the allotted 24 month period;

(C)

whether a significant volume reduction in wastes requiring disposal will be achieved by allowing short-lived radionuclides to decay;

(D)

whether a significant reduction in radiation exposure to workers can be achieved by allowing short-lived radionuclides to decay; and

(E)

other site-specific factors that the agency may consider appropriate on a case-by-case basis, such as the regulatory requirements of other government agencies, lawsuits, groundwater treatment activities, monitored natural ground-water restoration, actions that could result in more environmental harm than deferred cleanup, and other factors beyond the control of the licensee.

(14)

As the final step in decommissioning, the licensee shall do the following:

(A)

certify the disposition of all licensed material, including accumulated wastes; and

(B)

conduct a radiation survey of the premises where the licensed activities were carried out and submit a report of the results of this survey unless the licensee demonstrates that the premises are suitable for release in accordance with the radiological requirements for license termination specified in §289.202(ddd) of this title. The licensee shall do the following, as appropriate:

(i)

report levels of gamma radiation in units of millisieverts per hour (mSv/hr) (microroentgen per hour (µR/hr)) at 1 m from surfaces, and report levels of radioactivity, including alpha and beta, in units of megabecquerels (MBq) (disintegrations per minute (dpm) or µCi) per 100 cm 2 removable and fixed for surfaces, MBq (µCi) per milliliter (ml) for water, and becquerels (Bq) (picocuries (pCi)) per gram (g) for solids such as soils or concrete; and

(ii)

specify the manufacturer's name and model and serial number of survey instrument(s) used and certify that each instrument is properly calibrated and tested.

(15)

The agency will provide written notification to specific licenses, including former licenses with provisions continued in effect beyond the expiration date in accordance with subsection (y)(2) of this section, that the provisions of the license are no longer binding. The agency will provide such notification when the agency determines that:

(A)

radioactive material has been properly disposed;

(B)

reasonable effort has been made to eliminate residual radioactive contamination, if present;

(C)

a radiation survey has been performed that demonstrates that the premises are suitable for release in accordance with the radiological requirements for license termination specified in §289.202(ddd) of this title. or other information submitted by the licensee is sufficient to demonstrate that the premises are suitable for release in accordance with the radiological requirements for license termination specified in §289.202(ddd) of this title; and

(D)

any outstanding fees in accordance with §289.204 of this title are paid and any outstanding notices of violations of this chapter or of license conditions are resolved.

(16)

Each licensee shall submit to the agency all records required by §289.202(nn)(2) of this title before the license is terminated.

(z)

Renewal of license.

(1)

Requests for renewal of specific licenses shall be filed in accordance with subsection (d)(1)-(3) and (5) of this section.

(2)

In any case in which a licensee, not less than 30 days prior to expiration of an existing license, has filed a request in proper form for renewal or for a new license authorizing the same activities, such existing license shall not expire until the request has been finally determined by the agency. In any case in which a licensee, not more than 90 days after the expiration of an existing license, has filed a request in proper form for renewal or for a new license authorizing the same activities, the agency may reinstate the license and extend the expiration until the request has been finally determined by the agency.

(aa)

Amendment of licenses at request of licensee.

(1)

Requests for amendment of a license shall be filed in accordance with subsection (d)(1)-(3) of this section shall be signed by management or the RSO, and shall specify the respects in which the licensee desires a license to be amended and the grounds for the amendment.

(2)

Requests for amendments to delete a subsite from a license shall be filed in accordance with subsections (d)(1) and (2) and (y)(3) and (15) of this section.

(bb)

Agency action on requests to renew or amend. In considering a request by a licensee to renew or amend a license, the agency will apply the criteria in subsection (e) of this section as applicable.

(cc)

Transfer of material.

(1)

No licensee shall transfer radioactive material except as authorized in accordance with this chapter. This subsection does not include transfer for commercial distribution.

(2)

Except as otherwise provided in a license and subject to the provisions of paragraphs (3) and (4) of this subsection, any licensee may transfer radioactive material:

(A)

to the agency (A licensee may transfer material to the agency only after receiving prior approval from the agency.);

(B)

to the United States Department of Energy (DOE);

(C)

to any person exempt from this section to the extent permitted in accordance with such exemption;

(D)

to any person authorized to receive such material in accordance with the terms of a general license or its equivalent, or a specific license or equivalent licensing document, issued by the agency, the NRC, any agreement state, or any licensing state, or to any person otherwise authorized to receive such material by the federal government or any agency of the federal government, the agency, any agreement state, or any licensing state; or

(E)

as otherwise authorized by the agency in writing.

(3)

Before transferring radioactive material to a specific licensee of the agency, the NRC, an agreement state, or a licensing state, or to a general licensee who is required to register with the agency, the NRC, an agreement state, or a licensing state prior to receipt of the radioactive material, the licensee transferring the material shall verify that the transferee's license authorizes the receipt of the type, form, and quantity of radioactive material to be transferred.

(4)

The following methods for the verification required by paragraph (3) of this subsection are acceptable.

(A)

The transferor may possess and have read a current copy of the transferee's specific license.

(B)

When a current copy of the transferee's specific license described in subparagraph (A) of this paragraph is not readily available or when a transferor desires to verify that information received is correct or up-to-date, the transferor may obtain and record confirmation from the agency, the NRC, or the licensing agency of an agreement state or a licensing state that the transferee is licensed to receive the radioactive material.

(5)

Preparation for shipment and transport of radioactive material shall be in accordance with the provisions of subsection (ff) of this section.

(dd)

Modification and revocation of licenses.

(1)

The terms and conditions of all licenses shall be subject to amendment, revision, or modification. A license may be suspended or revoked by reason of amendments to the Act, or by reason of rules in this chapter and orders issued by the agency.

(2)

Any license may be revoked, suspended, or modified, in whole or in part, for any of the following:

(A)

any material false statement in the application or any statement of fact required under provisions of the Act;

(B)

conditions revealed by such application or statement of fact or any report, record, or inspection, or other means that would warrant the agency to refuse to grant a license on an original application; or

(C)

violation of, or failure to observe any of the terms and conditions of the Act, this chapter, or of the license, or order of the agency.

(3)

Each specific license revoked by the agency ends at the end of the day on the date of the agency's final determination to revoke the license, or on the revocation date stated in the determination, or as otherwise provided by the agency order.

(4)

Except in cases in which the occupational and public health, interest or safety requires otherwise, no license shall be modified, suspended, or revoked unless, prior to the institution of proceedings therefore, facts or conduct that may warrant such action shall have been called to the attention of the licensee in writing and the licensee shall have been accorded an opportunity to demonstrate compliance with all lawful requirements.

(ee)

Reciprocal recognition of licenses.

(1)

Subject to this section, any person who holds a specific license from the NRC, any agreement state, or any licensing state, and issued by the agency having jurisdiction where the licensee maintains an office for directing the licensed activity and at which radiation safety records are normally maintained, is hereby granted a general license to conduct the activities authorized in such licensing document within the state of Texas provided that:

(A)

the licensing document does not limit the activity authorized by such document to specified installations or locations;

(B)

the out-of-state licensee notifies the agency in writing at least three working days prior to engaging in such activity. If, for a specific case, the three working-day period would impose an undue hardship on the out-of-state licensee, the licensee may, upon application to the agency, obtain permission to proceed sooner. The agency may waive the requirement for filing additional written notifications during the remainder of the calendar year following the receipt of the initial notification from a person engaging in activities in accordance with the general license provided in this subsection. Such notification shall include:

(i)

the exact location, start date, duration, and type activity to be conducted;

(ii)

the identification of the sealed sources of radiation to be used;

(iii)

the name(s) and in-state address(es) of the individual(s) performing the activity;

(iv)

a copy of the pertinent license;

(v)

a copy of the licensee's operating, safety, and emergency procedures; and

(vi)

an annual fee as specified in §289.204 of this title.

(C)

the out-of-state licensee complies with all applicable rules of the agency and with all the terms and conditions of the licensee's licensing document, except any such terms and conditions that may be inconsistent with applicable rules of the agency;

(D)

the out-of-state licensee supplies such other information as the agency may request; and

(E)

the out-of-state licensee shall not transfer or dispose of radioactive material possessed or used in accordance with the general license provided in this subsection except by transfer to a person:

(i)

specifically licensed by the agency, the NRC, another agreement state, or another licensing state to receive such material, or

(ii)

exempt from the requirements for a license for such material in accordance with §289.251(e)(1) of this title.

(2)

In addition to the provisions of paragraph (1) of this subsection, any person who holds a specific license issued by the NRC, an agreement state, or a licensing state authorizing the holder to manufacture, transfer, install, or service the device described in §289.251 (h)(1)(C) and (k)(1) of this title, within areas subject to the jurisdiction of the licensing body, is hereby granted a general license to install, transfer, demonstrate, or service the device in the state of Texas provided that:

(A)

the person files a report with the agency within 30 days after the end of each calendar quarter in which any device is transferred to or installed in the state of Texas. Each report shall identify by name and address, each general licensee to whom the device is transferred, the type of device transferred by manufacturer's name, model and serial number of the device, and serial number of the sealed source, and the quantity and type of radioactive material contained in the device;

(B)

the device has been manufactured, labeled, installed, and serviced in accordance with applicable provisions of the specific license issued to the person by the NRC, an agreement state, or a licensing state;

(C)

the person assures that any labels required to be affixed to the device in accordance with requirements of the authority that licensed manufacture of the device bear a statement that "Removal of this label is prohibited"; and

(D)

the holder of the specific license furnishes to each general licensee to whom the holder of the specific license transfers the device, or on whose premises the holder of the specific license installs the device, a copy of the general license contained in §289.251(h)(1)(C) and (k)(1) of this title.

(3)

The agency may withdraw, limit, or qualify its acceptance of any specific license or equivalent licensing document issued by another agency, or any product distributed in accordance with the licensing document, upon determining that the action is necessary in order to prevent undue hazard to occupational and public health and safety or the environment.

(ff)

Preparation of radioactive material for transport. Requirements for the preparation of radioactive material for transport are specified in §289.257 of this title.

(gg)

Financial assurance and record keeping for decommissioning.

(1)

The applicant for each specific license authorizing the possession and use of unsealed radioactive material with a half-life greater than 120 days and in quantities exceeding 10 5 times the applicable quantities set forth in subsection (ii)(2) of this section shall submit a decommissioning funding plan as described in paragraph (5) of this subsection in an amount sufficient to allow the agency to engage a third party to decommission the license. The decommissioning funding plan must also be submitted when a combination of isotopes is involved if R divided by 10 5 is greater than 1 (unity rule), where R is defined as the sum of the ratios of the quantity of each isotope to the applicable value in subsection (ii)(2) of this section.

(2)

The applicant for each specific license authorizing possession and use of radioactive material of half-life greater than 120 days and in quantities specified in paragraph (4) of this subsection shall either:

(A)

submit a decommissioning funding plan as described in paragraph (5) of this subsection in an amount sufficient to allow the agency to engage a third party to decommission the license; or

(B)

submit a certification that financial assurance for decommissioning has been provided in the amount in accordance with paragraph (4) of this subsection using one of the methods described in paragraph (6) of this subsection in an amount sufficient to allow the agency to engage a third party to decommission the license. For an applicant, this certification may state that the appropriate assurance will be obtained after the application has been approved and the license issued, but prior to the receipt of licensed material. If the applicant defers execution of the financial instrument until after the license has been issued, a signed original of the financial instrument obtained to satisfy the requirements of paragraph (6) of this subsection shall be submitted to the agency before receipt of licensed material. If the applicant does not defer execution of the financial instrument, as part of the certification, a signed original of the financial instrument obtained to satisfy the requirements of paragraph (6) of this subsection shall be submitted to the agency.

(3)

The holder of each specific license issued:

(A)

on or after January 1, 1995, that is of a type described in paragraph (2) of this subsection shall provide financial assurance for decommissioning in accordance with the criteria specified in this section;

(B)

before January 1, 1995, and of a type described in paragraph (1) of this subsection, shall submit on or before January 1, 1995, a decommissioning funding plan or a certification of financial assurance for decommissioning in an amount at least equal to $750,000, in accordance with the criteria specified in this section. If the licensee submits the certification of financial assurance rather than a decommissioning funding plan at this time, the licensee shall include a decommissioning funding plan in any application for license renewal;

(C)

before January 1, 1995, and of a type described in paragraph (2) of this subsection, shall submit on or before January 1, 1995, a certification of financial assurance for decommissioning or a decommissioning funding plan in accordance with the criteria specified in this section.

(4)

The required amounts of financial assurance for decommissioning are determined by quantity of material and are as follows:

(A)

$750,000 for quantities of material greater than 104 but less than or equal to 10 5 times the applicable quantities in subsection (ii)(2) of this section in unsealed form. (For a combination of radionuclides, if R, as defined in paragraph (1) of this subsection, divided by 10 4 is greater than 1 but R divided by 10 5 is less than or equal to one.);

(B)

$150,000 for quantities of material greater than 103 but less than or equal to 10 4 times the applicable quantities in subsection (ii)(2) of this section in unsealed form. (For a combination of radionuclides, if R, as defined in paragraph (1) of this subsection, divided by 10 3 is greater than 1 but R divided by 10 4 if less than or equal to one.); or

(C)

$75,000 for quantities of material greater than 1010 times the applicable quantities in subsection (ii)(2) of this section in sealed sources or plated foils. (For a combination of radionuclides, if R, as defined in paragraph (1) of this subsection, divided by 10 10 is greater than one.)

(5)

Each decommissioning funding plan must contain a cost estimate for decommissioning in an amount sufficient to allow the agency to engage a third party to decommission the license and a description of the method of assuring funds for decommissioning from paragraph (6) of this subsection, including means of adjusting cost estimates and associated funding levels periodically over the life of the facility. The decommissioning funding plan shall also contain a certification by the licensee that financial assurance for decommissioning has been provided in an amount sufficient to allow the agency to engage a third party to decommission the license and a signed original of the financial instrument obtained to satisfy the requirements of paragraph (6) of this subsection.

(6)

Financial assurance for decommissioning must be provided by one or more of the following methods and must be reviewed and approved by the agency.

(A)

Prepayment. Prepayment is the deposit prior to the start of operation into an account segregated from licensee assets and outside the licensee's administrative control of cash or liquid assets such that the amount of funds would be sufficient to pay decommissioning costs. Prepayment may be in the form of a trust, escrow account, government fund, certificate of deposit, or deposit of government securities.

(B)

A surety method, insurance, or other guarantee method. These methods guarantee that decommissioning costs will be paid. A surety method may be in the form of a surety bond, letter of credit, or line of credit. A parent company guarantee of funds for decommissioning costs based on a financial test may be used if the guarantee and test are as contained in subsection (ii)(3) of this section. A parent company guarantee may not be used in combination with other financial methods to satisfy the requirements of this section. For commercial corporations that issue bonds, a guarantee of funds by the applicant or licensee for decommissioning costs based on a financial test may be used if the guarantee and test are as contained in subsection (ii)(4) of this section. For commercial companies that do not issue bonds, a guarantee of funds by the applicant or licensee for decommissioning costs may be used if the guarantee and test are as contained in subsection (ii)(5) of this section. For nonprofit entities, such as colleges, universities, and nonprofit hospitals, a guarantee of funds by the applicant or licensee may be used if the guarantee and test are as contained in subsection (ii)(6) of this section. A guarantee by the applicant or licensee may not be used in combination with any other financial methods to satisfy the requirements of this section or in any situation where the applicant or licensee has a parent company holding majority control of the voting stock of the company. Any surety method or insurance used to provide financial assurance for decommissioning must contain the following conditions.

(i)

The surety method or insurance must be open-ended or, if written for a specified term, such as five years, must be renewed automatically unless 90 days or more prior to the renewal date, the issuer notifies the agency, the beneficiary, and the licensee of its intention not to renew. The surety method or insurance must also provide that the full face amount be paid to the beneficiary automatically prior to the expiration without proof of forfeiture if the licensee fails to provide a replacement acceptable to the agency within 30 days after receipt of notification of cancellation.

(ii)

The surety method or insurance must be payable to a trust established for decommissioning costs. The trustee and trust must be acceptable to the agency. An acceptable trustee includes an appropriate state or federal government agency or an entity that has the authority to act as a trustee and whose trust operations are regulated and examined by a federal or state agency.

(iii)

The surety method or insurance must remain in effect until the agency has terminated the license.

(C)

An external sinking fund in which deposits are made at least annually, coupled with a surety method or insurance, the value of which may decrease by the amount being accumulated in the sinking fund. An external sinking fund is a fund established and maintained by setting aside funds periodically in an account segregated from licensee assets and outside the licensee's administrative control in which the total amount of funds would be sufficient to pay decommissioning costs at the time termination of operation is expected. An external sinking fund may be in the form of a trust, escrow account, government fund, certificate of deposit, or deposit of government securities. The surety or insurance provisions must be in accordance with subparagraph (B) of this paragraph.

(D)

In the case of federal, state, or local government licensees, a statement of intent containing a cost estimate for decommissioning or an amount in accordance with paragraph (4) of this subsection, and indicating that funds for decommissioning will be obtained when necessary.

(E)

When a governmental entity is assuming custody and ownership of a site, there shall be an arrangement that is deemed acceptable by such governmental entity.

(7)

Each person licensed in accordance with this section shall keep records of information important to the safe and effective decommissioning of the facility in an identified location until the license is terminated by the agency. If records of relevant information are kept for other purposes, reference to these records and their locations may be used. Information the agency considers important to decommissioning consists of the following:

(A)

records of spills or other unusual occurrences involving the spread of contamination in and around the facility, equipment, or site. These records may be limited to instances when contamination remains after any cleanup procedures or when there is reasonable likelihood that contaminants may have spread to inaccessible areas, as in the case of possible seepage into porous materials such as concrete. These records must include any known information on identification of involved nuclides, quantities, forms, and concentrations;

(B)

as-built drawings and modifications of structures and equipment in restricted areas where radioactive materials are used and/or stored, and of locations of possible inaccessible contamination such as buried pipes that may be subject to contamination. If required drawings are referenced, each relevant document need not be indexed individually. If drawings are not available, the licensee shall substitute appropriate records of available information concerning these areas and locations;

(C)

except for areas containing only sealed sources (provided the sealed sources have not leaked or no contamination remains after any leak) or byproduct materials having only half-lives of less than 65 days, a list contained in a single document and updated every two years, of the following:

(i)

all areas designated and formerly designated as restricted areas as defined in §289.201(b) of this title;

(ii)

all areas outside of restricted areas that require documentation under subparagraph (A) of this paragraph; and

(iii)

all areas outside of restricted areas where current and previous wastes have been buried as documented in accordance with §289.202(tt) of this title; and

(D)

records of the cost estimate performed for the decommissioning funding plan or of the amount certified for decommissioning, and records of the funding method used for assuring funds if either a funding plan or certification is used.

(8)

Any licensee who has submitted an application before January 1, 1995, for renewal of license in accordance with this section shall provide financial assurance for decommissioning in accordance with paragraphs (1) and (2) of this subsection. This assurance shall be submitted when this section becomes effective March 1, 1998.

(hh)

Emergency plan for responding to a release.

(1)

A new or renewal application for each specific license to possess radioactive materials in unsealed form, on foils or plated sources, or sealed in glass in excess of the quantities in subsection (ii)(7) of this section must contain either:

(A)

an evaluation showing that the maximum dose to a person offsite due to a release of radioactive material would not exceed 1 rem effective dose equivalent or 5 rems to the thyroid; or

(B)

an emergency plan for responding to a release of radioactive material.

(2)

One or more of the following factors may be used to support an evaluation submitted in accordance with paragraph (1)(A) of this subsection:

(A)

the radioactive material is physically separated so that only a portion could be involved in an accident;

(B)

all or part of the radioactive material is not subject to release during an accident because of the way it is stored or packaged;

(C)

the release fraction in the respirable size range would be lower than the release fraction in subsection (ii)(7) of this section due to the chemical or physical form of the material;

(D)

the solubility of the radioactive material would reduce the dose received;

(E)

facility design or engineered safety features in the facility would cause the release fraction to be lower than that in subsection (ii)(7) of this section;

(F)

operating restrictions or procedures would prevent a release fraction as large as that in subsection (ii)(7) of this section; or

(G)

other factors appropriate for the specific facility.

(3)

An emergency plan for responding to a release of radioactive material submitted in accordance with paragraph (1)(B) of this subsection must include the following information.

(A)

Facility description. A brief description of the licensee's facility and area near the site.

(B)

Types of accidents. An identification of each type of radioactive materials accident for which protective actions may be needed.

(C)

Classification of accidents. A classification system for classifying accidents as alerts or site area emergencies.

(D)

Detection of accidents. Identification of the means of detecting each type of accident in a timely manner.

(E)

Mitigation of consequences. A brief description of the means and equipment for mitigating the consequences of each type of accident, including those provided to protect workers onsite, and a description of the program for maintaining the equipment.

(F)

Assessment of releases. A brief description of the methods and equipment to assess releases of radioactive materials.

(G)

Responsibilities. A brief description of the responsibilities of licensee personnel should an accident occur, including identification of personnel responsible for promptly notifying offsite response organizations and the agency; also, responsibilities for developing, maintaining, and updating the plan.

(H)

Notification and coordination. A commitment to and a brief description of the means to promptly notify offsite response organizations and request offsite assistance, including medical assistance for the treatment of contaminated injured onsite workers when appropriate. A control point must be established. The notification and coordination must be planned so that unavailability of some personnel, parts of the facility, and some equipment will not prevent the notification and coordination. The licensee shall also commit to notify the agency immediately after notification of the appropriate offsite response organizations and not later than one hour after the licensee declares an emergency. These reporting requirements do not supersede or release licensees of complying with the requirements in accordance with the Emergency Planning and Community Right-to-Know-Act of 1986, Title III, Publication L. 99-499 or other state or federal reporting requirements.

(I)

Information to be communicated. A brief description of the types of information on facility status, radioactive releases, and recommended protective actions, if necessary, to be given to offsite response organizations and to the agency.

(J)

Training. A brief description of the frequency, performance objectives, and plans for the training that the licensee will provide workers on how to respond to an emergency, including any special instructions and orientation tours the licensee would offer to fire, police, medical, and other emergency personnel. The training shall familiarize personnel with site-specific emergency procedures. Also, the training shall thoroughly prepare site personnel for their responsibilities in the event of accident scenarios postulated as most probable for the specific site, including the use of team training for such scenarios.

(K)

Safe shutdown. A brief description of the means of restoring the facility to a safe condition after an accident.

(L)

Exercises. Provisions for conducting quarterly communications checks with offsite response organizations at intervals not to exceed three months and biennial onsite exercises to test response to simulated emergencies. Communications checks with offsite response organizations must include the check and update of all necessary telephone numbers. The licensee shall invite offsite response organizations to participate in the biennial exercises. Participation of offsite response organizations in biennial exercises, although recommended, is not required. Exercises must use accident scenarios postulated as most probable for the specific site and the scenarios shall not be known to most exercise participants. The licensee shall critique each exercise using individuals not having direct implementation responsibility for the plan. Critiques of exercises must evaluate the appropriateness of the plan, emergency procedures, facilities, equipment, training of personnel, and overall effectiveness of the response. Deficiencies found by the critiques must be corrected.

(M)

Hazardous chemicals. A certification that the applicant has met its responsibilities in accordance with the Emergency Planning and Community Right-to-Know Act of 1986, Title III, Publication L. 99-499, if applicable to the applicant's activities at the proposed place of use of the radioactive material.

(4)

The licensee shall allow the offsite response organizations expected to respond in case of an accident 60 days to comment on the licensee's emergency plan before submitting it to the agency. The licensee shall provide any comments received within the 60 days to the agency with the emergency plan.

(ii)

Appendices.

(1)

Subjects to be included in training courses:

(A)

fundamentals of radiation safety:

(i)

characteristics of radiation;

(ii)

units of radiation dose (rem) and activity of radioactivity (curie);

(iii)

significance of radiation dose;

(I)

radiation protection standards; and.

(II)

biological effects of radiation;

(iv)

levels of radiation from sources of radiation;

(v)

methods of controlling radiation dose;

(I)

time;

(II)

distance; and

(III)

shielding;

(vi)

radiation safety practices, including prevention of contamination and methods of decontamination; and

(vii)

discussion of internal exposure pathways;

(B)

radiation detection instrumentation to be used:

(i)

radiation survey instruments:

(I)

operation;

(II)

calibration; and

(III)

limitations;

(ii)

survey techniques;

(iii)

individual monitoring devices;

(C)

equipment to be used:

(i)

handling equipment and remote handling tools;

(ii)

sources of radiation;

(iii)

storage, control, disposal, and transport of equipment and sources of radiation;

(iv)

operation and control of equipment; and

(v)

maintenance of equipment;

(D)

the requirements of pertinent federal and state regulations;

(E)

the licensee's written operating, safety, and emergency procedures; and

(F)

the licensee's record keeping procedures.

(2)

Isotope quantities (for use in subsection (gg) of this section).

Figure: 25 TAC §289.252(ii)(2)

(3)

Criteria relating to use of financial tests and parent company guarantees for providing reasonable assurance of funds for decommissioning.

(A)

Introduction. An applicant or licensee may provide reasonable assurance of the availability of funds for decommissioning based on obtaining a parent company guarantee that funds will be available for decommissioning costs and on a demonstration that the parent company passes a financial test. This paragraph establishes criteria for passing the financial test and for obtaining the parent company guarantee.

(B)

Financial test.

(i)

To pass the financial test, the parent company must meet the criteria of either subclause (I) or (II) of this clause.

(I)

The parent company must have:

(-a-)

two of the following three ratios:

(-1-)

a ratio of total liabilities to net worth less than 2.0;

(-2-)

a ratio of the sum of net income plus depreciation, depletion, and amortization to total liabilities greater than 0.1; and

(-3-)

a ratio of current assets to current liabilities greater than 1.5;

(-b-)

net working capital and tangible net worth each at least six times the current decommissioning cost estimates for the total of all facilities or parts thereof (or prescribed amount if a certification is used);

(-c-)

tangible net worth of at least $10 million; and

(-d-)

assets located in the United States amounting to at least 90% of total assets or at least six times the current decommissioning cost estimates for the total of all facilities or parts thereof (or prescribed amount if a certification is used.)

(II)

The parent company must have:

(-a-)

a current rating for its most recent bond issuance of AAA, AA, A, or BBB as issued by Standard and Poor's or Aaa, Aa, A, or Baa as issued by Moody's;

(-b-)

tangible net worth each at least six times the current decommissioning cost estimate for the total of all facilities or parts thereof (or prescribed amount if a certification is used);

(-c-)

tangible net worth of at least $10 million; and

(-d-)

assets located in the United States amounting to at least 90% of total assets or at least six times the current decommissioning cost estimates for the total of all facilities or parts thereof (or prescribed amount if certification is used).

(ii)

The parent company's independent certified public accountant must have compared the data used by the parent company in the financial test, which is derived from the independently audited, year-end financial statements for the latest fiscal year, with the amounts in such financial statement. In connection with that procedure, the licensee shall inform the agency within 90 days of any matters coming to the auditor's attention that cause the auditor to believe that the data specified in the financial test should be adjusted and that the company no longer passes the test.

(iii)

After the initial financial test, the parent company must repeat the passage of the test within 90 days after the close of each succeeding fiscal year.

(iv)

If the parent company no longer meets the requirements of clause (i) of this subparagraph, the licensee must send notice to the agency of intent to establish alternate financial assurance as specified in the agency's regulations. The notice must be sent by certified mail within 90 days after the end of the fiscal year for which the year end financial data show that the parent company no longer meets the financial test requirements. The licensee must provide alternate financial assurance within 120 days after the end of such fiscal year.

(C)

Parent company guarantee. The terms of a parent company guarantee that an applicant or licensee obtains must provide that:

(i)

the parent company guarantee will remain in force unless the guarantor sends notice of cancellation by certified mail to the licensee and the agency. Cancellation may not occur, however, during the 120 days beginning on the date of receipt of the notice of cancellation by both the licensee and the agency, as evidenced by the return receipts;

(ii)

if the licensee fails to provide alternate financial assurance as specified in the agency's rules within 90 days after receipt by the licensee and the agency of a notice of cancellation of the parent company guarantee from the guarantor, the guarantor will provide such alternative financial assurance in the name of the licensee;

(iii)

the parent company guarantee and financial test provisions must remain in effect until the agency has terminated the license; and

(iv)

if a trust is established for decommissioning costs, the trustee and trust must be acceptable to the agency. An acceptable trustee includes an appropriate state or federal government agency or an entity that has the authority to act as a trustee and whose trust operations are regulated and examined by a federal or state agency.

(4)

Criteria relating to use of financial tests and self guarantees for providing reasonable assurance of funds for decommissioning.

(A)

Introduction. An applicant or licensee may provide reasonable assurance of the availability of funds for decommissioning based on furnishing its own guarantee that funds will be available for decommissioning costs and on a demonstration that the company passes a financial test of subparagraph (B) of this paragraph. Subparagraph (B) of this paragraph establishes criteria for passing the financial test for the self guarantee and establishes the terms for a self guarantee.

(B)

Financial test.

(i)

To pass the financial test, a company must meet all of the following criteria:

(I)

tangible net worth at least 10 times the total current decommissioning cost estimate for the total of all facilities or parts thereof (or the current amount required if certification is used for all decommissioning activities for which the company is responsible as self guaranteeing licensee and as parent-guarantor);

(II)

assets located in the United States amounting to at least 90% of total assets or at least 10 times the total current decommissioning cost estimate (or the current amount required if certification is used for all decommissioning activities for which the company is responsible as self-guaranteeing licensee and as parent-guarantor); and

(III)

a current rating for its most recent bond issuance of AAA, AA, A as issued by Standard and Poor's, or Aaa, Aa, A as issued by Moody's.

(ii)

To pass the financial test, a company must meet all of the following additional criteria:

(I)

the company must have at least one class of equity securities registered under the Securities Exchange Act of 1934.

(II)

the company's independent certified public accountant must have compared the data used by the company in the financial test which is derived from the independently audited year-end financial statements, based on United States generally accepted accounting practices, for the latest fiscal year, with the amounts in such financial statement. In connection with that procedure, the licensee shall inform the agency within 90 days of any matters coming to the auditor's attention that cause the auditor to believe that the data specified in the financial test should be adjusted and that the company no longer passes the test; and

(III)

after the initial financial test, the company must repeat the passage of the test within 90 days after the close of each succeeding fiscal year.

(iii)

If the licensee no longer meets the criteria of clause (i) of this subparagraph, the licensee must send immediate notice to the agency of its intent to establish alternate financial assurance as specified in the agency's rules within 120 days of such notice.

(C)

Company self guarantee. The terms of a self guarantee that an applicant or licensee furnishes must provide that:

(i)

the company guarantee will remain in force unless the licensee sends notice of cancellation by certified mail to the agency. Cancellation may not occur, however, during the 120 days beginning on the date of receipt of the notice of cancellation by the agency, as evidenced by the return receipt;

(ii)

the licensee shall provide alternate financial assurance as specified in the agency's rules within 90 days following receipt by the agency of a notice of cancellation of the guarantee;

(iii)

the guarantee and financial test provisions must remain in effect until the agency has terminated the license or until another financial assurance method acceptable to the agency has been put in effect by the licensee;

(iv)

the licensee will promptly forward to the agency and the licensee's independent auditor all reports covering the latest fiscal year filed by the licensee with the Securities and Exchange Commission in accordance with the requirements of the Securities and Exchange Act of 1934, §13;

(v)

if, at any time, the licensee's most recent bond issuance ceases to be rated in any category of "A" or above by either Standard and Poor's or Moody's, the licensee will provide notice in writing of such fact to the agency within 20 days after publication of the change by the rating service. If the licensee's most recent bond issuance ceases to be rated in any category of A or above by both Standard and Poor's and Moody's, the licensee no longer meets the criteria of subparagraph (B)(i) of this paragraph; and

(vi)

the applicant or licensee must provide to the agency a written guarantee (a written commitment by a corporate officer) that states that the licensee will fund and carry out the required decommissioning activities or, upon issuance of an order by the agency, the licensee will set up and fund a trust in the amount of the current cost estimates for decommissioning.

(5)

Criteria relating to use of financial tests and self guarantees for providing reasonable assurance of funds for decommissioning by commercial companies that have no outstanding rated bonds.

(A)

Introduction. An applicant or licensee may provide reasonable assurance of the availability of funds for decommissioning based on furnishing its own guarantee that funds will be available for decommissioning costs and on a demonstration that the company passes the financial test of subparagraph (B) of this paragraph. The terms of the self-guarantee are in subparagraph (C) of this paragraph. This paragraph establishes criteria for passing the financial test for the self-guarantee and establishes the terms for a self-guarantee.

(B)

Financial test.

(i)

To pass the financial test a company must meet the following criteria:

(I)

tangible net worth greater than $10 million, or at least 10 times the total current decommissioning cost estimate (or the current amount required if certification is used), whichever is greater, for all decommissioning activities for which the company is responsible as self-guaranteeing licensee and as parent-guarantor;

(II)

assets located in the United States amounting to at least 90% of total assets or at least ten times the total current decommissioning cost estimate (or the current amount required if certification is used) for all decommissioning activities for which the company is responsible as self-guaranteeing licensee and as parent-guarantor; and

(III)

a ratio of cash flow divided by total liabilities greater than 0.15 and a ratio of total liabilities divided by net worth less than 1.5.

(ii)

In addition, to pass the financial test, a company must meet all of the following requirements:

(I)

the company's independent certified public accountant must have compared the data used by the company in the financial test, which is required to be derived from the independently audited year end financial statement based on United States generally accepted accounting practices for the latest fiscal year, with the amounts in the financial statement. In connection with that procedure, the licensee shall inform the agency within 90 days of any matters that may cause the auditor to believe that the data specified in the financial test should be adjusted and that the company no longer passes the test;

(II)

after the initial financial test, the company must repeat passage of the test within 90 days after the close of each succeeding fiscal year; and

(III)

if the licensee no longer meets the requirements of subparagraph (B)(i) of this paragraph, the licensee must send notice to the agency of intent to establish alternative financial assurance as specified in the agency's rules. The notice must be sent by certified mail, return receipt requested, within 90 days after the end of the fiscal year for which the year end financial data show that the licensee no longer meets the financial test requirements. The licensee must provide alternative financial assurance within 120 days after the end of such fiscal year.

(C)

Company self-guarantee. The terms of a self-guarantee that an applicant or licensee furnishes must provide the following.

(i)

The guarantee shall remain in force unless the licensee sends notice of cancellation by certified mail, return receipt requested, to the agency. Cancellation may not occur until an alternative financial assurance mechanism is in place.

(ii)

The licensee shall provide alternative financial assurance as specified in the agency rules within 90 days following receipt by the agency of a notice of cancellation of the guarantee.

(iii)

The guarantee and financial test provisions must remain in effect until the agency has terminated the license or until another financial assurance method acceptable to the agency has been put in effect by the licensee.

(iv)

The applicant or licensee must provide to the agency a written guarantee (a written commitment by a corporate officer) that states that the licensee will fund and carry out the required decommissioning activities or, upon issuance of an order by the agency, the licensee will set up and fund a trust in the amount of the current cost estimates for decommissioning.

(6)

Criteria relating to use of financial tests and self-guarantee for providing reasonable assurance of funds for decommissioning by nonprofit entities, such as colleges, universities, and nonprofit hospitals.

(A)

Introduction. An applicant or licensee may provide reasonable assurance of the availability of funds for decommissioning based on furnishing its own guarantee that funds will be available for decommissioning costs and on a demonstration that the applicant or licensee passes the financial test of subparagraph (B) of this paragraph. The terms of the self- guarantee are in subparagraph (C) of this paragraph. This paragraph establishes criteria for passing the financial test for the self-guarantee and establishes the terms for a self-guarantee.

(B)

Financial test.

(i)

To pass the financial test, a college or university must meet the criteria of subclause (I) or (II) of this clause. The college or university must meet one of the following:

(I)

for applicants or licensees that issue bonds, a current rating for its most recent uninsured, uncollateralized, and unencumbered bond issuance of AAA, AA, or A as issued by Standard and Poors or Aaa, Aa, or A as issued by Moodys.

(II)

for applicants or licensees that do not issue bonds, unrestricted endowment consisting of assets located in the United States of at least $50 million, or at least 30 times the total current decommissioning cost estimate (or the current amount required if certification is used), whichever is greater, for all decommissioning activities for which the college or university is responsible as a self-guaranteeing licensee.

(ii)

To pass the financial test, a hospital must meet the criteria in subclause (I) or (II) of this clause. The hospital must meet one of the following:

(I)

for applicants or licensees that issue bonds, a current rating for its most recent uninsured, uncollateralized, and unencumbered bond issuance of AAA, AA, or A as issued by Standard and Poors or Aaa, Aa, or A as issued by Moodys;

(II)

for applicants or licensees that do not issue bonds, all the following tests must be met:

(-a-)

(total revenues less total expenditures) divided by total revenues must be equal to or greater than 0.04;

(-b-)

long term debt divided by net fixed assets must be less than or equal to 0.67;

(-c-)

(current assets and depreciation fund) divided by current liabilities must be greater than or equal to 2.55; and

(-d-)

operating revenues must be at least 100 times the total current decommissioning cost estimate (or the current amount required if certification is used) for all decommissioning activities for which the hospital is responsible as a self-guaranteeing license.

(iii)

In addition, to pass the financial test, a licensee must meet all the following requirements:

(I)

the licensee's independent certified public accountant must have compared the data used by the licensee in the financial test that is required to be derived from the independently audited year-end financial statements, based on United States generally accepted accounting practices, for the latest fiscal year, with the amounts in the financial statement. In connection with that procedure, the licensee shall inform the agency within 90 days of any matters coming to the attention of the auditor that cause the auditor to believe that the data specified in the financial test should be adjusted and that the licensee no longer passes the test;

(II)

after the initial financial test, the licensee must repeat passage of the test within 90 days after the close of each succeeding fiscal year;

(III)

if the licensee no longer meets the requirements of subparagraph (A) of this paragraph, the licensee must send notice to the agency of its intent to establish alternative financial assurance as specified in the agency's rules. The notice must be sent by certified mail, return receipt requested, within 90 days after the end of the fiscal year for which the year end financial data show that the licensee no longer meets the financial test requirements. The licensee must provide alternate financial assurance within 120 days after the end of such fiscal year.

(C)

Self-guarantee. The terms of a self-guarantee that an applicant or licensee furnishes must provide the following:

(i)

The guarantee shall remain in force unless the licensee sends notice of cancellation by certified mail, and/or return receipt requested, to the agency. Cancellation may not occur unless an alternative financial assurance mechanism is in place.

(ii)

The licensee shall provide alternative financial assurance as specified in the agency's regulations within 90 days following receipt by the agency of a notice of cancellation of the guarantee.

(iii)

The guarantee and financial test provisions must remain in effect until the agency has terminated the license or until another financial assurance method acceptable to the agency has been put in effect by the licensee.

(iv)

The applicant or licensee must provide to the agency a written guarantee (a written commitment by a corporate officer or officer of the institution) that states that the licensee will fund and carry out the required decommissioning activities or, upon issuance of an order by the agency, the licensee will set up and fund a trust in the amount of the current cost estimates for decommissioning.

(v)

If, at any time, the licensee's most recent bond issuance ceases to be rated in any category of "A" or above by either Standard and Poors or Moodys, the licensee shall provide notice in writing of the fact to the agency within 20 days after publication of the change by the rating service.

(7)

Quantities of radioactive materials requiring consideration of the need for an emergency plan for responding to a release. The following table contains quantities of radioactive materials requiring consideration of the need for an emergency plan for responding to a release.

Figure: 25 TAC §289.252(ii)(7)

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003513

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


25 TAC §289.253

The Texas Department of Health (department) proposes an amendment to §289.253, concerning radiation safety requirements for well logging service operations and tracer studies.

Government Code §2001.039 requires that each state agency review and consider for readoption each rule adopted by that agency pursuant to the Government Code, Chapter 2001 (Administrative Procedure Act). Section 289.253 has been reviewed and the department has determined that the reasons for adopting the section continue to exist; however, revisions to the rule are necessary.

The amendment deletes the definition for "Licensing state" because it is already defined in another section of this chapter. Language is added to the definitions of "Field station" and "Radiation safety officer" to clarify the intent of the definitions. The words "field station" and "radioactive material" are replaced with the words "additional authorized use/storage location and "sources of radiation" throughout the rule to clarify the intent of the section. Additional units of measurement for radiation survey instruments are added to reflect the International System units of measurement. Language is changed in the design and performance criteria for sealed sources used in well logging prototype testing to reflect appropriate terminology. Optically stimulated luminescence devices are added as an additional option for an appropriate individual monitoring device. Requirements for maintaining records/documents are clarified to specify what records/documents are required for inspection by the agency at additional/authorized use/storage locations and temporary job sites. The time interval for keeping certain records/documents is changed to reflect the agency's current inspection interval. An additional requirement is added to clarify that a licensee must consult with the well operator, well owner, drilling contractor, or land owner regarding retrieval methods for sources disconnected downhole. References to other sections of this chapter are clarified to reflect the Texas Register format. Grammatical changes are made for clarification. This amendment is also part of the department's continuing effort to update, clarify, and simplify its rules regarding the control of radiation based upon technological advances, public concerns, legislative directives, or other factors.

The department published a Notice of Intention to Review for §289.253 as required by Government Code §2001.039 in the Texas Register (25 TexReg 219) on January 7, 2000. No comments were received by the department on this section.

Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, has determined that for each year of the first five years the section will be in effect, there will be no fiscal implications for state or local government as a result of enforcing or administering the section as proposed.

Mrs. McBurney has also determined that for each year of the first five years the proposed section will be in effect, the public benefit anticipated as a result of enforcing the section will be to ensure continued protection of the public, workers, and the environment from unnecessary exposure to radiation. There will be no effect on micro businesses or small businesses. There are no anticipated economic costs to persons who are required to comply with the section as proposed. There is no anticipated impact on local employment. Licensees are currently required to have a written agreement with the well operator, well owner, drilling contractor or land owner concerning sources that are lost downhole. The additional requirement simply requires the licensee to consult concerning the methods of retrieval. The other revisions are clarifying only and do not impose new requirements or alleviate current requirements. Therefore, there are no economic effects associated with the section as proposed.

Comments on the proposal may be presented to Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, Texas Department of Health, 1100 West 49th Street, Austin, Texas 78756-3189, Telephone (512) 834- 6688 or electronic mail at Ruth.Mcburney@tdh.state.tx.us. Public comments will be accepted for 30 days following publication of this proposal in the Texas Register . In addition, a public meeting to accept oral comments will be held at 9:00 a.m., Tuesday, June 20, 2000, in Conference Room N218, Texas Department of Health, Bureau of Radiation Control, located at the Exchange Building, 8407 Wall Street, Austin, Texas.

The amendment is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with the authority to adopt rules for the performance of each duty imposed by law on the board, the department, and the commissioner of health.

The amendment affects Health and Safety Code, Chapter 401 and Chapter 12, and Government Code §2001.039.

§289.253. Radiation Safety Requirements for Well Logging Service Operations and Tracer Studies.

(a)

Purpose [ and scope ]. This section establishes radiation safety requirements for persons using sources of radiation for well logging service operations, including radioactive markers, mineral exploration and tracer studies. [ The requirements of this section are in addition to, and not in substitution for, the requirements of §289.112 of this title (relating to Hearing and Enforcement Procedures), §289.114 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections), §289.119 of this title (relating to Radiation Safety Requirements for Particle Accelerators), §289.122 of this title (relating to Registration of Radiation Machine Use and Services), §289.126 of this title (relating to Fees for Certificates of Registration, Radioactive Material(s) Licenses, Emergency Planning and Implementation, and other Regulatory Services), §289.201 of this title (relating to General Provisions), §289.202 of this title (relating to Standards for Protection Against Radiation), and §289.252 of this title (relating to Licensing of Radioactive Material). This section applies to all licensees or registrants who use sources of radiation for well logging service operations, radioactive markers, mineral exploration and tracer studies. ]

(b)

Scope. This section applies to all licensees or registrants who use sources of radiation for well logging service operations, radioactive markers, mineral exploration and tracer studies. In addition to the requirements of this section, licensees and registrants are subject to the requirements of §289.201 of this title (relating to General Provisions for Radioactive Material), §289.202 of this title (relating to Standards for Protection Against Radiation from Radioactive Material), §289.203 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections), §289.204 of this title (relating to Fees for Certificates of Registration, Radioactive Material Licenses, Emergency Planning and Implementation, and Other Regulatory Services), §289.205 of this title (relating to Hearing and Enforcement Procedures), §289.226 of this title (relating to Registration of Radiation Machine Use and Services), §289.229 of this title (relating to Radiation Safety Requirements for Particle Accelerators, Therapeutic Radiation Machines, and Simulators), §289.231 of this title (relating to General Provisions and Standards for Protection Against Machine-Produced Radiation), §289.252 of this title (relating to Licensing of Radioactive Material), and §289.257 of this title (relating to Packaging and Transportation of Radioactive Material).

(c)

[ (b) ] Definitions. The following words and terms when used in this section shall have the following meaning unless the context clearly indicates otherwise.

(1)

Field station (additional authorized use/storage location) -- A facility where sources of radiation may be stored or used and from which equipment is dispatched to temporary job sites.

(2)

Injection tool -- A device used for controlled injection of radioactive tracer material.

[ (3)

Licensing state -- Any state with rules equivalent to the Suggested State Regulations for Control of Radiation relating to, and an effective program for, the regulatory control of naturally occurring or accelerator-produced radioactive material (NARM) and has been designated as such by the Conference of Radiation Control Program Directors, Inc.]

(3)

[ (4) ] Logging assistant (equipment operator) -- Any individual who, under the personal supervision of a logging supervisor, handles sealed sources or tracers that are not in logging tools or shipping containers or who performs surveys required by subsection (y) [ (x) ] of this section.

(4)

[ (5) ] Logging supervisor (field engineer) -- The individual who provides personal supervision of the use [ utilization ] of sources of radiation at temporary job sites.

(5)

[ (6) ] Logging tool -- A device used subsurface to perform well logging.

(6)

[ (7) ] Mineral logging -- Any logging performed for the purpose of mineral exploration other than oil or gas.

(7)

[ (8) ] Personal supervision -- Guidance and instruction by the supervisor, who is physically present at the job site and in such proximity that visual contact can be maintained and immediate assistance given as required.

(8)

[ (9) ] Radiation safety officer -- An individual named by the licensee or registrant and listed on the license or certificate of registration who has a knowledge of, responsibility for, and authority to enforce appropriate radiation protection rules, standards, and practices on behalf of the licensee and/or registrant; and who meets the requirements of subsection (r) [ (q) ] of this section.

(9)

[ (10) ] Radioactive marker -- Radioactive material placed subsurface or upon a structure intended for subsurface use for the purpose of depth determination or direction orientation.

(10)

[ (11) ] Residential location -- Any area where structures in which people lodge or live are located, and the grounds on which these structures are located including, but not limited to, houses, apartments, condominiums, and garages.

(11)

[ (12) ] Service company -- Any contracted or subcontracted company that is present at the temporary job site, specifically, that company to which the licensee's equipment is connected and that is exposed to radioactive material.

(12)

[ (13) ] Source holder -- A housing or assembly into which a radioactive source is placed for the purpose of facilitating the handling and use of the source.

(13)

[ (14) ] Storage container -- A container designed to provide radiation safety and security when sources of radiation are being stored.

(14)

[ (15) ] Temporary job site -- A location where well logging or tracer studies are performed other than the specific location(s) listed on a license or certificate of registration.

(15)

[ (16) ] Tracer study -- The release of a substance tagged with radioactive material for the purpose of tracing the movement or position of the tagged substance in the wellbore, at the wellhead, or adjacent formation.

(16)

[ (17) ] Transport container -- A container that meets the requirements [ regulations ] of the United States Department of Transportation (DOT) and is designed to provide radiation safety and security when sources of radiation are being transported.

(17)

[ (18) ] Uranium sinker bar -- A weight containing depleted uranium used to aid in the descent of a logging tool down toward the bottom of a wellbore.

(18)

[ (19) ] Wellbore -- A drilled hole in which wireline service operations are performed.

(19)

[ (20) ] Well logging -- All operations involving the lowering and raising of measuring devices or logging tools (that may or may not contain sources of radiation) into wellbores or cavities for the purpose of obtaining information about the well and/or adjacent formations.

(20)

[ (21) ] Wireline -- An armored steel cable containing one or more electrical conductors used to lower and raise logging tools in the wellbore.

(21)

[ (22) ] Wireline service operation -- Any mechanical service that is performed in the wellbore using devices that are lowered into the well on a wireline for purposes of evaluation.

(d)

[ (c) ] Prohibitions [ Prohibition. ]

(1)

No licensee shall perform well logging service operations with a sealed source(s) in any well or wellbore unless, prior to commencement of the operation, the licensee has a written agreement with the well operator, well owner, drilling contractor, or land owner that specifies who will be responsible for ensuring the following requirements are met:

(A)

a reasonable effort at recovery will be made in the event a sealed source is lost or lodged downhole;

(B)

a person shall not attempt to recover a sealed source in a manner that, in the licensee's opinion, could result in a source rupture;

(C)

in the event the environment, any equipment, or personnel are contaminated with radioactive material, decontamination to levels specified in §289.202(f), (n), and (eee) [ §289.202(o) and (eee) ] of this title must be performed; and

(D)

the requirements of subsection (aa)(4) of this section shall be met in the event a decision is made to abandon the sealed source downhole.

(2)

No licensee shall perform tracer study operations with a substance tagged with radioactive material in any well or wellbore unless, prior to commencement of the operation, the licensee has a written agreement with the well operator, well owner, drilling contractor or land owner, and the service company to which the licensee's equipment is connected, as applicable, that specifies who will be responsible for ensuring the following requirements are met:

(A)

in the event the service company's personnel or equipment are contaminated with radioactive material, they must be decontaminated in accordance with §289.202(n) or (eee) [ §289.202(eee) ] of this title before release from the job site or release for unrestricted use;

(B)

in the event the well head or job site is [ are ] contaminated with radioactive material, it [ they ] must be decontaminated in accordance with §289.202(eee) [ §289.202(ddd) ] of this title [ to the concentration limits specified Table II, Column 2 in §289.202(ggg)(1) of this title, with the units changed from microcuries per milliliter to microcuries per gram before release for unrestricted use ]; and

(C)

in the event radioactive material is to be reversed from the well or the well screens out, the licensee must have established procedures and equipment or facilities to do the following:

(i)

reverse material into a preconstructed pit that is specifically established in the event of a screen out; or

(ii)

reverse material into suitable transport container(s) in the event of a screen out.

(3)

The licensee shall maintain a [ A ] copy of the written agreement in accordance with paragraphs (1) or (2) of this subsection [ shall be maintained ] for inspection by the agency for a period of five years following completion of the well logging service operation or tracer study.

(e)

[ (d) ] Limits on levels of radiation. Sources of radiation shall be used, stored, and transported in such a manner that the requirements of §289.202 of this title, §289.231 of this title, and §289.257 [ §289.252(t) ] of this title , as applicable, are met.

(f)

[ (e) ] Storage precautions.

(1)

Each source of radiation, except accelerators, shall be provided with a storage and/or transport container. Each [ The ] container shall have a lock (or tamper seal for calibration sources) to prevent unauthorized removal of, or exposure to, the source of radiation.

(2)

Each area or room in which sources of radiation are stored shall be posted in accordance with §289.202(aa)(5) or §289.231(x) of this title , as applicable .

(3)

Sources of radiation shall be stored downhole or in a bunker in order to minimize the danger from explosion and/or fire.

(4)

Sources of radiation may not be stored in residential locations. This section does not apply to storage of radioactive material in a vehicle in transit for use at temporary job sites, if the licensee complies with subsection (y)(2) [ (x)(2) ] of this section.

(5)

Sources of radiation in storage shall be secured to prevent tampering, or removal by unauthorized individuals.

(g)

[ (f) ] Transport precautions. Transport containers shall be locked and physically secured to the transporting vehicle to prevent shifting during transport, accidental loss, tampering, or unauthorized removal.

(h)

[ (g) ] Radiation survey instruments.

(1)

The licensee or registrant shall maintain a sufficient number of calibrated and operable radiation survey instruments at each location where sources of radiation are [ radioactive material is ] stored or used to make physical radiation surveys as required by this section and by §289.202(p) or §289.231(s), of this title , as applicable . Instrumentation shall be capable of measuring 0.1 milliroentgen per hour (mR/hr) (1 microsievert per hour (µSv/hr)) through at least 50 mR/hr (500 µSv/hr) [ milliroentgens per hour ]. (Instrumentation capable of measuring 0.1 mR/hr (1µSv/hr) through 50 mR/hr (500 µSv/hr) may not be sufficient to determine compliance with [ the regulations of the ] DOT requirements .)

(2)

A licensee using tracer material shall have available at each additional authorized use/storage location [ field station ] and temporary job site additional calibrated and operable radiation survey instruments sensitive enough to detect the radioactive surface contamination limits specified in §289.202(eee) of this title.

(3)

Each radiation survey instrument shall be calibrated:

(A)

by a person specifically licensed or registered by the agency, another agreement state or licensing state or the United States Nuclear Regulatory Commission (NRC) to perform such service;

(B)

at intervals not to exceed six months and after each survey instrument repair;

(C)

for the types of radiation used and at energies appropriate for use; and

(D)

at an accuracy within ñ [ plus or minus ] 20% of the true radiation level at each calibration point.

(4)

The licensee or registrant shall maintain calibration records [ Calibration records shall be maintained ] for a period of three [ five ] years from the date of calibration for inspection by the agency.

(i)

[ (h) ] Leak testing of sealed sources. Sealed sources [ Sources of radioactive material ] shall be tested for leakage and contamination in accordance with §289.201(g) of this title. The licensee shall maintain records [ Records ] of leak tests [ shall be maintained ] for inspection by the agency [ inspection ] for three [ five ] years from the date of the leak test.

(j)

[ (i) ] Quarterly inventory. Each licensee or registrant shall conduct a [ quarterly ] physical inventory to account for all sources of radiation received or possessed at intervals not to exceed three months. The licensee or registrant shall make and maintain records [ Records ] of inventories [ shall be maintained ] for three [ five ] years from the date of the inventory for inspection by the agency and shall include:

(1)

the quantities and kinds of sources of radiation;

(2)

the location where sources of radiation are assigned;

(3)

a unique identification of each source of radiation;

(4)

the date of the inventory; and

(5)

the name of the individual conducting the inventory.

(k)

[ (j) ] Utilization records. Each licensee or registrant shall make and maintain utilization records. Utilization records shall be maintained for three years from the date of the inventory for inspection by the agency and shall include the following information for each source of radiation: [ Each licensee or registrant shall maintain current records, that shall be kept available for inspection by the agency for five years from the date of the recorded event, showing the following information for each source of radiation: ]

(1)

identification of each source of radiation to include:

(A)

the make and model number and/or serial number (or if absent, a description) of each sealed source used; or

(B)

the radionuclide and activity of tracer materials and radioactive markers used at a particular well site and the disposition of any unused tracer materials.

(2)

the identity of the logging supervisor or individual who is responsible for receiving sources of radiation, to whom assigned; and

(3)

the locations where used and dates of use.

(l)

[ (k) ] Design and performance criteria for sealed sources used in well logging operations.

(1)

Each sealed source manufactured after August 1, 1992, (except those containing radioactive material in gaseous form) [ used in well logging operations ] shall be certified at the time of manufacture to meet the following minimum criteria.

(A)

The sealed source is of doubly encapsulated construction.

(B)

The sealed source contains radioactive material with a chemical/physical form as insoluble and nondispersible as practicable.

(C)

The sealed source's prototype has been tested and found to maintain its integrity after each of the following tests.

(i)

Temperature. The test source must be held at -40 degrees Celsius [ Centigrade ] for 20 minutes, 600 degrees Celsius [ Centigrade ] for one hour, and then be subjected to a thermal shock test with a temperature drop from 600 degrees Celsius [ Centigrade ] to 20 degrees Celsius [ Centigrade ] within 15 seconds.

(ii)

Impact. A 5 kilogram (kg) steel hammer, 2.5 centimeters (cm) in diameter, must be dropped from a height of 1 meter (m) onto the test source.

(iii)

Vibration. The test source must be subjected to a vibration from 25 Hertz (Hz) [ Hz ] to 500 Hz with a peak amplitude of five times the acceleration of gravity [ at 5 g amplitude ] for 30 minutes.

(iv)

Puncture. A 1 gm [ gram ] hammer and pin, 0.3 cm [ centimeter ] pin diameter, must be dropped from a height of 1 m [ meter ] onto the test source.

(v)

Pressure. The test source must be subjected to an external pressure of 24,600 pounds per square inch absolute (1.695 x 10 7 pascals) [ 1.695 x 107 Pascal) ] without leakage.

(2)

In the absence of prototype testing required by paragraph (1)(C) of this subsection, sealed sources (except those containing radioactive material in gaseous form) used after January 1, 1993, shall be certified to meet the requirements of paragraph (1)(C) of this subsection.

(3)

Certification of source criteria as required by paragraphs (1) and (2) of this subsection shall be performed only by persons specifically authorized to do so by the agency, another agreement or licensing state, or the NRC.

(4)

Certification documents shall be maintained by the licensee for inspection by the agency for a period of three [ five ] years after source disposal.

(m)

[ (l) ] Labeling.

(1)

Each source, source holder, or logging tool containing radioactive material in other than an exempt quantity, shall bear a durable, legible, and clearly visible marking or label that has, as a minimum, the standard radiation caution symbol with no color requirement, and the wording DANGER (or CAUTION), RADIOACTIVE--DO NOT HANDLE, NOTIFY CIVIL AUTHORITIES (OR NAME OF COMPANY).

(2)

The labeling specified in paragraph (1) of this subsection shall be on the smallest component , source, source holder, or logging tool, [ (i.e., source, source holder, or logging tool) ] that is transported as a separate piece of equipment.

(3)

Each transport container shall have permanently attached to it a durable, legible, and clearly visible label that has, as a minimum, the standard radiation caution symbol and the wording DANGER (or CAUTION), RADIOACTIVE, NOTIFY CIVIL AUTHORITIES (OR NAME OF COMPANY).

(4)

Each [ After August 1, 1993, each ] transport container shall have attached to it a durable, legible, and clearly visible label(s) that has, as a minimum, the licensee's name, address, and telephone number, the radionuclide, its activity, and [ the ] assay date.

(n)

[ (m) ] Inspection and maintenance.

(1)

Each licensee or registrant shall conduct, at intervals not to exceed six months, a program of visual inspection and maintenance of source holders (or sealed source, if there is no source holder), logging tools, source handling tools, storage containers, transport containers, and injection tools to assure proper labeling and physical condition. The inspection program may be performed concurrently with routine leak testing of sealed sources. Records of inspection and maintenance shall be made and maintained by the licensee or registrant for a period of three [ five ] years for inspection by the agency.

(2)

If any inspection conducted in accordance with paragraph (1) of this subsection reveals damage to labeling or components critical to radiation safety, the device shall be removed from service at the time the damage is discovered and until repairs have been made.

(3)

Any operation, such as drilling, cutting, or chiseling on a source holder containing a sealed source, shall be performed on the source holder only by persons specifically licensed to do so by the agency, another agreement or licensing state, or the NRC. The provisions of this paragraph do not apply to logging tool recovery (fishing) operations conducted in accordance with the provisions of subsection (aa)(3) of this section.

(4)

The repair, opening, or modification of any sealed source shall be performed only by persons specifically licensed to do so by the agency, another agreement or licensing state, or the NRC.

(o)

[ (n) ] Training requirements.

(1)

No licensee or registrant shall permit any individual to act as a logging supervisor until such individual has met the following requirements :

(A)

successfully completed an agency-accepted course or [ in ] a course recognized by [ the agency, ] another agreement or licensing state, or the NRC, including at least 24 hours of formal training in the subjects outlined in subsection (bb)(1) of this section;

(B)

received copies of and instruction in the following :

(i)

the requirements [ rules ] contained in this section and the applicable subsections of §§[ 289.114, ] 289.201, 289.202, 289.203 , and 289.231 of this title or their equivalent , as applicable ;

(ii)

the conditions of the appropriate license or certificate of registration; and

(iii)

the licensee's or registrant's operating , safety , and emergency procedures;

(C)

demonstrated understanding of the requirements in subparagraph (A) and (B) of this paragraph by successfully completing a written examination administered by the licensee or registrant;

(D)

completed two months of on-the-job training under the supervision of a logging supervisor; and

(E)

demonstrated through a field evaluation, competence in the use of sources of radiation, related handling tools, and the type of radiation survey instruments that will be used in the job assignment.

(2)

No licensee or registrant shall permit any individual to act as a logging assistant until such individual has met the following requirements :

(A)

received copies of and instruction in the applicable subsections of §§[ 289.114 ,] 289.201, 289.202 , 289.203, and 289.231 of this title or their equivalent , as applicable, and the licensee's or registrant's operating and emergency procedures;

(B)

demonstrated understanding of the requirements in subparagraph (A) of this paragraph by successfully completing a written examination administered by the licensee or registrant; and

(C)

demonstrated competence to use, under the personal supervision of the logging supervisor, the sources of radiation, related handling tools, and radiation survey instruments that will be used in the job assignment.

(3)

The licensee or registrant shall provide an annual radiation safety review for logging supervisors and logging assistants.

(4)

Each licensee or registrant shall maintain records that document that the requirements of paragraphs (1)-(3) [ (1), (2), and (3) ] of this subsection are met. Such records shall be maintained for inspection by the agency for three years after the employee terminates employment with the licensee or registrant [ until the agency authorizes their disposal ].

(p)

[ (o) ] Operating , safety, and emergency procedures. The licensee or registrant shall maintain written operating , safety, and emergency procedures that include descriptions of and directions in at least the items listed in subsection (bb)(4) of this section.

(q)

[ (p) ] Personnel monitoring.

(1)

In addition to the requirements of §289.202(p)(3) and (q) [ §289.202(p) and (q) ] of this title or §289.231(n) and (s)(3) of this title, as applicable, no licensee or registrant shall permit any individual to act as a logging supervisor or logging assistant unless that individual wears either a film badge , [ or ] a thermoluminescent dosimeter (TLD) , or an optically stimulated luminescence device (OSL) at all times during well logging service operations and/or tracer studies utilizing sources of radiation. Each film badge , [ or ] TLD , or OSL shall be assigned to and worn by only one individual. Film badges must be replaced at least monthly . TLDs and OSLs must be [ and TLDs ] replaced at least quarterly. After replacement, each film badge , [ or ] TLD , or OSL must be returned to the supplier for processing within 14 calendar days or as soon as practicable. In circumstances that make it impossible to return each film badge , [ or ] TLD , or OSL within 14 calendar days, such circumstances must be documented and available for review by the agency.

(2)

When necessary in order to aid in determining the extent of an individual's exposure to concentrations of radioactive material, the agency may require a licensee to make available to the individual appropriate bioassay services and to furnish a copy of the reports of such services to the agency.

(3)

Personnel monitoring records shall be maintained by the licensee or registrant for inspection by the agency until the agency authorizes their disposal.

(r)

[ (q) ] Radiation safety officer.

(1)

A radiation safety officer (RSO) shall be designated for every license and certificate of registration issued by the agency.

(2)

The RSO's documented qualifications shall include:

(A)

possession of a high school diploma or a certificate of high school equivalency based on the GED test;

(B)

completion of the training and testing requirements of subsection (o)(1) [ (n)(1) ] of this section; and

(C)

two years of experience as a logging supervisor to include knowledge of well logging service operations and tracer studies.

(3)

The [ specific ] duties of the RSO include, but are not limited to, the following:

(A)

[ to ] establish and oversee operating , safety, and [ , ] emergency, and as low as reasonably achievable (ALARA) procedures, and to review them regularly to ensure that the procedures are current and conform with this chapter;

(B)

[ to ] oversee and approve all phases of the training program for well logging service operations and/or tracer studies personnel so that appropriate and effective radiation protection practices are taught;

(C)

[ to ] ensure that required radiation surveys and leak tests are performed and documented in accordance with this chapter, including any corrective measures when levels of radiation exceed established limits;

(D)

[ to ] ensure that personnel monitoring is used properly by occupationally-exposed personnel, that records are kept of the monitoring results, and that timely notifications are made as required by §289.203 [ §289.114 ] of this title;

(E)

[ to ] investigate and report to the agency each known or suspected case of radiation exposure to an individual or radiation level detected in excess of limits established by this chapter and each theft or loss of source(s) of radiation, to determine the cause, and to take steps to prevent its recurrence;

(F)

[ to ] have a thorough knowledge of management policies and administrative procedures of the licensee or registrant;

(G)

[ to ] assume control and have the authority to institute corrective actions including shutdown of operations when necessary in emergency situations or unsafe conditions;

(H)

[ to ] maintain records as required by this chapter (see subsection (bb)(5) of this section);

(I)

[ to ] ensure the proper storing, labeling, transport, and use of sources of radiation, storage, and/or transport containers;

(J)

[ to ] ensure that [ quarterly ] inventories are performed in accordance with subsection (j) [ (i) ] of this section; [ and ]

(K)

[ to ] ensure that personnel are complying with this chapter, the conditions of the license or the registration, and the operating , safety, and emergency procedures of the licensee or registrant ; and [ . ]

(L)

be the primary contact with the agency.

(s)

[ (r) ] Security. During each well logging or tracer application, the logging supervisor or other [ designated ] employee who is authorized by the specific licensee for that activity, is responsible for protecting against unautho rized and/or unnecessary entry into a restricted area, as defined in §289.201(b) [ §289.201 ] of this title, or §289.231 of this title, as applicable .

(t)

[ (s) ] Handling tools. The licensee shall provide and require the use of tools that will assure remote handling of sealed sources other than low activity calibration sources.

(u)

[ (t) ] Tracer studies.

(1)

Appropriate [ Protective gloves and other appropriate ] protective clothing and equipment shall be used by all personnel handling radioactive tracer material. Precautions shall be taken to avoid ingestion or inhalation of radioactive material, and to avoid contamination of field stations, temporary job sites, vehicles, associated equipment, and clothing.

(2)

No licensee shall permit the injection of radioactive material into usable quality groundwater (3,000 parts per million (ppm) total dissolved solids or less) without prior written authorization from the agency.

(v)

[ (u) ] Particle accelerators. No licensee or registrant shall permit above-ground testing of particle accelerators that results in the production of radiation except in areas or facilities controlled or shielded to meet the requirements of §289.202(f) or (n) of this title, or §289.231(m) or (o) of this title, as applicable.

(w)

[ (v) ] Radioactive markers. The licensee may use radioactive markers in wells only if the individual markers contain quantities of radioactive material not exceeding the quantities specified in §289.251(r)(2) [ §289.251(q)(2) ] of this title. The use of markers is subject only to the provisions of this subsection and subsection (j) [ (i) ] of this section.

(x)

[ (w) ] Uranium sinker bars. The licensee may use a depleted uranium sinker bar in well logging service operations only if it is legibly impressed with the wording DANGER (or CAUTION), RADIOACTIVE-DEPLETED URANIUM, NOTIFY CIVIL AUTHORITIES (OR NAME OF COMPANY).

(y)

[ (x) ] Radiation surveys.

(1)

Radiation surveys (and calculations[ , ] for neutron sources) shall be made and recorded for each area where radioactive materials are stored.

(2)

Radiation surveys (and calculations[ , ] for neutron sources) of the radiation levels in occupied positions and on the exterior of each vehicle used to transport radioactive materials shall be made and recorded. Such surveys (and calculations[ , ] for neutron sources) shall include all sources [ each source ] of radiation [ and combination of sources of radiation ] transported in the vehicle.

(3)

If the sealed source assembly is removed from the logging tool before departing the job site, a survey of the tool [ meter ] shall be performed [ used ] to verify that the logging tool is free of contamination.

(4)

If the licensee has reason to believe that the encapsulation of the sealed source could be damaged by an operation, the licensee shall immediately conduct a radiation survey, including a contamination survey, during and after the operation.

(5)

Radiation surveys shall be made and recorded at the job site and/or well head for each tracer operation except for those utilizing hydrogen-3, carbon-14, sulfur-35, or krypton-85. These surveys shall include measurements of radiation levels before and after the operation.

(6)

Records required in accordance with paragraphs (1)-(5) of this subsection shall also include the dates, the identification of individual(s) making the survey, the unique identification of survey instrument(s) used, radiation measurements in milliroentgen per hour (mR/hr), calculations in millirem per hour (mrem/hr) , and an exact description of the location of the survey. Each licensee or registrant shall make and maintain records [ Records ] of these surveys [ shall be maintained ] for inspection by the agency for three [ two ] years after completion of the survey.

(z)

[ (y) ] Records/documents for inspection by the agency. [ Records and documents required at field stations. ]

(1)

Each licensee or registrant shall maintain the records/documents specified in subsection (bb)(5) of this section for inspection by the agency.

(2)

[ (1) ] Each licensee or registrant maintaining additional authorized use/storage locations [ field stations ] from which well logging service operations are conducted shall have copies of the [ following ] records/documents specified in subsection (bb)(5)(B)-(E) and (G)-(O) of this section that are specific to the site [ records and documents ] available at each site [ station ] for inspection by the agency . [ : ]

[ (A)

a copy of the appropriate license or certificate of registration;]

[ (B)

operating and emergency procedures;]

[ (C)

applicable rules as listed in the license or certificate of registration;]

[ (D)

survey records required in accordance with subsection (x) of this section;]

[ (E)

quarterly inventories required in accordance with subsection (i) of this section;]

[ (F)

utilization records required in accordance with subsection (j) of this section;]

[ (G)

records of inspection and maintenance required in accordance with subsection (m) of this section;]

[ (H)

records of the survey instrument calibration and leak test for the specific devices and sources at the field station;]

[ (I)

records of personnel monitoring required in accordance with subsection (p) of this section for personnel employed at the field station;]

[ (J)

training records required in accordance with subsection (n) of this section;]

[ (K)

shipping papers for the transportation of radioactive material; and]

[ (L)

records of receipt, transfer, and disposal of radioactive material at the field station.]

(3)

[ (2) ] Records /documents required in accordance with paragraph (2) [ (1)(A)-(L) ] of this subsection shall be maintained in accordance with subsection (bb)(5) of this section.

(4)

[ (z) ] [ Records and documents required at temporary job sites. ] Each licensee or registrant conducting well logging service operations at a temporary job site shall have copies of the records/documents specified in subsection (bb)(5)(B), (C), (I), (K), (L), and (N) of this section [ following records and documents ] available at that site for inspection by the agency . [ : ]

[ (1)

a copy of the appropriate license or certificate of registration;]

[ (2)

operating and emergency procedures;]

[ (3)

survey records required in accordance with subsection (x) of this section for the period of operation at that site;]

[ (4)

evidence of current calibration for the radiation survey instruments in use at the site;]

(5)

Records/documents required by paragraph (4) of this subsection shall be maintained at the temporary job site for the period of operation at that site for inspection by the agency. [ a copy of the current leak test record for the source(s) in use; and ]

[ (6)

shipping papers for the transportation of radioactive material.]

(aa)

Notification of incidents and lost sources; abandonment procedures for irretrievable sources.

(1)

Notification of incidents and sources lost in other than downhole well logging operations shall be made in accordance with appropriate provisions of §289.202 of this title , or §289.231 of this title, as applicable .

(2)

(No change.)

(3)

Whenever a sealed source or device containing radioactive material is lost downhole, the licensee shall do the following :

(A)

consult with the well operator, well owner, drilling contractor, or land owner regarding methods to retrieve the source or device that may reduce the likelihood that the source or device will be damaged or ruptured during the logging tool recovery (fishing) operations;

(B)

[ (A) ] monitor with a radiation survey instrument (or logging tool adjusted to detect gamma emissions from source(s) lost downhole), at the surface for the presence of radioactive contamination during logging tool recovery (fishing) operations; and

(C)

[ (B) ] notify the agency immediately by telephone and submit written notification within 30 days if radioactive contamination is detected at the surface or if the source appears to be damaged.

(4)

When it becomes apparent that efforts to recover the radioactive source will not be successful, the licensee shall do the following :

(A)

advise the well operator of the Texas Railroad Commission requirements [ rules ] regarding abandonment and an appropriate method of abandonment, that shall include the following :

(i)-(iii)

(No change.)

(B)

(No change.)

(C)

file a written report with the agency within 30 days of the abandonment, providing [ setting forth ] the following information:

(i)-(viii)

(No change.)

(5)

Whenever a sealed source containing radioactive material is abandoned downhole, the licensee shall provide a permanent plaque (an example of a suggested plaque is shown in subsection (bb)(3) of this section) for posting on the well or wellbore. This plaque shall meet the following requirements :

(A)

be constructed of long-lasting material such as stainless steel, brass, bronze, or monel. The size of the plaque should be convenient for use on active or inactive wells; for example [ e.g. ], a 7-inch square. Letter size of the word "CAUTION" should be approximately twice the letter size of the rest of the information; for example [ e.g. ], 1/2 inch and 1/4 inch letter size, respectively; and

(B)

contain the following engraved information on its face:

(i)

the word "CAUTION ; "[ ; ]

(ii)-(vii)

(No change.)

(viii)

an appropriate warning, depending on the specific circumstances of each abandonment, such as the following:

(I)

"Do not drill below plug back depth ; "[ ; ]

(II)

"Do not enlarge casing ; "[ ; ] or

(III)

(No change.)

(6)-(7)

(No change.)

(bb)

Appendices.

(1)

Subjects to be included in training courses for well logging service operations and/or tracer studies are as follows:

(A)

(No change.)

(B)

radiation detection instrumentation to be used that includes:

(i)-(ii)

(No change.)

(iii)

use of individual [ personnel ] monitoring devices, including [ equipment specifying ] film badges, TLDs [ thermoluminescent dosimeters (TLDs) ], OSLs, and pocket dosimeters;

(C)

(No change.)

(D)

[ the requirements of ] pertinent federal and state requirements [ regulations ];

(E)

the licensee's or registrant's written operating , safety, and emergency procedures;

(F)-(G)

(No change.)

(2)-(3)

(No change.)

(4)

The licensee's or registrant's operating , safety, and emergency procedures shall include descriptions of and instructions in at least the following:

(A)

(No change.)

(B)

the handling and use of sources of radiation to be employed so that no individual is likely to be exposed to radiation doses in excess of the limits established in §289.202 of this title , or §289.231 of this title, as applicable . Every reasonable effort shall be made to keep radiation exposures and releases of radioactive material in soils and effluents to unrestricted areas as low as is reasonably achievable;

(C)-(R)

(No change.)

(S)

actions to be taken if a sealed source is ruptured, including actions to prevent the spread of contamination and minimize inhalation and ingestion of radioactive material, and actions to obtain suitable radiation survey instruments as required by subsection (h) [ (g) ] of this section.

(5)

The following records/documents shall be maintained by the licensee or registrant for inspection by the agency. [ The following are time retention requirements for record keeping. ]

Figure: 25 TAC §289.253(bb)(5)

[ Figure: 25 TAC §289.253(bb)(5) ]

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003511

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


25 TAC §289.256

The Texas Department of Health (department) proposes the repeal of §289.256 and new §289.256, concerning medical and veterinary use of radioactive material.

Government Code §2001.039 requires that each state agency review and consider for readoption each rule adopted by that agency pursuant to the Government Code, Chapter 2001 (Administrative Procedure Act). Section 289.256 has been reviewed and the department has determined that the reasons for adopting the section continue to exist; however revisions to the rule are necessary.

The new section adds requirements for licensing medical uses of radioactive material that are deleted from another section, concerning licensing of radioactive material. The new section adds requirements for the veterinary use of radioactive material. The requirement concerning patient release criteria for individuals receiving radioactive material therapy is changed from an activity-based to a dose-based criteria. This revision is an item of compatibility with the United States Nuclear Regulatory Commission (NRC) and as agreement state, Texas must adopt it. The new section adds specific requirements from the proposed NRC medical licensing rules concerning remote control brachytherapy units, teletherapy units, and gamma stereotactic radiosurgery units. Criteria for written directives and revised requirements for reports and notifications of medical events (misadministrations) are added and are also based on NRC proposed medical rules. When adopted, the proposed NRC medical rules will be items of compatibility. Qualifications for radiation safety officers (RSO) for licenses with and without broad scope authorization are added. Duties and responsibilities of the radiation safety committee (RSC) are revised. Records/documents to be kept at authorized use sites are specified. The new section is also part of the department's continuing effort to update, clarify, and simplify its rules regarding the control of radiation based upon technological advances, public concerns, legislative directives, or other factors.

The department published a Notice of Intention to Review for §289.256 as required by Government Code §2001.039 in the Texas Register (25 TexReg 219) on January 7, 2000. No comments were received by the department on this section.

Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, has determined that for each year of the first five years the sections will be in effect, there will be no fiscal implications for state or local government as a result of enforcing or administering the sections as proposed.

Mrs. McBurney has also determined that for each year of the first five years the proposed sections will be in effect, the public benefit anticipated as a result of enforcing the sections will be to ensure continued protection of the public, workers, and the environment from unnecessary exposure to radiation by ensuring that licensees are aware of the requirements for the medical use of radioactive material and that RSOs and RSCs are qualified to perform their duties and responsibilities. The addition of specific RSO qualifications and RSC duties and responsibilities formalizes in rule current agency policy. The addition of requirements for veterinary use of radioactive material likewise formalizes in rule what is currently agency policy. The addition of requirements for remote control brachytherapy units, teletherapy units, and gamma stereotactic radiosurgery units also formalizes in rule what is currently agency policy. Therefore, there are anticipated economic costs to micro businesses, small businesses, or persons required to comply with these proposed requirements. The revision of the patient release criteria from an activity- based criteria to a dose-based criteria will require additional time for record keeping and instruction to the patient. The additional time is estimated to be 15 minutes per patient released. If the individual responsible for record keeping and provision of the patient instruction has an hourly salary ranging from $30 to $50, the additional cost would be approximately $7 to $12 per patient released under the proposed criteria. The requirement for written directives is estimated to require one to two minutes for preparation of the written directive. If the individual preparing the written directive has an hourly salary ranging from $75 to $100, the additional cost would be approximately $2 to $3 per written directive. These costs will be the same for micro businesses, small businesses, and persons required to comply with the proposed requirements. However, a written directive is already a standard of practice for most radioactive material therapy, thus, no additional costs would be incurred by these individuals. There is no anticipated impact on local employment.

Comments on the proposal may be presented to Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, Texas Department of Health, 1100 West 49th Street, Austin, Texas 78756-3189, Telephone (512) 834-6688 or electronic mail at Ruth.Mcburney@tdh.state.tx.us. Public comments will be accepted for 30 days following publication of this proposal in the Texas Register . In addition, a public meeting to accept oral comments will be held at 1:30 p.m., Tuesday, June 13, 2000, in Conference Room N218, Texas Department of Health, Bureau of Radiation Control, located at the Exchange Building, 8407 Wall Street, Austin, Texas.

(Editor's note: The text of the following section proposed for repeal will not be published. The section may be examined in the offices of the Texas Department of Health or in the Texas Register office, Room 245, James Earl Rudder Building, 1019 Brazos Street, Austin.)

The repeal is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with the authority to adopt rules for the performance of each duty imposed by law on the board, the department, and the commissioner of health.

The repeal affects Health and Safety Code, Chapter 401 and Chapter 12, and Government Code §2001.039.

§289.256.Use of Sealed Sources in the Healing Arts.

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003509

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


The new section is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with the authority to adopt rules for the performance of each duty imposed by law on the board, the department, and the commissioner of health.

The new section affects Health and Safety Code, Chapter 401 and Chapter 12, and Government Code §2001.039.

§289.256.Medical and Veterinary Use of Radioactive Material.

(a)

Purpose. This section establishes requirements for the medical and veterinary use of radioactive material and for the issuance of specific licenses authorizing the medical and veterinary use of radioactive material. Unless otherwise exempted, no person shall receive, possess, use, transfer, own, or acquire radioactive material for medical or veterinary use except as authorized in a license issued in accordance with this section. A person who receives, possesses, uses, transfers, owns, or acquires radioactive material prior to receiving a license is subject to the requirements of this chapter.

(b)

Scope.

(1)

In addition to the requirements of this section, all licensees, unless otherwise specified, are subject to the requirements of §289.201 of this title (relating to General Provisions for Radioactive Material), §289.202 of this title (relating to Standards for Protection Against Radiation from Radioactive Material), §289.203 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections), §289.204 of this title (relating to Fees for Certificates of Registration, Radioactive Material Licenses, Emergency Planning and Implementation, and Other Regulatory Services), §289.205 of this title (relating to Hearing and Enforcement Procedures), §289.252 of this title (relating to Licensing of Radioactive Material), and §289.257 of this title (relating to Packaging and Transportation of Radioactive Material).

(2)

Veterinarians who receive, possess, use, transfer, own, or acquire radioactive material in the practice of veterinary medicine shall do the following:

(A)

comply with the requirements in this subsection and subsections (a), (c), (e)-(j), (k)(2)-(7), (m)-(p), (s), (t), (v), (x), (y)(1), (z)(1), (aa)(1)-(3), and (bb)(1)-(7) of this section; and

(B)

verify that the training and experience specified in subsection (c)(3)(B) of this section has been obtained within the five years preceding the date of application or the individual must have had related continuing education and experience since the required training and experience was completed.

(c)

Definitions. The following words and terms when used in this section shall have the following meaning unless the context clearly indicates otherwise.

(1)

Address of use - The building or buildings that are identified on the license and where radioactive material may be prepared, received, used, or stored.

(2)

Area of use - A portion of an address of use that has been set aside for the purpose of preparing, receiving, using, or storing radioactive material.

(3)

Authorized user - Authorized user is defined as either of the following:

(A)

for medical use, a physician licensed by the Texas State Board of Medical Examiners who meets the applicable requirements in subsections (y)-(dd) of this section; or

(B)

for veterinary use, a veterinarian licensed by the Texas Board of Veterinary Medical Examiners and certified by the American College of Veterinary Radiology who is authorized for the use of radioactive materials in veterinary medicine.

(4)

Brachytherapy - A method of radiation therapy in which plated, embedded, activated, or sealed sources are utilized to deliver a radiation dose at a distance of up to a few centimeters, by surface, intracavitary, intraluminal, or interstitial application.

(5)

Brachytherapy sealed source - A sealed source or a manufacturer-assembled source train, or a combination of these sources that is designed to deliver a therapeutic dose within a distance of a few centimeters.

(6)

High dose-rate remote afterloader - A device that remotely delivers a dose rate in excess of 1200 rads (12 gray (Gy)) per hour at the point or surface where the dose is prescribed.

(7)

Institutional Review Board (IRB) - Any board, committee, or other group formally designated by an institution and approved by the United States Food and Drug Administration to review, approve the initiation of, and conduct periodic review of biomedical research involving human subjects.

(8)

Low dose-rate remote afterloader - A device that remotely delivers a dose rate of less than or equal to 200 rads (2 Gy) per hour at the point or surface where the dose is prescribed.

(9)

Licensed medical physicist - An individual holding a current Texas license under the Medical Physics Practice Act, Article 4512n, in therapeutic radiological physics.

(10)

Management - The chief executive officer or other individual delegated the authority to manage, direct, or administer the licensee's activities.

(11)

Manual brachytherapy - A type of brachytherapy in which the sealed sources, for example, seeds and ribbons, are manually inserted either into the body cavities that are in close proximity to a treatment site or directly in the tissue volume.

(12)

Medical institution - An organization in which several medical disciplines are practiced.

(13)

Medical use - The intentional internal or external administration of radioactive material, or the radiation from radioactive material, to patients or human research subjects under the supervision of an authorized user.

(14)

Medical event - An event that meets the criteria in subsection (ee)(1) of this section.

(15)

Medium dose-rate afterloader - A device that remotely delivers a dose rate greater than 200 rads (2 Gy) and less than or equal to 1200 rads (12 Gy) per hour at the point or surface where the dose is prescribed.

(16)

Output - The exposure rate, dose rate, or a quantity related in a known manner to these rates from a teletherapy unit, a brachytherapy source, a remote afterloader unit, or a gamma stereotactic radiosurgery unit, for a specified set of exposure conditions.

(17)

Preceptor - An individual who provides or directs the training and experience requirements.

(18)

Permanent facility - A building or buildings that are identified on the license within the state of Texas and where radioactive material may be prepared, received, used, or stored. This may also include an area or areas where administrative activities related to the license are performed.

(19)

Prescribed dosage - The specified activity or range of activity of a radiopharmaceutical as documented in a written directive or in accordance with the directions of the authorized user for procedures in subsections (y) and (z) of this section.

(20)

Prescribed dose - Prescribed dose means one of the following:

(A)

for gamma stereotactic radiosurgery, the total dose as documented in the written directive;

(B)

for teletherapy, the total dose and dose per fraction as documented in the written directive;

(C)

for brachytherapy, either the total sealed source strength and exposure time, or the total dose, as documented in the written directive; or

(D)

for remote afterloaders, the total dose and dose per fraction as documented in the written directive.

(21)

Pulsed dose-rate remote afterloader - A special type of remote afterloading device that uses a single sealed source capable of delivering dose rates greater than 1200 rads (12 Gy) per hour, but is approximately one-tenth of the activity of typical high dose-rate remote afterloader sealed sources and is used to simulate the radiobiology of a low dose rate remote afterloader treatment by inserting the sealed source for a given fraction of each hour.

(22)

Sealed source and device registry - The national registry that contains all the registration certificates, generated by both the NRC and the agreement states, that summarize the radiation safety information for sealed sources and devices and describe the licensing and use conditions approved for the product.

(23)

Stereotactic radiosurgery - The use of external radiation in conjunction with a guidance device to very precisely deliver a dose to a tissue volume by the use of three- dimensional coordinates.

(24)

Technologist - Technologist is defined as either of the following:

(A)

in nuclear medicine, a person (nuclear medicine technologist) skilled in the performance of nuclear medicine procedures under the supervision of a physician; and/or

(B)

in therapy, as described in subsections (bb) and (dd) of this section, a person (radiation therapy technologist or radiation therapist) who delivers courses of radiation therapy as prescribed by a radiation oncologist.

(25)

Teletherapy - Therapeutic irradiation in which the sealed source is at a distance from the patient or human research subject.

(26)

Therapeutic dosage - The specified activity or range of activity of radioactive material that is intended to deliver a radiation dose to a patient or human research subject for palliative or curative treatment.

(27)

Therapeutic dose - A radiation dose delivered from a sealed source containing radioactive material to a patient or human research subject for palliative or curative treatment.

(28)

Treatment site - The anatomical description of the tissue intended to receive a radiation dose, as described in a written directive.

(29)

Type of use - Use of radioactive material as specified under the following subsections:

(A)

training, uptake, and dilution studies in subsection (y) of this section;

(B)

imaging and localization studies in subsection (z) of this section;

(C)

therapy with unsealed radioactive material in subsection (aa) of this section;

(D)

manual brachytherapy with sealed sources in subsection (bb) of this section;

(E)

sealed sources for diagnosis in subsection (cc) of this section; and

(F)

sealed source in a remote afterloader unit, teletherapy unit, or gamma stereotactic radiosurgery unit in subsection (dd) of this section.

(30)

Unit dosage - A dosage prepared for medical use for administration as a single dosage to a patient or human research subject without any further modification of the dosage after it is initially prepared.

(31)

Veterinary use - The intentional internal or external administration of radioactive material, or the radiation from radioactive material, to animal patients under the supervision of an authorized user.

(32)

Written directive - An authorized user's written order for the administration of radioactive material or radiation from radioactive material to a specific patient or human research subject, as specified in subsection (p) of this section.

(d)

Provisions for research involving human subjects.

(1)

A licensee may only conduct research involving human subjects if medical use of radioactive material is authorized on the license.

(2)

The licensee may conduct research specified in paragraph (1) of this subsection provided that:

(A)

the research is conducted, funded, supported, or regulated by a federal agency that has implemented the Federal Policy for the Protection of Human Subjects as required by Title 10, Code of Federal Regulations (CFR), §35.6; and

(B)

the licensee has applied for and received approval of a specific amendment to its license before conducting the research.

(3)

Prior to conducting research as specified in paragraph (1) of this subsection, the licensee shall obtain the following:

(A)

"informed consent," as defined and described in the Federal Policy, from the human research subjects; and

(B)

prior review and approval of the research activities from an IRB as required by Title 45, CFR, Part 46 and Title 21, CFR Part 56, and in accordance with the Federal Policy. The IRB must include at least one authorized user to direct any human use of radioactive material in accordance with §289.202(b) of this title.

(4)

Nothing in this subsection relieves licensees from complying with the other requirements of this chapter.

(e)

Implementation.

(1)

If a license condition exempted a licensee from a provision of this section or §289.252 of this title on October 1, 2000, then the license condition continues to exempt the licensee from the requirements in the corresponding provision until there is a license amendment or license renewal that modifies or removes the license condition.

(2)

When a requirement in this section differs from the requirement in an existing license condition, the requirement in this section shall govern.

(3)

Licensees shall continue to comply with any license condition that requires implementation of procedures required by subsection (dd)(4) and (10)-(12) of this section until there is a license amendment or renewal that modifies the license condition.

(f)

Specific requirements for the issuance of licenses. In addition to the requirements in §289.252(e) of this title and subsections (j)-(l) of this section, as applicable, a license will be approved if the agency determines that:

(1)

the applicant satisfies any applicable special requirement in this section;

(2)

qualifications of the designated radiation safety officer (RSO) as specified in subsection (h) of this section are adequate for the purpose requested in the application; and

(3)

the following submitted by the applicant is approved:

(A)

an operating, safety, and emergency procedures manual to include:

(i)

specific information on the following:

(I)

radiation safety precautions and instructions;

(II)

methodology for measurement of dosages or doses to be administered to patients or human research subjects; and

(III)

calibration, maintenance, and repair of instruments and equipment necessary for radiation safety; and

(ii)

any additional information requested by the agency to assist in its review of the application;

(B)

full page drawings of each room used for preparing, compounding, using, and storing radioactive material;

(C)

qualifications of the following:

(i)

RSO in accordance with subsection (h) of this section;

(ii)

authorized user(s) in accordance with subsection (ff)(1) of this section as applicable to the use(s) being requested; and

(iii)

radiation safety committee (RSC), if applicable, in accordance with subsection (i) of this section;

(4)

the applicant's permanent facility is located in Texas; and

(5)

the owner of the property is aware that radioactive material is stored and/or used on the property, if the proposed storage facility is not owned by the applicant. The applicant shall provide a written statement from the owner indicating such.

(g)

Radiation safety officer.

(1)

Every license issued by the agency shall have an RSO designated by the licensee's management. The licensee shall:

(A)

establish in writing the authority, duties, and responsibilities of the RSO;

(B)

provide the RSO sufficient authority, organizational freedom, time, resources, and management prerogative, to perform the following duties:

(i)

establish and oversee operating, safety, emergency, and as low as reasonably achievable (ALARA) procedures, and to review them at least annually to ensure that the procedures are current and conform with this chapter;

(ii)

ensure that required radiation surveys and leak tests are performed and documented in accordance with this chapter, including any corrective measures when levels of radiation exceed established limits;

(iii)

ensure that individual monitoring devices are used properly by occupationally-exposed personnel, that records are kept of the monitoring results, and that timely notifications are made in accordance with §289.203 of this title;

(iv)

investigate and cause a report to be submitted to the agency for each known or suspected case of radiation exposure to an individual or radiation level detected in excess of limits established by this chapter and each theft or loss of source(s) of radiation, to determine the cause(s), and to take steps to prevent a recurrence;

(v)

investigate and cause a report to be submitted to the agency for each known or suspected case of release of radioactive material to the environment in excess of limits established by this chapter;

(vi)

have a thorough knowledge of management policies and administrative procedures of the licensee;

(vii)

assume control and institute corrective actions, including shutdown of operations when necessary, in emergency situations or unsafe conditions;

(viii)

ensure that records are maintained as required by this chapter.

(ix)

ensure the proper storing, labeling, transport, use, and disposal of sources of radiation, storage, and/or transport containers;

(x)

ensure that inventories are performed in accordance with the activities for which the license application is submitted;

(xi)

ensure that personnel are complying with this chapter, the conditions of the license, and the operating, safety, and emergency procedures of the licensee; and

(xii)

serve as the primary contact with the agency; and

(C)

have the RSO agree in writing to be responsible for implementing the radiation safety program.

(2)

The RSO's documented qualifications shall include training and experience in accordance with subsection (h) of this section.

(3)

For up to 60 days each calendar year, a licensee may permit an authorized user or an individual qualified to be an RSO to function as a temporary RSO and to perform the duties of an RSO in accordance with paragraph (1)(A) and (C) of this subsection, provided the licensee takes the actions required in paragraphs (1) and (2) of this subsection, and the RSO meets the qualifications in subsection (h) of this section. Records of qualifications and dates of service shall be maintained in accordance with subsection (ff)(2) of this section for inspection by the agency.

(h)

Qualifications for radiation safety officer.

(1)

The qualifications for RSOs for licenses for medical use of radioactive material without broad-scope authorization shall include the following:

(A)

certification by a speciality board whose certification process includes all of the requirements in subparagraph (B) of this paragraph and whose certification has been recognized by the agency; or

(B)

completion of a structured educational program consisting of the following:

(i)

200 hours of didactic training in the following areas:

(I)

radiation physics and instrumentation;

(II)

radiation protection;

(III)

mathematics pertaining to the use and measurement of radioactivity;

(IV)

radiation biology; and

(V)

radiation dosimetry; and

(ii)

one year of full-time radiation safety experience under the supervision of the individual identified as the RSO on an agency, NRC, agreement state, or licensing state license that authorizes similar type(s) of use(s) of radioactive material involving the following:

(I)

shipping, receiving, and performing related radiation surveys;

(II)

using and performing checks for proper operation of dose calibrators, survey meters, and instruments used to measure radionuclides;

(III)

securing and controlling radioactive material;

(IV)

using administrative controls to avoid mistakes in the administration of radioactive material;

(V)

using procedures to prevent or minimize radioactive contamination and using proper decontamination procedures; and

(VI)

disposing of radioactive material; and

(iii)

has obtained written certification, signed by the supervising RSO, specified in clause (ii) of this subparagraph, that the individual has satisfactorily completed the requirements in clauses (i) and (ii) of this subparagraph and has achieved a level of radiation safety knowledge sufficient to independently function as an RSO for medical uses of radioactive material; or

(C)

is an authorized user or licensed medical physicist identified on the licensee's radioactive material license and has experience with the radiation safety aspects of similar types of use of radioactive material for which the individual has RSO responsibilities.

(2)

The qualifications for RSOs for licenses for medical use of radioactive material with broad-scope authorization shall include the following:

(A)

a bachelor's degree in health physics, radiological health, physical science or a biological science with a physical science minor and four years of applied health physics experience in a program with radiation safety problems similar to those in the program to be managed;

(B)

a master's degree in health physics or radiological health and three years of applied health physics experience in a program with radiation safety problems similar to those in the program to be managed; or

(C)

two years of applied health physics experience in a program with radiation safety problems similar to those in the program to be managed and one of the following:

(i)

doctorate degree in health physics or radiological health;

(ii)

comprehensive certification by the American Board of Health Physics;

(iii)

certification by the American Board of Radiology in Medical Nuclear Physics;

(iv)

certification by the American Board of Science in Nuclear Medicine in Radiation Protection; or

(v)

certification by the American Board of Medical Physics in Medical Health Physics.

(3)

The qualifications in paragraphs (1)(A)-(C) and (2)(A)-(C) of this subsection do not apply to RSOs on radioactive material licenses issued prior to October 1, 2000.

(i)

Radiation safety committee. Licensees with broad scope authorization and licensees who are authorized for two or more different types of uses of radioactive material under subsections (aa), (bb), and (dd) of this section, or two or more types of units under subsection (dd) of this section shall establish an RSC to oversee all uses of radioactive material permitted by the license.

(1)

The RSC for licenses for medical use with broad scope authorization shall be composed of the following individuals as approved by the agency:

(A)

authorized users from each type of use of radioactive material (including research, diagnostic, and therapeutic uses);

(B)

the RSO;

(C)

a representative of nursing service;

(D)

a representative of management who is neither an authorized user nor the RSO;

(E)

a technologist representative; and

(F)

may include other members as the licensee deems appropriate.

(2)

The RSC for licenses for medical use authorized for two or more different types of uses of radioactive material under subsections (aa), (bb), and (dd) of this section, or two or more types of units under subsection (dd) of this section shall be composed of the following individuals as approved by the agency:

(A)

an authorized user of each type of use permitted by the license;

(B)

the RSO;

(C)

a representative of nursing service;

(D)

a representative of management who is neither an authorized user nor the RSO;

(E)

a technologist representative; and

(F)

may include other members as the licensee deems appropriate.

(3)

Duties and responsibilities of the RSC.

(A)

For licensees without broad scope authorization, the duties and responsibilities of the RSC include, but are not limited to, the following:

(i)

meeting as often as necessary to conduct business but not less than every three months;

(ii)

reviewing personnel dosimetry data;

(iii)

reviewing the results of required radiation safety surveys and any significant incidents, including spills, contamination, or medical events;

(iv)

reviewing the results of inspections and taking appropriate action when noncompliance is identified;

(v)

reviewing the program for maintaining doses ALARA, and providing any necessary recommendations to ensure doses are ALARA; and

(vi)

reviewing the audit of the radiation safety program and acting upon the findings.

(B)

For licensees with broad scope authorization, the duties and responsibilities of the RSC include, but are not limited to, the items in subparagraph (A) of this paragraph and the following:

(i)

reviewing the overall compliance status for authorized users;

(ii)

sharing responsibility with the RSO to conduct periodic audits of the radiation safety program;

(iii)

developing criteria to evaluate training and experience of new authorized user applicants;

(iv)

evaluating and approving authorized user applicants who request authorization to use radioactive material at the facility; and

(v)

reviewing and approving permitted program and procedural changes prior to implementation.

(j)

Licenses for medical uses of radioactive material without broad scope authorization. In addition to the requirements of subsection (f) of this section, a license for medical use of radioactive material as described in the applicable subsections (y), (z), and (aa)-(cc) of this section will be issued if the agency approves the following information submitted by the applicant:

(1)

documentation that the physician(s) designated on the application as the authorized user(s) is qualified in accordance with subsections (y), (z), and (aa)-(cc) of this section as applicable;

(2)

evidence that the radiation detection and measuring instrumentation is appropriate for performing surveys and procedures for the uses involved;

(3)

documentation that the radiation safety operating procedures are adequate for the handling and disposal of the radioactive material involved in the uses; and

(4)

evidence of an established RSC in accordance with subsection (i)(2) of this section, if applicable.

(k)

License for medical uses of radioactive material with broad scope authorization. In addition to the requirements in subsection (f) of this section, a license for medical use of radioactive material with broad scope authorization will be issued if the agency approves the following information submitted by the applicant:

(1)

documentation that the review of authorized user qualifications by the RSC is in accordance with subsections (y), (z), and (aa)-(dd) of this section, as applicable;

(2)

evidence that the application is for a license authorizing unspecified forms and/or multiple types of radioactive material for medical research, diagnosis, and therapy;

(3)

evidence that the radiation detection and measuring instrumentation is appropriate for performing surveys and procedures for the uses involved;

(4)

documentation that the radiation safety operating procedures are adequate for the handling and disposal of the radioactive material involved in the uses;

(5)

evidence that staff has substantial experience in the use of a variety of radioactive material for a variety of human uses;

(6)

documentation of a full-time RSO meeting the requirements of subsection (h)(2) of this section; and

(7)

evidence of an established RSC in accordance with subsection (i)(1) of this section.

(l)

License for the use of remote control brachytherapy units, teletherapy units, or gamma stereotactic radiosurgery units. In addition to the requirements in subsection (f) of this section, a license for the use of remote control brachytherapy (RCB) units, teletherapy units, or gamma stereotactic radiosurgery units will be issued if the agency approves the following information submitted by the applicant:

(1)

documentation that the physician(s) designated on the application as the authorized user(s) is qualified in accordance with subsection (dd) of this section;

(2)

evidence that the radiation detection and measuring instrumentation is appropriate for performing surveys and procedures for the uses involved;

(3)

documentation that the radiation safety operating procedures are adequate for the handling and disposal of the radioactive material involved in the uses; and

(4)

documentation of the following:

(A)

list of radioactive isotopes to be possessed;

(B)

the sealed source manufacturer(s) name(s) and the model number(s) of the sealed source(s) to be installed;

(C)

the maximum number of sealed sources of each isotope to be possessed, including the activity of each sealed source;

(D)

the manufacturer and model name and/or number of the following units, as applicable:

(i)

RCB unit;

(ii)

teletherapy unit; or

(iii)

gamma stereotactic radiosurgery unit;

(E)

the licensed medical physicist's current Texas license in therapeutic radiological physics;

(F)

the successful completion of unit-specific, manufacturer-provided training that includes standard clinical and emergency procedures for remote control brachytherapy and gamma stereotactic radiosurgery units for the following personnel:

(i)

licensed medical physicist;

(ii)

technologists; and

(iii)

authorized user;

(G)

safety procedures and instructions as required by subsection (dd)(4) of this section;

(H)

spot check procedures as required by subsection (dd)(10)-(12), as applicable; and

(I)

an established RSC in accordance with subsection (i)(1) or (2) of this section if applicable.

(m)

Amendment of licenses at request of licensee.

(1)

Requests for amendment of a license or deletion of a subsite shall be filed in accordance with §289.252(aa) of this title.

(2)

A licensee without broad-scope authorization shall apply for and must receive a license amendment prior to the following:

(A)

receiving or using radioactive material for a type of use that is permitted under this section, but that is not authorized on their current license issued in accordance with this section;

(B)

permitting anyone to work as an authorized user or licensed medical physicist under the license;

(C)

changing RSOs, except as provided in subsection (g)(3) of this section;

(D)

receiving radioactive material in excess of the amount or in a different form, or receiving a different radionuclide than is authorized on the license;

(E)

adding or changing the areas identified in the application or on the license;

(F)

changing the address(es) of use identified in the application or on the license; and

(G)

changing operating, safety, and emergency procedures.

(3)

A licensee with broad-scope authorization shall apply for and must receive a license amendment prior to paragraph (2)(A) and (C)-(G) of this subsection.

(n)

Records/documents to be kept at authorized use site(s). Each licensee shall maintain copies of the records and documents specified in subsection (ff)(2) of this section.

(o)

Supervision. A licensee may permit the receipt, possession, use, or transfer of radioactive material by an individual under the supervision of an authorized user, unless prohibited by license condition.

(1)

A licensee who permits the receipt, possession, use, or transfer of radioactive material by an individual under the supervision of an authorized user shall do the following:

(A)

instruct the supervised individual in the licensee's written operating, safety, and emergency procedures, written directive procedures, requirements of this chapter, and license conditions with respect to the use of radioactive material; and

(B)

require the supervised individual to follow the instructions of the supervising authorized user for medical uses of radioactive material, written operating, safety, and emergency procedures established by the licensee, requirements of this chapter, and license conditions with respect to the medical use of radioactive material.

(2)

A licensee who permits the preparation of radioactive material for medical use by an individual under the supervision of an authorized user, shall do the following:

(A)

instruct the supervised individual in the preparation of radioactive material for medical use, as appropriate to that individual's involvement with radioactive material; and

(B)

require the supervised individual to follow the instructions of the supervising authorized user regarding the preparation of radioactive material for medical use, the written operating, safety, and emergency procedures established by the licensee, the requirements of this chapter, and license conditions.

(3)

A licensee who permits supervised activities under paragraphs (1) and (2) of this subsection is responsible for the acts and omissions of the supervised individual.

(p)

Written directives.

(1)

A written directive must be dated and signed by an authorized user prior to administration of sodium iodide I-131 greater than 30 microcuries (µCi)(1.11 MBq), any therapeutic dosage of unsealed radioactive material, or any therapeutic dose of radiation from radioactive material.

(A)

A written revision to an existing written directive may be made provided that the revision is dated and signed by an authorized user prior to the administration of the dosage of radioactive drug containing radioactive material, the brachytherapy dose, the gamma stereotactic radiosurgery dose, the teletherapy dose, or the next fractional dose.

(B)

If, because of the emergent nature of the patient's condition, a delay in order to provide a written directive or to revise a written directive would jeopardize the patient's health, an oral directive or an oral revision to an existing written directive is acceptable. The information contained in the oral directive or oral revision shall be documented as soon as possible in writing in the patient's record. A written directive shall be prepared and signed by the authorized user within 48 hours of the oral directive or oral revision.

(2)

The written directive shall contain the patient or human research subject's name and the following information:

(A)

for any administration of quantities greater than 30 µCi (1.11 MBq) of sodium iodide I-131: the dosage;

(B)

for an administration of a therapeutic dosage of a radiopharmaceutical other than sodium iodide I-131: the radiopharmaceutical, dosage, and route of administration;

(C)

for gamma stereotactic radiosurgery: the total dose, treatment site, and number of target coordinate settings per treatment for each anatomically distinct treatment site;

(D)

for teletherapy: the total dose, dose per fraction, number of fractions, and treatment site;

(E)

for high-dose rate remote afterloading brachytherapy: the radionuclide, treatment site, dose per fraction, number of fractions, and total dose; or

(F)

for all other brachytherapy:

(i)

prior to implantation: the treatment site, the radionuclide, number of sealed sources, and dose; and

(ii)

after implantation but prior to completion of the procedure: the radionuclide, treatment site, number of sealed sources, total sealed source strength and exposure time or, equivalently, the total dose.

(3)

The licensee shall maintain the written directive in accordance with subsection (ff)(2) of this section.

(4)

Procedures for administrations requiring a written directive.

(A)

For any administration requiring a written directive, the licensee shall develop, implement, and maintain written procedures to ensure that:

(i)

the patient's or human research subject's identity is verified before each administration; and

(ii)

each administration is in accordance with the written directive.

(B)

The procedures required by subparagraph (A) of this paragraph must, at a minimum, address the following items that are applicable for the licensee's use of radioactive material:

(i)

verification of the identity of the patient or human research subject;

(ii)

verification that the specific details of the administration are in accordance with the treatment plan, if applicable, and the written directive;

(iii)

a check of both manual and computer-generated dose calculations; and

(iv)

verification that any computer-generated dose calculations are correctly transferred into the consoles of therapeutic medical units authorized by subsection (dd) of this section.

(q)

Possession, use, and calibration of dose calibrators to measure the activity of unsealed radioactive material.

(1)

For direct measurements performed in accordance with subsection (r) of this section, the licensee shall possess and use instrumentation to measure the activity of unsealed radioactive material before it is administered to each patient or human research subject.

(2)

The licensee shall calibrate the instrumentation as specified in paragraph (1) of this subsection in accordance with nationally recognized standards or the manufacturer's instructions.

(3)

The calibration required by paragraph (2) of this subsection shall include tests for constancy, accuracy, linearity, and geometry dependence, as appropriate to demonstrate proper operation of the instrument. The tests for constancy, accuracy, linearity, and geometry dependence shall be conducted at the following intervals:

(A)

constancy at least once each day prior to assay of patient dosages;

(B)

linearity at installation and at least quarterly thereafter;

(C)

geometry dependence at installation; and

(D)

accuracy at installation and at least annually thereafter.

(4)

The licensee shall maintain a record of each instrument calibration in accordance with subsection (ff)(2) of this section. The record shall include the following:

(A)

model and serial number of the instrument and calibration sources;

(B)

dates of the calibration;

(C)

results of the calibration; and

(D)

name of the individual who performed the calibration.

(r)

Determination of dosages of radioactive material for medical use.

(1)

Before medical use, the licensee shall perform the following:

(A)

record the activity of each dosage; and

(B)

determine the activity of each dosage using a dose calibrator, by direct measurement of radioactivity, or a decay correction, based on the activity or activity concentration determined by the following:

(i)

a manufacturer or preparer licensed in accordance with §289.252(r) of this title, or under an equivalent NRC, agreement state, or licensing state license; or

(ii)

an NRC or agreement state licensee for use in research in accordance with a Radioactive Drug Research Committee-approved protocol or an Investigational New Drug (IND) protocol accepted by the FDA.

(2)

For other than unit dosages, this determination shall be made by:

(A)

direct measurement of radioactivity; or

(B)

combination of direct measurement of radioactivity and mathematical calculations.

(3)

Unless otherwise directed by the authorized user, a licensee shall not use a dosage if the dosage does not fall within the prescribed dosage range or if the dosage differs from the prescribed dosage by more than 20%.

(4)

A licensee restricted to only unit doses prepared in accordance with §289.252(r) need not comply with the requirements in paragraph (1)(B) of this subsection, unless the administration time of the unit dose deviates from the nuclear pharmacy's pre-calibrated time by 15 minutes or more.

(5)

A licensee shall maintain a record of the dosage determination required by this subsection in accordance with subsection (ff)(2) of this section. The record shall contain the following:

(A)

radionuclide, generic name, trade name, or abbreviation of the radiopharmaceutical;

(B)

patient's or human research subject's name or identification number if one has been assigned;

(C)

prescribed dosage;

(D)

determined dosage or a notation that the total activity is less than 30 µCi (1.1 MBq);

(E)

the date and time of the dosage determination; and

(F)

the name of the individual who determined the dosage.

(s)

Authorization for calibration and reference sources. Any licensee authorized by subsections (j)-(l) of this section for medical use of radioactive material may receive, possess, and use the following radioactive material for check, calibration, and reference use:

(1)

sealed sources manufactured and distributed by a person licensed in accordance with §289.252 of this title and that do not exceed 30 millicurie (mCi) (1.11GBq) each;

(2)

any radioactive material with a half-life not longer than 120 days in individual amounts not to exceed 15 mCi (0.555 Gbq);

(3)

any radioactive material with a half-life longer than 120 days in individual amounts not to exceed the smaller of 200 µCi (7.4 MBq) or 1000 times the quantities in §289.252(w)(6) of this title; and

(4)

technetium-99m in amounts as needed.

(t)

Requirements for possession of sealed sources and brachytherapy sealed sources. A licensee in possession of any sealed source or brachytherapy source shall:

(1)

follow the radiation safety and handling instructions supplied by the manufacturer and the leakage test requirements in accordance with §289.201(g) of this title.

(2)

conduct a physical inventory at intervals not to exceed six months to account for all sealed sources received, possessed, and transferred. Records of the inventories shall be maintained for inspection by the agency in accordance with subsection (ff)(2) of this section and shall include the quantities and kinds of radioactive material, sealed source identification numbers, location of sealed sources, the dates of the inventory, and the identification of the individual(s) making the record.

(u)

Labeling of vials and syringes. Each syringe and vial that contains a radiopharmaceutical shall be labeled to identify the radioactive drug. Each syringe shield and vial shield shall also be labeled unless the label on the syringe or vial is visible when shielded.

(v)

Surveys for ambient radiation exposure rate.

(1)

Except as provided in paragraph (2) of this subsection, a licensee shall survey with a radiation detection survey instrument at the end of each day of use all areas where radioactive material requiring a written directive was prepared for use or administered.

(2)

A licensee does not need to perform the surveys required by paragraph (1) of this subsection in an area(s) where patients or human research subjects are confined when they cannot be released in accordance with subsection (w) of this section.

(3)

A record of each survey shall be maintained in accordance with subsection (ff)(2) of this section. The record shall include the following:

(A)

dates of the survey;

(B)

results of the survey;

(C)

manufacturer's name and model and serial number of the instrument used to make the survey; and

(D)

name of the individual who performed the survey.

(w)

Release of individuals containing radioactive drugs or implants containing radioactive material.

(1)

The licensee may authorize the release from its control any individual who has been administered radioactive drugs or implants containing radioactive material in accordance with a written directive specified in subsection (p) of this section if the total effective dose equivalent (TEDE) to any other individual from exposure to the released individual is not likely to exceed 0.5 rem (5 mSv). Patients treated with temporary eye plaques may be released from the hospital provided that the procedures ensure that the exposure rate from the patient is less than 5 milliroentgens per hour at a distance of 1 meter from the eye plaque location;

(2)

The licensee shall provide the released individual, or the individual's parent or guardian, with written instructions on actions recommended to maintain doses to other individuals ALARA if the TEDE to any other individual is likely to exceed 0.1 rem (1 mSv). If the TEDE to a breast-feeding infant or child could exceed 0.1 rem (1 mSv), assuming there was no interruption of breast-feeding, the instructions shall also include the following:

(A)

guidance on the interruption or discontinuation of breast-feeding; and

(B)

information on the potential consequences, if any, of failure to follow the guidance.

(3)

The licensee shall maintain a record in accordance with subsection (ff)(2) of this section of each patient released in accordance with paragraph (1) of this subsection. The record shall include the following:

(A)

the basis for authorizing the release of an individual; and

(B)

the instructions provided to a breast-feeding woman if the radiation dose to the infant or child from continued breast-feeding could result in a TEDE exceeding 0.5 rem (5 mSv).

(x)

Decay-in-storage.

(1)

The licensee may hold radioactive material with a physical half-life of less than 65 days for decay-in-storage and dispose of it without regard to its radioactivity if the licensee does the following:

(A)

monitors radioactive material at the surface before disposal and determines that its radioactivity cannot be distinguished from the background radiation level with an appropriate radiation detection survey meter set on its most sensitive scale and with no interposed shielding; and

(B)

removes or obliterates all radiation labels, except for material that will be handled as biomedical waste after it has been released.

(2)

The licensee shall maintain a record of each disposal permitted under paragraph (1) of this subsection in accordance with subsection (ff)(2) of this section. The record shall include the following:

(A)

dates of the disposal;

(B)

manufacturer's name and model and serial number of the survey instrument used;

(C)

background dose rate;

(D)

dose rate measured at the surface of each waste container; and

(E)

name of the individual who performed the disposal.

(y)

Use of and training for radioactive material for uptake, dilution, and excretion studies that do not require a written directive.

(1)

Use of radioactive material for uptake, dilution, and excretion studies. Except for quantities that require a written directive in accordance with subsection (p) of this section, the licensee may use any unsealed radioactive material prepared for medical use for uptake, dilution, or excretion studies that meets the following:

(A)

is obtained from a manufacturer or preparer licensed in accordance with §289.252 of this title or equivalent NRC, agreement state, or licensing state requirements;

(B)

is prepared by a physician who is an authorized user and who meets the requirements specified in paragraph (2) of this subsection, or an individual under the supervision of an authorized user as specified in subsection (o) of this section;

(C)

is obtained from an NRC, agreement state, or licensing state licensee for use in research in accordance with a Radioactive Drug Research Committee-approved protocol or an IND protocol accepted by the FDA; or

(D)

is prepared by the licensee for use in research in accordance with a Radioactive Drug Research Committee-approved application or an IND protocol accepted by the FDA.

(2)

Training for uptake, dilution, and excretion studies. An authorized user of radiopharmaceuticals for the uses authorized in paragraph (1) of this subsection shall be a physician who meets the requirements of subsection (ff)(1)(A) and (I) or (ff)(1)(H) and (I) of this section.

(z)

Use of and training for radioactive material for imaging and localization studies that do not require a written directive.

(1)

Use of radioactive material for imaging and localization studies. Except for quantities that require a written directive in accordance with subsection (p) of this section, the licensee may use any unsealed radioactive material prepared for medical use for imaging and localization studies that meets the following:

(A)

is obtained from a manufacturer or preparer licensed in accordance with § 289.252 of this title or equivalent NRC, agreement state, or licensing state requirements;

(B)

is prepared by a physician who is an authorized user and who meets the requirements specified in paragraph (4) of this subsection, or an individual under the supervision of an authorized user as specified in subsection (o) of this section;

(C)

is obtained from an NRC, agreement state, or licensing state licensee for use in research in accordance with a Radioactive Drug Research Committee-approved protocol or an Investigational New Drug (IND) protocol accepted by the FDA; or

(D)

is prepared by the licensee for use in research in accordance with a Radioactive Drug Research Committee-approved application or an IND protocol accepted by FDA.

(2)

Any licensee who processes and prepares radiopharmaceuticals for human use shall do so according to instructions that are furnished by the manufacturer on the label attached to or in the FDA-accepted instructions in the leaflet or brochure that accompanies the generator or reagent kit.

(3)

Permissible molybdenum-99 concentration.

(A)

The licensee may not administer to humans a radiopharmaceutical containing more than 0.15 µCi of molybdenum-99 per millicurie of technetium-99m (0.15 kilobecquerel of molybdenum-99 per megabecquerel of technetium-99m).

(B)

The licensee who uses molybdenum-99/technetium-99m generators for preparing a technetium-99m radiopharmaceutical shall measure the molybdenum-99 concentration of the first eluate after receipt of a generator to demonstrate compliance with paragraph (1) of this subsection.

(C)

If the licensee is required to measure the molybdenum-99 concentration, the licensee shall maintain a record of each measurement in accordance with subsection (ff)(2) of this section. The record shall include the following for each measured elution of technetium-99m:

(i)

ratio of the measures expressed as microcuries of molybdenum-99 per millicurie of technetium-99m (kilobecquerel of molybdenum-99 per megabecquerel of technetium-99m);

(ii)

times and dates of the measurement; and

(iii)

name of the individual who made the measurement.

(4)

Training for imaging and localization studies. An authorized user of radiopharmaceuticals for the uses authorized in paragraph (1) of this subsection shall be a physician who meets the requirements of subsection (ff)(1)(B) and (I) or (ff)(1)(H) and (I) of this section.

(aa)

Use of and training for unsealed radioactive material for therapy that requires a written directive.

(1)

Use of unsealed radioactive material for therapy. A licensee may use any unsealed radioactive material prepared for medical use that requires a written directive in accordance with subsection (p) of this section that meets the following:

(A)

is obtained from a manufacturer or preparer licensed in accordance with §289.252 of this title or equivalent NRC, agreement state, or licensing state requirements;

(B)

is prepared by a physician who is an authorized user and who meets the requirements specified in paragraph (4) of this subsection, or an individual under the supervision of an authorized user as specified in subsection (o) of this section;

(C)

is obtained from an NRC, agreement state, or licensing state licensee for use in research in accordance with an IND application accepted by the FDA; or

(D)

is prepared by the licensee for use in research in accordance with an IND protocol accepted by FDA.

(2)

Safety instruction to personnel.

(A)

The licensee shall provide radiation safety instruction, initially and at least annually, to personnel caring for patients or human research subjects who have received therapy with a drug containing radioactive material and cannot be released in accordance with subsection (w) of this section. The instruction must be appropriate to the personnel's assigned duties and include the following:

(i)

patient or human research subject control; and

(ii)

visitor control to include the following:

(I)

routine visitation to hospitalized individuals in accordance with §289.202(n) of this title;

(II)

contamination control;

(III)

waste control; and

(IV)

notification of the RSO, or his or her designee, and the authorized user if the patient or the human research subject dies or has a medical emergency.

(B)

The licensee shall maintain a record, in accordance with subsection (ff)(2) of this section, of individuals receiving instruction. The record shall include the following:

(i)

list of the topics covered;

(ii)

date of the instruction or training;

(iii)

name(s) of the attendee(s); and

(iv)

name(s) of the individual(s) who provided the instruction.

(3)

Safety precautions for patients or human research subjects receiving radiopharmaceutical therapy.

(A)

For each patient or human research subject receiving radiopharmaceutical therapy and hospitalized in accordance with subsection (w) of this section, the licensee shall do the following:

(i)

provide a private room with a private sanitary facility;

(ii)

post the patient's or the human research subject's room with a "Radioactive Materials" sign and note on the door and in the patient's or human research subject's chart where and how long visitors may stay in the patient's or the human research subject's room; and

(iii)

either monitor material and items removed from the patient's or the human research subject's room to determine that their radioactivity cannot be distinguished from the natural background radiation level with a radiation detection survey instrument set on its most sensitive scale and with no interposed shielding, or handle such material and items as radioactive waste.

(B)

The RSO, or his or her designee, and the authorized user shall be notified immediately if the patient or human research subject has a medical emergency or if the patient dies.

(4)

Training for use of radioactive material for therapy that requires a written directive. An authorized user of radiopharmaceuticals for the uses authorized in paragraph (1) of this subsection shall be a physician who meets the requirements of subsection (ff)(1)(C) and (I) or (ff)(1)(H) and (I) of this section.

(bb)

Use of and training for sealed sources for manual brachytherapy.

(1)

Use of sealed sources for manual brachytherapy. The licensee shall use only brachytherapy sealed sources for therapeutic medical uses as follows:

(A)

as approved in the Sealed Source and Device Registry; or

(B)

in research in accordance with an effective Investigational Device Exemption (IDE) application accepted by the FDA and as approved by the agency.

(2)

Surveys after sealed source implants and removal.

(A)

Immediately after implanting sealed sources in a patient or a human research subject, the licensee shall perform a survey to locate and account for all sealed sources that have not been implanted.

(B)

Immediately after removing the last temporary implant sealed source from a patient or a human research subject, the licensee shall make a survey of the patient or the human research subject with a radiation detection survey instrument to confirm that all sealed sources have been removed.

(C)

A record of each survey shall be maintained in accordance with subsection (ff)(2) of this section. The record shall include the following:

(i)

dates of the survey;

(ii)

results of the survey;

(iii)

manufacturer's name and model and serial number of the instrument used to make the survey; and

(iv)

name of the individual who performed the survey.

(3)

Brachytherapy sealed sources inventory.

(A)

The licensee shall maintain accountability at all times for all brachytherapy sealed sources in storage or use.

(B)

Promptly after removing sealed sources from a patient or a human research subject, the licensee shall return brachytherapy sealed sources to a secure storage area.

(C)

The licensee shall maintain a record of the brachytherapy sealed source accountability in accordance with subsection (ff)(2) of this section.

(i)

The following information shall be recorded when temporary implants are removed from storage:

(I)

number and activity of sealed sources;

(II)

times and dates;

(III)

name of the individual who removed them from storage;

(IV)

location of use; and

(V)

when returned to storage, the information in subclauses (I)-(III) of this clause.

(ii)

The following information shall be recorded when permanent implants are removed from storage:

(I)

number and activity of sealed sources;

(II)

dates;

(III)

name of the individual who removed them from storage;

(IV)

the information in subclauses (I)-(III) of this clause for all sealed sources not implanted; and

(V)

the number and activity of sealed sources permanently implanted in the patient or human research subject.

(4)

Safety instruction to personnel. The licensee shall provide radiation safety instruction, initially and at least annually, to personnel caring for patients or human research subjects who are undergoing implant therapy and who cannot be released in accordance with subsection (w) of this section.

(A)

The instruction must be appropriate to the personnel's assigned duties and include the following:

(i)

size and appearance of brachytherapy sealed sources;

(ii)

safe handling and shielding instructions;

(iii)

patient or human research subject control;

(iv)

visitor control to include visitation to hospitalized individuals in accordance with §289.202(n) of this title; and

(v)

notification of the RSO, or his or her designee, and an authorized user if the patient or the human research subject dies or has a medical emergency.

(B)

A licensee shall maintain a record, in accordance with subsection (ff)(2) of this section, of individuals receiving instruction. The record shall include the following:

(i)

list of the topics covered;

(ii)

date of the instruction or training;

(iii)

name(s) of the attendee(s); and

(iv)

name(s) of the individual(s) who provided the instruction.

(5)

Safety precautions for the use of brachytherapy.

(A)

For each patient or human research subject who is receiving brachytherapy and cannot be released in accordance with subsection (w) of this section, the licensee shall:

(i)

provide a private room with a private sanitary facility;

(ii)

post the patient's or the human research subject's room with a "Radioactive Materials" sign and note on the door or in the patient's or human research subject's chart where and how long visitors may stay in the patient's or the human research subject's room; and

(iii)

have available near each treatment room emergency response equipment to respond to a sealed source that is inadvertently dislodged from the patient or inadvertently lodged within the patient following removal of the sealed source applicators.

(B)

The RSO, or his or her designee, and the authorized user shall be notified if the patient or human research subject has a medical emergency and, immediately, if the patient dies.

(6)

Calibration measurements of brachytherapy sealed sources.

(A)

Prior to the first medical use of a brachytherapy sealed source on or after October 1, 2000, the licensee shall do the following:

(i)

determine the sealed source output or activity using a dosimetry system that meets the requirements of subsection (dd)(6) of this section;

(ii)

determine sealed source positioning accuracy within applicators; and

(iii)

use published protocols accepted by nationally recognized bodies to meet the requirements of clauses (i) and (ii) of this subparagraph.

(B)

The licensee may use measurements provided by the sealed source manufacturer that are made in accordance with subparagraph (A) of this paragraph.

(C)

The licensee shall mathematically correct the outputs or activities determined in subparagraph (A) of this paragraph for physical decay at intervals consistent with 1.0% physical decay.

(D)

The licensee shall maintain a record of each calibration in accordance with subsection (ff)(2) of this section. The record shall include the following:

(i)

dates of the calibration;

(ii)

manufacturer's name and model and serial number for the sealed source and instruments used to calibrate the sealed source;

(iii)

sealed source output or activity;

(iv)

sealed source positioning accuracy within applicators; and

(v)

signature of a licensed medical physicist.

(7)

Therapy-related computer systems. The licensee shall perform acceptance testing on the treatment planning system in accordance with published protocols accepted by nationally recognized bodies. At a minimum, the acceptance testing must include, as applicable, verification of the following:

(A)

the sealed source-specific input parameters required by the dose calculation algorithm;

(B)

the accuracy of dose, dwell time, and treatment time calculations at representative points;

(C)

the accuracy of isodose plots and graphic displays; and

(D)

the accuracy of the software used to determine radioactive sealed source positions from radiographic images.

(8)

Training for use of manual brachytherapy sealed sources.

(A)

An authorized user of sealed sources for the uses authorized in paragraph (1) of this subsection shall be a physician who meets the requirements of subsection (ff)(1)(D), (E), and (I) or (ff)(1)(H) and (I) of this section.

(B)

An authorized user who is limited to the use of eye applicators shall be a physician who meets the requirements of subsection (ff)(1)(E) and (I) or (ff)(1)(H) and (I) of this section.

(cc)

Use of and training for sealed sources for diagnosis.

(1)

Use of sealed sources for diagnosis. The licensee shall use only sealed sources for diagnostic medical uses as approved in the Sealed Source and Device Registry.

(2)

Training for use of sealed sources for diagnosis. An authorized user of radiopharmaceuticals for the uses authorized in paragraph (1) of this subsection shall be a physician who meets the requirements of subsection (ff)(1)(F) and (I) or (ff)(1)(H) and (I) of this section.

(dd)

Use of and training for a sealed source in a remote afterloader unit, teletherapy unit, or gamma stereotactic radiosurgery unit.

(1)

Use of a sealed source in a remote afterloader unit, teletherapy unit, or gamma stereotactic radiosurgery unit. The licensee shall use sealed sources in photon-emitting remote afterloader units, teletherapy units, or gamma stereotactic units for therapeutic medical uses as follows:

(A)

as approved in the Sealed Source and Device Registry; or

(B)

in research in accordance with an effective Investigational Device Exemption (IDE) application accepted by the FDA.

(2)

Surveys of patients and human research subjects treated with a remote afterloader unit.

(A)

Before releasing a patient or a human research subject from licensee control, the licensee shall perform a survey of the patient or the human research subject and the remote afterloader unit with a portable radiation detection survey instrument to confirm that the sealed source(s) has been removed from the patient or human research subject and returned to the safe shielded position.

(B)

The licensee shall maintain a record of the surveys in accordance with subsection (ff)(2) of this section. The record shall include the following:

(i)

dates of the survey;

(ii)

results of the survey;

(iii)

manufacturer's name and model and serial number of the survey instrument used; and

(iv)

name of the individual who made the survey.

(3)

Installation, maintenance, adjustment, and repair.

(A)

Only a person specifically licensed by the agency, the NRC, an agreement state, or licensing state shall install, maintain, adjust, or repair a remote afterloader unit, teletherapy unit, or gamma stereotactic radiosurgery unit that involves work on the sealed source(s) shielding, the sealed source(s) driving unit, or other electronic or mechanical component that could expose the sealed source(s), reduce the shielding around the sealed source(s), or compromise the radiation safety of the unit or the sealed source(s).

(B)

Except for low dose-rate remote afterloader units, only a person specifically licensed by the agency, the NRC, an agreement state, or licensing state shall install, replace, relocate, or remove a sealed source or sealed source contained in other remote afterloader units, teletherapy units, or gamma stereotactic units.

(C)

For a low dose-rate remote afterloader unit, only a person specifically licensed by the agency, the NRC, an agreement state, a licensing state, or a licensed medical physicist shall install, replace, relocate, or remove a sealed source(s) contained in the unit.

(D)

The licensee shall maintain a record of the installation, maintenance, adjustment and repair done on remote afterloader units, teletherapy units, and gamma stereotactic radiosurgery units in accordance with subsection (ff)(2) of this section. For each installation, maintenance, adjustment and repair, the record shall include the dates, description of the service, and name(s) of the individual(s) who performed the work.

(4)

Safety procedures and instructions for remote afterloader units, teletherapy units, and gamma stereotactic radiosurgery units. A licensee shall do the following:

(A)

secure the unit, the console, the console keys, and the treatment room when not in use or unattended;

(B)

permit only individuals approved by the authorized user, RSO, or licensed medical physicist to be present in the treatment room during treatment with the sealed source(s);

(C)

prevent dual operation of more than one radiation producing device in a treatment room if applicable;

(D)

develop, implement, and maintain written procedures for responding to an abnormal situation when the operator is unable to place the sealed source(s) in the shielded position, or remove the patient or human research subject from the radiation field with controls from outside the treatment room;

(i)

The procedure required by this paragraph must include the following:

(I)

instructions for responding to equipment failures and the names of the individuals responsible for implementing corrective actions;

(II)

the process for restricting access to and posting of the treatment area to minimize the risk of inadvertent exposure; and

(III)

the names and telephone numbers of the authorized users, the licensed medical physicist, and the RSO to be contacted if the unit or console operates abnormally.

(ii)

A copy of the procedures required by this paragraph must be physically located at the unit console.

(E)

post instructions at the unit console to inform the operator of the following:

(i)

the location of the procedures required by subparagraph (D) of this paragraph; and

(ii)

the names and telephone numbers of the authorized users, the licensed medical physicist, and the RSO to be contacted if the unit or console operates abnormally;

(F)

provide instruction initially and at least annually, to all individuals who operate the unit, as appropriate to the individual's assigned duties, in the following:

(i)

procedures identified in subparagraph (D) of this paragraph; and

(ii)

operating procedures for the unit;

(G)

ensure that operators, licensed medical physicists, and authorized users participate in drills of the emergency procedures, initially and at least annually; and

(H)

maintain a record, in accordance with subsection (ff)(2) of this section, of individuals receiving instruction and participating in drills required by subparagraphs (F) and (G) of this paragraph. The record shall include the following:

(i)

a list of the topics covered;

(ii)

date of the instruction or drill;

(iii)

name(s) of the attendee(s); and

(iv)

name(s) of the individual(s) who provided the instruction.

(5)

Safety precautions for remote afterloader units, teletherapy units, and gamma stereotactic radiosurgery units. The licensee shall do the following:

(A)

control access to the treatment room by a door at each entrance;

(B)

equip each entrance to the treatment room with an electrical interlock system that will do the following:

(i)

prevent the operator from initiating the treatment cycle unless each treatment room entrance door is closed;

(ii)

cause the sealed source(s) to be shielded promptly when an entrance door is opened; and

(iii)

prevent the sealed source(s) from being exposed following an interlock interruption until all treatment room entrance doors are closed and the sealed source(s) "on-off" control is reset at the console;

(C)

require any individual entering the treatment room to assure, through the use of appropriate radiation monitors, that radiation levels have returned to ambient levels;

(D)

except for low-dose remote afterloader units, construct or equip each treatment room with viewing and intercom systems to permit continuous observation of the patient or the human research subject from the treatment console during irradiation;

(E)

for licensed activities where sealed sources are placed within the patient's or human research subject's body, only conduct treatments that allow for expeditious removal of a decoupled or jammed sealed source;

(F)

in addition to the requirements specified in subparagraph (B) of this paragraph, require the following for low dose-rate, medium dose-rate, and pulsed dose-rate remote afterloader units:

(i)

a licensed medical physicist and either an authorized user or a physician, under the supervision of an authorized user, who has been trained in the operation and emergency response for the unit, be physically present during the initiation of all patient treatments involving the unit; and

(ii)

a licensed medical physicist and either an authorized user or an individual, under the supervision of an authorized user, who has been trained to remove the sealed source applicator(s) in the event of an emergency involving the unit, be immediately available during continuation of all patient treatments involving the unit;

(G)

in addition to the requirements specified in subparagraphs (A) and (B) of this paragraph, require the following for high dose-rate remote afterloader units:

(i)

an authorized user and a licensed medical physicist be physically present during the initiation of all patient treatments involving the unit; and

(ii)

a licensed medical physicist and either an authorized user or a physician, under the supervision of an authorized user, who has been trained in the operation and emergency response for the unit, be physically present during continuation of all patient treatments involving the unit;

(H)

in addition to the requirements specified in subparagraphs (A) and (B) of this paragraph, require that an authorized user and a licensed medical physicist be physically present throughout all patient treatments involving gamma stereotactic radiosurgery units;

(I)

notify the RSO, or his or her designee, and an authorized user as soon as possible, if the patient or human research subject has a medical emergency and, immediately, if the patient dies; and

(J)

have available, near each treatment room, emergency response equipment, as applicable, to respond to a sealed source that inadvertently remains in the unshielded position or inadvertently lodges within the patient following completion of the treatment.

(6)

Dosimetry equipment.

(A)

Except for low dose-rate remote afterloader sealed sources where the sealed source output or activity is determined by the manufacturer, the licensee shall have a calibrated dosimetry system available for use. To satisfy this requirement, one of the following two conditions must be met.

(i)

The system must have been calibrated using a system or sealed source traceable to the National Institute of Standards and Technology (NIST) and published protocols accepted by nationally recognized bodies; or by a calibration laboratory accredited by the American Association of Physicists in Medicine (AAPM). The calibration must have been performed within the previous two years and after any servicing that may have affected system calibration.

(ii)

The system must have been calibrated within the previous four years. Eighteen to 30 months after that calibration, the system must have been intercompared with another dosimetry system that was calibrated within the past 24 months by NIST or by a calibration laboratory accredited by the AAPM. The results of the intercomparison must have indicated that the calibration factor of the licensee's system had not changed by more than 2.0%. The licensee may not use the intercomparison result to change the calibration factor. When intercomparing dosimetry systems to be used for calibrating sealed sources for therapeutic unit, the licensee shall use a comparable unit with beam attenuators or collimators, as applicable, and sealed sources of the same radionuclide as the sealed source used at the licensee's facility.

(B)

The licensee shall have available for use a dosimetry system for spot check output measurements, if applicable. To satisfy this requirement, the system may be compared with a system that has been calibrated in accordance with subparagraph (A) of this paragraph. This comparison must have been performed within the previous year and after each servicing that may have affected system calibration. The spot check system may be the same system used to meet the requirement in subparagraph (A) of this paragraph.

(C)

The licensee shall maintain a record of each calibration, intercomparison, and comparison of dosimetry equipment in accordance with subsection (ff)(2) of this section. The record shall include the following:

(i)

dates of the calibration;

(ii)

model and serial numbers of the instruments that were calibrated, intercompared, or compared;

(iii)

the correction factor that was determined from the calibration or comparison or the apparent correction factor that was determined from an intercomparison; and

(iv)

the names of the individuals who performed the calibration, intercomparison, or comparison.

(7)

Full calibration measurements on teletherapy units.

(A)

The licensee shall perform full calibration measurements on each teletherapy unit as follows:

(i)

before the first medical use of the unit; and

(ii)

before medical use under the following conditions:

(I)

whenever spot check measurements indicate that the output differs by more than 5.0% from the output obtained at the last full calibration corrected mathematically for radioactive decay;

(II)

following replacement of the sealed source or following reinstallation of the teletherapy unit in a new location;

(III)

following any repair of the teletherapy unit that includes removal of the sealed source or major repair of the components associated with the sealed source exposure assembly; and

(iii)

at intervals not to exceed one year.

(B)

Full calibration measurements must include determination of the following:

(i)

output within plus or minus 3.0% for the range of field sizes and for the distance or range of distances used for medical use;

(ii)

the coincidence of the radiation field and the field indicated by the light beam localizing device;

(iii)

uniformity of the radiation field and its dependence on the orientation of the useful beam;

(iv)

timer constancy and linearity over the range of use;

(v)

"on-off" error; and

(vi)

the accuracy of all distance measuring and localization devices in medical use.

(C)

The licensee shall use the dosimetry system described in paragraph(6)(A) of this subsection to measure the output for one set of exposure conditions. The remaining radiation measurements required in subparagraph (B)(i) of this paragraph may be made using a dosimetry system that indicates relative dose rates.

(D)

The licensee shall make full calibration measurements required by subparagraph (A) of this paragraph in accordance with published protocols accepted by nationally recognized bodies.

(E)

The licensee shall mathematically correct the outputs determined in subparagraph (B)(i) of this paragraph for physical decay at intervals not to exceed one month for cobalt-60, six months for cesium-137, or at intervals consistent with 1.0% decay for all other nuclides.

(F)

Full calibration measurements required by subparagraph (A) of this paragraph and physical decay corrections required by paragraph (E) of this subsection must be performed by a licensed medical physicist.

(G)

The licensee shall maintain a record of each calibration in accordance with subsection (ff)(2) of this section. The record shall include the following:

(i)

dates of the calibration;

(ii)

manufacturer's name and model and serial number for the unit's sealed source;

(iii)

instruments used to calibrate the unit;

(iv)

results and an assessment of the full calibration; and

(v)

signature of the licensed medical physicist who performed the full calibration.

(8)

Full calibration measurements on remote afterloader units.

(A)

The licensee shall perform full calibration measurements on each remote afterloader unit as follows:

(i)

before the first medical use of the unit; and

(ii)

before medical use under the following conditions:

(I)

following replacement of the sealed source;

(II)

following reinstallation of the unit in a new location outside the facility;

(III)

following any repair of the unit that includes removal of the sealed source or major repair of the components associated with the sealed source exposure assembly;

(iii)

at intervals not to exceed three months for high dose-rate, medium dose-rate, and pulsed dose-rate remote afterloader units with sealed sources whose half- life exceeds 75 days; and

(iv)

at intervals not to exceed one year for low dose rate afterloader units.

(B)

Full calibration measurements must include, as applicable, determination of the following:

(i)

the output within plus or minus 5.0%;

(ii)

sealed source positioning accuracy to within plus or minus 1 mm;

(iii)

sealed source retraction with backup battery upon power failure;

(iv)

length of the sealed source transfer tubes;

(v)

timer accuracy and linearity over the typical range of use;

(vi)

length of the applicators; and

(vii)

function of the sealed source transfer tubes, applicators, and transfer tube-applicator interfaces.

(C)

A licensee shall use the dosimetry system described in paragraph (6)(A) of this subsection to measure the output.

(D)

A licensee shall make full calibration measurements required by subparagraph (A) of this paragraph in accordance with published protocols accepted by nationally recognized bodies.

(E)

In addition to the requirements for full calibrations for low dose-rate remote afterloader units in subparagraph (B) of this paragraph, a licensee shall perform an autoradiograph of the sealed source(s) to verify inventory and sealed source(s) arrangement at intervals not to exceed three months.

(F)

For low dose-rate remote afterloader units, a licensee may use measurements provided by the sealed source manufacturer that are made in accordance with subparagraphs (A)-(E) of this paragraph.

(G)

The licensee shall mathematically correct the outputs determined in subparagraph (B)(i) of this paragraph for physical decay at intervals consistent with 1.0% physical decay.

(H)

Full calibration measurements required by subparagraph (A) of this paragraph and physical decay corrections required by subparagraph (G) of this paragraph must be performed by a licensed medical physicist.

(I)

The licensee shall maintain a record of each calibration in accordance with subsection (ff)(2) of this section. In addition to the items in paragraph (7)(G) of this subsection, the record shall also include results of the autoradiograph required for low dose-rate remote afterloader units.

(9)

Full calibration measurements on gamma stereotactic radiosurgery units.

(A)

The licensee shall perform full calibration measurements on each gamma stereotactic radiosurgery unit as follows:

(i)

before the first medical use of the unit;

(ii)

before medical use under the following conditions:

(I)

whenever spot check measurements indicate that the output differs by more than 5.0% from the output obtained at the last full calibration corrected mathematically for radioactive decay;

(II)

following replacement of the sealed sources or following reinstallation of the gamma stereotactic radiosurgery unit in a new location;

(III)

following any repair of the gamma stereotactic radiosurgery unit that includes removal of the sealed sources or major repair of the components associated with the sealed source exposure assembly; and

(iii)

at intervals not to exceed one year.

(B)

Full calibration measurements must include determination of the following:

(i)

the output within plus or minus 3.0%;

(ii)

relative helmet factors;

(iii)

isocenter coincidence;

(iv)

timer accuracy and linearity over the range of use;

(v)

"on-off" error;

(vi)

trunnion centricity;

(vii)

treatment table retraction mechanism, using backup battery power or hydraulic backups with the unit "off";

(viii)

helmet microswitches;

(ix)

emergency timing circuits; and

(x)

stereotactic frames and localizing devices (trunnions).

(C)

The licensee shall use the dosimetry system described in paragraph (6)(A) of this subsection to measure the output for one set of exposure conditions. The remaining radiation measurements required in subparagraph (B)(i) of this paragraph may be made using a dosimetry system that indicates relative dose rates.

(D)

The licensee shall make full calibration measurements required by subparagraph (A) of this paragraph in accordance with published protocols accepted by nationally recognized bodies.

(E)

The licensee shall mathematically correct the outputs determined in subparagraph (B)(i) of this paragraph at intervals not to exceed one month for cobalt-60 and at intervals consistent with 1.0% physical decay for all other radionuclides.

(F)

Full calibration measurements required by subparagraph (A) of this paragraph and physical decay corrections required by subparagraph (E) of this paragraph must be performed by a licensed medical physicist.

(G)

The licensee shall maintain a record of each calibration in accordance with subsection (ff)(2) of this section. The record shall include the following:

(i)

dates of the calibration;

(ii)

manufacturer's name and model and serial number for the unit's sealed source;

(iii)

instruments used to calibrate the unit;

(iv)

results and an assessment of the full calibration; and

(v)

signature of the licensed medical physicist who performed the full calibration.

(10)

Periodic spot checks for teletherapy units.

(A)

The licensee authorized to use teletherapy units for medical use shall perform output spot checks on each teletherapy unit once in each calendar month that include determination of the following:

(i)

timer constancy and linearity over the range of use;

(ii)

"on-off" error;

(iii)

the coincidence of the radiation field and the field indicated by the light beam localizing device;

(iv)

the accuracy of all distance measuring and localization devices used for medical use;

(v)

the output for one typical set of operating conditions measured with the dosimetry system described in paragraph (6)(A) of this subsection; and

(vi)

the difference between the measurement made in subparagraph (A)(v) of this section and the anticipated output, expressed as a percentage of the anticipated output, the value obtained at last full calibration corrected mathematically for physical decay.

(B)

The licensee shall perform measurements required by subparagraph (A) of this paragraph in accordance with procedures established by a licensed medical physicist. That individual need not actually perform the spot check measurements.

(C)

The licensee authorized to use a teletherapy unit for medical use shall perform safety spot checks of each teletherapy facility once in each calendar month and after each sealed source installation to assure proper operation of the following:

(i)

electrical interlocks at each teletherapy room entrance;

(ii)

electrical or mechanical stops installed for the purpose of limiting use of the primary beam of radiation (restriction of sealed source housing angulation or elevation, carriage or stand travel and operation of the beam "on-off" mechanism);

(iii)

sealed source exposure indicator lights on the teletherapy unit, on the control console, and in the facility;

(iv)

viewing and intercom systems;

(v)

treatment room doors from inside and outside the treatment room; and

(vi)

electrically assisted treatment room doors with the teletherapy unit electrical power turned "off".

(D)

The licensee shall have a licensed medical physicist review the results of each spot check and submit a written report to the licensee within 15 days of the spot check.

(E)

If the results of the checks required in subparagraph (C) of this paragraph indicate the malfunction of any system, the licensed medical physicist shall immediately notify the licensee and the licensee shall lock the control console in the "off" position and not use the unit except as may be necessary to repair, replace, or check the malfunctioning system.

(F)

The licensee shall maintain a record of each spot check required by subparagraphs (A) and (D) of this paragraph, in accordance with subsection (ff)(2) of this section. The record shall include the following:

(i)

dates of the spot-check;

(ii)

manufacturer's name and model and serial number for the teletherapy unit, and sealed source and instrument used to measure the output of the teletherapy unit;

(iii)

assessment of timer linearity and constancy;

(iv)

calculated "on-off" error;

(v)

determination of the coincidence of the radiation field and the field indicated by the light beam localizing device;

(vi)

the determined accuracy of each distance measuring and localization device;

(vii)

the difference between the anticipated output and the measured output;

(viii)

notations indicating the operability of each entrance door electrical interlock, each electrical or mechanical stop, each sealed source exposure indicator light, and the viewing and intercom system and doors;

(ix)

name of the individual who performed the periodic spot-check; and

(x)

the signature of the licensed medical physicist who reviewed the record of the spot check.

(11)

Periodic spot checks for remote afterloader units.

(A)

The licensee shall perform spot checks of each remote afterloader facility and on each unit as follows:

(i)

at the beginning of each day of use of a high dose-rate, medium dose-rate, or pulsed dose-rate remote afterloader unit;

(ii)

before each patient treatment with a low dose-rate remote afterloader unit; and

(iii)

after each sealed source installation.

(B)

The licensee shall perform the measurements required by subparagraph (A) of this paragraph in accordance with written procedures established by a licensed medical physicist. That individual need not actually perform the spot check measurements.

(C)

The licensee shall have a licensed medical physicist review the results of each spot check and submit a written report to the licensee within 15 days of the spot check.

(D)

To satisfy the requirements of subparagraph (A) of this paragraph, spot checks must, at a minimum, assure proper operation of the following:

(i)

electrical interlocks at each remote afterloader unit room entrance;

(ii)

sealed source exposure indicator lights on the remote afterloader unit, on the control console, and in the facility;

(iii)

viewing and intercom systems in each high dose-rate, medium dose-rate, and pulsed dose-rate remote afterloader facility;

(iv)

emergency response equipment;

(v)

radiation monitors used to indicate the sealed source position;

(vi)

timer accuracy;

(vii)

clock (date and time) in the unit's computer; and

(viii)

decayed sealed source(s) activity in the unit's computer.

(E)

If the results of the checks required in subparagraph (D) of this paragraph indicate the malfunction of any system, the licensee shall lock the control console in the "off" position and not use the unit except as may be necessary to repair, replace, or check the malfunctioning system.

(F)

The licensee shall maintain a record, in accordance with subsection (ff)(2) of this section, of each check required by subparagraph (A) of this paragraph. The record shall include the following, as applicable:

(i)

dates of the spot-check;

(ii)

manufacturer's name and model and serial number for the remote afterloader unit and sealed source;

(iii)

an assessment of timer accuracy;

(iv)

notations indicating the operability of each entrance door electrical interlock, radiation monitors, sealed source exposure indicator lights, viewing and intercom systems, clock, and decayed sealed source activity in the unit's computer;

(v)

name of the individual who performed the periodic spot-check; and

(vi)

the signature of the licensed medical physicist who reviewed the record of the spot check.

(12)

Periodic spot checks for gamma stereotactic radiosurgery units.

(A)

The licensee shall perform spot checks of each gamma stereotactic radiosurgery facility and on each unit as follows:

(i)

monthly;

(ii)

at the beginning of each day of use; and

(iii)

after each source installation.

(B)

The licensee shall perform the measurements required by subparagraph (A) of this paragraph in accordance with written procedures established by a licensed medical physicist. That individual need not actually perform the spot check measurements.

(C)

The licensee shall have a licensed medical physicist review the results of each spot check and submit a written report to the licensee within 15 days of the spot check.

(D)

To satisfy the requirements of subparagraph (A)(i) of this paragraph, spot checks must, at a minimum, achieve the following by:

(i)

assurance of proper operation of these items:

(I)

treatment table retraction mechanism, using backup battery power or hydraulic backups with the unit "off";

(II)

helmet microswitches;

(III)

emergency timing circuits; and

(IV)

stereotactic frames and localizing devices (trunnions); and

(ii)

determination of the following:

(I)

the output for one typical set of operating conditions measured with the dosimetry system described in paragraph (6)(A) of this subsection;

(II)

the difference between the measurement made in subclause (I) of this clause and the anticipated output, expressed as a percentage of the anticipated output, the value obtained at last full calibration corrected mathematically for physical decay;

(III)

sealed source output against computer calculation;

(IV)

timer accuracy and linearity over the range of use;

(V)

"on-off" error; and

(VI)

trunnion centricity.

(E)

To satisfy the requirements of subparagraph (A)(ii) and (iii) of this paragraph, spot checks must assure proper operation of the following:

(i)

electrical interlocks at each gamma stereotactic radiosurgery room entrance;

(ii)

sealed source exposure indicator lights on the gamma stereotactic radiosurgery unit, on the control console, and in the facility;

(iii)

viewing and intercom systems;

(iv)

timer termination;

(vi)

radiation monitors used to indicate room exposures; and

(vii)

emergency "off" buttons.

(F)

The licensee shall arrange for prompt repair of any system identified in subparagraph (D) of this paragraph that is not operating properly.

(G)

If the results of the checks required in subparagraph (D) of this paragraph indicate the malfunction of any system, the licensee shall lock the control console in the "off" position and not use the unit except as may be necessary to repair, replace, or check the malfunctioning system.

(H)

The licensee shall retain a record of each check required by subparagraphs (D) and (E) of this paragraph in accordance with subsection (ff)(2) of this section. The record shall include the following:

(i)

dates of the spot check;

(ii)

manufacturer's name and model and serial number for the gamma stereotactic radiosurgery unit and the instrument used to measure the output of the unit;

(iii)

an assessment of timer linearity and accuracy;

(iv)

the calculated "on-off" error;

(v)

a determination of trunnion centricity;

(vi)

the difference between the anticipated output and the measured output;

(vii)

an assessment of sealed source output against computer calculations;

(viii)

notations indicating the operability of radiation monitors, helmet microswitches, emergency timing circuits, emergency "off" buttons, electrical interlocks, sealed source exposure indicator lights, viewing and intercom systems, timer termination treatment table retraction mechanism, and stereotactic frames and localizing devices (trunnions);

(ix)

the name of the individual who performed the periodic spot check; and

(x)

the signature of the licensed medical physicist who reviewed the record of the spot check.

(13)

Additional technical requirements for mobile remote afterloader units.

(A)

The licensee providing mobile remote afterloader service shall do the following:

(i)

check survey instruments before medical use at each address of use or on each day of use, whichever is more frequent; and

(ii)

account for all sealed sources before departure from a client's address of use.

(B)

In addition to the periodic spot checks required by paragraph (11) of this subsection, the licensee shall perform checks on each remote afterloader unit before medical use at each address of use. At a minimum, checks must be made to verify the operation of the following:

(i)

electrical interlocks on treatment area access points;

(ii)

sealed source exposure indicator lights on the remote afterloader unit, on the control console, and in the facility;

(iii)

viewing and intercom systems;

(iv)

applicators, sealed source transfer tubes, and transfer tube- applicator interfaces;

(v)

radiation monitors used to indicate room exposures;

(vi)

sealed source positioning (accuracy); and

(vii)

radiation monitors used to indicate whether the sealed source has returned to a safe shielded position.

(C)

In addition to the requirements for checks in subparagraph (B) of this paragraph, the licensee shall ensure overall proper operation of the remote afterloader unit by conducting a simulated cycle of treatment before use at each address of use.

(D)

If the results of the checks required in subparagraph (B) of this paragraph indicate the malfunction of any system, the licensee shall lock the control console in the "off" position and not use the unit except as may be necessary to repair, replace, or check the malfunctioning system.

(E)

The licensee shall retain a record, in accordance with subsection (ff)(2) of this section, of each check required by subparagraph (B) of this paragraph. The record shall include the following:

(i)

dates of the check;

(ii)

manufacturer's name and model and serial number of the remote afterloader unit;

(iii)

notations accounting for all sealed sources before the licensee departs from a facility;

(iv)

notations indicating the operability of each entrance door electrical interlock, radiation monitors, sealed source exposure indicator lights, viewing and intercom system, applicators and sealed source transfer tubes, and sealed source positioning accuracy; and

(v)

the signature of the individual who performed the check.

(14)

Radiation surveys.

(A)

In addition to the survey requirement in §289.202(p) of this title, a person licensed to use sealed sources in this subsection shall make surveys as defined in the Sealed Source and Device Registry to assure that the maximum radiation levels and average radiation levels from the surface of the main sealed source safe with the sealed source(s) in the shielded position do not exceed the levels stated in the Registry.

(B)

The licensee shall make the survey required by paragraph (A) of this section at installation of a new sealed source and following repairs to the sealed source(s) shielding, the sealed source(s) driving unit, or other electronic or mechanical component that could expose the sealed source, reduce the shielding around the sealed source(s), or compromise the radiation safety of the unit or the sealed source(s).

(C)

The licensee shall retain a record, in accordance with subsection (ff)(2) of this section, of the radiation surveys required by subparagraph (A) of this paragraph. The record shall include:

(i)

dates of the measurements;

(ii)

manufacturer's name and model and serial number of the treatment unit, sealed source, and instrument used to measure radiation levels;

(iii)

each dose rate measured around the sealed source while the unit is in the "off" position and the average of all measurements; and

(iv)

the signature of the individual who performed the test.

(15)

Five-year inspection for teletherapy and gamma stereotactic radiosurgery units.

(A)

The licensee shall have each teletherapy unit and gamma stereotactic radiosurgery unit fully inspected and serviced during sealed source replacement or at intervals not to exceed five years, whichever comes first, to assure proper functioning of the sealed source exposure mechanism.

(B)

This inspection and servicing may only be performed by persons specifically licensed to do so by the agency, the NRC, an agreement state, or licensing state.

(C)

The licensee shall keep a record of the inspection and servicing in accordance with subsection (ff)(2) of this section. The record shall include the following:

(i)

dates of inspection;

(ii)

manufacturer's name and model and serial number of both the treatment unit and the sealed source;

(iii)

a list of components inspected and serviced, and the type of service; and

(iv)

the radioactive material license number and the signature of the individual performing the inspection.

(16)

Therapy-related computer systems. The licensee shall perform acceptance testing on the treatment planning system in accordance with published protocols accepted by nationally recognized bodies. At a minimum, the acceptance testing must include, as applicable, verification of the following:

(A)

the sealed source-specific input parameters required by the dose calculation algorithm;

(B)

the accuracy of dose, dwell time, and treatment time calculations at representative points;

(C)

the accuracy of isodose plots and graphic displays;

(D)

the accuracy of the software used to determine sealed source positions from radiographic images; and

(E)

the accuracy of electronic transfer of the treatment delivery parameters to the treatment delivery unit from the treatment planning system.

(17)

Training for use of remote afterloader units, teletherapy units, and gamma stereotactic radiosurgery units. An authorized user of radiopharmaceuticals for the uses authorized in paragraph (1) of this subsection shall be a physician who meets the requirements of subsection (ff)(1)(G) and (I) or (ff)(1)(H) and (I) of this section.

(ee)

Report and notification of a medical event.

(1)

The licensee shall report any event, except for events that result from intervention by a patient or human research subject, in which the administration of radioactive material, or radiation from radioactive material, results in the following:

(A)

a dose that differs from the prescribed dose by more than 5 rem (0.05 Sv) effective dose equivalent, 50 rem (0.5 Sv) to an organ or tissue, or 50 rem (0.5 Sv) shallow dose equivalent to the skin and either:

(i)

the total dose delivered differs from the prescribed dose by 20% or more;

(ii)

the total dosage delivered differs from the prescribed dosage by 20% or more or falls outside the prescribed dosage range; or

(iii)

the fractionated dose delivered differs from the prescribed dose, for a single fraction, by 50% or more.

(B)

a dose that exceeds 5 rem (0.05 Sv) effective dose equivalent, 50 rem (0.5 Sv) to an organ or tissue, or 50 rem (0.5 Sv) shallow dose equivalent to the skin from any of the following:

(i)

an administration of a wrong radioactive drug containing radioactive material;

(ii)

an administration of a radioactive drug containing radioactive material by the wrong route of administration;

(iii)

an administration of a dose or dosage to the wrong individual or human research subject;

(iv)

an administration of a dose or dosage delivered by the wrong mode of treatment; or

(v)

a leaking sealed source.

(C)

a dose to the skin or an organ or tissue other than the treatment site that exceeds by 50 rem (0.5 Sv) to an organ or tissue and 50% of the dose expected from the administration defined in the written directive (excluding, for permanent implants, seeds that were implanted in the correct site but migrated outside the treatment site).

(2)

The licensee shall report any event resulting from intervention of a patient or human research subject in which the administration of radioactive material, or radiation from radioactive material, results or will result in an unintended permanent functional damage to an organ or a physiological system, as determined by a physician.

(3)

The licensee shall notify the agency by telephone no later than the next calendar day after discovery of the medical event.

(4)

The licensee shall submit a written report to the agency within 15 days after discovery of the medical event. The written report shall include the following, excluding the individual's name or any other information that could lead to identification of the individual:

(A)

the licensee's name and radioactive material license number;

(B)

the name of the prescribing physician;

(C)

a brief description of the medical event;

(D)

why the event occurred;

(E)

the effect, if any, on the individual(s) who received the administration;

(F)

actions, if any, that have been taken, or are planned, to prevent recurrence;

(G)

whether the licensee notified the individual (or the individual's responsible relative or guardian), and if not, why not; and

(H)

if there was notification, what information was provided.

(5)

The licensee shall notify the referring physician and also notify the individual who is the subject of the medical event no later than 24 hours after its discovery, unless the referring physician personally informs the licensee either that he or she will inform the individual or that, based on medical judgement, telling the individual would be harmful. The licensee is not required to notify the individual without first consulting the referring physician. If the referring physician or the affected individual cannot be reached within 24 hours, the licensee shall notify the individual as soon as possible thereafter. The licensee shall not delay any appropriate medical care for the individual, including any necessary remedial care as a result of the medical event, because of any delay in notification. To meet the requirements of this subsection, the notification of the individual who is the subject of the medical event may be made instead to that individual's responsible relative or guardian. If a verbal notification is made, the licensee shall inform the individual or appropriate responsible relative or guardian, that a written description of the event can be obtained from the licensee upon request. The licensee shall provide the written description if requested.

(6)

Aside from the notification requirement, nothing in this section affects any rights or duties of licensees and physicians in relation to each other, to individuals affected by the medical event, or to that individual's responsible relatives or guardians.

(7)

The licensee shall maintain a record of the medical event in accordance with subsection (ff)(2) of this section. A copy of the record shall be provided to the referring physician if other than the licensee. The record shall contain the following:

(A)

licensee's name and radioactive material license number;

(B)

names of the individuals involved;

(C)

the identification number of the individual who is the subject of the medical event;

(D)

brief description of the event and why it occurred;

(E)

the effect, if any, on the individual; and

(F)

the actions, if any, taken, or planned, to prevent recurrence; and

(G)

whether the licensee notified the individual or the individual's responsible relative or guardian, and if not, whether the failure to notify was based on guidance from the referring physician.

(8)

The licensee shall report any dose to an embryo/fetus that is greater than 5 rem (50 mSv) dose equivalent that is a result of an administration of radioactive material or radiation from radioactive material to a pregnant individual, unless the dose to the embryo/fetus was specifically approved, in advance, by the authorized user.

(9)

The licensee shall report any dose to a nursing child that is a result of an administration of radioactive material to a breast feeding individual that:

(A)

is greater than 5 rem (50 mSv) TEDE; or

(B)

has resulted in unintended permanent functional damage to an organ or a physiological system, as determined by a physician.

(10)

The licensee shall notify the agency by telephone no later than the next calendar day after discovery of a dose to the embryo/fetus or nursing child that requires a report in accordance with paragraphs (8) or (9) of this subsection.

(11)

The licensee shall submit a written report to the agency no later than 15 days after discovery of a dose to the embryo/fetus or nursing child that requires a report in accordance with paragraphs (8) or (9) of this subsection. The written report shall include the items in paragraph (4)(A)-(F) of this subsection, excluding the individual's or child's name or any other information that could lead to identification of the individual or child.

(12)

The licensee shall notify the referring physician and also notify the pregnant individual or mother, both hereafter referred to as the mother, no later than 24 hours after discovery of an event that would require reporting in accordance with paragraphs (8) or (9) of this subsection, unless the referring physician personally informs the licensee either that he or she will inform the mother or that, based on medical judgement, telling the mother would be harmful.

(13)

To meet the requirements of this subsection, the notification may be made to the mother's or child's responsible relative or guardian instead of the mother, when appropriate.

(14)

The licensee is not required to notify the mother without first consulting with the referring physician. If the referring physician or mother cannot be reached within 24 hours, the licensee shall make the appropriate notifications as soon as possible thereafter. The licensee may not delay any appropriate medical care for the embryo/fetus or for the nursing child, including any necessary remedial care as a result of the event, because of any delay in notification.

(15)

If notification was made in accordance with paragraphs (12) and (13) of this subsection, the licensee shall also furnish, within 15 days after discovery of the event, a written report to the mother or responsible relative or guardian, by sending either of the following:

(A)

a copy of the report that was submitted to the agency; or

(B)

a brief description of both the event and the consequences as they may affect the embryo/fetus or nursing child.

(16)

The licensee shall retain a record of a dose to an embryo/fetus or a nursing child in accordance with subsection (ff)(2) of this section. The record shall contain items in paragraph (7)(A) of this subsection.

(ff)

Appendices.

(1)

Acceptable training and experience for medical uses of radioactive material.

(A)

Training for uptake, dilution, and excretion studies.

(i)

The licensee shall require the authorized user of radiopharmaceuticals for uptake, dilution, and excretion studies to be a physician who:

(I)

is certified in:

(-a-)

nuclear medicine by the American Board of Nuclear Medicine (ABNM);

(-b-)

diagnostic radiology or radiology by the American Board of Radiology (ABR);

(-c-)

diagnostic radiology or radiology by the American Osteopathic Board of Radiology (AOBR);

(-d-)

nuclear medicine by the Royal College of Physicians and Surgeons of Canada (RCPSC); or

(-e-)

nuclear medicine by the American Osteopathic Board of Nuclear Medicine (AOBNM); or

(II)

has successfully completed classroom and laboratory training in basic radioisotope handling techniques applicable to the use of prepared radiopharmaceuticals and supervised clinical experience as follows:

(-a-)

40 hours of classroom and laboratory training that includes:

(-1-)

radiation physics and instrumentation;

(-2-)

radiation protection;

(-3-)

mathematics pertaining to the use and measurement of radioactivity;

(-4-)

radiation biology; and

(-5-)

radiopharmaceutical chemistry; and

(-b-)

20 hours of supervised clinical experience under the supervision of an authorized user and that includes:

(-1-)

examining patients and reviewing their case histories to determine their suitability for radioisotope diagnosis, limitations, or contraindications;

(-2-)

selecting the suitable radiopharmaceuticals and calculating and measuring the dosages;

(-3-)

administering dosages to patients and using syringe radiation shields;

(-4-)

collaborating with the authorized user in the interpretation of radioisotope test results; and

(-5-)

patient follow-up; or

(-c-)

has successfully completed a six-month training program in nuclear medicine as part of a residency program that has been accredited by the Accreditation Council for Graduate Medical Education (ACGME) or the Council on Postdoctoral Training of the American Osteopathic Association (COPT-AOA) and that included classroom and laboratory training, work experience, and supervised clinical experience in all the topics identified in this subclause.

(ii)

Training in all the topics identified in clause (i)(II)(-a-) of this subparagraph, which is not a part of a residency program as in clause (i)(II)(-c-) of this subparagraph, shall be obtained in an ACGME- or COPT-AOA-accredited medical teaching institution. The 40 hours of classroom and laboratory training in clause (i)(II)(-a-) of this subparagraph shall have been initiated prior to completion of the clinical experience in clause (i)(II)(-b-) of this subparagraph. The clinical experience described in clause (i)(II)(-b-) of this subparagraph shall be supervised by a physician licensed for the full scope of diagnostic nuclear medicine procedures or by an authorized physician in an ACGME- or COPT-AOA- accredited medical teaching institution.

(iii)

Notwithstanding the requirements of clauses (i) and (ii) of this subparagraph, proof of alternative training that includes the topics and hours listed in subparagraph (B)(i)(II) of this paragraph may be accepted on a case-by-case basis if the agency, after providing the Medical Committee of the Texas Radiation Advisory Board with the opportunity to review and comment, determines that the alternative training would give an equal or greater level of training to the standards in clauses (i) and (ii) of this subparagraph.

(B)

Training for imaging and localization studies.

(i)

The licensee shall require the authorized user of a radiopharmaceuticals for imaging and localization studies to be a physician who:

(I)

is certified in:

(-a-)

nuclear medicine by the ABNM;

(-b-)

diagnostic radiology or radiology by the ABR;

(-c-)

diagnostic radiology or radiology by the AOBR;

(-d-)

nuclear medicine by the RCPSC; or

(-e-)

nuclear medicine by the AOBNM; or

(II)

has successfully completed classroom and laboratory training in basic radioisotope handling techniques applicable to the use of prepared radiopharmaceuticals, generators, and reagent kits, supervised work experience, and supervised clinical experience as follows:

(-a-)

200 hours of classroom and laboratory training that includes:

(-1-)

radiation physics and instrumentation;

(-2-)

radiation protection;

(-3-)

mathematics pertaining to the use and measurement of radioactivity;

(-4-)

radiopharmaceutical chemistry; and

(-5-)

radiation biology; and

(-b-)

500 hours of supervised work experience under the supervision of an authorized user that includes:

(-1-)

ordering, receiving, and unpacking radioactive materials safely and performing the related radiation surveys;

(-2-)

calibrating dose calibrators and diagnostic instruments and performing checks for proper operation of survey meters;

(-3-)

calculating and safely preparing patient dosages;

(-4-)

using administrative controls to prevent the misadministration of byproduct material;

(-5-)

using procedures to contain spilled byproduct material safely and using proper decontamination procedures; and

(-6-)

eluting technetium-99m from generator systems, measuring and testing the eluate for molybdenum-99 and alumina contamination, and processing the eluate with reagent kits to prepare technetium-99m labeled radiopharmaceuticals; and

(-c-)

500 hours of supervised clinical experience under the supervision of an authorized user that includes:

(-1-)

examining patients and reviewing their case histories to determine their suitability for radioisotope diagnosis, limitations, or contraindications;

(-2-)

selecting the suitable radiopharmaceuticals and calculating and measuring the dosages;

(-3-)

administering dosages to patients and using syringe radiation shields;

(-4-)

collaborating with the authorized user in the interpretation of radioisotope test results; and

(-5-)

patient follow-up; or

(-d-)

has successfully completed a six-month training program in nuclear medicine as part of a residency program that has been accredited by the ACGME or the COPT-AOA and that included classroom and laboratory training, work experience, and supervised clinical experience in all the topics identified in this subclause.

(ii)

Training in all the topics identified in clause (i)(II)(-a-) of this subparagraph, which is not a part of a residency program as in clause (i)(II)(-d-) of this subparagraph, shall be obtained in a medical teaching institution that provides appropriate training programs that have been accredited by the ACGME or the COPT-AOA. The 200 hours of classroom and laboratory training in clause (i)(II)(-a-) of this subparagraph shall have been initiated prior to completion of the work and clinical experience in clauses (i)(II)(-b-) and (-c-) of this subparagraph. The work and clinical experience described in clause (i)(II)(-b-) and (-c-) of this subparagraph shall be supervised by a physician licensed for the full scope of diagnostic nuclear medicine procedures or by a licensed authorized physician in a medical teaching institution that also provides appropriate training programs that have been accredited by the ACGME or the COPT-AOA. The experience in clause (i)(II)(-b-) and (-c-) of this subparagraph may be obtained concurrently.

(iii)

Classroom and laboratory training identified in clause (i)(II)(-a-) of this subparagraph that was initiated before October 1, 1995, and completed by October 1, 1997, will be accepted if it is obtained in an accredited medical school, a federal teaching hospital, or a training program for medical use of radioactive material that has been accepted by the agency, NRC, or another agreement state.

(iv)

Notwithstanding the requirements of clauses (i) and (ii) of this subparagraph, proof of alternative training that includes the topics and hours listed in clause (i)(II) of this subparagraph may be accepted on a case-by-case basis if the agency, after providing the Medical Committee of the Texas Radiation Advisory Board with the opportunity to review and comment, determines that the alternative training would give an equal or greater level of training to the standards in clauses (i) and (ii) of this subparagraph.

(C)

Training for the therapeutic use of radiopharmaceuticals.

(i)

The licensee shall require the authorized user of radiopharmaceuticals for therapeutic use to be a physician who:

(I)

is certified in:

(-a-)

nuclear medicine by the ABNM;

(-b-)

radiology or therapeutic radiology by the ABR;

(-c-)

therapeutic radiology or radiology by the AOBR;

(-d-)

nuclear medicine by the RCPSC; or

(-e-)

nuclear medicine by the AOBNM; or

(II)

has classroom and laboratory training in basic radioisotope handling techniques applicable to the use of therapeutic radiopharmaceuticals and supervised clinical experience as follows:

(-a-)

80 hours of classroom and laboratory training that includes:

(-1-)

radiation physics and instrumentation;

(-2-)

radiation protection;

(-3-)

mathematics pertaining to the use and measurement of radioactivity; and

(-4-)

radiation biology; and

(-b-)

supervised clinical experience under the supervision of an authorized physician user for the type of therapy authorization requested from the following list:

(-1-)

use of iodine-131 for diagnosis of thyroid function and the treatment of hyperthyroidism in 10 individuals;

(-2-)

use of iodine-131 for treatment of thyroid carcinoma in three individuals;

(-3-)

use of colloidal phosphorus-32 for intracavitary treatment in three patients;

(-4-)

use of phosphorus-32 for treatment of polycythemia vera, leukemia and/or bone metastasis in three patients;

(-5-)

use of colloidal gold-198 for intracavitary treatment in three patients; or

(-6-)

use of radiopharmaceuticals not listed in subitems (-1-) through (-5-) of this item for therapeutic treatment in three patients; or

(-7-)

has successfully completed a six-month training program in nuclear medicine as part of a residency program that has been accredited by the ACGME or the COPT-AOA and that included classroom and laboratory training, work experience and supervised clinical experience in all the topics identified in this subclause.

(ii)

Training in all the topics identified in clause (i)(II) of this subparagraph, which is not a part of a residency program as in clause (i)(II)(-b-) of this subparagraph, shall be obtained in a medical teaching institution accredited by the ACGME or the COPT-AOA.

(D)

Training for use of brachytherapy sealed sources (except for beta applicators - See subparagraph (E) of this paragraph).

(i)

The licensee shall require the authorized user of a brachytherapy sealed source to be a physician who:

(I)

is certified in:

(-a-)

therapeutic radiology, radiation oncology, or radiology by the ABR; or

(-b-)

therapeutic radiology, radiation oncology, or radiology by the AOBR; or

(-c-)

radiology with specialization in radiotherapy, as a British "Fellow of the Faculty of Radiology" or "Fellow of the Royal College of Radiology"; or

(-d-)

therapeutic radiology by the Canadian Royal College of Physicians and Surgeons; or

(II)

is in the active practice of therapeutic radiology, has had classroom training in radioisotope handling techniques applicable to the therapeutic use of brachytherapy sealed sources, and supervised clinical experience as follows:

(-a-)

200 hours of classroom and laboratory training that includes:

(-1-)

radiation physics and instrumentation;

(-2-)

radiation protection;

(-3-)

mathematics pertaining to the use and measurement of radioactivity; and

(-4-)

radiation biology; and

(-b-)

500 hours of supervised work experience under the supervision of an authorized user at a medical institution that includes:

(-1-)

ordering, receiving, and unpacking radioactive materials safely and performing the related radiation surveys;

(-2-)

checking survey meters for proper operation;

(-3-)

preparing, implanting, and removing sealed sources;

(-4-)

maintaining running inventories of material on hand;

(-5-)

using administrative controls to prevent the misadministration of byproduct material; and

(-6-)

using emergency procedures to control byproduct material; and

(-c-)

three years of supervised clinical experience that includes one year in a formal training program approved by the Residency Review Committee for Radiology of the ACGME or the COPT-AOA, and an additional two years of clinical experience in therapeutic radiology under the supervision of an authorized user at a medical institution that includes:

(-1-)

examining individuals and reviewing their case histories to determine their suitability for brachytherapy treatment, and any limitations or contraindications;

(-2-)

selecting the proper brachytherapy sealed sources and dose and method of administration;

(-3-)

calculating the dose; and

(-4-)

post-administration follow-up and review of case histories in collaboration with the authorized user.

(ii)

Training in all the topics identified in clause (i)(II)(-a-) of this subparagraph shall be accredited by the ACGME or the COPT-AOA. The clinical experience described in clause (i)(II)(-b-) and (-c-) of this subparagraph should be supervised by a physician licensed to use brachytherapy sealed sources. The experience in clause (i)(II)(-b-) and (-c-) of this subparagraph may be obtained concurrently.

(E)

Training for ophthalmic use of strontium-90.

(i)

The licensee shall require the authorized user of only strontium-90 for ophthalmic radiotherapy to be a physician who:

(I)

is certified in:

(-a-)

therapeutic radiology, radiation oncology, or radiology by the ABR;

(-b-)

therapeutic radiology, radiation oncology, or radiology by the AOBR;

(-c-)

radiology with specialization in radiotherapy, as a British "Fellow of the Faculty of Radiology" or "Fellow of the Royal College of Radiology"; or

(-d-)

therapeutic radiology by the Canadian Royal College of Physicians and Surgeons; or

(II)

is in the active practice of therapeutic radiology or ophthalmology, and has had classroom and laboratory training in basic radioisotope handling techniques applicable to the use of strontium-90 for ophthalmic radiotherapy, and a period of supervised clinical training in ophthalmic radiotherapy as follows:

(-a-)

24 hours of classroom and laboratory training that includes:

(-1-)

radiation physics and instrumentation;

(-2-)

radiation protection;

(-3-)

mathematics pertaining to the use and measurement of radioactivity; and

(-4-)

radiation biology; and

(-b-)

supervised clinical training in ophthalmic radiotherapy under the supervision of an authorized user at a medical institution that includes the use of strontium-90 for the ophthalmic treatment of five individuals that includes:

(-1-)

examination of each individual to be treated;

(-2-)

calculation of the dose to be administered;

(-3-)

administration of the dose; and

(-4-)

follow-up and review of each individual's case history.

(ii)

Training in all the topics identified in clause (i)(II)(-a-) of this subparagraph shall be obtained in a medical teaching institution or shall be accredited by the ACGME or the COPT-AOA. The clinical experience described in clause (i)(II)(-b-) of this subparagraph shall be supervised by a physician licensed for the use of sealed sources in therapy.

(F)

Training for use of sealed sources for diagnosis.

(i)

The licensee shall require the authorized user of a sealed source in the devices listed in clause (ii) of this subparagraph, to be a physician, dentist, or podiatrist who:

(I)

is certified in:

(-a-)

therapeutic radiology, diagnostic radiology, radiation oncology, or radiology by the ABR;

(-b-)

nuclear medicine by the ABNM;

(-c-)

diagnostic radiology or radiology by the AOBR; or

(-d-)

nuclear medicine by the RCPSC; or

(-e-)

nuclear medicine by the AOBNM; or

(II)

has had eight hours of classroom and laboratory training in radioisotope handling techniques specifically applicable to the use of the device that includes:

(-a-)

radiation physics, mathematics pertaining to the use and measurement of radioactivity, and instrumentation;

(-b-)

radiation biology;

(-c-)

radiation protection; and

(-d-)

training in the use of the device for the uses requested.

(ii)

The following sealed sources shall be used in accordance with the manufacturer's radiation safety and handling instructions:

(I)

iodine-125, americium-241, or gadolinium-153 as a sealed source in a device for bone mineral analysis; and

(II)

iodine-125 as a sealed source in a portable imaging device.

(iii)

Training in all the topics identified in clause (i)(II) of this subparagraph shall be obtained in a medical teaching institution or shall be accredited by the ACGME or the COPT-AOA. The clinical experience shall be supervised by a physician, dentist, or podiatrist licensed to use the devices.

(G)

Training for teletherapy, remote afterloader units, and gamma stereotactic radiosurgery.

(i)

The licensee shall require the authorized user of a sealed source in a teletherapy unit to be a physician who:

(I)

is certified in:

(-a-)

therapeutic radiology, radiation oncology, or radiology by the ABR;

(-b-)

therapeutic radiology, radiation oncology, or radiology by the AOBR;

(-c-)

radiology with specialization in radiotherapy, as a British "Fellow of the Faculty of Radiology" or "Fellow of the Royal College of Radiology"; or

(-d-)

therapeutic radiology by the Canadian Royal College of Physicians and Surgeons; or

(II)

is in the active practice of therapeutic radiology, and has had classroom and laboratory training in basic radioisotope techniques applicable to the use of a sealed source in a teletherapy unit, supervised work experience, and supervised clinical experience as follows:

(-a-)

200 hours of classroom and laboratory training that includes:

(-1-)

radiation physics and instrumentation;

(-2-)

radiation protection;

(-3-)

mathematics pertaining to the use and measurement of radioactivity; and

(-4-)

radiation biology; and

(-b-)

500 hours of supervised work experience under the supervision of an authorized user at a medical institution that includes:

(-1-)

review of the full calibration measurements and periodic spot checks;

(-2-)

preparing treatment plans and calculating treatment times;

(-3-)

using administrative controls to prevent misadministration;

(-4-)

implementing emergency procedures to be followed in the event of the abnormal operation of a teletherapy unit or console; and

(-5-)

checking and using survey meters; and

(-c-)

three years of supervised clinical experience that includes one year in a formal training program accredited by the ACGME or the COPT-AOA and an additional two years of clinical experience in therapeutic radiology under the supervision of an authorized user at a medical institution that includes:

(-1-)

examining individuals and reviewing their case histories to determine their suitability for teletherapy treatment; and any limitations or contraindications;

(-2-)

selecting the proper dose and how it is to be administered;

(-3-)

calculating the therapy doses and collaborating with the authorized user in the review of patients' progress and consideration of the need to modify originally prescribed doses as warranted by patients' reaction to radiation; and

(-4-)

post-administration follow-up and review of case histories.

(ii)

Training in all the topics identified in clause (i)(II)(-a-) of this subparagraph shall be accredited by the ACGME or the COPT-AOA. The clinical experience described in clause (i)(II)(-b-) and (-c-) of this subparagraph shall be supervised by a physician licensed for teletherapy procedures. The experience in clause (i)(II)(-b-) and (-c-) of this subparagraph may be obtained concurrently.

(H)

Training for experienced authorized users. Physicians, dentists, or podiatrists identified as authorized users for the medical, dental, or podiatric use of radioactive material on a NRC or agreement state license issued before September 1, 1993, and those issued by the agency before October 1, 1995, who perform only those methods of use for which they were authorized on that date need not comply with the training requirements in this paragraph.

(I)

Recentness of training. The training and experience specified in this paragraph for medical use must have been obtained within the five years preceding the date of application or the individual must have had related continuing education and experience since the required training and experience was completed.

(2)

Records/documents for agency inspection. Each licensee shall make the following records/documents available to the agency for inspection, upon reasonable notice.

Figure: 25 TAC §289.256(ff)(2)

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003510

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


25 TAC §289.258

The Texas Department of Health (department) proposes an amendment to §289.258 concerning licensing and radiation safety requirements for irradiators.

Government Code §2001.039 requires that each state agency review and consider for readoption each rule adopted by that agency pursuant to the Government Code, Chapter 2001 (Administrative Procedure Act). Section 289.118 has been reviewed and the department has determined that the reasons for adopting the section continue to exist; however revisions to the rule are necessary.

The proposed amendment adds the definitions for "Category I self-contained, dry-source irradiator" and "Onsite" to clarify the intent of the rule. Language is added that clarifies that cesium-137 can only be used with Category I self-contained, dry-source irradiators. Additional language was added to clarify the requirements for operator attendance during irradiator operations. The amendment reflects corrections of references to other sections of this chapter. Grammatical changes are made for clarification. This amendment is also part of the department's continuing effort to update, clarify, and simplify its rules regarding the control of radiation based upon technological advances, public concerns, legislative directives, or other factors.

The department published a Notice of Intention to Review for §289.258 as required by Government Code §2001.039 in the Texas Register on January 7, 2000 (25 TexReg 219). No comments were received by the department on this section.

Mrs. Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, has determined that for the first five-year period the section is in effect, there will be no fiscal implications for state or local government as a result of enforcing or administering the section as proposed.

Mrs. McBurney has also determined that for each year of the first five years the section is in effect, the public benefit anticipated as a result of enforcing the section will be to ensure that new and operating irradiators are used in accordance with standardized requirements designed to protect public health and safety and the environment. There will be no effect on micro businesses or small businesses. There are no anticipated economic costs to persons who are required to comply with the section as proposed. There is no anticipated impact on local employment. The requirement for limiting use of cesium-137 to Category I self-contained, dry-source irradiators formalizes in rule agency policy for licensing irradiators. The addition of the definition of "onsite" and the language concerning operator attendance clarify the intent of existing requirements concerning the availability of trained individuals during irradiator operation. Because the amendment is clarifying and does not impose any additional requirements such as record keeping, regulatory limits, procedures, or processes, there are no economic effects associated with the section as proposed.

Comments on the proposal may be presented in writing to Mrs. Ruth E. McBurney, C.H.P., Director, Division of Licensing, Registration and Standards, Bureau of Radiation Control, Texas Department of Health, 1100 West 49th Street, Austin, Texas 78756-3189, (512)834-6688. Public comments will be accepted for 30 days following publication of these proposed changes in the Texas Register . In addition, a public meeting will be held at 10:30 a.m., Tuesday, June 20, 2000, in conference room N218, Texas Department of Health, Bureau of Radiation Control, located at the Exchange Building, 8407 Wall Street, Austin, Texas.

The amendment is proposed under the Health and Safety Code, Chapter 401, which provides the Texas Board of Health (board) with authority to adopt rules and guidelines relating to the control of radiation; and §12.001, which provides the board with the authority to adopt rules for the performance of each duty imposed by law on the board, the department, and the commissioner of health.

The amendment affects Health and Safety Code, Chapter 401 and Chapter 12, and Government Code §2001.039.

§289.258.Licensing and Radiation Safety Requirements for Irradiators.

(a)

Purpose. This section contains requirements for the issuance of a license authorizing the use of sealed sources containing radioactive material in irradiators that irradiate objects or materials using gamma radiation. This section also contains radiation safety requirements for operating irradiators.

[ (a)

Purpose and scope. ]

[ (1)

This section contains requirements for the issuance of a license authorizing the use of sealed sources containing radioactive material in irradiators that irradiate objects or materials using gamma radiation. This section also contains radiation safety requirements for operating irradiators. In addition to the requirements of this section, all licensees, unless otherwise specified, are subject to the requirements of §289.112 of this title (relating to Hearing and Enforcement Procedures), §289.114 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections), §289.126 of this title (relating to Fees for Certificates of Registration, Radioactive Material(s) Licenses, Emergency Planning and Implementation, and other Regulatory Services), §289.201 of this title (relating to General Provisions), §289.202 of this title (relating to Standards for Protection of Radiation), and §289.252 of this title (relating to Licensing of Radioactive Material). Nothing in this section relieves the licensee from complying with other applicable federal, state and local regulations governing the siting, zoning, land use, and building code requirements for industrial facilities. ]

[ (2)

The requirements in this section apply to panoramic irradiators that have either dry or wet storage of the radioactive sealed sources and to underwater irradiators in which both the source and the product being irradiated are underwater. Irradiators whose dose rates exceed 500 rads (5 grays) per hour at 1 meter from the radioactive sealed sources in air or in water, as applicable for the irradiator type, are covered by this section. ]

[ (3)

The requirements in this section do not apply to self-contained, dry-source- storage irradiators (those in which both the source and the area subject to irradiation are contained within a device and are not accessible by personnel), medical radiology or teletherapy, radiography (the irradiation of materials for nondestructive testing purposes), gauging, or open- field (agricultural) irradiations. ]

(b)

Scope.

(1)

In addition to the requirements of this section, all licensees, unless otherwise specified, are subject to the requirements of §289.201 of this title (relating to General Provisions for Radioactive Material), §289.202 of this title (relating to Standards for Protection Against Radiation from Radioactive Material), §289.203 of this title (relating to Notices, Instructions, and Reports to Workers; Inspections), §289.204 of this title (relating to Fees for Certificates of Registration, Radioactive Material Licenses, Emergency Planning and Implementation, and Other Regulatory Services), §289.205 of this title (relating to Hearing and Enforcement Procedures), §289.252 of this title (relating to Licensing of Radioactive Material), and §289.257 of this title (relating to Packaging and Transportation of Radioactive Material). Nothing in this section relieves the licensee from complying with other applicable federal, state and local regulations governing the siting, zoning, land use, and building code requirements for industrial facilities.

(2)

The requirements in this section apply to panoramic irradiators that have either dry or wet storage of the radioactive sealed sources and to underwater irradiators in which both the source and the product being irradiated are under water. Irradiators whose dose rates exceed 500 rads (5 grays) per hour at 1 meter from the radioactive sealed sources in air or in water, as applicable for the irradiator type, are covered by this section.

(3)

The requirements in this section do not apply to self- contained, dry-source-storage irradiators (those in which both the source and the area subject to irradiation are contained within a device and are not accessible by personnel), medical radiology or teletherapy, radiography (the irradiation of materials for nondestructive testing purposes), gauging, or open-field (agricultural) irradiations.

(c)

[ (b) ] Definitions. The following words and terms, when used in these sections, shall have the following meanings, unless the context clearly indicates otherwise.

(1)

Annually - At intervals not to exceed 390 days.

(2)

Doubly encapsulated sealed source - A sealed source in which the radioactive material is sealed within a capsule and that capsule is sealed within another capsule.

(3)

Category I self-contained, dry- source irradiator - An irradiator in which the sealed source is completely contained in a dry container constructed of solid materials and is shielded at all times, and in which human access to the sealed source and the volume undergoing irradiation is not physically possible in its designed configuration.

(4)

[ (3) ] Irradiator - A facility that uses radioactive sealed sources for the irradiation of objects or materials and in which radiation dose [ doses ] rates exceeding 500 rads (5 grays) per hour exist at 1 meter (m) from the sealed radioactive sources in air or water, as applicable for the irradiator type, but does not include irradiators in which both the sealed source and the area subject to irradiation are contained within a device and are not accessible to personnel.

(5)

[ (4) ] Irradiator operator - An individual who has successfully completed the training and testing described in subsection (s) [ (r) ] of this section and is authorized by the terms of the license to operate the irradiator without a supervisor who is present and [ , ] who has completed the requirements of subsection (s)(1)-(3) [ (r)(1)-(3) ] of this section.

(6)

[ (5) ] Panoramic dry-source-storage irradiator - An irradiator in which the irradiations occur in air in areas potentially accessible to personnel and in which the sources are stored in shields made of solid materials. The term includes beam-type dry- source-storage irradiators in which only a narrow beam of radiation is produced for performing irradiations.

(7)

[ (6) ] Panoramic irradiator - An irradiator in which the irradiations are done in air in areas potentially accessible to personnel. The term includes beam- type irradiators.

(8)

[ (7) ] Panoramic wet-source-storage irradiator - An irradiator in which the irradiations occur in air in areas potentially accessible to personnel and in which the sources are stored under water in a storage pool.

(9)

[ (8) ] Pool irradiator - Any irradiator in which the sources are stored or used in a pool of water, including panoramic wet-source-storage irradiators and underwater irradiators.

(10)

[ (9) ] Product conveyor system - A system for moving the product to be irradiated to, from, and within the area where irradiation takes place.

(11)

Onsite - A physical presence within the building housing the irradiator or on property controlled by the licensee that is contiguous with the building housing the irradiator.

(12)

[ (10) ] Radiation room - A shielded room in which irradiations take place. Underwater irradiators do not have radiation rooms.

(13)

[ (11) ] Seismic area - Any area where the probability of horizontal acceleration in rock of more than 0.3 times the acceleration of gravity in 250 years is greater than 10%, as designated by the United States Geological Survey.

(14)

[ (12) ] Underwater irradiator - An irradiator in which the sources always remain shielded under water [ underwater ] and humans do not have access to the sealed sources or the space subject to irradiation without entering the pool.

(d)

[ (c) ] Application for a specific license. Applications for specific licenses shall be filed in accordance with §289.252(d) of this title.

(e)

[ (d) ] Specific licenses for irradiators.

(1)

The agency will approve an application for a specific license for the use of licensed material in an irradiator if the applicant meets the requirements contained in this section.

(2)

The applicant shall satisfy the general requirements specified in §289.252 of this title and the requirements contained in this section.

(3)

The application shall describe the training provided to irradiator operators including:

(A)

classroom training;

(B)

on-the-job or simulator training;

(C)

safety reviews;

(D)

means employed by the applicant to test each operator's understanding of the agency's rules [ regulations ] and licensing requirements and the irradiator operating, safety, and emergency procedures; and

(E)

minimum training and experience of personnel who may provide training.

(4)

The application shall include a copy of the written operating, safety, and emergency procedures as outlined in subsection (t) [ (s) ] of this section that describes the radiation safety aspects of the procedures.

(5)

The application shall describe the organizational structure for managing the irradiator, specifically the radiation safety responsibilities and authorities of the radiation safety officer (RSO) and those management personnel who have radiation safety responsibilities or authorities. In particular, the application shall specify who, within the management structure, has the authority to stop unsafe operations. The application shall also describe the training and experience required for the position of RSO [ radiation safety officer ].

(6)

The application shall include a description of the access control systems required by subsection (i) [ (h) ] of this section, the radiation monitors required by subsection (l) [ (k) ] of this section, the method of detecting leaking sources required by subsection (w) [ (v) ] of this section, including the sensitivity of the method, and a diagram of the facility that shows the locations of all required interlocks and radiation monitors.

(7)

If the applicant intends to perform and analyze leak tests of dry-source- storage sealed sources, the applicant shall establish procedures for leak testing and submit a description of these procedures to the agency. The description shall include at least the following:

(A)

instruments to be used;

(B)

methods of performing the analysis; and

(C)

pertinent experience of the individual who analyzes the samples.

(8)

If licensee personnel are to load or unload sources, the applicant shall describe the qualifications and training of the personnel and the procedures to be used. If the applicant intends to contract for source loading or unloading at its facility, the loading or unloading shall be done by a person specifically authorized by the agency, the United States Nuclear Regulatory Commission (NRC) [ commission ], an agreement state, or a licensing state to load or unload irradiator sources.

(9)

The applicant shall describe the inspection and maintenance checks, including the frequency of the checks required by subsection (x) [ (w) ] of this section.

(f)

[ (e) ] Start of construction. The applicant may not begin construction of a new irradiator prior to the submission to the agency of both an application for a license for the irradiator and the fee required by §289.204 [ §289.126 ] of this title. As used in this section, the term "construction" includes the construction of any portion of the permanent irradiator structure on the site but does not include: engineering and design work; purchase of a site; site surveys or soil testing; site preparation; site excavation; construction of warehouse or auxiliary structures; and other similar tasks. Any construction activities undertaken prior to the issuance of a license are entirely at the risk of the applicant and have no bearing on the issuance of a license with respect to the requirements of the Texas Radiation Control Act (Act), rules, [ regulations, ] and orders issued under the Act.

(g)

[ (f) ] Applications for exemptions. Any applications for a license or for amendment of a license authorizing use of a teletherapy-type unit for irradiation of materials or objects may include proposed alternatives for the requirements of this section. The agency will approve the proposed alternatives if the applicant provides adequate rationale for the proposed alternatives and demonstrates that they are likely to provide an adequate level of safety for workers and the public.

(h)

[ (g) ] Performance criteria for sealed sources.

(1)

Cesium-137 shall not be used in any irradiator other than a Category I self-contained, dry-source irradiator as defined in subsection (c) of this section.

(2)

[ (1) ] Sealed sources. Sealed sources installed after August 1, 1996 shall meet the following requirements :

(A)

have been evaluated in accordance with §289.252(i) of this title;

(B)

be doubly encapsulated;

(C)

use radioactive material that is as nondispersible as practical and that is as insoluble as practical if the source is used in a wet-source-storage or wet-source-change irradiator;

(D)

be encapsulated in a material resistant to general corrosion and to localized corrosion, such as 316L stainless steel or other material with equivalent resistance if the sources are for use in irradiator pools; and

(E)

have been leak tested and found leak-free in prototype testing of the sealed source after each of the tests described in paragraphs (3)-(8) [ (2)-(7) ] of this subsection.

(3)

[ (2) ] Temperature. The test source shall be held at -40 degrees Celsius for 20 minutes, 600 degrees Celsius for one [ 1 ] hour, and then be subjected to thermal shock test with a temperature drop from 600 degrees Celsius to 20 degrees Celsius within 15 seconds.

(4)

[ (3) ] Pressure. The test source shall be twice subjected for at least five [ 5 ] minutes to an external pressure (absolute) of 2 million newtons per square meter.

(5)

[ (4) ] Impact. A 2-kilogram steel weight, 2.5 centimeters in diameter, shall be dropped from a height of 1 meter onto the test source.

(6)

[ (5) ] Vibration. The test source shall be subjected three times for ten [ 10 ] minutes each to vibrations sweeping from 25 hertz to 500 hertz with a peak amplitude of five times the acceleration of gravity. In addition, each test source shall be vibrated for 30 minutes at each resonant frequency found.

(7)

[ (6) ] Puncture. A 50-gram weight and pin, 0.3-centimeter pin diameter, shall be dropped from a height of 1 m [ meter ] onto the test source.

(8)

[ (7) ] Bend. If the length of the source is more than 15 times larger than the minimum cross-sectional dimension, the test source shall be subjected to a force of 2,000 newtons at its center equidistant from two support cylinders, the distance between which is 10 times the minimum cross-sectional dimension of the source.

(i)

[ (h) ] Access control requirements in addition to the requirements of §289.202(u) of this title.

(1)

Each entrance to a radiation room at a panoramic irradiator shall have a door or other physical barrier to prevent inadvertent entry of personnel if the sources are not in the shielded position. Product conveyor systems may serve as barriers as long as they reliably and consistently function as a barrier. It shall not be possible to move the sources out of their shielded position if the door or barrier is open. Opening the door or barrier while the sources are exposed shall cause the sources to return promptly to the shielded position. The personnel entrance door or barrier shall have a lock that is operated by the same key used to move the sources. The doors and barriers shall not prevent any individual in the radiation room from leaving.

(2)

In addition, each entrance to a radiation room at a panoramic irradiator shall have an independent backup access control to detect personnel entry while the sources are exposed. Detection of entry while the sources are exposed shall cause the sources to return to their fully shielded position and shall also activate a visible and audible alarm to make the individual entering the room aware of the hazard. The alarm shall also make at least one other individual who is onsite aware of the entry. That individual shall be trained on how to respond to the alarm and be prepared to promptly render or summon assistance.

(3)

A radiation monitor shall be provided to detect the presence of high radiation levels in the radiation room of a panoramic irradiator before personnel entry. The monitor shall be integrated with personnel access door locks to prevent room access when radiation levels are high. Attempted personnel entry while the monitor measures high radiation levels shall activate the alarm described in paragraph (2) of this subsection. The monitor may be located in the entrance (normally referred to as the maze) but not in the direct radiation beam.

(4)

Before the sources move from their shielded position in a panoramic irradiator, the source control shall automatically activate conspicuous visible and audible alarms to alert people in the radiation room that the sources will be moved from their shielded position. The alarms shall give individuals enough time to leave the room and to operate the control described in paragraph (5) of this subsection before the sources leave the shielded position.

(5)

Each radiation room at a panoramic irradiator shall have a clearly visible and readily accessible control that allows an individual in the room to return the sources to their fully shielded position.

(6)

Each radiation room of a panoramic irradiator shall contain a control that prevents the sources from moving from the shielded position unless the control has been activated and the door or barrier to the radiation room has been closed within a preset time after activation of the control.

(7)

Each entrance to the radiation room of a panoramic irradiator and each entrance to the area within the personnel access barrier of an underwater irradiator shall have a sign bearing the radiation symbol and the words, "CAUTION (or DANGER), RADIOACTIVE MATERIAL." Panoramic irradiators shall also have a sign stating "CAUTION (or DANGER), HIGH RADIATION AREA," or "GRAVE DANGER, VERY HIGH RADIATION AREA," whichever is applicable, but the sign may be removed, covered, or otherwise made inoperative when the sources are fully shielded.

(8)

If the radiation room of a panoramic irradiator has roof plugs or other movable shielding, it shall not be possible to operate the irradiator unless the shielding is in its proper location. The requirement may be met by interlocks that prevent operation if shielding is not placed properly or by an operating procedure requiring inspection of shielding before operating.

(9)

Underwater irradiators shall have a personnel access barrier around the pool that shall be locked to prevent access when the irradiator is not attended. Only operators and facility management may have access to keys to the personnel access barrier. There shall be an intrusion alarm to detect unauthorized entry when the personnel access barrier is locked. Activation of the intrusion alarm shall alert an individual (not necessarily onsite) who is prepared to respond or summon assistance.

(j)

[ (i) ] Shielding.

(1)

The radiation dose rate in areas that are normally occupied during operation of a panoramic irradiator may not exceed 2 millirems (mrem) (0.02 millisievert (mSv) ) per hour at any location 30 centimeters (cm) or more from the wall of the room when the sources are exposed. The dose rate shall be averaged over an area not to exceed 100 square centimeters (cm 2 ) having no linear dimension greater than 20 cm [ centimeters ]. Areas where the radiation dose rate exceeds 2 mrem [ millirems ] (0.02 mSv [ millisievert ]) per hour shall be locked, roped off, or posted.

(2)

The radiation dose at 30 cm [ centimeters ] over the edge of the pool of a pool irradiator may not exceed 2 mrem [ millirems ] (0.02 mSv [ millisievert ]) per hour when the sources are in the fully shielded position.

(3)

The radiation dose rate at 1 m [ meter ] from the shield of a dry-source-storage panoramic irradiator when the source is shielded may not exceed 2 mrem [ millirems ] (0.02 mSv [ millisievert ]) per hour and at 5 cm [ centimeters ] from the shield may not exceed 20 mrem [ millirems ] (0.2 mSv [ millisievert ]) per hour.

(k)

[ (j) ] Fire protection.

(1)

The radiation room at a panoramic irradiator shall have heat and smoke detectors. The detectors shall activate an audible alarm. The alarm shall be capable of alerting a person who is prepared to summon assistance promptly. The sources shall automatically become fully shielded if a fire is detected.

(2)

The radiation room at a panoramic irradiator shall be equipped with a fire extinguishing system capable of extinguishing a fire without the entry of personnel into the room. If water is used, the system for the radiation room shall have a shut-off valve to control flooding into unrestricted areas.

(l)

[ (k) ] Radiation monitors.

(1)

Irradiators with automatic product conveyor systems shall have a radiation monitor with an audible alarm located to detect loose radioactive sources that are carried toward the product exit. If the monitor detects a source, an alarm shall sound and product conveyors shall stop automatically. The alarm shall be capable of alerting an individual in the facility who is prepared to summon assistance. Underwater irradiators in which the product moves within an enclosed stationary tube are exempt from the requirements of this paragraph.

(2)

Underwater irradiators that are not in a shielded radiation room shall have a radiation monitor over the pool to detect abnormal radiation levels. The monitor shall have an audible alarm and a visible indicator at entrances to the personnel access barrier around the pool. The audible alarm may have a manual shut-off. The alarm shall be capable of alerting an individual who is prepared to respond promptly.

(m)

[ (l) ] Control of source movement.

(1)

The mechanism that moves the sources of a panoramic irradiator shall require a key to actuate. Actuation of the mechanism shall cause an audible signal to indicate that the sources are leaving the shielded position. Only one key may be in use at any time, and only operators or facility management may possess it. The key shall be attached to a portable radiation survey meter by a chain or cable. The lock for source control shall be designed so that the key may not be removed if the sources are in an unshielded position. The door to the radiation room shall require the same key.

(2)

The console of a panoramic irradiator shall have a source position indicator that indicates when the sources are in the fully shielded position, when they are in transit, and when the sources are in the fully exposed position.

(3)

The control console of a panoramic irradiator shall have a control that when activated, shall return the source to its fully shielded position within its normal transit time.

(4)

Each control for a panoramic irradiator shall be clearly marked as to its function.

(n)

[ (m) ] Irradiator pools.

(1)

For licenses initially issued after August 1, 1996, irradiator pools shall either:

(A)

have a water-tight stainless steel liner or a liner metallurgically compatible with other components in the pool; or

(B)

be constructed so that there is a low likelihood of substantial leakage and have a surface designed to facilitate decontamination. In either case, the licensee shall have a method to safely store the sources during repairs of the pool.

(2)

For licenses initially issued after August 1, 1996, irradiator pools shall have no outlets more than 0.5 m [ meter ] below the normal low water level that could allow water to drain out of the pool. Pipes that have openings more than 0.5 m [ meter ] below the normal low water level and that could act as siphons shall have siphon breakers to prevent the siphoning of pool water.

(3)

A means shall be provided to replenish water losses from the pool.

(4)

A visible indicator shall be provided in a clearly visible location to indicate if the pool water level is below the normal low water level or above the normal high water level.

(5)

Irradiator pools shall be equipped with a purification system designed to be capable of maintaining the water during normal operation at a conductivity of 20 microsiemens per centimeter or less and with a clarity so that the sources can be seen clearly.

(6)

A physical barrier, such as a railing or cover, shall be used around or over irradiator pools during normal operation to prevent personnel from accidentally falling into the pool. The barrier may be removed during maintenance, inspection, and service operations.

(7)

If long-handled tools or poles are used in irradiator pools, the radiation dose rate on the handling areas of the tools may not exceed 2 mrem [ millirems ] (0.02 mSv [ millisievert ]) per hour.

(o)

[ (n) ] Source rack protection. If the product to be irradiated moves on a product conveyor system, the source rack and the mechanism that moves the rack shall be protected by a carrier or guides to prevent products and product carriers from hitting or touching the rack or mechanism.

(p)

[ (o) ] Power failures.

(1)

If electrical power at a panoramic irradiator is lost for longer than 10 seconds, the sources shall automatically return to the shielded position.

(2)

The lock on the door of the radiation room of a panoramic irradiator shall not be deactivated by a power failure.

(3)

During a power failure, the area of any irradiator where sources are located may be entered only when using an operable and calibrated radiation survey meter.

(q)

[ (p) ] Design requirements for irradiators. The following are design [ Design ] requirements for irradiators that have construction beginning after August 1, 1996.

(1)

Shielding. For panoramic irradiators, the licensee shall design shielding walls to meet generally accepted building code requirements for reinforced concrete and design the walls, wall penetrations, and entrance ways to meet the radiation shielding requirements of subsection (j) [ (i) ] of this section. If the irradiator will use more than 5 million curies (2 x 10 17 becquerels) of activity, the licensee shall evaluate the effects of heating of the shielding walls by the irradiator sources.

(2)

Foundations. For panoramic irradiators, the licensee shall design the foundation, with consideration given to soil characteristics, to ensure it is adequate to support the weight of the facility shield walls.

(3)

Pool integrity. For pool irradiators, the licensee shall design the pool to assure that it is leak resistant, that it is strong enough to bear the weight of the pool water and shipping casks, that a dropped cask would not fall on sealed sources, that all outlets or pipes meet the requirements of subsection (n)(2) [ (m)(2) ] of this section, and that metal components are metallurgically compatible with other components in the pool.

(4)

Water handling system. For pool irradiators, the licensee shall verify that the design of the water purification system is adequate to meet the requirements of subsection (n)(5) [ (m)(5) ] of this section. The system shall be designed so that water leaking from the system does not drain to unrestricted areas without being monitored.

(5)

Radiation monitors. For all irradiators, the licensee shall evaluate the location and sensitivity of the monitor to detect sources carried by the product conveyor system as required by subsection (l)(1) [ (k)(1) ] of this section. The licensee shall verify that the product conveyor is designed to stop before a source on the product conveyor would cause a radiation overexposure to any person. For pool irradiators, if the licensee uses radiation monitors to detect contamination under subsection (w)(2) [ (v)(2) ] of this section, the licensee shall verify that the design of radiation monitoring systems to detect pool contamination includes sensitive detectors located close to where contamination is likely to concentrate.

(6)

Source rack. For pool irradiators, the licensee shall verify that there are no crevices on the source or between the source and source holder that would promote corrosion on a critical area of the source. For panoramic irradiators, the licensee shall determine that source rack drops due to loss of power will not damage the source rack and that source rack drops due to failure of cables (or alternate means of support) will not cause loss of integrity of sealed sources. For panoramic irradiators, the licensee shall review the design of the mechanism that moves the sources to assure that the likelihood of a stuck source is low and that, if the rack sticks, a means exists to free it with minimal risk to personnel.

(7)

Access control. For panoramic irradiators, the licensee shall verify from the design and logic diagram that the access control system will meet the requirements of subsection (i) [ (h) ] of this section.

(8)

Fire protection. For panoramic irradiators, the licensee shall verify that the number, locations, and spacing of the smoke and heat detectors are appropriate to detect fires and that the detectors are protected from mechanical and radiation damage. The licensee shall verify that the design of the fire extinguishing system provides the necessary discharge patterns, densities, and flow characteristics for complete coverage of the radiation room and that the system is protected from mechanical and radiation damage.

(9)

Source return. For panoramic irradiators, the licensee shall verify that the source rack will automatically return to the fully shielded position if power is lost for more than 10 seconds.

(10)

Seismic. For panoramic irradiators to be built in seismic areas, the licensee shall design the reinforced concrete radiation shields to retain their integrity in the event of an earthquake by designing to the seismic requirements of an appropriate source such as American Concrete Institute Standard ACI 318-89, "Building Code Requirements for Reinforced Concrete," Chapter 21, "Special Provisions for Seismic Design," or local building codes, if current.

(11)

Wiring. For panoramic irradiators, the licensee shall verify that electrical wiring and electrical equipment in the radiation room are selected to minimize failures due to prolonged exposure to radiation.

(r)

[ (q) ] Construction monitoring and acceptance testing requirements . The following are construction monitoring and acceptance testing requirements to be met prior to loading sources in [ for ] irradiators that have begun construction [ beginning ] after August 1, 1996.

(1)

Shielding. For panoramic irradiators, the licensee shall monitor the construction of the shielding to verify that its construction meets design specifications and generally accepted building code requirements for reinforced concrete.

(2)

Foundations. For panoramic irradiators, the licensee shall monitor the construction of the foundations to verify that the foundation construction meets design specifications.

(3)

Pool integrity. For pool irradiators, the licensee shall verify that the pool meets design specifications and shall test the integrity of the pool. The licensee shall verify that outlets and pipes meet the requirements of subsection (n)(2) [ (m)(2) ] of this section.

(4)

Water handling system. For pool irradiators, the licensee shall verify that the water purification system, the conductivity meter, and the water level indicators operate properly.

(5)

Radiation monitors. For all irradiators, the licensee shall verify the proper operation of the monitor to detect sources carried on the product conveyor system and the related alarms and interlocks required by subsection (l)(1) [ (k)(1) ] of this section. For pool irradiators, the licensee shall verify the proper operation of the radiation monitors and the related alarm if used to meet subsection (w)(2) [ (v)(2) ] of this section. For underwater irradiators, the licensee shall verify the proper operation of the over-the-pool monitor, alarms, and interlocks required by subsection (l)(2) [ (k)(2) ] of this section.

(6)

Source rack. For panoramic irradiators, the licensee shall test the movement of the source racks for proper operation prior to source loading . [ ; ] Testing [ testing ] shall include source rack lowering due to simulated loss of power. For all irradiators with product conveyor systems, the licensee shall observe and test the operation of the conveyor system to assure that the requirements in subsection (o) [ (n) ] of this section are met for protection of the source rack and the mechanism that moves the rack . [ ; ] Testing [ testing ] shall include tests of any limit switches and interlocks used to protect the source rack and mechanism that moves that rack from moving product carriers.

(7)

Access control. For panoramic irradiators, the licensee shall test the completed access control system to assure that it functions as designed and that all alarms, controls, and interlocks work properly.

(8)

Fire protection. For panoramic irradiators, the licensee shall test the ability of the heat and smoke detectors to detect a fire, to activate alarms, and to cause the source rack to automatically become fully shielded. The licensee shall test the operability of the fire extinguishing system.

(9)

Source return. For panoramic irradiators, the licensee shall demonstrate that the source racks can be returned to their fully shielded positions without power.

(10)

Computer systems. For panoramic irradiators that use a computer system to control the access control system, the licensee shall verify that the access control system will operate properly if power is lost and shall verify that the computer has security features that prevent an irradiator operator from commanding the computer to override the access control system when it is required to be operable.

(11)

Wiring. For panoramic irradiators, the licensee shall verify that the electrical wiring and electrical equipment that were installed meet the design specifications.

(s)

[ (r) ] Training.

(1)

Before an individual is permitted to operate an irradiator without a supervisor present, who has completed the requirements of this paragraph and paragraphs (2) and (3) of this subsection, the individual shall be instructed in:

(A)

the fundamentals of radiation protection applied to irradiators (including the differences between external radiation and radioactive contamination, units of radiation dose, dose limits, why large radiation doses shall be avoided, how shielding and access controls prevent large doses, how an irradiator is designed to prevent contamination, the proper use of survey meters and individual monitoring devices [ personnel dosimeters ], other radiation safety features of an irradiator, and the basic function of the irradiator);

(B)

the requirements of this section and §289.203 [ §289.114 ] of this title that are relevant to the irradiator;

(C)

the operation of the irradiator;

(D)

those operating, safety, and emergency procedures listed in subsection (t) [ (s) ] of this section that the individual is responsible for performing; and

(E)

case histories of accidents or problems involving irradiators.

(2)

Before an individual is permitted to operate an irradiator without a supervisor present, who has completed the requirements of this paragraph and paragraphs (1) and (3) of this subsection, the individual shall pass a written test on the instruction received consisting primarily of questions based on the licensee's operating, safety, and emergency procedures that the individual is responsible for performing and other operations necessary to safely operate the irradiator without supervision.

(3)

Before an individual is permitted to operate an irradiator without a supervisor present, who has completed the requirements of this paragraph and paragraphs (1) and (2) of this subsection, the individual shall have received on-the-job training or simulator training in the use of the irradiator as described in the license application. The individual shall also demonstrate the ability to perform those portions of the operating, safety, and emergency procedures that he or she is to perform.

(4)

The licensee shall conduct safety reviews for irradiator operators at least annually. The licensee shall give each operator a brief written test on the information. Each safety review shall include, to the extent appropriate, each of the following:

(A)

changes in operating, safety, and emergency procedures since the last review, if any;

(B)

changes in rules and license conditions since the last review, if any;

(C)

reports on recent accidents, mistakes, or problems that have occurred at irradiators, if any;

(D)

relevant results of inspections of operator safety performance;

(E)

relevant results of the facility's inspection and maintenance checks; and

(F)

a drill to practice an emergency or abnormal event procedure.

(5)

The licensee shall evaluate the safety performance of each irradiator operator at least annually to ensure that agency rules [ regulations ], license conditions, and operating, safety, and emergency procedures are followed. The licensee shall discuss the results of the evaluation with the operator and shall instruct the operator on how to correct any mistakes or deficiencies observed.

(6)

Individuals who will be permitted unescorted access to the radiation room of the irradiator or the area around the pool of an underwater irradiator, but who have not received the training required for operators and the RSO [ radiation safety officer ], shall be instructed and tested in any precautions they should take to avoid radiation exposure, any procedures or parts of procedures listed in subsection (t) [ (s) ] of this section that they are expected to perform or comply with, and their proper response to alarms required in this section. Tests may be oral.

(7)

Individuals who shall be prepared to respond to alarms required by subsections (i)(2) and (9), (k), (l), and (w)(2) [ (h)(2) and (9), (j), (k), and (v)(2) ] of this section shall be trained and tested on how to respond. Each individual shall be retested at least once a year. Tests may be oral.

(t)

[ (s) ] Operating, safety, and emergency procedures.

(1)

The licensee shall have and follow written operating , safety, and emergency procedures for:

(A)

operation of the irradiator, including entering and leaving the radiation room;

(B)

use of individual monitoring devices [ personnel dosimeters ];

(C)

surveying the shielding of panoramic irradiators;

(D)

monitoring pool water for contamination while the water is in the pool and before release of pool water to unrestricted areas;

(E)

leak testing of sources;

(F)

inspection and maintenance checks required by subsection (x) [ (w) ] of this section;

(G)

loading, unloading, and repositioning sources, if the operations will be performed by the licensee; and

(H)

inspection of movable shielding required by subsection (i)(8) [ (h)(8) ] of this section, if applicable.

(2)

The licensee shall have and follow emergency or abnormal event procedures, appropriate for the irradiator type, for:

(A)

sources stuck in the unshielded position;

(B)

personnel overexposures;

(C)

a radiation alarm from the product exit portal monitor or pool monitor;

(D)

detection of leaking source, pool contamination, or alarm caused by contamination of pool water;

(E)

a low or high water level indicator, an abnormal water loss, or leakage from the source storage pool;

(F)

a prolonged loss of electrical power;

(G)

a fire alarm or explosion in the radiation room;

(H)

an alarm indicating unauthorized entry into the radiation room, area around pool, or another alarmed area;

(I)

natural phenomena, including an earthquake, a tornado, flooding, or other phenomena as appropriate for the geographical location of the facility; and

(J)

the jamming of automatic conveyor systems.

(3)

The licensee may revise operating, safety, and emergency procedures without agency approval only if all of the following conditions are met:

(A)

the revisions do not reduce the safety of the facility;

(B)

the revisions are consistent with the outline or summary of procedures including procedures for changes to operating, safety, and emergency procedures submitted with the license application;

(C)

the revisions have been reviewed and approved by the radiation safety officer; and

(D)

the users or operators are instructed and tested on the revised procedures before they are put into use . [ ; and ]

[ (E)

changes to operating, safety, and emergency procedures shall be submitted to the agency after subparagraphs (A)-(D) of this paragraph are completed. ]

(4)

Changes to operating, safety, and emergency procedures shall be submitted to the agency after the provisions of paragraph (3) of this subsection are completed.

(u)

[ (t) ] Personnel monitoring.

(1)

Irradiator operators shall wear either a film badge , [ or ] a thermoluminescent dosimeter (TLD) , or optically stimulated luminescence device (OSL) while operating a panoramic irradiator or while in the area around the pool of an underwater irradiator. The film badge , [ or ] TLD , or OSL processor shall be accredited by the National Voluntary Laboratory Accreditation Program for high energy photons in the normal and accident dose ranges (see §289.202(p)(3) of this title). Each film badge , [ or ] TLD , or OSL shall be assigned to and worn by only one individual. Film badges shall be replaced at an interval not to exceed monthly and TLDs or OSLs shall be replaced at an interval not to exceed three months. After replacement, each film badge , [ or ] TLD , or OSL shall be returned to the supplier for processing within 14 calendar days of the exchange date specified by the personnel monitoring supplier or as soon as practicable. In circumstances that make it impossible to return each film badge , [ or ] TLD , or OSL within 14 calendar days, such circumstances shall be documented and available for review by the agency.

(2)

Other individuals who enter the radiation room of a panoramic irradiator shall wear a dosimeter, which may be a pocket dosimeter. For groups of visitors, only two people who enter the radiation room are required to wear dosimeters. If pocket dosimeters are used to meet the requirements of the paragraph, a check of their response to radiation shall be done at least annually. Acceptable dosimeters shall read within plus or minus 30% of the true radiation dose.

(v)

[ (u) ] Radiation surveys.

(1)

A radiation survey of the area outside the shielding of the radiation room of a panoramic irradiator shall be conducted with the sources in the exposed position before the facility starts to operate. A radiation survey of the area above the pool of pool irradiators shall be conducted after the sources are loaded but before the facility starts to operate. Additional radiation surveys of the shielding shall be performed at intervals not to exceed three years and before resuming operation after addition of new sources or any modification to the radiation room shielding or structure that might increase dose rates.

(2)

If the radiation levels specified in subsection (j) [ (i) ] of this section are exceeded, the facility shall be modified to comply with the requirements in subsection (j) [ (i) ] of this section.

(3)

Portable radiation survey meters shall be calibrated at least annually to an accuracy of plus or minus 20% for the gamma energy of the sources in use. The calibration shall be done at two points on each scale or, for digital instruments, at one point per decade over the range that will be used. Portable radiation survey meters shall be of a type that does not saturate and read zero at high radiation dose rates.

(4)

Water from the irradiator pool, other potentially contaminated liquids, and sediments from pool vacuuming shall be monitored for radioactive contamination before release to unrestricted areas. Radioactive concentrations shall not exceed those specified in Table 2, Column 2 or Table 3 of §289.202(ggg)(2) of this title.

(5)

Before releasing resins for unrestricted use, they shall be monitored in an area with a background level less than 0.05 mrem [ millirem ] (0.5 µSv [ microsievert ]) per hour. The resins may be released only if the survey does not detect radiation levels above background radiation levels. The survey meter used shall be capable of detecting radiation levels of 0.05 mrem [ millirem ] (0.5 µSv [ microsievert ]) per hour.

(w)

[ (v) ] Detection of leaking sources.

(1)

Each dry-source-storage sealed source shall be tested for leakage at intervals not to exceed six months using a leak test kit or method approved by the agency, the commission, an agreement state, or a licensing state. In the absence of a certificate from a transferor that a test has been made within the six months before the transfer, the sealed source may not be used until tested. The test shall be capable of detecting the presence of 0.005 microcurie (200 becquerels) of radioactive material and shall be performed by a person approved by the agency, the NRC [ commission ], an agreement state, or a licensing state to perform the test.

(2)

For pool irradiators, sources may not be put into the pool unless the licensee tests the sources for leaks or has a certificate from a transferor that a leak test has been done within the six months before the transfer. Water from the pool shall be checked for contamination each day the irradiator operates. The check may be done either by using a radiation monitor on a pool water circulating system or by analysis of a sample of pool water. If a check for contamination is done by analysis of a sample of pool water, the results of the analysis shall be available within 24 hours. If the licensee uses a radiation monitor on a pool water circulating system, the detection of above normal radiation levels shall activate an alarm. The alarm set-point shall be set as low as practical, but high enough to avoid false alarms. The licensee may reset the alarm set-point to a higher level if necessary to operate the pool water purification system to clear up contamination in the pool if specifically provided for in written emergency procedures.

(3)

If a leaking source is detected, the licensee shall arrange to remove the leaking source from service and have it decontaminated, repaired, or disposed of by an agency, NRC [ commission ], agreement state, or licensing state licensee who is authorized to perform these functions. The licensee shall promptly check its personnel, equipment, facilities, and irradiated product for radioactive contamination. No product may be shipped until the product has been checked and found free of contamination. If a product has been shipped that may have been inadvertently contaminated, the licensee shall arrange to locate and survey that product for contamination. If any personnel are found to be contaminated, decontamination shall be performed promptly. If contaminated equipment, facilities, or products are found, the licensee shall arrange to have them decontaminated or disposed of by an agency, NRC [ commission ], agreement state, or licensing state licensee who is authorized to perform these functions. If a pool is contaminated, the licensee shall arrange to clean the pool until the contamination levels do not exceed the appropriate concentration in Table 2, Column 2 of §289.202(ggg)(2) of this title. (See §289.202(xx) and (yy) of this title for reporting requirements.)

(x)

[ (w) ] Inspection and maintenance.

(1)

The licensee shall perform inspection and maintenance checks that include, as a minimum, each of the following at the frequency specified in the license or license application:

(A)

operability of each aspect of the access control system required by subsection (i) [ (h) ] of this section;

(B)

functioning of the source position indicator required by subsection (m)(2) [ (l)(2) ] of this section;

(C)

operability of the radiation monitor for radioactive contamination in pool water required by subsection (w)(2) [ (v)(2) ] of this section using a radiation check source, if applicable;

(D)

operability of the over-pool radiation monitor at underwater irradiators as required by subsection (l)(2) [ (k)(2) ] of this section;

(E)

operability of the product exit monitor required by subsection (l)(1) [ (k)(1) ] of this section;

(F)

operability of the emergency source return control required by subsection (m)(3) [ (l)(3) ] of this section;

(G)

leak-tightness of systems through which pool water circulates (visual inspection);

(H)

operability of the heat and smoke detectors and extinguisher system required by subsection (k) [ (j) ] of this section (but without turning extinguishers on);

(I)

operability of the means of pool water replenishment required by subsection (n)(3) [ (m)(3) ] of this section;

(J)

operability of the indicators of high and low pool water levels required by subsection (n)(4) [ (m)(4) ] of this section;

(K)

operability of the intrusion alarm required by subsection (i)(8) [ (h)(8) ] of this section, if applicable;

(L)

functioning and wear of the system, mechanisms, and cables used to raise and lower sources;

(M)

condition of the barrier to prevent products from hitting the sources or source mechanism as required by subsection (o) [ (n) ] of this section;

(N)

amount of water added to the pool to determine if the pool is leaking;

(O)

electrical wiring on required safety systems for radiation damage; [ and ]

(P)

pool water conductivity measurements and analysis as required by subsection (y)(2) [ (x)(2) ] of this section ; and [ . ]

(Q)

operability of automatic communications systems used to alert individuals to alarms, emergencies, or abnormal event conditions if required by subsection (z)(2)(A) of this section.

(2)

Malfunctions and defects found during inspection and maintenance checks shall be repaired without undue delay. If repairs are required, the irradiator shall not be operated unless alternative methods are utilized to provide an equivalent level of safety until repairs are completed.

(y)

[ (x) ] Pool water purity.

(1)

Pool water purification system shall be run sufficiently to maintain the conductivity of the pool water below 20 microsiemens per centimeter under normal circumstances. If pool water conductivity rises above 20 microsiemens per centimeter, the licensee shall take prompt actions to lower the pool water conductivity and shall take corrective actions to prevent future recurrences.

(2)

The licensee shall measure the pool water conductivity frequently enough, but no less than weekly, to assure that the conductivity remains below 20 microsiemens per centimeter. Conductivity meters shall be calibrated at least annually.

(z)

[ (y) ] Attendance during operation.

(1)

Both an irradiator operator and at least one other individual, who is trained on how to respond to alarms in accordance with subsection (s)(7) of this section and is prepared to promptly render or summon assistance [ if the access control alarm sounds ], shall be present onsite whenever it is necessary to enter the radiation room. [ the: ]

[ (A)

irradiator is operated using an automatic product conveyor system; and ]

[ (B)

product is moved into or out of the radiation room when the irradiator is operated in a batch mode. ]

(2)

At least one individual who has received the training on how to respond to alarms described in subsection (s)(7) of this section shall be available and prepared to promptly respond to alarms, emergencies, or abnormal event conditions at any time a panoramic irradiator is operating. If the individual is not onsite, the following requirements shall be met.

(A)

Automatic means of communications shall be provided from the irradiator control system to alert the individual to alarms, emergencies, or abnormal event conditions. As a minimum, the automatic communication system shall alert the individual to those emergency or abnormal events listed in subsection (t)(2) of this section.

(B)

The irradiator control system must be secured from unauthorized access at any time an irradiator operator is not onsite. This security must include physically securing the key described in subsection (m)(1) of this section to ensure the key is not removed from the control console.

[ (2)

At a panoramic irradiator at which static irradiations (no movement of the product) are occurring, a person who has received the training on how to respond to alarms described in subsection (r)(7) of this section shall be onsite. ]

(3)

At an underwater irradiator, an irradiator operator shall be present at the facility whenever the product is moved into or out of the pool. Individuals who move the product into or out of the pool of an underwater irradiator need not be qualified as irradiator operators; however, they shall have received the training described in subsection (s)(6) and (7) [ (r)(6) and (7) ] of this section. Static irradiations may be performed without a person present at the facility.

(aa)

[ (z) ] Entering and leaving the radiation room.

(1)

Upon first entering the radiation room of a panoramic irradiator after an irradiation, the irradiator operator shall use a survey meter to determine that the source has returned to its fully shielded position. The operator shall check the functioning of the survey meter with a radiation check source prior to entry.

(2)

Before exiting from and locking the door to the radiation room of a panoramic irradiator prior to a planned irradiation, the irradiator operator shall do the following :

(A)

visually inspect the entire radiation room to verify that no one else is in it; and

(B)

activate a control in the radiation room that permits the sources to be moved from the shielded position only if the door to the radiation room is locked within a preset time after setting the control.

(3)

During a power failure, the area around the pool of an underwater irradiator may not be entered without using an operable and calibrated radiation survey meter unless the over-the-pool monitor required by subsection (l)(2) [ (k)(2) ] of this section is operating with backup power.

(bb)

[ (aa) ] Irradiation of explosive or flammable materials.

(1)

Irradiation of explosive material is prohibited unless the licensee has received prior written authorization from the agency. Authorization will not be granted unless the licensee can demonstrate that detonation of the explosive would not rupture the sealed sources, injure personnel, damage safety systems, or cause radiation overexposures of personnel.

(2)

Irradiation of more than small quantities of flammable material (flash point below 140 degrees Fahrenheit) is prohibited in panoramic irradiators unless the licensee has received prior written authorization from the agency. Authorization will not be granted unless the licensee can demonstrate that a fire in the radiation room could be controlled without damage to sealed sources or safety systems and without radiation overexposures of personnel.

(cc)

[ (bb) ] Records/documents. The licensee shall maintain the following records/documents at the irradiator for the time intervals indicated for inspection by the agency: [ Records to be kept at the irradiator and retention periods. ]

(1)

a [ A ] copy of the license, license conditions, documents incorporated into a license by reference, and amendments to the license [ thereto ] until superseded by new documents or until the agency terminates the license;

(2)

records of each individual's training, tests, and safety reviews provided to meet the requirements of subsection (s)(1)-(4), (6), and (7) [ (r)(1)-(4), (6) and (7) ] of this section until three years after the individual terminates work;

(3)

records of the annual evaluations of the safety performance of irradiator operators required by subsection (s)(5) [ (r)(5) ] of this section for three years after the evaluation;

(4)

a copy of the current operating, safety, and emergency procedures required by subsection (t) [ (s) ] of this section until superseded or the agency terminates the license. Records of the RSO [ radiation safety officers ] review and approval of changes in procedures as required by subsection (t)(3)(C) [ (s)(3)(C) ] of this section, retained for three years from the date of the change;

(5)

film badge , [ and ] TLD , or OSL results required by subsection (u) [ (t) ] of this section until the agency terminates the license;

(6)

records of radiation surveys required by subsection (v) [ (u) ] of this section for three years from the date of the survey;

(7)

records of radiation survey meter calibrations required by subsection (v) [ (u) ] of this section and pool water conductivity meter calibrations required by subsection (y)(2) [ (x)(2) ] of this section until three years from the date of calibration;

(8)

records of the results of leak tests required by subsection (w)(1) [ (v)(1) ] of this section and the results of contamination checks required by subsection (w)(2) [ (v)(2) ] of this section for three years from the date of each test;

(9)

records of inspection and maintenance checks required by subsection (x) [ (w) ] of this section for three years;

(10)

records of major malfunctions, significant defects, operating difficulties or irregularities, and major operating problems that involve required radiation safety equipment for three years after repairs are completed;

(11)

records of the receipt, transfer and disposal, of all licensed sealed sources as required by §289.201(d) and §289.252(x) and (cc) [ §289.252(k) and (p) ] of this title;

(12)

records on the design checks required by subsection (q) [ (p) ] of this section and the construction control checks as required by subsection (r) [ (q) ] of this section until the license is terminated. The records shall be signed and dated. The title or qualification of the person signing shall be included; and

(13)

records related to decommissioning of the irradiator as required by §289.252(gg)(7) [ §289.252(u)(7) ] of this title.

(dd)

[ (cc) ] Reports.

(1)

In addition to the reporting requirements in other sections of this title, the licensee shall report the following events if not reported under other sections of this title:

(A)

source stuck in an unshielded position;

(B)

any fire or explosion in a radiation room;

(C)

damage to the source racks;

(D)

failure of the cable or drive mechanism used to move the source racks;

(E)

inoperability of the access control system;

(F)

detection of radiation source by the product exit monitor;

(G)

detection of radioactive contamination attributable to licensed radioactive material;

(H)

structural damage to the pool liner or walls;

(I)

abnormal water loss or leakage from the source storage pool; and

(J)

pool water conductivity exceeding 100 microsiemens per centimeter during normal operations.

(2)

The report shall include a telephone report within 24 hours as described in §289.202(xx)(8)(A) [ §289.252(r)(3)(A) ] of this title, and a written report within 30 days as described in §289.202(xx)(8)(B) [ §289.252(r)(3)(B) ] of this title.

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003527

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236


Chapter 295. OCCUPATIONAL HEALTH

Subchapter C. TEXAS ASBESTOS HEALTH PROTECTION

25 TAC §§295.31, 295.32, 295.63

The Texas Department of Health (department) proposes amendments to §§295.31 and 295.32 and new §295.63 concerning authority of the department to administer and enforce the federal Asbestos Hazard Emergency Response Act (AHERA, 40 CFR, Part 763 Subpart E, excluding appendices). The U.S. Environmental Protection Agency (U.S. EPA) issued a notification of approval of the department's Asbestos Containing Materials in Schools Program and a waiver of U.S. EPA's AHERA administration and enforcement authority, which was published in the Federal Register (Volume 65, No. 36, Wednesday, February 23, 2000, pp. 8974-8976).

Amended §295.31 expands the scope of the rules to include administration and enforcement of AHERA by the department. Amended §295.32 adds one new definition. New §295.63 transfers authority from U.S. EPA to the department for administration and enforcement of AHERA.

Mr. Claren J. Kotrla, Director, Toxic Substances Control Division, has determined that for the first five-year period the sections are in effect, there will be fiscal implications as a result of administering the rules as proposed. The effect on state government will mean an increase in revenue to the department estimated to be $19,950 in FY2001, $9,925 in FY2002, $4,950 in FY2003, $3,750 in FY2004, and $3,750 in FY2005. It is estimated that the costs to the department to administer the new provisions will equal the estimated revenue increases. There will be no impact on local government. This transfer of authority does not change the requirement for public school districts to comply with AHERA.

Mr. Kotrla has also determined that for each year of the first five years the sections are in effect, the public benefit anticipated as a result of enforcing or administering the sections will be increased compliance with AHERA, which will reduce exposure of school children and other building occupants to asbestos. There are no anticipated costs to small and micro businesses. There are no additional costs to persons required to comply with the sections as proposed because these rules only transfer the authority from federal to state government. There is no anticipated impact on local employment.

Comments on the proposal may be directed to Mr. Claren Kotrla, Director, Toxic Substances Control Division, Texas Department of Health, 1100 West 49th Street, Austin, Texas 78756 (512) 834-6600, or 1-800-572-5548. Comments will be accepted for 30 days following publication of this proposal in the Texas Register . In addition, a public hearing on the propose sections will be held at 9:00 a.m., Thursday, June 8, 2000, in the Texas Department of Health Auditorium, K-100, 1100 West 49th Street, Austin, Texas.

The amendments and new section are proposed under Texas Civil Statutes, Article 4477-3a, §12(c), which provides the Board of Health (board) with the authority to adopt rules specifying performance standards at least as stringent as applicable federal standards, and the Health and Safety Code, §12.001, which provides the board with the authority to adopt rules for the performance of every duty imposed by law on the board, the department, and the commissioner of health.

The amendments and new section affect Texas Civil Statutes, Article 4477-3a.

§295.31.General Provisions.

(a)-(b)

(No change.)

(c)

Scope.

(1)-(3)

(No change.)

(4)

For the purposes of the Asbestos Hazard Emergency Response Act (AHERA) of 1986, U.S.C. 2605, 2607(c), 2643, and 2646, enforcement only: §§295.32 and 295.63 of this title (relating to Definitions and Asbestos Hazard Emergency Response Act (AHERA) Compliance) apply to all LEAs. Sections 295.32 and 295.63 of this title shall apply to the extent necessary to allow the department to adopt and enforce the federal AHERA.

(d)-(e)

(No change.)

§295.32.Definitions.

The following words and terms, when used with these sections, shall have the following meaning, unless the context clearly indicates otherwise.

(1)-(52)

(No change)

(53)

Local Education Agency (LEA) - means:

(A)

A public board of education or other public authority legally constituted within a State for either administrative control or direction of, or to perform a service function for, public elementary or secondary schools in a city, county, township, school district, or other political subdivision of a State, or for such combination of school districts or counties as are recognized in a State as an administrative agency for its public elementary or secondary schools.

(B)

The term includes any other public institution or agency having administrative control and direction of a public elementary or secondary school.

(C)

The term includes an elementary or secondary school funded by the Bureau of Indian Affairs but only to the extent that such inclusion makes such school eligible for programs for which specific eligibility is not provided to such school in another provision of law and such school does not have a student population that is smaller than the student population of the local educational agency receiving assistance under this chapter with the smallest student population, except that such school shall not be subject to the jurisdiction of any State educational agency other than the Bureau of Indian Affairs.

(D)

The owner or governing authority of any nonpublic, nonprofit elementary, or secondary school building.

(54)

[ (53) ] Major Fiber Release Episode - Any uncontrolled or unintentional disturbance of ACBM, resulting in a visible emission, which involves the falling or dislodging of more than 3 square or linear feet of friable ACBM.

(55)

[ (54) ] Management plan - A written plan describing appropriate actions for surveillance and management of asbestos containing material (ACM).

(56)

[ (55) ] Minor Fiber Release Episode - Any uncontrolled or unintentional disturbance of ACBM, resulting in a visible emission, which involves the falling or dislodging of 3 square or linear feet or less of friable ACBM.

(57)

[ (56) ] Model accreditation plan - A United States Environmental Protection Agency plan which provides standards for initial training, examinations, refresher training courses, applicant qualifications, decertification, and reciprocity, as described in Title 40, CFR, Part 763, Subpart E, Appendix C.

(58)

[ (57) ] NESHAP - The United States Environmental Protection Agency National Emissions Standards for Hazardous Air Pollutants, as described in Title 40, CFR, Part 61.

(59)

[ (58) ] NIOSH - The National Institute of Occupational Safety and Health.

(60)

[ (59) ] Nonfriable material - Material which, when dry, may not be crumbled, pulverized, or reduced to powder by hand pressure.

(61)

[ (60) ] NVLAP - The National Voluntary Laboratory Accreditation Program.

(62)

[ (61) ] Operations and maintenance (O&M) - Operations and maintenance activities are repairs, maintenance, renovation, installation, replacement, or cleanup of building materials or equipment.

(63)

[ (62) ] Operations and maintenance (O&M) contractor - A person who holds an Asbestos Operations & Maintenance Contractor (Restricted) license for general asbestos O&M work in a public building for himself or herself, as a building owner or agent, or as a contractor, if working for others, and follows the guidance contained in the EPA "Green Book". A contractor working for others must have the specified insurance for an abatement contractor.

(64)

[ (63) ] Operations and maintenance (O&M) manual - A record of O&M activities in a public building. The public building owner shall record each individual O&M activity in the manual, including the date of activity, the persons performing the activity, complete description of the activity, including methods used to prevent the emission of asbestos fibers, and the amount of asbestos removed. An updated total of the amount of asbestos abated shall be kept as a comparison to the amount estimated in the annual O&M notification. The manual will be made available to the department upon request.

(65)

[ (64) ] OSHA - The Occupational Safety and Health Administration of the United States Department of Labor.

(66)

[ (65) ] OSHA Regulations - Regulations found in 29 Code of Federal Regulations.

(67)

[ (66) ] Owner or operator of a demolition or renovation activity - Any person who owns, leases, operates, controls, or supervises the facility being demolished or renovated or any person who owns, leases, operates, controls, or supervises the demolition or renovation operation or both.

(68)

[ (67) ] PAT - Proficiency Analytical Testing.

(69)

[ (68) ] PCM - Phase-contrast microscopy, a method of analysis for overall airborne fiber counts using an optical microscope.

(70)

[ (69) ] PEL - Permissible Exposure Limit as defined by OSHA regulations (29 CFR §1926.1101).

(71)

[ (70) ] Plans and specifications - Site-specific asbestos abatement description which includes drawings, floor plans or equivalent of sufficient size and detail, that display the location of asbestos abatement activities, the location of regulated area(s), and a clear and understandable written description of the work to be performed.

(72)

[ (71) ] PLM - Polarized-light microscopy, a method of analysis for detection of the presence and type of asbestos.

(73)

[ (72) ] Person - A person is:

(A)

an individual;

(B)

an organization such as a corporation, partnership, sole proprietorship, governmental subdivision, or agency; or

(C)

any other legal entity recognized by law as the subject of rights and duties.

(74)

[ (73) ] Public building - The interior space of a building used or to be used for purposes that provide for public access or occupancy, including prisons and similar buildings. Interior space includes exterior hallways connecting buildings, porticos, and mechanical systems used to condition interior space. The term includes any building during a period of vacancy, including the period during preparations prior to actual demolition. The term does not include:

(A)

an industrial facility to which access is limited principally to employees of the facility because of processes or functions that are hazardous to human safety or health;

(B)

a federal building or installation (civilian or military);

(C)

a private residence;

(D)

an apartment building with no more than four dwelling units; or

(E)

a manufacturing facility or building that is limited to workers and invited guests under controlled conditions.

(F)

a building, facility, or any portion of which has been determined to be structurally unsound and in danger of imminent collapse by a professional engineer, registered architect, or a city, county, or state government official.

(75)

[ (74) ] Public school - Any elementary or secondary school operated by publicly elected or appointed school officials in which the program and activities are under the control of these officials and which is supported primarily by public funds.

(76)

[ (75) ] Regulated area - The demarcated area in which asbestos abatement activity takes place, and in which the possibility of exceeding the permissible exposure limits (PEL) for the concentrations of airborne asbestos exists.

(77)

[ (76) ] Renovation - Additions to or alterations of the building for purposes of restoration by removal, repairing, and rebuilding.

(78)

[ (77) ] Response action - A method, including removal, encapsulation, enclosure, repair, and operation and maintenance, that protects human health and the environment from friable ACBM.

(79)

[ (78) ] Responsible person - The individual that is designated by the licensed Asbestos Abatement Contractor, Asbestos Operations and Maintenance Contractor, Asbestos Laboratory, Asbestos Consultant Agency, or Asbestos Management Planner Agency, as responsible for their operations and compliance with these rules.

(80)

[ (79) ] School - Any public or private, non-profit, elementary or secondary (kindergarten through grade 12) school as defined in the Elementary and Secondary Education Act of 1965 (20 U.S.C. 8801).

(81)

[ (80) ] School building - Any structure suitable for use as a classroom, including a school facility such as a laboratory, library, school eating facility, or facility used for the preparation of food. Any gymnasium or other facility which is specially designed for athletic or recreational activities for an academic course in physical education. Any other facility used for the instruction or housing of students or for the administration of educational or research programs. Any maintenance, storage, or utility facility, including any hallway, essential to the operation of any facility described in this definition of "school building." Any portico or covered exterior hallway or walkway. Any exterior portion of a mechanical system used to condition interior space.

(82)

[ (81) ] Small-scale, short-duration activities (SSSD) - Are tasks such as, but not limited to removal of asbestos-containing insulation on pipes; removal of small quantities of asbestos-containing insulation on beams or above ceilings; replacement of an asbestos-containing gasket on a valve; installation or removal of a small section of drywall; installation of electrical conduits through or proximate to asbestos-containing materials. These tasks, when performed in a commercial building, do not require accreditation. SSSD can be further defined by the following considerations.

(A)

Removal of small quantities of ACM only if required in the performance of another maintenance activity not intended as asbestos abatement.

(B)

Removal of asbestos-containing thermal system insulation not to exceed amounts greater than those which can be contained in a single glove bag.

(C)

Minor repairs to damaged thermal system insulation which do not require removal.

(D)

Repairs to a piece of asbestos-containing wallboard.

(E)

Repairs, involving encapsulation, enclosure, or removal, to small amounts of friable ACBM only if required in the performance of emergency or routine maintenance activity and not intended solely as asbestos abatement. Such work may not exceed amounts greater than those which can be contained in a single prefabricated mini-enclosure. Such an enclosure shall conform spatially and geometrically to the localized work areas, in order to perform its intended containment function.

(83)

[ (82) ] Start date - The dates defined as:

(A)

asbestos abatement start date - The date on which the disturbance of asbestos begins;

(B)

demolition/renovation start date - The date on which the demolition or renovation process begins.

(84)

[ (83) ] Stop date - The dates defined as:

(A)

asbestos abatement stop date (completion date) - The date upon which air monitoring clearance of asbestos abatement has been achieved. Where air clearance is not required, such as roofing removal, the date upon which the removal of asbestos-containing material is completed.

(B)

demolition/renovation stop date - The date on which the demolition or renovation is complete.

(85)

[ (84) ] Survey - An activity undertaken in a school building, or a public and commercial building to determine the presence or location, or to assess the condition of, friable or non-friable asbestos-containing building material (ACBM) or suspected ACBM, whether by visual or physical examination, or by collecting samples of such material. This term includes reinspections of friable and non-friable known or assumed ACBM which has been previously identified. The term does not include the following:

(A)

periodic surveillance of the type described in 40 CFR §763.92(b) solely for the purpose of recording or reporting a change in the condition of known or assumed ACBM;

(B)

inspections performed by employees or agents of federal, state, or local government solely for the purpose of determining compliance with applicable statutes or regulations; or

(C)

visual inspections of the type described in 40 CFR §763.90(i) solely for the purpose of determining completion of response actions.

(86)

[ (85) ] TEM - Transmission Electron Microscopy.

(87)

[ (86) ] Transportation of asbestos containing material (ACM) - Moving asbestos materials from one site to another.

(88)

[ (87) ] Working days- Monday through Friday including holidays which fall on those days.

§295.63.Asbestos Hazard Emergency Response Act (AHERA) Compliance.

(a)

Authority. The Texas Department of Health (department) adopts by reference federal rules 40 CFR, Part 763, Subpart E, regarding AHERA in accordance with §12(c) of the Act.

(b)

Scope. A Local Education Agency shall assure compliance with AHERA for all schools under its jurisdiction.

(c)

Inspections. The department may enter any regulated school building to inspect and investigate conditions to determine compliance.

(d)

Enforcement. The department will enforce the provisions of the AHERA in accordance with §295.70 of this title (relating to Compliance: Administrative Penalty).

This agency hereby certifies that the proposal has been reviewed by legal counsel and found to be within the agency's legal authority to adopt.

Filed with the Office of the Secretary of State, on May 22, 2000.

TRD-200003594

Susan K. Steeg

General Counsel

Texas Department of Health

Earliest possible date of adoption: July 2, 2000

For further information, please call: (512) 458-7236