reglab/statecodes huggingface dataset:
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-421 - Control of Access to Very-high Radiation Areas

Current through Register Vol. 30, No. 28, July 12, 2024
A. In addition to the requirements in
				R9-7-420, a licensee or registrant
				shall institute measures to ensure that an individual is not able to gain
				unauthorized or inadvertent access to areas in which radiation levels could be
				encountered at 5 Gy (500 rad) or more in one hour at 1 meter from a source or
				from any surface that the radiation penetrates. This requirement does not apply
				to rooms or areas in which diagnostic x-ray systems are the only source of
				radiation or non-self-shielded irradiators.
B. The registrant is not required to control
				entrance or access to rooms or other areas containing sources of radiation
				capable of producing a very high radiation area, described in subsection (A),
				if the registrant has met all requirements for access and control specified in
				other applicable Articles, such as Article 5 for industrial radiography,
				Article 6 for x-rays in the healing arts, and Article 9 for particle
				accelerators.
C. Each licensee or
				registrant shall maintain records of tests made according to R9-7-422(B)(9) on
				entry control devices for very-high radiation areas. These records shall
				include the date, time, and results of each test of function.
D. The licensee or registrant shall retain
				the records required by this Section for three years after the record is
				made.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-422 - Control of Access to Irradiators (Very-high Radiation Areas)

Current through Register Vol. 30, No. 28, July 12, 2024
A. This Section
				applies to licensees or registrants with sources of radiation in
				non-self-shielded irradiators. This Section does not apply to sources of
				radiation that are used in teletherapy, industrial radiography, or completely
				self-shielded irradiators in which the source of radiation is both stored and
				operated within the same shielding radiation barrier and, in the designed
				configuration of the irradiator, is always physically inaccessible to any
				individual and cannot create high levels of radiation in an area that is
				accessible to any individual.
B. A
				licensee or registrant shall ensure that each area in which radiation levels
				may exceed 5 Gy (500 rad) in one hour at 1 meter from a source that is used to
				irradiate materials meets the following requirements:
1. Each entrance or access point shall be
				equipped with entry control devices that:
a.
				Function automatically to prevent any individual from inadvertently entering a
				very high radiation area;
b. Permit
				deliberate entry into the area only after a control device is actuated that
				causes the radiation level within the area, from the source of radiation, to be
				reduced below that at which it would be possible for an individual to receive a
				deep-dose equivalent in excess of 1 mSv (0.1 rem) in one hour; and
c. Prevent operation of the source of
				radiation if it would produce radiation levels in the area that could result in
				a deep-dose equivalent to an individual in excess of 1 mSv (0.1 rem) in one
				hour.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-423 - Use of Process or Other Engineering Controls

Current through Register Vol. 30, No. 28, July 12, 2024
A licensee shall use, to the extent practicable, process or
				  other engineering controls, such as containment, decontamination, or
				  ventilation, to control the concentration of radioactive material in
				  air.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-424 - Use of Other Controls

Current through Register Vol. 30, No. 28, July 12, 2024
A. If
				it is not practical to apply process or other engineering controls to control
				concentrations of radioactive material in the air to values below those that
				define an airborne radioactivity area, the licensee shall, consistent with
				maintaining the total effective dose equivalent according to
				R9-7-407(B),
				increase monitoring and limit intakes by one or more of the following means:
1. Control access,
2. Limit exposure times,
3. Use respiratory protection equipment,
				or
4. Use other controls.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-426 - Security of Stored Sources of Radiation

Current through Register Vol. 30, No. 28, July 12, 2024
A licensee or registrant shall secure from unauthorized
				  removal or access licensed or registered sources of radiation that are stored
				  in unrestricted areas.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-427 - Control of Sources of Radiation Not in Storage

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee shall control and maintain
				constant surveillance of licensed radioactive material that is in an
				unrestricted area and is not in storage or in a patient.
B. A registrant shall maintain control of
				radiation machines that are in an unrestricted area and not in
				storage.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-428 - Caution Signs

Current through Register Vol. 30, No. 28, July 12, 2024
A.
				Unless otherwise authorized by the Department, a licensee or registrant shall
				use the symbol prescribed by this Section with the colors magenta, or purple,
				or black on yellow background as the standard radiation symbol. The symbol
				prescribed is the three-bladed design as follows:
RADIATION SYMBOL
1.
				Cross-hatched area is to be magenta, purple, or black; and
2. The background is to be yellow.
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Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-429 - Posting

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee or
				registrant shall post each radiation area with a conspicuous sign or signs
				bearing the radiation symbol and the words "CAUTION, RADIATION AREA."
B. The licensee or registrant shall post each
				high radiation area with a conspicuous sign or signs bearing the radiation
				symbol and the words "CAUTION, HIGH RADIATION AREA" or "DANGER, HIGH RADIATION
				AREA."
C. The licensee or
				registrant shall post each very-high radiation area with a conspicuous sign or
				signs bearing the radiation symbol and the words "GRAVE DANGER, VERY HIGH
				RADIATION AREA."
D. The licensee
				shall post each airborne radioactivity area with a conspicuous sign or signs
				bearing the radiation symbol and the words "CAUTION, AIRBORNE RADIOACTIVITY
				AREA" or "DANGER, AIRBORNE RADIOACTIVITY AREA."
E. The licensee shall post each area or room
				in which there is used or stored an amount of licensed material exceeding 10
				times the quantity of licensed material specified in Appendix C with a
				conspicuous sign or signs bearing the radiation symbol and the words "CAUTION,
				RADIOACTIVE MATE-RIAL(S)" or "DANGER, RADIOACTIVE MATERIAL(S)."
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-430 - Exceptions to Posting Requirements

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee or registrant is not required
				to post caution signs in areas or rooms containing sources of radiation for
				periods of less than eight hours, if each of the following conditions is met:
1. The sources of radiation are constantly
				attended during these periods by an individual who takes precautions necessary
				to prevent exposure of individuals to sources of radiation in excess of limits
				established in this Article; and
2.
				The area or room is subject to the licensee's or registrant's
				control.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-431 - Labeling Containers and Radiation Machines

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee shall ensure that each
				container of licensed material is labeled with a durable, clearly visible
				radiation symbol and the words "CAUTION, RADIOACTIVE MATERIAL" or "DANGER,
				RADIOACTIVE MATERIAL." The label shall also provide information, such as the
				radionuclides present, an estimate of the quantity of radioactivity, the date
				for which the radioactivity is estimated, radiation level, kind of material,
				and mass enrichment, to permit an individual handling or using a container, or
				working in the vicinity of a container, to take precautions to avoid or
				minimize exposure.
B. Before
				removal or disposal of an empty, uncontaminated container to an unrestricted
				area, each licensee shall remove or deface the radioactive material label or
				otherwise clearly indicate that the container no longer contains radioactive
				materials.
C. Each registrant shall
				ensure that each radiation machine is labeled in a conspicuous manner to
				caution an individual that radiation is produced when it is
				energized.
D. A licensee shall
				label each syringe and vial that contains a radiopharmaceutical used in the
				practice of medicine with the radiopharmaceutical content. Each syringe shield
				and vial shield shall be labeled, unless the label on the syringe or vial is
				visible when shielded. The label shall contain the radiophar-maceutical name or
				its abbreviation, the clinical procedure to be performed, or the name of the
				person being administered the radiopharmaceutical. Color-coding syringe shields
				and vial shields does not meet the labeling requirement.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-432 - Labeling Exemptions

Current through Register Vol. 30, No. 28, July 12, 2024
A licensee is not required to label:
1. Containers holding licensed material in
				quantities less than the quantities listed in Appendix C;
2. Containers holding licensed material in
				concentrations less than those specified in Table III of Appendix B;
3. Containers attended by an individual who
				takes precautions necessary to prevent exposure of individuals to radiation in
				excess of the limits established in this Article;
4. Containers holding radioactive material
				that do not exceed the limits for excepted quantity or article as defined and
				limited in 49 CFR
				173.403, and
				173.421 through
				173.424, and are transported,
				packaged, and labeled in accordance with
				49 CFR
				172.436 through
				172.440 (Revised October 1, 2007,
				incorporated by reference, and available under R9-7-101. This incorporated
				material contains no future editions or amendments.);
5. Containers that are accessible only to
				individuals authorized to handle, use, or work in the vicinity of the
				containers, if the contents are identified to these individuals by a readily
				available written record, retained as long as the container is in use for the
				purpose indicated on the record. (Examples of containers of this type are
				containers in locations such as water-filled canals, storage vaults, or hot
				cells.); or
6. Installed
				manufacturing or process equipment, such as piping and tanks.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-433 - Procedures for Receiving and Opening Packages

Current through Register Vol. 30, No. 28, July 12, 2024
A. Each licensee who expects to receive a
				package containing quantities of radioactive material in excess of a Type A
				quantity, as defined in
				10
				CFR 71.4, January 1, 2005, which is
				incorporated by reference, published by the Office of the Federal Register,
				National Archives and Records Administration, Washington, D.C. 20408, and on
				file with the Department. The material incorporated by reference contains no
				future editions or amendments. The licensee shall make arrangements to receive:
1. The package when the carrier offers it for
				delivery; or
2. The notification of
				the arrival of the package at the carrier's terminal and to take possession of
				the package expeditiously.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-434 - General Requirements for Waste Disposal

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee shall dispose of licensed
				material only:
1. By transfer to an
				authorized recipient as provided in R9-7-439 or in Article 3, or to the U.S.
				Department of Energy;
2. By decay
				in storage, according to R9-7-438(C);
3. By release in effluents within the limits
				in R9-7-416; or
4. As authorized according to R9-7-435,
				R9-7-436, R9-7-437, R9-7-438, or R9-7-438.01;
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-435 - Method for Obtaining Approval of Proposed Disposal Procedures

Current through Register Vol. 30, No. 28, July 12, 2024
For disposal of licensed material generated in the licensee's
				  operations, a licensee or applicant for a license may apply to the Department
				  for approval of proposed disposal procedures, not otherwise authorized in this
				  Chapter. Each application shall include:
1. A description of the waste containing
				licensed material to be disposed of, including the physical and chemical
				properties that have an impact on risk evaluation;
2. The proposed manner and conditions of
				waste disposal;
3. An analysis and
				evaluation of pertinent information on the nature of the environment;
4. The nature and location of other
				potentially affected facilities; and
5. An analysis and procedure to ensure that
				doses comply with
				R9-7-407(B), and
				are within the dose limits in this Article.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-436 - Disposal by Release into Sanitary Sewerage System

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee may discharge licensed material
				into sanitary sewerage if each of the following conditions is satisfied:
1. The material is readily soluble or is
				readily dispersible biological material, in water;
2. The quantity of licensed radioactive
				material that the licensee releases into the sewer in one month divided by the
				average monthly volume of water released into the sewer by the licensee or
				registrant does not exceed the concentration listed in Appendix B, Table III;
				and
3. If more than one
				radionuclide is released, the following conditions shall also be satisfied:
a. The licensee shall determine the fraction
				of the limit in Appendix B, Table III represented by discharges into sanitary
				sewerage by dividing the actual monthly average concentration of each
				radionuclide released by the licensee or registrant into the sewer by the
				concentration of that radionuclide listed in Appendix B, Table III;
b. The sum of the fractions for each
				radionuclide required by subsection (A)(3)(a) does not exceed unity;
				and
c. The total quantity of
				licensed radioactive material that the licensee releases into the sanitary
				sewerage in a year does not exceed 185 GBq (5 Ci) of Hydrogen-3, 37 GBq (1 Ci)
				of Carbon-14, and 37 GBq (1 Ci) of all other radioactive materials
				combined.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-437 - Treatment or Disposal by Incineration

Current through Register Vol. 30, No. 28, July 12, 2024
A licensee shall treat or dispose of licensed material by
				  incineration only in the amounts and forms specified in R9-7-438 or as
				  specifically approved by the Department according to
				  R9-7-435.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-438 - Disposal of Specific Wastes

Current through Register Vol. 30, No. 28, July 12, 2024
A.
				A licensee may dispose of the following licensed material as if it were not
				radioactive:
1. 1.85 kBq (0.05 µCi), or less,
				of Hydrogen-3 or Carbon-14 per gram of medium used for liquid scintillation
				counting; and
2. 1.85 kBq (0. 05
				µCi), or less, of Hydrogen-3 or Carbon-14 per gram of animal tissue, averaged
				over the weight of the entire animal.
3. 1.85 kBq (0.05 µCi), or less, of
				Iodine-125 per gram of medium used in analyzing in vitro laboratory samples and
				associated sample holders contaminated during the laboratory
				procedure.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-438.01 - Disposal of Certain Radioactive Material

Current through Register Vol. 30, No. 28, July 12, 2024
A. Licensed material as defined in the
				definition of radioactive material in
				R9-7-102 may be disposed of in
				accordance with this Article, even though it is not defined as low-level
				radioactive waste. Therefore, any licensed radioactive material being disposed
				of at a facility, or transferred for ultimate disposal at a facility licensed
				by the Department, must meet the requirements of R9-7-439.
B. A licensee may dispose of radioactive
				material, as defined in the definition of radioactive material in
				R9-7-102, at a disposal facility
				authorized to dispose of such material in accordance with any federal or state
				solid or hazardous waste law, including the Solid Waste Disposal Act, as
				authorized under the Energy Policy Act of 2005.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-439 - Transfer for Disposal and Manifests

Current through Register Vol. 30, No. 28, July 12, 2024
A. Any licensee shipping radioactive waste
				intended for ultimate disposal at a licensed land disposal facility (for
				purposes of this rule "land disposal facility" means the land, buildings,
				structures, and equipment that are intended to be used for the disposal of
				radioactive waste. A geologic repository is not a land disposal facility) shall
				comply with 10 CFR
				20.2006 and 10 CFR 20 Appendix G, published
				January 1, 2013, incorporated by reference, and available under
				R9-7-101. This incorporated
				material contains no future editions or amendments.
B. An authorized representative of the waste
				generator shall provide the certification required in 10 CFR 20, Appendix G,
				Section II, which is incorporated by reference in subsection (A).
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-440 - Compliance with Environmental and Health Protection Regulations

Current through Register Vol. 30, No. 28, July 12, 2024
Nothing in R9-7-434, R9-7-435, R9-7-436, R9-7-437, R9-7-438,
				  or R9-7-439 relieves the licensee from complying with other applicable federal,
				  state, and local rules or regulations governing any other toxic or hazardous
				  properties of materials that may be disposed of according to the rules listed
				  in Article 4 of this Chapter.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-441 - Records of Waste Disposal

Current through Register Vol. 30, No. 28, July 12, 2024
A.
				Each licensee shall maintain records of the disposal of licensed materials made
				in accordance with R9-7-435, R9-7-436, R9-7-437, R9-7-438, and disposal by
				burial in soil, including burials authorized before February 25,
				1985.
B. The licensee shall retain
				the records required by subsection (A) until the Department terminates each
				pertinent license requiring the record. The licensee shall provide for the
				disposition of these records prior to license termination.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-442 - Department Inspection of Shipments of Waste

Current through Register Vol. 30, No. 28, July 12, 2024
Each shipment of waste to a disposal facility, licensed under
				  R9-7-1302(D)(11), is subject to inspection by the Department before shipment or
				  transportation. The waste shipper shall notify the Department not less than
				  five working days before the scheduled shipment or transportation of waste to a
				  licensed disposal facility.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-443 - Reports of Stolen, Lost, or Missing Licensed or Registered Sources of Radiation

Current through Register Vol. 30, No. 28, July 12, 2024
A.
				Each licensee or registrant shall report to the Department by telephone, as
				specified in R9-7-448(C), as follows:
1.
				Immediately after it becomes known to the licensee that licensed radioactive
				material in an aggregate quantity equal to or greater than 1,000 times the
				quantity specified in Appendix C is stolen, lost, or missing under
				circumstances that indicate to the licensee that an exposure could result to
				individuals in unrestricted areas;
2. Within 30 days after it becomes known to
				the licensee that licensed radioactive material in an aggregate quantity
				greater than 10 times the quantity specified in Appendix C is stolen, lost, or
				missing, and is still missing; and
3. Immediately after it becomes known to the
				registrant that a radiation machine is stolen, lost, or missing.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-444 - Reports of Exposures, Radiation Levels, and Concentrations of Radioactive Material Exceeding the Limits

Current through Register Vol. 30, No. 28, July 12, 2024
A. In addition to the notification required
				by R9-7-445, each licensee or registrant shall submit a written report within
				30 days after learning of any of the following:
1. Incidents for which notification is
				required by R9-7-445;
2. Doses in
				excess of any of the following:
a. The
				occupational dose limits for adults in
				R9-7-408;
b. The occupational dose limits for a minor
				in R9-7-414;
c. The limits for an embryo or fetus of a
				declared pregnant woman in
				R9-7-415;
d. The limits for an individual member of the
				public in R9-7-416;
e. Any applicable limit in the license or
				registration; or
f. The ALARA limit
				on air emissions in R9-7-407;
3. Levels of radiation or concentrations of
				radioactive material in:
a. A restricted area
				in excess of applicable limits in the license or registration, or
b. An unrestricted area in excess of 10 times
				the applicable limit in this Article or in the license or registration, whether
				or not this involves an exposure of any individual to a dose in excess of the
				limits in R9-7-416;
4. Radiation levels or concentrations of
				radioactive material in excess of the standards in 40 CFR 190, 2003 edition,
				published July 1, 2003, by the Office of the Federal Register, National
				Archives and Records Administration, Washington, D.C. 20408 which is
				incorporated by reference and on file with the Department, if the licensee is
				subject to these federal standards, or there is a license condition referencing
				the 40 CFR 190 standards. This incorporation by reference contains no future
				editions or amendments.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-445 - Notification of Incidents

Current through Register Vol. 30, No. 28, July 12, 2024
A.
				Immediate notification: Each licensee or registrant shall immediately report to
				the Department, as specified in
				R9-7-448(C),
				any event involving a radiation source that may have caused or threatens to
				cause any of the following conditions:
1. An
				individual to receive:
a. A total effective
				dose equivalent of 0.25 Sv (25 rem) or more;
b. A lens dose equivalent of 0.75 Sv (75 rem)
				or more; or
c. A shallow-dose
				equivalent to the skin or extremities of 2.5 Gy (250 rads) or more;
				or
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-446 - Notifications and Reports to Individuals

Current through Register Vol. 30, No. 28, July 12, 2024
A. Requirements for notification and reports
				to individuals of exposure to radiation or radioactive material are specified
				in R9-7-1004.
B. In addition to the
				reporting requirements in R9-7-444 and R9-7-445, each licensee or registrant
				shall notify the individual exposed to radiation or radioactive material. The
				notice to the exposed individual shall be provided no later than the date the
				report is submitted to the Department and shall comply with
				R9-7-1004(A).
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-447 - Vacating Premises

Current through Register Vol. 30, No. 28, July 12, 2024
A. If
				a facility has been used for activities involving radioactive material a
				licensee shall notify the Department in writing of the intent to vacate the
				facility no less than 45 days before relinquishing possession or control of the
				facility.
B. If a facility is
				contaminated with radioactive material, a licensee vacating the facility shall
				decontaminate it using Department-approved procedures.
C. The Department shall inspect a vacated
				facility to determine whether it is contaminated with radioactive
				material.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-448 - Additional Reporting

Current through Register Vol. 30, No. 28, July 12, 2024
A.
				Each licensee shall notify the Department , according to subsection (C), as
				soon as possible, but not later than four hours after the discovery of an
				event, and take immediate protective actions necessary to avoid exposures to
				radiation or radioactive materials that could exceed the limits specified in
				this Chapter or releases of licensed material that could exceed the limits
				specified in this Chapter. For purposes of this Section, event means a
				radiation accident involving a fire, explosion, gas release, or similar
				occurrence.
B. Each licensee shall
				notify the Department, according to subsection (C), within 24 hours after
				discovering any of the following events involving licensed material:
1. A contamination event that:
a. Requires that anyone having access to the
				contaminated area be restricted for more than 24 hours by the imposition of
				additional radiological controls to prohibit entry into the area;
b. Involves a quantity of radioactive
				material greater than five times the lowest annual limit on intake specified in
				Appendix B of this Article; and
c.
				Results in access to the contaminated area being restricted for a reason other
				than to allow radionuclides with a half-life of less than 24 hours to decay
				prior to decontamination.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-449 - Survey Instruments and Pocket Dosimeters

Current through Register Vol. 30, No. 28, July 12, 2024
A. Each licensee or registrant shall ensure
				that survey instruments used to show compliance with this Article have been
				calibrated before first use, annually, and following repair, unless otherwise
				specified in this Chapter.
B. To
				satisfy the requirements of subsection (A), the licensee or registrant shall:
1. For each scale to be calibrated, calibrate
				two readings separated by at least 50 percent of scale rating; and
2. Conspicuously note on the instrument the
				apparent radiation level, in appropriate units for the type of survey
				instrument being used and the date of calibration.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-450 - Sealed Sources

Current through Register Vol. 30, No. 28, July 12, 2024
A. A
				licensee shall only receive, possess, and use radioactive materials contained
				in a sealed source that has been manufactured, labeled, packaged, and
				distributed in accordance with a specific license for its manufacture and
				distribution. The license to manufacture and distribute a sealed source shall
				be issued by the Department, the U.S. Nuclear Regulatory Commission, a
				Licensing State, or another Agreement State.
B. A licensee who possesses and uses a sealed
				source, or any device or equipment that contains a sealed source, shall follow
				the radiation safety and handling instructions approved by the Department or
				follow the radiation safety and handling instructions furnished by the
				manufacturer on the label attached to the source, on the permanent container of
				the source, or in a leaflet or brochure that accompanies the source, and
				maintain the instructions in a legible and conveniently available form. If the
				handling instructions, leaflet, or brochure is no longer available and a copy
				cannot be obtained from the manufacturer, the licensee shall notify the
				Department that the source handling information is no longer
				available.
C. Inventories:
1. An inventory shall be conducted at
				intervals not to exceed six months, unless a shorter interval is specified by
				license condition.
2. The records
				of the inventory shall be maintained for three years from the date of the
				inventory, and shall be available for inspection by the Department.
3. The information recorded shall include:
a. The kind and quantity of radioactive
				material,
b. The model and serial
				number of the source or the device in which it is mounted,
c. The location of the sealed
				source,
d. The date of the
				inventory, and
e. The signature of
				the person performing the inventory.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-451 - Termination of a Radioactive Material License or a Licensed Activity

Current through Register Vol. 30, No. 28, July 12, 2024
A. As the final
				step before terminating a radioactive material use program licensed under
				R9-7-312, the licensee shall:
1. Certify to
				the Department the disposition of all licensed material, including accumulated
				wastes, by submitting a complete description of a disposal plan with signed
				receipts from all licensed persons receiving the licensed material;
				and
2. Conduct a radiation survey
				of the premises where the licensed activities were carried out to demonstrate
				that the premises are suitable for release in accordance with the criteria for
				decommissioning in R9-7-452 and submit to the Department a report of the
				results of this survey, unless the licensee demonstrates in some other manner
				acceptable to the Department that the premises are suitable for release in
				accordance with the criteria for decommissioning in R9-7-452.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-452 - Radiological Criteria for License Termination

Current through Register Vol. 30, No. 28, July 12, 2024
A. General provisions and scope:
1. The criteria in this Section apply to the
				decommissioning of facilities licensed under Article 3 of this Chapter. The
				criteria do not apply to uranium and thorium recovery facilities already
				subject to 10 CFR 40, Appendix A, or to uranium solution extraction
				facilities.
2. The criteria in this
				Section do not apply to sites that:
a. Have
				been decommissioned before the effective date of this Section; or
b. Have previously submitted and received
				Department approval of a license termination plan (LTP) or decommissioning
				plan.
3. If a site has
				been decommissioned and the license terminated in accordance with the criteria
				in this Section, the Department shall not require additional cleanup unless,
				based on new information, the Department determines that the criteria of this
				Section were not met and residual radioactivity at the site is a threat to
				public health and safety.
4. When
				calculating the TEDE for the average member of the critical group, a licensee
				shall use the peak annual dose expected within the first 1000 years after
				decommissioning.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Table 1 - Acceptable Surface Contamination 1 Levels

Current through Register Vol. 30, No. 28, July 12, 2024
Radionuclide1.
Average2,3
Maximum2,4
Removable2,5
U-nat, U-235, U-238, and associated decay
							 products
5,000 dpm/ 100 cm2
15,000 dpm/ 100cm2
1,000 dpm/ 100 cm2
Transuranics, Ra-226, Ra-228, Th-230, Pa-231, Ac-227,
							 I-125, I-129
100dpm/ 100cm2
300 dpm/ 100cm2
20dpm/ 100cm2
Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232, I-126,
							 I-131, I-133
1000 dpm/ 100cm2
3000 dpm/ 100cm2
200 dpm/ 100cm2
Beta-gamma (Exceptions noted above)
5,000 dpm/ 100 cm2
15,000 dpm/ 100cm2
1,000 dpm/ 100 cm2
1 Where surface contamination by
				  both alpha-and beta-gamma-emitting radionuclides exists, the limits established
				  for alpha-and beta-gamma-emitting radionuclides apply independently.
2As used in this table, dpm
				  (disintegrations per minute) means the rate of emission by radioactive material
				  as determined by correcting the counts per minute observed on an instrument
				  calibrated for background, efficiency, and geometric factors associated with
				  the instrumentation, in accordance with R9-7-449.
3Measurements of average
				  contamination level shall not be averaged over more than one square meter. For
				  objects of less surface area, the average shall be derived for each
				  object.
4The maximum contamination level
				  applies to an area of not more than 100 cm2.
5The amount of removable
				  radioactive material per 100 cm2 of surface area
				  shall be determined by wiping that area with dry filter or soft absorbent
				  paper, applying moderate pressure, and assessing the amount of radioactive
				  material on the wipe with an instrument calibrated in accordance with R9-7-449.
				  When removable contamination on objects of surface area A (where A is less than
				  100 sq. cm) is determined, the entire surface shall be wiped and the
				  contamination level multiplied by 100/A to convert to a "per 100 sq. cm" basis.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-453 - Reports to Individuals of Exceeding Dose Limits

Current through Register Vol. 30, No. 28, July 12, 2024
Any licensee or registrant that reports a personnel exposure
				  to the Department in accordance with
				  R9-7-413(A)(6),
				  R9-7-444, or R9-7-452 shall:
1. Notify
				the exposed individual of the exposure addressed in the report; and
2. Transmit the report to the exposed
				individual at the same time the Department is notified of the
				exposure.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-454 - Nationally Tracked Sources.

Current through Register Vol. 30, No. 28, July 12, 2024
A.
				A licensee who manufactures, receives, transfers, disassembles, or disposes of
				a nationally tracked source shall complete and submit to the Nuclear Regulatory
				Commission's National Source Tracking System and the Department, a National
				Source Tracking Transaction Report that contains the information required in
				10 CFR
				20.2207(a) through (e),
				revised August 9, 2021, incorporated by reference, and available under
				R9-7-101.
				This incorporated material contains no future editions or amendments. The
				report shall be submitted by the close of the next business day after the
				transaction using a reporting method specified in
				10 CFR
				20.2207(f), revised January
				1, 2008, incorporated by reference, and available under
				R9-7-101.
				This incorporated material contains no future editions or amendments.
B. The initial National Source Tracking
				Transaction Report shall contain the information required in subsection (A), be
				submitted using a method specified in
				10 CFR
				20.2207(f), revised August
				9, 2021, incorporated by reference, and available under
				R9-7-101.
				This incorporated material contains no future editions or amendments.
C. A licensee shall correct any error in
				previously filed National Source Tracking Transaction Reports or file a new
				report for any missed transaction within five business days of the discovery of
				the error or missed transaction in accordance with
				10 CFR
				20.2207(g), revised August
				9, 2021, incorporated by reference, and available under
				R9-7-101.
				This incorporated material contains no future editions or amendments.
D. A licensee who receives a nationally
				tracked sealed source shall not disassemble the source unless specifically
				authorized to do so by the Department.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-455 - Security Requirements for Portable Gauges

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee that uses a portable gauge
				shall use a minimum of two independent controls to maintain security while:
1. Transporting a portable gauge;
				and
2. Storing a portable
				gauge.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 5 - SEALED SOURCE INDUSTRIAL RADIOGRAPHY › Section R9-7-502 - License Requirements

Current through Register Vol. 30, No. 28, July 12, 2024
A. The
				Department shall review an application for a specific license for the use of
				radioactive material in industrial radiography and approve the license if an
				applicant meets all of the following requirements:
1. The applicant satisfies the general
				requirements in R9-7-309 and any special requirements contained in this
				Article; and
2. The applicant
				submits a program for training radiographers and radiographers' assistants that
				complies with R9-7-543, except that:
a. After
				the effective date of this Section, an applicant is not required to describe
				its initial training and examination program for radiographers;
b. An applicant shall affirm that an
				individual who is acting as an industrial radiographer is certified in
				radiation safety by a certifying organization, as required in R9-7-543, before
				permitting the individual to act as a radiographer. This affirmation
				substitutes for a description of the applicant's initial training and
				examination program for radiographers in the subjects outlined in R9-7-543(G);
				and
c. An applicant shall submit
				procedures for verifying and documenting the certification status of each
				radiographer and for ensuring that the certification remains valid.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 5 - SEALED SOURCE INDUSTRIAL RADIOGRAPHY › Section R9-7-503 - Performance Requirements for Equipment

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee shall ensure that equipment
				used in industrial radio-graphic operations meets the following minimum
				criteria:
1. Each radiographic exposure
				device, source assembly or sealed source, and all associated equipment meet the
				requirements in American National Standards Institute, N432-1980 "Radiological
				Safety for the Design and Construction of Apparatus for Gamma Radiography"
				(published as NBS Handbook 136, issued January 1981) by the American National
				Standards Institute, which is incorporated by reference and on file with the
				Department. This incorporation by reference contains no future editions or
				amendments. This publication may be purchased from the American National
				Standards Institute, Inc., 25 West 43rd Street, New York, New York 10036
				Telephone (212) 642-4900. A copy of the document is also on file at the
				National Archives and Records Administration (NARA). For information on the
				availability of this material at NARA, call (202) 741-6030, or go to:
http://www.archives.gov/federal_register/code_of_federal_regulations/ibr_locations.html
;
				or
2. An engineering safety
				analysis demonstrates the applicability of previously performed testing on
				similar individual radiography equipment components. Based on a review of the
				analysis, the Department may find that previously performed testing can be
				substituted for testing of the component under the standards in subsection
				(A)(1).
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 5 - SEALED SOURCE INDUSTRIAL RADIOGRAPHY › Section R9-7-504 - Radiation Survey Instruments

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee shall maintain at least two
				calibrated and operable radiation survey instruments at each location where
				sources of radiation are present to make radiation surveys required by this
				Article and Article 4 of this Chapter. Instrumentation required by this Section
				shall be capable of measuring a range from 0.02 millisieverts (2 millirems) per
				hour through 0.01 sievert (1 rem) per hour.
B. A licensee shall ensure that each
				radiation survey instrument required under subsection (A) is calibrated:
1. At intervals that do not exceed six
				months, and after instrument servicing, except for battery changes;
2. For linear scale instruments, at two
				points located approximately one-third and two-thirds of full-scale on each
				scale; for logarithmic scale instruments, at mid-range of each decade, and at
				two points of at least one decade; and for digital instruments, at 3 points
				between 0.02 and 10 millisieverts (2 and 1000 millirems) per hour;
				and
3. So that an accuracy within
				plus or minus 20% of the calibration source can be demonstrated at each point
				checked.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 5 - SEALED SOURCE INDUSTRIAL RADIOGRAPHY › Section R9-7-506 - Quarterly Inventory

Current through Register Vol. 30, No. 28, July 12, 2024
A. A
				licensee shall conduct a quarterly physical inventory to account for all sealed
				sources and devices that contain depleted uranium.
B. A licensee shall maintain a record of the
				quarterly inventory required under subsection (A) for three years after it is
				made.
C. The record required in
				subsection (B) shall include the date of the inventory, name of the individual
				who conducted the inventory, radionuclide, number of becquerels (curies) or
				mass (for DU) in each device, location of sealed source and associated devices,
				and manufacturer, model, and serial number of each sealed source and device as
				applicable.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 5 - SEALED SOURCE INDUSTRIAL RADIOGRAPHY › Section R9-7-507 - Utilization Logs

Current through Register Vol. 30, No. 28, July 12, 2024
A. A
				licensee shall maintain for each sealed source a utilization log that provides
				all of the following information:
1. A
				description, including the make, model, and serial number of each radiographic
				exposure device, and each sealed source transport and storage container that
				contains a sealed source;
2. The
				identity and signature of the radiographer using the source; and
3. The plant or site where the source is used
				and dates of use, including the date each source is removed from and returned
				to storage.