reglab/statecodes huggingface dataset:
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-309 - General Requirements for Issuance of Specific Licenses

Current through Register Vol. 30, No. 28, July 12, 2024
A license application shall be approved if the Department
				  determines that:
1. The applicant is
				qualified by reason of training and experience to use the material in question
				for the purpose requested according to these rules, in a manner that will
				minimize danger to public health and safety or property;
2. The applicant's proposed equipment,
				facilities, and procedures are adequate to minimize danger to public health and
				safety or property;
3. The issuance
				of the license will not be inimical to the health and safety of the
				public;
4. The applicant satisfies
				all applicable special requirements in R9-7-310,
				R9-7-311, R9-7-322,
				R9-7-323, and 9 A.A.C. 7, Articles
				5, 7, and 17; and
5. The applicant
				demonstrates that a letter has been sent, return receipt requested, to the
				Mayor's office of the city, town, or, if not within an incorporated community,
				to the County Board of Supervisors of the county in which the applicant
				proposes to operate which describes:
a. The
				nature of the proposed activity involving radioactive material; and
b. The facility, including use and storage
				areas.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-310 - Special Requirements for Issuance of Specific Broad Scope Licenses

Current through Register Vol. 30, No. 28, July 12, 2024
A. The Department
				shall issue three classes of academic and industrial broad scope licenses, and
				only a single class A medical broad scope license.
1. The license may authorize the radioactive
				materials in multi-curie quantities, and may authorize other radioactive
				materials and forms in addition to those listed in subsection (A)(1)(a). A
				license is a broad scope class A license if it:
a. Contains the exact wording "Any
				radioactive material with Atomic Number 3 through 83" or "Any radioactive
				material with Atomic Number 84 through 92" in License Item 6; and
b. Contains the word "any" to authorize the
				chemical or physical form of the materials in License Item 7;
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-312 - Issuance of Specific Licenses

Current through Register Vol. 30, No. 28, July 12, 2024
A. Upon determination that a license
				application meets the requirements of the Act and Department rules, the
				Department shall grant a specific license that may contain conditions or
				limitations if the Department has determined that additional requirements
				regarding the proposed activity will protect health and safety.
B. The Department may incorporate in any
				license at the time of issuance, or thereafter by rule or order, additional
				requirements and conditions with respect to the licensee's receipt, possession,
				use, and transfer of radioactive material in order to:
1. Minimize danger to public health and
				safety or property;
2. Require
				reports and recordkeeping, and provide for inspections of activities under the
				license as may be necessary to protect health and safety; and
3. Prevent loss or theft of material subject
				to this Article.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-313 - Specific Terms and Conditions

Current through Register Vol. 30, No. 28, July 12, 2024
A. Each license issued under this Article is
				subject to all provisions of A.R.S. Title 30, Chapter 4 and to all rules,
				regulations, and orders of the Department.
B. A licensee shall not transfer, assign, or
				in any manner dispose of a license issued or granted under this Article or a
				right to possess or utilize radioactive material granted by any license issued
				under this Article unless the Department finds that the transfer is consistent
				with the Department's statutes and rules, and gives its consent in writing. An
				application for transfer of license must include:
1. The identity, technical and financial
				qualifications of the proposed transferee; and
2. Financial assurance for decommissioning
				information required by
				R9-7-323.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-314 - Expiration of License

Current through Register Vol. 30, No. 28, July 12, 2024
Except as provided in R9-7-315(B), each specific license
				  expires at the end of the day, in the month and year stated on the
				  license.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-315 - Renewal of License

Current through Register Vol. 30, No. 28, July 12, 2024
A. An
				applicant shall file an application for renewal of a specific license according
				to R9-7-308.
B. If a licensee files
				a renewal application not less than 30 days before the license expiration date
				and the existing license and associated renewal application is in proper form,
				the existing license does not expire until a final renewal determination is
				made by the Department.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-316 - Amendment of Licenses at Request of Licensee

Current through Register Vol. 30, No. 28, July 12, 2024
An applicant shall file an application for amendment of a
				  specific license by complying with
				  R9-7-308 and specifying the grounds
				  for the amendment.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-317 - Department Action on Applications to Renew or Amend

Current through Register Vol. 30, No. 28, July 12, 2024
In considering an application by a licensee to renew or amend
				  a specific license, the Department shall apply the criteria set forth in
				  R9-7-309, R9-7-310, or
				  R9-7-311, as
				  applicable.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-318 - Transfer of Radioactive Material

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee shall not transfer radioactive
				material except as authorized under this Section.
B. Except as otherwise provided in the
				license and subject to the provisions of subsections (C) and (D), any licensee
				may transfer radioactive material:
1. To the
				Department, after receiving prior approval from the Department;
2. To the Department of Energy;
3. To any person exempt from the rules in
				this Article to the extent permitted under the exemption;
4. To any person authorized to receive
				radioactive material under terms of a general license or its equivalent, or a
				specific license or equivalent licensing document, issued by the Department,
				the U.S. Nuclear Regulatory Commission, or any Agreement State or Licensing
				State, or to any person otherwise authorized to receive radioactive material by
				the Federal Government or any agency of the Federal Government, the Department,
				any Agreement State or Licensing State; or
5. As otherwise authorized by the Department
				in writing.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-319 - Modification, Revocation, or Termination of a License

Current through Register Vol. 30, No. 28, July 12, 2024
A. The terms and conditions of all licenses
				are subject to amendment, revision, or modification, and a license may be
				suspended or revoked by reason of amendments to the Department's statutes or
				rules and orders issued by the Department.
B. The Department may revoke, suspend, or
				modify any license, in whole or in part, for any material false statement in
				the application; any omission or misstatement of fact required by statute,
				rule, or order, or because of conditions revealed by the application or any
				report, record, or inspection or other means that would cause the Department to
				refuse to grant a license; or any violation of license terms and conditions, or
				the Department's statutes, rules, or orders.
C. Except in cases of willfulness or those in
				which the public health, interest, or safety requires otherwise, the Department
				shall not modify, suspend, or revoke a license unless, before the institution
				of proceedings, facts or conduct that may warrant action have been called to
				the attention of the licensee in writing and the licensee has been accorded an
				opportunity to demonstrate or achieve compliance.
D. The Department may terminate a specific
				license upon a written request by the licensee that provides evidence the
				licensee has met the termination criteria in
				R9-7-451 and R9-7-452, and the
				decommissioning requirements in
				R9-7-323.
E. Specific licenses, including expired
				licenses, continue in effect until terminated by written notice to the
				licensee, when the Department determines that the licensee has:
1. Properly disposed of all radioactive
				material;
2. Made a reasonable
				effort to eliminate residual radioactive contamination, if present;
3. Performed an accurate radiation survey
				that demonstrates the premises are suitable for release in accordance with the
				criteria for decommissioning in
				R9-7-323;
4. Submitted other information that is
				sufficient to demonstrate that the premises are suitable for release in
				accordance with the criteria for decommissioning in
				R9-7-323.
5. Provided records to the Department that
				detail the disposal of all radioactive material in unsealed form with a
				half-life greater than 120 days, and copies of the records required by
				10 CFR
				30.35(g), January 1, 2004,
				which is incorporated by reference and on file with the Department. 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 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-320 - Reciprocal Recognition of Licenses

Current through Register Vol. 30, No. 28, July 12, 2024
A. This subsection grants a general license
				to perform specific licensed activities in Arizona for a period not to exceed
				days in any calendar year to any person who holds a specific license from an
				Agreement State, where the licensee maintains an office for directing the
				licensed activity and retaining radiation safety records, is granted a general
				license to conduct the same activity involving the use of radioactive material
				from the U.S. Nuclear Regulatory Commission, Licensing State, or any Agreement
				State, provided that:
1. The license does not
				limit the activity to specific installations or locations;
2. Following the first notification,
				application, and payment of fees, the licensee shall notify the Department
				three days prior to entering the state and prior to each non-consecutive visit
				while reciprocity remains in effect.
3. The out-of-state licensee complies with
				all applicable statutes, now or hereafter in effect, rules, and orders of the
				Department and with all the terms and conditions of the license, except those
				terms and conditions inconsistent with applicable statutes, rules and orders of
				the Department;
4. The out-of-state
				licensee supplies any other information the Department requests; and
5. The out-of-state licensee does not
				transfer or dispose of radioactive material possessed or used under the general
				license provided in this Section except by transfer to a person:
a. Specifically licensed by the Department or
				by the U.S. Nuclear Regulatory Commission to receive the radioactive material;
				or
b. Exempt under
				R9-7-303(A).
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-322 - The Need for an Emergency Plan for Response to a Release of Radioactive Material

Current through Register Vol. 30, No. 28, July 12, 2024
A. For
				purposes of this Section, "Emergency Plan" means a procedure that will be
				followed when an accident occurs involving licensed radioactive materials for
				which an offsite response may be needed from organizations, such as police,
				fire, or medical organizations.
B.
				Each application to possess radioactive materials in unsealed form, on foils or
				plated sources, or sealed in glass in excess of the quantities in Exhibit D,
				"Radioactive Material Quantities Requiring Consideration for an Emergency Plan"
				shall contain either:
1. An evaluation showing
				that the maximum dose to a person off-site due to a release of radioactive
				materials would not exceed 1 rem effective dose equivalent or 5 rems to the
				thyroid; or
2. An emergency plan
				for responding to a release of radioactive material.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-323 - Financial Assurance and Recordkeeping for Decommissioning

Current through Register Vol. 30, No. 28, July 12, 2024
A. For purposes of
				terminating specific licensed activities:
1.
				"Decommissioning" means to remove a radioactive material use facility safely
				from service and to reduce residual radioactivity to a level that permits
				release of the property for unrestricted use and termination of the radioactive
				material use license.
2. "Byproduct
				material" as used in 10 CFR 30, means "radioactive material" which is defined
				in A.R.S. §
										30-651.
3. "Facility" means the entire site of
				radioactive material use, or any separate building or outdoor area where it is
				used.
4. "Appendix B to Part 30" as
				used in 10 CFR 30, means Appendix E in 9 A.A.C. 7, Article 4.
5. "Financial security" means having a net
				worth of not less than $10,000.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-324 - Public Notification and Public Participation

Current through Register Vol. 30, No. 28, July 12, 2024
Upon the receipt of a license termination plan (LTP) or
				  decommissioning plan from a licensee, or a proposal by a licensee for
				  decommissioning of a site in accordance with R9-7-452(C) and (D) or for other
				  events when the Department deems a notice to be in the public interest, the
				  Department shall:
1. Notify and
				solicit comments from:
a. State and local
				governments and any Indian Nation or other indigenous people who have legal
				rights that could be affected by the decommissioning, and
b. The Arizona Department of Environmental
				Quality for cases in which the licensee proposes to decommission a site in
				accordance with R9-7-452(D).
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Section R9-7-325 - Timeliness in Decommissioning Facilities

Current through Register Vol. 30, No. 28, July 12, 2024
A. "Principal activities," as used in this
				Section, means activities authorized by the license that are essential to
				achieving the purposes for which the license was issued or amended. Storage,
				during which licensed material is not accessed for use, or disposal and other
				activities incidental to decontamination or decommissioning are not principal
				activities.
B. Each specific
				license revoked by the Department expires at midnight on the date of the
				Department's final determination to revoke the license, the expiration date
				stated in the determination, or as otherwise provided by Department
				order.
C. Each specific license
				continues in effect, beyond the expiration date if necessary, with respect to
				possession of radioactive material, until the Department notifies the licensee
				in writing that the license is terminated. During this time, the licensee
				shall:
1. Limit actions involving radioactive
				material to those related to decommissioning;
2. Continue to control entry to restricted
				areas until they are suitable for release in accordance with NRC requirements;
				and
3. Pay the applicable annual
				fee for the license category listed in R9-7-1306.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Exhibit D - Radioactive Material Quantities Requiring Consideration for an Emergency Plan (R9-7-322)

Current through Register Vol. 30, No. 28, July 12, 2024
Radioactive Material
Release Fraction
Quantity (Ci
)
Actinium-228
0.001
4,000
Americium-241
.001
2
Americium-242
.001
2
Americium-243
.001
2
Antimony-124
.01
4,000
Antimony-126
.01
6,000
Barium-133
.01
10,000
Barium-140
.01
30,000
Bismuth-207
.01
5,000
Bismuth-210
.01
600
Cadmium-109
.01
1,000
Cadmium-113
.01
80
Calcium-45
.01
20,000
Californium-252
.001
9 (20 mg)
Carbon-14 (Non CO)
.01
50,000
Cerium-141
.01
10,000
Cerium-144
.01
300
Cesium-134
.01
2,000
Cesium-137
.01
3,000
Chlorine-36
.5
100
Chromium-51
.01
300,000
Cobalt-60
.001
5,000
Copper-64
.01
200,000
Curium-242
.001
60
Curium-243
.001
3
Curium-244
.001
4
Curium-245
.001
2
Europium-152
.01
500
Europium-154
.01
400
Europium-155
.01
3,000
Gadolinium-153
.01
5,000
Germanium-68
.01
2,000
Gold-198
.01
30,000
Hafnium-172
.01
400
Hafnium-181
.01
7,000
Holmium-166m
.01
100
Hydrogen-3
.5
20,000
Indium-114m
.01
1,000
Iodine-125
.5
10
Iodine-131
.5
10
Iridium-192
.001
40,000
Iron-55
.01
40,000
Iron-59
.01
7,000
Krypton-85
1.0
6,000,000
Lead-210
.01
8
Manganese-56
.01
60,000
Mercury-203
.01
10,000
Molybdenum-99
.01
30,000
Neptunium-237
.001
2
Nickel-63
.01
20,000
Niobium-94
.01
300
Phosphorus-32
.5
100
Phosphorus-33
.5
1,000
Polonium-210
.01
10
Potassium-42
.01
9,000
Promethium-145
.01
4,000
Promethium-147
.01
4,000
Radium-226
.001
100
Ruthenium-106
.01
200
Samarium-151
.01
4,000
Scandium-46
.01
3,000
Selenium-75
.01
10,000
Silver-110m
.01
1,000
Sodium-22
.01
9,000
Sodium-24
.01
10,000
Strontium-89
.01
3,000
Strontium-90
.01
90
Sulfur-35
.5
900
Technetium-99
.01
10,000
Technetium-99m
.01
400,000
Tellurium-127m
.01
5,000
Tellurium-129m
.01
5,000
Terbium-160
.01
4,000
Thulium-170
.01
4,000
Tin-113
.01
10,000
Tin-123
.01
3,000
Tin-126
.01
1,000
Titanium-44
.01
100
Vanadium-48
.01
7,000
Xenon-133
1.0
900,000
Yttrium-91
.01
2,000
Zinc-65
.01
5,000
Zirconium-93
.01
400
Zirconium-95
.01
5,000
Any other beta-gamma emitter
.01
10,000
Mixed fission products
.01
1,000
Mixed corrosion products
.01
10,000
Contaminated equipment beta-gamma
.001
10,000
Irradiated material, any form other than solid
								non-combustible
.01
1,000
Irradiated material, solid non-combustible
.001
10,000
Mixed radioactive waste, beta-gamma
.01
1,000
Packaged mixed waste, beta gamma
.001
10,000
Any other alpha emitter
.001
2
Contaminated equipment, alpha
.0001
20
Packaged waste, alpha
.0001
20
Combinations of radioactive materials listed above:
For combinations of radioactive materials, consideration of
				  the need for an emergency plan is required if the sum of the ratios of the
				  quantity of each radioactive material authorized to the quantity listed for
				  that material in Exhibit D exceeds 1.
NOTE: Waste packaged in Type B containers does not require
				  an
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 3 - RADIOACTIVE MATERIAL LICENSING › Exhibit E - Application Information

Current through Register Vol. 30, No. 28, July 12, 2024
1.
Radioactive Material (RAM) Specific License Application
				Information
An applicant shall provide the following information in a
				  specific license application before a license is issued to the applicant. The
				  Department shall provide an application form to an applicant with a guide, when
				  possible, to ensure that correct information is provided in the
				  application:
Name and mailing address of applicant
Use location
Contact person
Telephone number
Users of RAM
Training of users
Radiation Safety Officer identity (RSO)
Duties of RSO
Description of RAM and uses
Description of radiation detection/ measurement
								instruments and their calibration
Personnel monitoring
Bioassay program
Facility description
Survey program
Leak test program
Records management program
Instruction to personnel
Waste disposal program
Emergency procedures
Procedures for ordering, receiving, and opening
								packages
Description of animal use
Licensing fee provided with application
Copy of letter-of-intent
Description of ALARA and quality management to
								local governing body
programs
Description of transportation procedures
Certifying signature
Legal structure of licensee's operation
Other licensing requirements listed in: R9-7-310,
				  R9-7-311, R9-7-312, R9-7-511,
				  R9-7-703, and R9-7-1721
2.
Radioactive Material (RAM) General License Application
				Information
An applicant shall provide the following information on a
				  registration certificate. The certificate will be validated and returned to the
				  applicant if the information provided is complete.
Name and address
Telephone number
Where will the radioactive material be used
Address of use location
Description of radioactive material use
Date
Authorizing signature and printed name
Position of person signing the form
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-401 - Purpose

Current through Register Vol. 30, No. 28, July 12, 2024
A. Article 4
				establishes standards for protection against ionizing radiation resulting from
				activities conducted according to licenses or registrations issued by the
				Department. These rules are issued according to A.R.S. Title 30, Chapter 4, as
				amended.
B. The requirements of
				Article 4 are designed to control the receipt, possession, use, transfer, and
				disposal of sources of radiation by any licensee or registrant so the total
				dose equivalent to an individual, including radiation exposure resulting from
				all sources of radiation other than radiation prescribed by a physician in the
				practice of medicine, radiation received while voluntarily participating in a
				medical research program, and background radiation, does not exceed the
				standards for protection against radiation prescribed in this Article. However,
				this Article does not limit actions that may be necessary to protect health and
				safety.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-402 - Scope

Current through Register Vol. 30, No. 28, July 12, 2024
Except as specifically provided in other Articles, Article 4
				  applies to persons licensed or registered by the Department to receive,
				  possess, use, transfer, or dispose of sources of ionizing
				  radiation.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-404 - Units and Quantities

Current through Register Vol. 30, No. 28, July 12, 2024
A.
				Each licensee or registrant shall use the Standard International (SI) units
				becquerel, gray, sievert, and coulomb per kilogram, or the special units curie,
				rad, rem, and roentgen, including multiples and subdivisions, and shall clearly
				indicate the units of all quantities on records required by this
				Article.
B. The licensee or
				registrant shall make a clear distinction among the quantities entered on the
				records required by this Article, such as, total effective dose equivalent,
				total organ dose equivalent, shallow dose equivalent, lens dose equivalent,
				deep dose equivalent, or committed effective dose equivalent.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-405 - Form of Records

Current through Register Vol. 30, No. 28, July 12, 2024
A. A
				licensee or registrant shall ensure that each record required by this Article
				is legible throughout the specified retention period. The record shall be the
				original, a reproduced copy, or a microform, provided that the copy or
				microform is authenticated by authorized personnel and that the microform is
				capable of producing a clear copy throughout the required retention period. As
				an alternative the record may be stored in electronic media capable of
				producing legible records during the required retention period. Records, such
				as letters, drawings, and specifications, shall include all pertinent
				information, such as stamps, initials, and signatures. A licensee or registrant
				shall maintain adequate safeguards against tampering with and loss of
				records.
B. In the records required
				by this Article, a licensee or registrant may record quantities in SI units in
				parentheses following each of the required units, curie, rad, and rem, and
				include multiples and subdivisions.
C. Notwithstanding subsection (B), the
				licensee or registrant shall ensure that information is recorded in the
				International System of Units (SI) or in SI and the units specified in
				subsection (B) on each shipment manifest as required in R9-7-439(A).
D. A licensee or registrant shall make a
				clear distinction among the quantities entered on the records required by this
				Section (e.g., total effective dose equivalent, shallow-dose equivalent, lens
				dose equivalent, deep-dose equivalent, committed effective dose
				equivalent).
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-406 - Implementation

Current through Register Vol. 30, No. 28, July 12, 2024
Any existing license or registration condition that is more
				  restrictive than this Article remains in force until amendment or renewal of
				  the license or registration.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-407 - Radiation Protection Programs

Current through Register Vol. 30, No. 28, July 12, 2024
A. Each licensee or registrant shall develop,
				document, and implement a radiation protection program sufficient to ensure
				compliance with the provisions of Article 4.
B. The licensee or registrant shall use, to
				the extent practical, procedures and engineering controls based upon sound
				radiation protection principles to achieve occupational doses and public doses
				that are as low as is reasonably achievable (ALARA).
C. The licensee or registrant shall, at
				intervals not to exceed 12 months, review the radiation protection program
				content and implementation.
D. To
				implement the ALARA requirements in subsection (B), and notwithstanding the
				requirements in
				R9-7-416, each licensee or
				registrant governed by 9 A.A.C. 7, Article 3 shall limit air emissions of
				radioactive material to the environment so that individual members of the
				public likely to receive the highest dose will not receive a total effective
				dose equivalent in excess of 0.1mSv (10 mrem) per year from the emissions. If a
				licensee or registrant subject to this requirement exceeds this limit, the
				licensee or registrant shall report the incident to the Department, in
				accordance with R9-7-444, and take prompt corrective action to prevent
				additional violations.
E. Records.
1. Each licensee or registrant shall maintain
				records of the radiation protection program, including:
a. The provisions of the program; and
b. Audits and other reviews of
				program content and implementation.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-408 - Occupational Dose Limits for Adults

Current through Register Vol. 30, No. 28, July 12, 2024
A. Each licensee or registrant shall control
				the occupational dose to individual adults, except for planned special
				exposures required in
				R9-7-413, to the following dose
				limits:
1. An annual limit, which is the more
				limiting of:
a. The total effective dose
				equivalent being equal to 0.05 Sv (5 rem): or
b. The sum of the deep-dose equivalent and
				the committed dose equivalent to any individual organ or tissue other than the
				lens of the eye being equal to 0.5 Sv (50 rem).
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-409 - Summation of External and Internal Doses

Current through Register Vol. 30, No. 28, July 12, 2024
A. If a licensee or registrant is required to
				monitor according to both
				R9-7-419(B) and
				(C), the licensee or registrant shall add
				external and internal doses, and use the sum to demonstrate compliance with
				dose limits. If the licensee or registrant is required to monitor only
				according to
				R9-7-419(B) or
				only according to
				R9-7-419(C),
				summation is not required to demonstrate compliance with dose limits. The
				licensee or registrant may demonstrate compliance with the requirements for
				summation of external and internal doses according to subsections (B), (C), and
				(D). The dose equivalents for the lens of the eye, the skin, and the
				extremities are not included in the summation but are subject to separate
				limits (See
				R9-7-408(A)(2)
				).
B. If the only intake of
				radionuclides is by inhalation, the total effective dose equivalent limit is
				not exceeded if the sum of the deep-dose equivalent divided by the total
				effective dose equivalent limit, and one of the following, does not exceed
				unity (1):
1. The sum of the fractions of the
				inhalation ALI for each radionuclide, or
2. The total number of derived air
				concentration-hours (DAC-hours) for all radionuclides divided by 2,000,
				or
3. The sum of the calculated
				committed effective dose equivalents to all significantly irradiated organs or
				tissues (T) calculated from bioassay data using applicable biological models
				and expressed as a fraction of the annual limit. For purposes of this
				requirement, an organ or tissue is deemed to be significantly irradiated if,
				for that organ or tissue, the product of the weighting factors,
				WT, and the committed dose equivalent,
				HT,50, per unit intake is greater than 10% of the
				maximum weighted value of HT,50, that is,
				wTHT,50, per unit intake for any
				organ or tissue.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-410 - Determination of External Dose from Airborne Radioactive Material

Current through Register Vol. 30, No. 28, July 12, 2024
A. Each licensee
				shall, when determining the dose from airborne radioactive material, include
				the contribution to the deep-dose equivalent, lens dose equivalent, and shallow
				dose equivalent from external exposure to the radioactive cloud. See Appendix
				B, footnotes 1 and 2.
B. Airborne
				radioactivity measurements and DAC values shall not be used as the primary
				means to assess the deep-dose equivalent when the airborne radioactive material
				includes radionuclides other than noble gases or if the cloud of airborne
				radioactive material is not relatively uniform. The determination of the
				deep-dose equivalent to an individual shall be based upon measurements using
				instruments or individual monitoring devices.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-411 - Determination of Internal Exposure

Current through Register Vol. 30, No. 28, July 12, 2024
A. For purposes of assessing dose used to
				determine compliance with occupational dose equivalent limits, each licensee or
				registrant shall, when required according to
				R9-7-419, take suitable and timely
				measurements of:
1. Concentrations of
				radioactive materials in air in work areas,
2. Quantities of radionuclides in the
				body,
3. Quantities of
				radionuclides excreted from the body, or
4. Combinations of these
				measurements,
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-412 - Determination of Prior Occupational Dose

Current through Register Vol. 30, No. 28, July 12, 2024
A. For each individual who is likely to
				receive in a year an occupational dose that requires monitoring according to
				R9-7-419 the licensee shall:
1. Determine the occupational radiation dose
				received during the current year, and
2. Attempt to obtain the records of lifetime
				cumulative occupational radiation dose.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-413 - Planned Special Exposures

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee or registrant may authorize an
				adult worker to receive doses in addition to and accounted for separately from
				the doses received under the limits specified in
				R9-7-408, provided that each of the
				following conditions is satisfied:
1. The
				licensee or registrant authorizes a planned special exposure only in an
				exceptional situation when alternatives that might avoid the dose estimated
				from the planned special exposure are unavailable or impractical.
2. The licensee or registrant, and employer
				if the employer is not the licensee or registrant, specifically authorizes the
				planned special exposure, in writing, before the exposure occurs.
3. Before a planned special exposure, the
				licensee or registrant ensures that each individual involved is:
a. Informed in writing of the purpose of the
				planned special exposure;
b.
				Informed in writing of the estimated doses, associated potential risks, and
				specific radiation levels or other conditions that might be involved in
				performing the task; and
c.
				Instructed in the measures to be taken to keep the dose ALARA, considering
				other risks that may be present.
4. Before permitting an individual to
				participate in a planned special exposure, the licensee or registrant shall
				ascertain prior doses as required by R9-7-412(B) for each individual
				involved.
5. Subject to
				R9-7-408(B), the licensee or registrant shall not authorize a planned special
				exposure that would cause an individual to receive a dose from all planned
				special exposures and all doses that exceed:
a. The numerical value of any of the dose
				limits in R9-7-408(A) in any
				year, and
b. Five times the annual
				dose limits in
				R9-7-408(A) during
				the individual's lifetime.
6. The licensee or registrant shall maintain
				records of a planned special exposure in accordance with subsections (B) and
				(C) and submit a written report to the Department within 30 days after the date
				of any planned special exposure conducted in accordance with this Section,
				informing the Department that a planned special exposure was conducted and
				indicating the date the planned special exposure occurred and the information
				required by subsection (B).
7. The
				licensee or registrant shall record the best estimate of the dose resulting
				from the planned special exposure in the individual's record and inform the
				individual, in writing, of the dose within 30 days after the date of the
				planned special exposure. The dose from a planned special exposure shall not be
				considered in controlling future occupational dose of the individual according
				to R9-7-408(A) but
				shall be included in evaluations required by subsections (A)(4) and
				(A)(5).
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-414 - Occupational Dose Limits for Minors

Current through Register Vol. 30, No. 28, July 12, 2024
The annual occupational dose limits for minors are 10% of the
				  annual occupational dose limits specified for adult workers in
				  R9-7-408.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-415 - Dose Equivalent to an Embryo or Fetus

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee or registrant shall ensure that
				the dose equivalent to an embryo or fetus during the entire pregnancy, due to
				occupational exposure of a declared pregnant woman, does not exceed 5 mSv (0.5
				rem). Records shall be maintained according to
				R9-7-419(E)(4) and
				(5).
B. The licensee or registrant shall make
				efforts to avoid substantial variation above a uniform monthly exposure rate to
				a declared pregnant woman to satisfy the limit in subsection (A).
C. For purposes of this Section, the dose
				equivalent to the embryo or fetus is the sum of:
1. The deep-dose equivalent to the declared
				pregnant woman; and
2. The dose
				equivalent to the embryo or fetus resulting from radionuclides in the embryo or
				fetus and radionuclides in the declared pregnant woman.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-416 - Dose Limits for Individual Members of the Public

Current through Register Vol. 30, No. 28, July 12, 2024
A. Each licensee or registrant shall conduct
				operations so that:
1. The total effective
				dose equivalent to any individual member of the public from the licensed or
				registered operation does not exceed 1 mSv (0.1 rem) in a year, excluding the
				dose contribution from background radiation, medical administration of
				radiation, exposure to an individual who has been administered radioactive
				material and released in accordance with
				R9-7-719, voluntary participation
				in a medical research program, and the licensee's or registrant's disposal of
				radioactive material into sanitary sewerage in accordance with R9-7-436;
				and
2. The dose in any unrestricted
				area from an external source excluding the dose contribution from an individual
				who has been administered radioactive material and released in accordance with
				R9-7-719, does not exceed 0.02 mSv
				(0.002 rem) in any 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 R9-7-417 - Testing for Leakage or Contamination of Sealed Sources

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee in possession of any sealed
				source shall ensure that:
1. Each sealed
				source, except as specified in subsection (B), is tested for leakage or
				contamination and the test results are received before the sealed source is put
				into use unless the licensee has a certificate from the transferor indicating
				that the sealed source was tested within six months before transfer to the
				licensee or registrant.
2. Each
				sealed source that is not designed to emit alpha particles is tested for
				leakage or contamination at intervals not to exceed six months or at
				alternative intervals approved by the Department, after evaluation of
				information specified by
				R9-7-311(D)(2) or
				equivalent information specified by an Agreement State, a Licensing State, or
				the U.S. Nuclear Regulatory Commission.
3. Each sealed source that is designed to
				emit alpha particles is tested for leakage or contamination at intervals not to
				exceed three months or at alternative intervals approved by the Department,
				after evaluation of information specified by
				R9-7-311(D)(2) or
				equivalent information specified by an Agreement State, a Licensing State, or
				the Nuclear Regulatory Commission.
4. Each sealed source suspected of damage or
				leakage is tested for leakage or contamination before further use.
5. Tests for leakage for all sealed sources,
				except brachytherapy sources manufactured to contain radium, are capable of
				detecting the presence of 185 Bq (0.005 µCi) of radioactive material on a test
				sample. The person conducting the test shall take test samples from the sealed
				source or from the surfaces of the container in which the sealed source is
				stored or mounted on which contamination could accumulate. For a sealed source
				contained in a device, the person conducting the test shall obtain test samples
				when the source is in the "off" position.
6. The test for leakage from brachytherapy
				sources containing radium is capable of detecting an absolute leakage rate of
				37 Bq (0.001 µCi) of Radon-222 in a 24-hour period when the collection
				efficiency for Radon-222 and its daughters has been determined with respect to
				collection method, volume, and time.
7. Tests for contamination from radium
				daughters are taken on the interior surface of brachytherapy source storage
				containers and are capable of detecting the presence of 185 Bq (0.005 µCi) of a
				radium daughter which has a half-life greater than four days.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-418 - Surveys and Monitoring

Current through Register Vol. 30, No. 28, July 12, 2024
A.
				Each licensee or registrant shall make, or cause to be made, surveys if surveys
				are:
1. Necessary for the licensee or
				registrant to comply with Article 4, and
2. Reasonable under the circumstances to
				evaluate:
a. The magnitude and extent of
				radiation levels, and
b.
				Concentrations or quantities of residual radioactivity, and
c. The potential radiological hazards of the
				radiation levels and residual radioactivity detected.
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-419 - Conditions Requiring Individual Monitoring of External and Internal Occupational Dose

Current through Register Vol. 30, No. 28, July 12, 2024
A.
				Each licensee or registrant shall monitor exposures from sources of radiation
				at levels sufficient to demonstrate compliance with the occupational dose
				limits of this Article.
B. At
				minimum each licensee or registrant shall supply and require the use of
				individual monitoring devices by the following personnel:
1. Adults likely to receive, in one year, an
				intake in excess of 10% of the applicable ALI in Table I, Columns 1 and 2, of
				Appendix B;
2. Minors and declared
				pregnant women likely to receive, in one year, a committed effective dose
				equivalent in excess of 0.5 mSv (0.05 rem);
3. Adults likely to receive, in one year from
				radiation sources external to the body, a dose in excess of 10 percent of the
				limits in R9-7-408(A);
4. Minors likely to receive, in one year,
				from radiation sources external to the body, a deep dose equivalent in excess
				of 1 mSv (0.1 rem), a lens dose equivalent in excess of 1.5 mSv (0.15 rem), or
				a shallow dose equivalent to the skin or to the extremities in excess of 5 mSv
				(0.5 rem);
5. Declared pregnant
				women likely to receive during the entire pregnancy, from radiation sources
				external to the body, a deep dose equivalent in excess of 1 mSv (0.1 rem)
				(Note: All of the occupational doses in
				R9-7-408 continue to be applicable
				to the declared pregnant worker as long as the embryo/fetus dose limit is not
				exceeded.);
6. Individuals entering
				a high or very high radiation area;
7. Individuals operating mobile x-ray
				equipment as described in R9-7-608;
8. Individuals holding animals for diagnostic
				x-ray procedures, as described in
				R9-7-613;
9. Individuals servicing enclosed beam x-ray
				systems with bypassed interlocks, as described in R9-7-803;
10. Individuals operating open beam
				fluoroscopic systems and ancillary personnel working in the room when the
				fluoroscopic system is in use, except when relieved of this requirement by
				registration condition;
11.
				Individuals performing well logging, as described in Article 17;
12. Individuals, wearing a finger or wrist
				individual monitoring device, during the operation of an open-beam or hand held
				analytical x-ray system or equipment with no safety devices as described in
				R9-7-806(C) and (F); and
13.
				Individuals, wearing a finger or wrist individual monitoring device, performing
				repairs that require the presence of a primary beam of the analytical x-ray
				system or equipment, as described in R9-7-806(C) and (F).
Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 4 - STANDARDS FOR PROTECTION AGAINST IONIZING RADIATION › Section R9-7-420 - Control of Access to High Radiation Areas

Current through Register Vol. 30, No. 28, July 12, 2024
A. A licensee or registrant shall ensure that
				each entrance or access point to a high radiation area has one or more of the
				following features:
1. A control device that,
				upon entry into the area, causes the level of radiation to be reduced below the
				level at which an individual might receive a deep-dose equivalent of 1 mSv (0.1
				rem) in one hour at 30 centimeters from the source from any surface that the
				radiation penetrates;
2. A control
				device that energizes a conspicuous visible or audible alarm signal so that the
				individual entering the high radiation area and the supervisor of the activity
				are made aware of the entry; or
3.
				Entryways that are locked, except during periods when access to the areas is
				required, with positive control over each individual
				entity.