R313-19. Requirements of General Applicability to Licensing of Radioactive Material  


R313-19-1. Purpose and Authority
Latest version.

  (1) The purpose of this rule is to prescribe requirements governing the licensing of radioactive material. This rule also gives notice to all persons who knowingly provide to any licensee, applicant, certificate of registration holder, contractor, or subcontractor, components, equipment, materials, or other goods or services, that relate to a licensee's, applicant's or certificate of registration holder's activities subject to these rules, that they may be individually subject to Director enforcement action for violation of Section R313-19-5.

  (2) The rules set forth herein are adopted pursuant to the provisions of Subsections 19-3-104(4) and 19-3-104(7).


R313-19-2. General
Latest version.

  (1) A person shall not manufacture, produce, receive, possess, use, transfer, own or acquire radioactive material except as authorized in a specific or general license issued pursuant to Rules R313-21 or R313-22 or as otherwise provided in Rule R313-19.

  (2) In addition to the requirements of Rules R313-19, R313-21 or R313-22, all licensees are subject to the requirements of Rules R313-12, R313-15, and R313-18. Licensees engaged in source material milling operations, authorized to possess byproduct material, as defined in Section R313-12-3 (see definition (b)) from source material milling operations, authorized to possess and maintain a source material milling facility in standby mode, authorized to receive byproduct material from other persons for disposal, or authorized to possess and dispose of byproduct material generated by source material milling operations are subject to the requirements of Rule R313-24. Licensees engaged in land disposal of radioactive material are subject to the requirements of Rule R313-25. Licensees using radioactive material in the healing arts are subject to the requirements of Rule R313-32. Licensees authorized to use sealed sources containing radioactive materials in panoramic irradiators with dry or wet storage of radioactive sealed sources, underwater irradiators, or irradiators with high dose rates from radioactive sealed sources are subject to the requirements of Rule R313-34. Licensees engaged in industrial radiographic operations are subject to the requirements of Rule R313-36. Licensees possessing category 1 or category 2 quantities of radioactive material, as defined in Section R313-37-3 (incorporating 10 CFR 37.5 by reference), are subject to the physical protection requirements of Rule R313-37. Licensees engaged in wireline and subsurface tracer studies are subject to the requirements of Rule R313-38.


R313-19-5. Deliberate Misconduct
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(1) Any licensee, certificate of registration holder, applicant for a license or certificate of registration, employee of a licensee, certificate of registration holder or applicant; or any contractor, including a supplier or consultant, subcontractor, employee of a contractor or subcontractor of any licensee or certificate of registration holder or applicant for a license or certificate of registration, who knowingly provides to any licensee, applicant, certificate holder, contractor, or subcontractor, any components, equipment, materials, or other goods or services that relate to a licensee's, certificate holder's or applicant's activities in these rules, may not:

(a) Engage in deliberate misconduct that causes or would have caused, if not detected, a licensee, certificate of registration holder, or applicant to be in violation of any rule or order; or any term, condition, or limitation of any license issued by the Director; or

(b) Deliberately submit to the Director, a licensee, certificate of registration holder, an applicant, or a licensee's, certificate holder's or applicant's, contractor or subcontractor, information that the person submitting the information knows to be incomplete or inaccurate in some respect material to the Director.

(2) A person who violates Subsections R313-19-5(1)(a) or (b) may be subject to enforcement action in accordance with Rule R313-14.

(3) For the purposes of Subsection R313-19-5(1)(a), deliberate misconduct by a person means an intentional act or omission that the person knows:

(a) Would cause a licensee, certificate of registration holder or applicant to be in violation of any rule or order; or any term, condition, or limitation, of any license issued by the Director; or

(b) Constitutes a violation of a requirement, procedure, instruction, contract, purchase order, or policy of a licensee, certificate of registration holder, applicant, contractor, or subcontractor.


R313-19-7. Carriers
Latest version.

  Common and contract carriers, freight forwarders, warehousemen, and the U.S. Postal Service are exempt from the regulations in Rules R313-19, R313-21, R313-22, R313-32, R313-34, R313-36, R313-37, and R313-38 and the requirements for a license set forth in Subsection 19-3-104(3) to the extent that they transport or store radioactive material in the regular course of carriage for another or storage incident thereto.


R313-19-13. Exemptions
Latest version.

  (1) Source material.

  (a) A person is exempt from Rules R313-19, R313-21, and R313-22 to the extent that the person receives, possesses, uses, owns, or transfers source material in a chemical mixture, compound, solution or alloy in which the source material is by weight less than 1/20 of one percent (0.05 percent) of the mixture, compound, solution, or alloy.

  (b) A person is exempt from Rules R313-19, R313-21, and R313-22 to the extent that the person receives, possesses, uses or transfers unrefined and unprocessed ore containing source material; provided, that, except as authorized in a specific license, such person shall not refine or process the ore.

  (c) A person is exempt from the requirements in Rules R313-15, R313-18, R313-19, R313-21, and R313-22 to the extent that the person receives, possesses, uses or transfers:

  (i) any quantities of thorium contained in:

  (A) incandescent gas mantles,

  (B) vacuum tubes,

  (C) welding rods,

  (D) electric lamps for illuminating purposes: provided that, each lamp does not contain more than 50 milligrams of thorium,

  (E) germicidal lamps, sunlamps, and lamps for outdoor or industrial lighting provided that each lamp does not contain more than two grams of thorium,

  (F) rare earth metals and compounds, mixtures, and products containing not more than 0.25 percent by weight thorium, uranium, or any combination of these, or

  (G) personnel neutron dosimeters provided that each dosimeter does not contain more than 50 milligrams of thorium;

  (ii) source material contained in the following products:

  (A) glazed ceramic tableware manufactured before October 16, 2017, provided that the glaze contains not more than 20 percent by weight source material;

  (B) piezoelectric ceramic containing not more than two percent by weight source material; or

  (C) glassware containing not more than two percent by weight source material or, for glassware manufactured before October 16, 2017, not more than ten percent by weight source material, but not including commercially manufactured glass brick, pane glass, ceramic tile, or other glass or ceramic used in construction;

  (iii) photographic film, negatives and prints containing uranium or thorium;

  (iv) a finished product or part fabricated of, or containing, tungsten-thorium or magnesium-thorium alloys, provided that the thorium content of the alloy does not exceed four percent by weight and that this exemption shall not be deemed to authorize the chemical, physical, or metallurgical treatment or processing of the product or part;

  (v) uranium contained in counterweights installed in aircraft, rockets, projectiles, and missiles, or stored or handled in connection with installation or removal of the counterweights, provided that:

  (A) each counterweight has been impressed with the following legend clearly legible through any plating or other covering: "DEPLETED URANIUM",

  (B) each counterweight is durably and legibly labeled or marked with the identification of the manufacturer and the statement: "UNAUTHORIZED ALTERATIONS PROHIBITED",

  (C) The requirements specified in Subsections R313-19-13(1)(c)(v)(A) and (B) need not be met by counterweights manufactured prior to December 31, 1969, provided that such counterweights were manufactured under a specific license issued by the Atomic Energy Commission and were impressed with the legend, "CAUTION - RADIOACTIVE MATERIAL - URANIUM", as previously required by the rules in effect on June 30, 1969, and

  (E) the exemption contained in Subsection R313-19-13(1)(c)(v) shall not be deemed to authorize the chemical, physical, or metallurgical treatment or processing of any such counterweights other than repair or restoration of any plating or other covering;

  (vi) natural or depleted uranium metal used as shielding constituting part of a shipping container which is conspicuously and legibly impressed with the legend "CAUTION - RADIOACTIVE SHIELDING - URANIUM" and the uranium metal is encased in mild steel or equally fire resistant metal of minimum wall thickness of one eighth inch (3.2 mm);

  (vii) thorium or uranium contained in or on finished optical lenses and mirrors, provided that each lens or mirror does not contain more than 10 percent by weight thorium or uranium or, for lenses manufactured before October 16, 2017, 30 percent by weight of thorium, and that this exemption shall not be deemed to authorize either:

  (A) the shaping, grinding, or polishing of a lens or manufacturing processes other than the assembly of such lens into optical systems and devices without alteration of the lens, or

  (B) the receipt, possession, use, or transfer of thorium contained in contact lenses, or in spectacles, or in eyepieces in binoculars or other optical instruments;

  (viii) thorium contained in a finished aircraft engine part containing nickel-thoria alloy, provided that:

  (A) the thorium is dispersed in the nickel-thoria alloy in the form of finely divided thoria (thorium dioxide), and

  (B) the thorium content in the nickel-thoria alloy does not exceed four percent by weight.

  (ix) No person may initially transfer for sale or distribution a product containing source material to persons exempt under Subsection R313-19-13(1)(c), or equivalent regulations of an Agreement State, unless authorized by a license issued under 10 CFR 40.52 to initially transfer such products for sale or distribution.

  (A) A person initially distributing source material in products covered by the exemptions in this Subsection R313-19-13(1)(c) before (Utah effective date to be set by the Board), without specific authorization may continue such distribution for one year beyond this date. Initial distribution may also be continued until the director takes final action on a pending application for license or license amendment to specifically authorize distribution submitted no later than one year beyond this date.

  (B) A person authorized to manufacture, process, or produce these materials or products containing source material by an Agreement State, and a person who imports finished products or parts, for sale or distribution must be authorized by a license issued under 10 CFR 40.52 for distribution only and are exempt from the requirements of Rules R313-15 and R313-18 and Subsections R313-22-33(1)(a) and (b).

  (d) The exemptions in Subsection R313-19-13(1)(c) do not authorize the manufacture of any of the products described.

  (2) Radioactive material other than source material.

  (a) Exempt concentrations.

  (i) Except as provided in Subsection R313-19-13(2)(a)(iii) a person is exempt from Rules R313-19, R313-21 and R313-22 to the extent that the person receives, possesses, uses, transfers, owns or acquires products or materials containing:

  (A) radioactive material introduced in concentrations not in excess of those listed in Section R313-19-70, or

  (B) diffuse sources of natural occurring radioactive materials containing less than 15 picocuries per gram radium-226.

  (ii) A manufacturer, processor, or producer of a product or material is exempt from the requirements for a license set forth in Rules R313-19, R313-21 and R313-22 and Rules R313-32, R313-34, R313-36, and R313-38 to the extent that the person transfers:

  (A) radioactive material contained in a product or material in concentrations not in excess of those specified in R313-19-70; and

  (B) introduced into the product or material by a licensee holding a specific license issued by the U.S. Nuclear Regulatory Commission authorizing the introduction.

  (C) The exemption in R313-19-13-2(a)(ii)(A) and R313-19-13-2(a)(ii)(B) does not apply to the transfer of radioactive material contained in any food, beverage, cosmetic, drug, or other commodity or product designed for ingestion or inhalation by, or application to, a human being.

  (iii) A person may not introduce radioactive material into a product or material knowing or having reason to believe that it will be transferred to persons exempt under Subsection R313-19-13(2)(a)(i) or equivalent regulations of a Licensing State, the U.S. Nuclear Regulatory Commission or an Agreement State, except in accordance with a specific license issued pursuant to Subsection R313-22-75(1).

  (b) Exempt quantities.

  (i) Except as provided in Subsections R313-19-13(2)(b)(ii) through (iv) a person is exempt from these rules to the extent that the person receives, possesses, uses, transfers, owns, or acquires radioactive material in individual quantities which do not exceed the applicable quantity set forth in Section R313-19-71.

  (ii) Subsection R313-19-13(2)(b) does not authorize the production, packaging or repackaging of radioactive material for purposes of commercial distribution, or the incorporation of radioactive material into products intended for commercial distribution.

  (iii) A person may not, for purposes of commercial distribution, transfer radioactive material in the individual quantities set forth in Section R313-19-71, knowing or having reason to believe that the quantities of radioactive material will be transferred to persons exempt under Subsection R313-19-13(2)(b) or equivalent regulations of a Licensing State, the U.S. Nuclear Regulatory Commission or an Agreement State, except in accordance with a specific license issued by the U.S. Nuclear Regulatory Commission, pursuant to 10 CFR Part 32 or by the Director pursuant to Subsection R313-22-75(2), which license states that the radioactive material may be transferred by the licensee to persons exempt under Subsection R313-19-13(2)(b) or the equivalent regulations of a Licensing State, the U.S. Nuclear Regulatory Commission or an Agreement State.

  (iv) A person who possesses radioactive material received or acquired prior to September 25, 1971, under the general license formerly provided in 10 CFR Part 31.4 or equivalent regulations of a State is exempt from the requirements for a license set forth in Rule R313-19 to the extent that the person possesses, uses, transfers or owns radioactive material. This exemption does not apply for diffuse sources of radium-226.

  (v) No person may, for purposes of producing an increased radiation level, combine quantities of radioactive material covered by this exemption so that the aggregate quantity exceeds the limits set forth in R313-19-71, except for radioactive material combined within a device placed in use before May 3, 1999, or as otherwise provided by these rules.

  (c) Exempt items.

  (i) Certain items containing radioactive material. Except for persons who apply radioactive material to, or persons who incorporate radioactive material into the following products, a person is exempt from these rules to the extent that person receives, possesses, uses, transfers, owns or acquires the following products:

  (A) Timepieces or hands or dials containing not more than the following specified quantities of radioactive material and not exceeding the following specified levels of radiation:

  (I) 25 millicuries (925.0 MBq) of tritium per timepiece;

  (II) five millicuries (185.0 MBq) of tritium per hand;

  (III) 15 millicuries (555.0 MBq) of tritium per dial. Bezels when used shall be considered as part of the dial;

  (IV) 100 microcuries (3.7 MBq) of promethium-147 per watch or 200 microcuries (7.4 MBq) of promethium-147 per any other timepiece;

  (V) 20 microcuries (0.74 MBq) of promethium-147 per watch hand or 40 microcuries (1.48 MBq) of promethium-147 per other timepiece hand;

  (VI) 60 microcuries (2.22 MBq) of promethium-147 per watch dial or 120 microcuries (4.44 MBq) of promethium-147 per other timepiece dial. Bezels when used shall be considered as part of the dial;

  (VII) the radiation dose rate from hands and dials containing promethium-147 will not exceed, when measured through 50 milligrams per square centimeter of absorber:

  for wrist watches, 0.1 millirad (1.0 uGy) per hour at ten centimeters from any surface;

  for pocket watches, 0.1 millirad (1.0 uGy) per hour at one centimeter from any surface;

  for other timepieces, 0.2 millirad (2.0 uGy) per hour at ten centimeters from any surface;

  (VIII) one microcurie (37.0 kBq) of radium-226 per timepiece in timepieces manufactured prior to November 30, 2007.

  (B)(I) Static elimination devices which contain, as sealed source or sources, radioactive material consisting of a total of not more than 18.5 MBq (500 uCi) of polonium-210 per device.

  (II) Ion generating tubes designed for ionization of air that contain, as a sealed source or sources, byproduct material consisting of a total of not more than 18.5 MBq (500 uCi) of polonium-210 per device or of a total of not more than 1.85 GBq (50 mCi) of hydrogen-3 (tritium) per device.

  (III) Such devices authorized before October 23, 2012 for use under the general license then provided in 10 CFR 31.3 (January 1, 2012) or equivalent regulations of the Commission or an Agreement State and manufactured, tested, and labeled by the manufacturer in accordance with the specifications contained in a specific license issued by the Commission or Agreement State.

  (C) Precision balances containing not more than one millicurie (37.0 MBq) of tritium per balance or not more than 0.5 millicurie (18.5 MBq) of tritium per balance part manufactured before June 9, 2010.

  (D) Marine compasses containing not more than 750 millicuries (27.8 GBq) of tritium gas and other marine navigational instruments containing not more than 250 millicuries (9.25 GBq) of tritium gas manufactured before June 9, 2010.

  (E) Ionization chamber smoke detectors containing not more than 1 microcurie (37 kBq) of americium-241 per detector in the form of a foil and designed to protect life and property from fires.

  (F) Electron tubes, including spark gap tubes, power tubes, gas tubes including glow lamps, receiving tubes, microwave tubes, indicator tubes, pick-up tubes, radiation detection tubes, and other completely sealed tubes that are designed to conduct or control electrical currents; provided that each tube does not contain more than one of the following specified quantities of radioactive material:

  (I) 150 millicuries (5.55 GBq) of tritium per microwave receiver protector tube or ten millicuries (370.0 MBq) of tritium per any other electron tube;

  (II) one microcurie (37.0 kBq) of cobalt-60;

  (III) five microcuries (185.0 kBq) of nickel-63;

  (IV) 30 microcuries (1.11 MBq) of krypton-85;

  (V) five microcuries (185.0 kBq) of cesium-137;

  (VI) 30 microcuries (1.11 MBq) of promethium-147;

  (VII) one microcurie (37.0 kBq) of radium-226;

  and provided further, that the radiation dose rate from each electron tube containing radioactive material will not exceed one millirad (10.0 uGy) per hour at one centimeter from any surface when measured through seven milligrams per square centimeter of absorber.

  (G) Ionizing radiation measuring instruments containing, for purposes of internal calibration or standardization, one or more sources of radioactive material, provided that:

  (I) each source contains no more than one exempt quantity set forth in Section R313-19-71; and

  (II) each instrument contains no more than ten exempt quantities. For purposes of this requirement, an instrument's source(s) may contain either one type or different types of radionuclides and an individual exempt quantity may be composed of fractional parts of one or more of exempt quantities in Section R313-19-71, provided that the sum of the fractions shall not exceed unity;

  (III) for purposes of Subsection R313-19-13(2)(c)(i)(G), 0.05 microcurie (1.85 kBq) of americium-241 is considered an exempt quantity under Section R313-19-71.

  (ii) Self-luminous products containing radioactive material.

  (A) Except for persons who manufacture, process, produce, or initially transfer for sale or distribution self-luminous products containing tritium, krypton-85, or promethium-147, and except as provided in R313-19-13(2)(c)(ii)(C), any person is exempt from the regulations in R313-15, R313-19, R313-21, R313-22, R313-32, R313-34, R313-36, and R313-38 to the extent that such a person receives, possesses, uses, transfers, owns, or acquires tritium, krypton-85, or promethium-147 in self-luminous products manufactured, processed, produced, or initially transferred in accordance with a specific license issued pursuant to 10 CFR 32.22 (2015), which license authorizes the initial transfer of the product for use.

  (B) Any person who desires to manufacture, process, or produce, or initially transfer for sale or distribution self-luminous products containing tritium, krypton-85, or promethium-147 for use under R313-19-13(2)(c)(ii)(A), should apply for a license under 10 CFR 32.22 (2015) and for a certificate of registration in accordance with 10 CFR 32.210 (2015).

  (C) The exemption in R313-19-13(2)(c)(ii)(A) does not apply to tritium, krypton-85, or promethium-147 used in products primarily for frivolous purposes or in toys or adornments.

  (D) Radium-226. A person is exempt from these rules, to the extent that such person receives, possesses, uses, transfers, or owns articles containing less than 0.1 microcurie (3.7 kBq) of radium-226 which were acquired prior to the effective date of these rules.

  (iii) Gas and aerosol detectors containing radioactive material.

  (A) Except for persons who manufacture, process, produce, or initially transfer for sale or distribution gas and aerosol detectors containing radioactive material, any person is exempt from the regulations in parts R313-18, R313-15, R313-19, R313-21, R313-22, R313-32, R313-34, R313-36, and R313-38 to the extent that such person receives, possesses, uses, transfers, owns, or acquires byproduct material in gas and aerosol detectors designed to protect health, safety, or property, and manufactured, processed, produced, or initially transferred in accordance with a specific license issued under 10 CFR 32.26 (2015), which license authorizes the initial transfer of the product for use under this section. This exemption also covers gas and aerosol detectors manufactured or distributed before November 30, 2007, in accordance with a specific license issued by a State under comparable provisions to 10 CFR 32.26 (2015) authorizing distribution to persons exempt from regulatory requirements.

  (B) Any person who desires to manufacture, process, or produce gas and aerosol detectors containing byproduct material, or to initially transfer such products for use under paragraph (a)of this section, should apply for a specific license issued by the U.S. Nuclear Regulatory Commission pursuant to 10 CFR Part 32.26 (2015) and for a certificate of registration in accordance with R313-22-210 or equivalent regulations of an Agreement State.

  (iv) Capsules containing carbon-14 urea for "in vivo" diagnostic use for humans.

  (A) Except as provided in Subsection R313-19-13(2)(c)(iv)(B), any person is exempt from the requirements in Rules R313-19 and R313-32 provided that the person receives, possesses, uses, transfers, owns, or acquires capsules containing 37 kBq (1 uCi) carbon-14 urea (allowing for nominal variation that may occur during the manufacturing process) each, for "in vivo" diagnostic use for humans.

  (B) Any person who desires to use the capsules for research involving human subjects shall apply for and receive a specific license pursuant to Rule R313-32.

  (C) Nothing in Subsection R313-19-13(2)(c)(iv) relieves persons from complying with applicable United States Food and Drug Administration, other Federal, and State requirements governing receipt, administration, and use of drugs.

  (v) Certain industrial devices.

  (A) Except for persons who manufacture, process, produce, or initially transfer for sale or distribution industrial devices containing radioactive material designed and manufactured for the purpose of detecting, measuring, gauging or controlling thickness, density, level, interface location, radiation, leakage, or qualitative or quantitative chemical composition, or for producing an ionized atmosphere, any person is exempt from the regulations in parts R313-18, R313-15, R313-18, R313-15, R313-19, R313-21, R313-22, R313-32, R313-34, R313-36, and R313-38 to the extent that such person receives, possesses, uses, transfers, owns, or acquires radioactive material, in these certain detecting, measuring, gauging, or controlling devices and certain devices for producing an ionized atmosphere, and manufactured, processed, produced, or initially transferred in accordance with a specific license issued under 10 CFR 32.30 (2015), which license authorizes the initial transfer of the device for use under this rule. This exemption does not cover sources not incorporated into a device, such as calibration and reference sources.

  (B) Any person who desires to manufacture, process, produce, or initially transfer for sale or distribution industrial devices containing byproduct material for use under R313-19-13(2)(c)(v)(A), should apply for a license under 10 CFR 32.30 (2015) and for a certificate of registration in accordance with R313-22-210.

  (vi) With respect to Subsections R313-19-13(2)(b)(iii), R313-19-13(2)(c)(i), (iii) and (iv), the authority to transfer possession or control by the manufacturer, processor, or producer of equipment, devices, commodities, or other products containing byproduct material whose subsequent possession, use, transfer, and disposal by other persons is exempted from regulatory requirements may be obtained only from the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.


R313-19-20. Types of Licenses
Latest version.

Licenses for radioactive materials are of two types: general and specific.

(1) General licenses provided in Rule R313-21 are effective without the filing of applications with the Director or the issuance of licensing documents to the particular persons, although the filing of a registration certificate with the Director may be required by the particular general license. The general licensee is subject to the other applicable portions of these rules and limitations of the general license.

(2) Specific licenses require the submission of an application to the Director and the issuance of a licensing document by the Director. The licensee is subject to applicable portions of these rules as well as limitations specified in the licensing document.


R313-19-25. Prelicensing Inspection
Latest version.

The Director may verify information contained in applications and secure additional information deemed necessary to make a reasonable determination as to whether to issue a license and whether special conditions should be attached thereto by visiting the facility or location where radioactive materials would be possessed or used, and by discussing details of the proposed possession or use of the radioactive materials with the applicant or representatives designated by the applicant. Such visits may be made by representatives of the Director.


R313-19-30. Reciprocal Recognition of Licenses
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(1) Subject to these rules, a person who holds a specific license from the U.S. Nuclear Regulatory Commission, an Agreement State, or Licensing State, and issued by the agency having jurisdiction where the licensee maintains an office for directing the licensed activity and at which radiation safety records are normally maintained, is hereby granted a general license to conduct the activities authorized in the licensing document within this state, except in areas of exclusive federal jurisdiction, for a period not in excess of 180 days in a calendar year provided that:

(a) the licensing document does not limit the activity authorized by the document to specified installations or locations;

(b) the out-of-state licensee notifies the Director in writing at least three days prior to engaging in such activity. Notifications shall indicate the location, period, and type of proposed possession and use within the state, and shall be accompanied by a copy of the pertinent licensing document. If, for a specific case, the three-day period would impose an undue hardship on the out-of-state licensee, the licensee may, upon application to the Director, obtain permission to proceed sooner. The Director may waive the requirement for filing additional written notifications during the remainder of the calendar year following the receipt of the initial notification from a person engaging in activities under the general license provided in Subsection R313-19-30(1);

(c) the out-of-state licensee complies with all applicable rules of the Board and with the terms and conditions of the licensing document, except those terms and conditions which may be inconsistent with applicable rules of the Board;

(d) the out-of-state licensee supplies other information as the Director may request; and

(e) the out-of-state licensee shall not transfer or dispose of radioactive material possessed or used under the general license provided in Subsection R313-19-30(1) except by transfer to a person specifically licensed by the Director or by the U.S. Nuclear Regulatory Commission, a Licensing State, or an Agreement State to receive the material.

(2) Notwithstanding the provisions of Subsection R313-19-30(1), a person who holds a specific license issued by the U.S. Nuclear Regulatory Commission, a Licensing State, or an Agreement State authorizing the holder to manufacture, transfer, install, or service a device described in Subsection R313-21-22(4) within the areas subject to the jurisdiction of the licensing body is hereby granted a general license to install, transfer, demonstrate, or service a device in this state provided that:

(a) the person shall file a report with the Director within thirty days after the end of a calendar quarter in which a device is transferred to or installed in this state. Reports shall identify each general licensee to whom a device is transferred by name and address, the type of device transferred, and the quantity and type of radioactive material contained in the device;

(b) the device has been manufactured, labeled, installed, and serviced in accordance with applicable provisions of the specific license issued to the person by the Nuclear Regulatory Commission, a Licensing State, or an Agreement State;

(c) the person shall assure that any labels required to be affixed to the device under rules of the authority which licensed manufacture of the device bear a statement that "Removal of this label is prohibited"; and

(d) the holder of the specific license shall furnish to the general licensee to whom the device is transferred or on whose premises a device is installed a copy of the general license contained in Subsection R313-21-22(4) or in equivalent rules of the agency having jurisdiction over the manufacture and distribution of the device.

(3) The Director may withdraw, limit, or qualify his acceptance of a specific license or equivalent licensing document issued by the U.S. Nuclear Regulatory Commission, a Licensing State or an Agreement State, or a product distributed pursuant to the licensing document, upon determining that the action is necessary in order to prevent undue hazard to public health and safety or the environment.


R313-19-34. Terms and Conditions of Licenses
Latest version.

  (1) Licenses issued pursuant to Rule R313-19 shall be subject to provisions of the Act, now or hereafter in effect, and to all rules, and orders of the Director.

  (2)(a) Licenses issued or granted under Rules R313-21 and R313-22 and rights to possess or utilize radioactive material granted by a license issued pursuant to Rules R313-21 and R313-22 shall not be transferred, assigned, or in any manner disposed of, either voluntarily or involuntarily, directly or indirectly, through transfer of control of a license to a person unless the Director shall, after securing full information find that the transfer is in accordance with the provisions of the Act now or hereafter in effect, and to all rules, and orders of the Director, and shall give his consent in writing.

  (b) An application for transfer of license shall include:

  (i) The identity, technical and financial qualifications of the proposed transferee; and

  (ii) Financial assurance for decommissioning information required by R313-22-35.

  (3) Persons licensed by the Director pursuant to Rules R313-21 and R313-22 shall confine use and possession of the material licensed to the locations and purposes authorized in the license.

  (4) Licensees shall notify the Director in writing and request termination of the license when the licensee decides to terminate activities involving materials authorized under the license.

  (5) Licensees shall notify the Director in writing immediately following the filing of a voluntary or involuntary petition for bankruptcy under any Chapter of Title 11, Bankruptcy, of the United States Code by or against:

  (a) the licensee;

  (b) an entity, as that term is defined in 11 USC 101(15), controlling the licensee or listing the license or licensee as property of the estate; or

  (c) an affiliate, as that term is defined in 11 USC 101(2), of the licensee.

  (6) The notification specified in Subsection R313-19-34(5) shall indicate:

  (a) the bankruptcy court in which the petition for bankruptcy was filed; and

  (b) the date of the filing of the petition.

  (7) Licensees required to submit emergency plans pursuant to Subsection R313-22-32(8) shall follow the emergency plan approved by the Director. The licensee may change the approved plan without the Director's approval only if the changes do not decrease the effectiveness of the plan. The licensee shall furnish the change to the Director and to affected off-site response organizations within six months after the change is made. Proposed changes that decrease, or potentially decrease, the effectiveness of the approved emergency plan may not be implemented without prior application to and prior approval by the Director.

  (8) Each licensee preparing technetium-99m radiopharmaceuticals from molybdenum-99/technetium-99m generators or rubidium-82 from strontium-82/rubidium-82 generators shall test the generator eluates for molybdenum-99 breakthrough or strontium-82 and strontium-85 contamination, respectively, in accordance with Rule R313-32 (incorporating 10 CFR 35.204 by reference). The licensee shall record the results of each test and retain each record for three years after the record is made. The licensee shall report the results of each test that exceeds the permissible concentration listed in R313-32 (incorporating 10 CFR 35.204(a)) at the time of generator elution, in accordance with R313-32 (incorporating 10 CFR 35.3204).

  (9) Each portable gauge licensee shall use a minimum of two independent physical controls that form tangible barriers to secure portable gauges from unauthorized removal, whenever portable gauges are not under the control and constant surveillance of the licensee.

  (10)(a) Authorization under Subsection R313-22-32(9) to produce Positron Emission Tomography (PET) radioactive drugs for noncommercial transfer to medical use licensees in its consortium does not relieve the licensee from complying with applicable FDA, other Federal, and State requirements governing radioactive drugs.

  (b) A licensee authorized under Subsection R313-22-32(9) to produce PET radioactive drugs for noncommercial transfer to medical use licensees in its consortium shall:

  (i) Satisfy the labeling requirements in Subsection R313-22-75(9)(a)(iv) for each PET radioactive drug transport radiation shield and each syringe, vial, or other container used to hold a PET radioactive drug intended for noncommercial distribution to members of its consortium.

  (ii) Possess and use instrumentation to measure the radioactivity of the PET radioactive drugs intended for noncommercial distribution to members of its consortium and meet the procedural, radioactivity measurement, instrument test, instrument check, and instrument adjustment requirements in Subsection R313-22-75(9)(c).

  (c) A licensee that is a pharmacy authorized under Subsection R313-22-32(9) to produce PET radioactive drugs for noncommercial transfer to medical use licensees in its consortium shall require that any individual that prepares PET radioactive drugs shall be:

  (i) an authorized nuclear pharmacist that meets the requirements in Subsection R313-22-75(9)(b)(ii); or

  (ii) an individual under the supervision of an authorized nuclear pharmacist as specified in Rule R313-32 (incorporating 10 CFR 35.27 by reference).

  (d) A pharmacy authorized under Subsection R313-22-32(9) to produce PET radioactive drugs for noncommercial transfer to medical use licensees in its consortium that allows an individual to work as an authorized nuclear pharmacist, shall meet the requirements of Subsection R313-22-75(9)(b)(v).


R313-19-41. Transfer of Material
Latest version.

(1) Licensees shall not transfer radioactive material except as authorized pursuant to Section R313-19-41.

(2) Except as otherwise provided in the license and subject to the provisions of Subsections R313-19-41(3) and (4), licensees may transfer radioactive material:

(a) to the Director, if prior approval from the Director has been received;

(b) to the U.S. Department of Energy;

(c) to persons exempt from the rules in Rule R313-19 to the extent permitted under the exemption;

(d) to persons authorized to receive the material under terms of a general license or its equivalent, or a specific license or equivalent licensing document, issued by the Director, the U.S. Nuclear Regulatory Commission, an Agreement State or a Licensing State, or to a person otherwise authorized to receive the material by the federal government or an agency thereof, the Director, an Agreement State or a Licensing State; or

(e) as otherwise authorized by the Director in writing.

(3) Before transferring radioactive material to a specific licensee of the Director, the U.S. Nuclear Regulatory Commission, an Agreement State or a Licensing State, or to a general licensee who is required to register with the Director, the U.S. Nuclear Regulatory Commission, an Agreement State or a Licensing State prior to receipt of the radioactive material, the licensee transferring the material shall verify that the transferee's license authorizes the receipt of the type, form, and quantity of radioactive material to be transferred.

(4) The following methods for the verification required by Subsection R313-19-41(3) are acceptable:

(a) the transferor may possess, and read a current copy of the transferee's specific license or registration certificate;

(b) the transferor may possess a written certification by the transferee that the transferee is authorized by license or registration certificate to receive the type, form, and quantity of radioactive material to be transferred, specifying the license or registration certificate number, issuing agency, and expiration date;

(c) for emergency shipments, the transferor may accept oral certification by the transferee that the transferee is authorized by license or registration certificate to receive the type, form, and quantity of radioactive material to be transferred, specifying the license or registration certificate number, issuing agency, and expiration date, provided that the oral certification is confirmed in writing within ten days;

(d) the transferor may obtain other information compiled by a reporting service from official records of the Director, the U.S. Nuclear Regulatory Commission, an Agreement State, or a Licensing State regarding the identity of licensees and the scope and expiration dates of licenses and registration; or

(e) when none of the methods of verification described in Subsection R313-19-41(4) are readily available or when a transferor desires to verify that information received by one of the methods is correct or up-to-date, the transferor may obtain and record confirmation from the Director, the U.S. Nuclear Regulatory Commission, an Agreement State, or a Licensing State that the transferee is licensed to receive the radioactive material.

(5) Shipment and transport of radioactive material shall be in accordance with the provisions of Section R313-19-100.


R313-19-50. Reporting Requirements
Latest version.

  (1) Licensees shall notify the Director as soon as possible but not later than four hours after the discovery of an event that prevents immediate protective actions necessary to avoid exposures to radiation or radioactive materials that could exceed regulatory limits or releases of licensed material that could exceed regulatory limits. Events may include fires, explosions, toxic gas releases, etc.

  (2) The following events involving licensed material require notification of the Director by the licensee within 24 hours:

  (a) an unplanned contamination event that:

  (i) requires access to the contamination area, by workers or the public, to be restricted for more than 24 hours by imposing additional radiological controls or by prohibiting entry into the area;

  (ii) involves a quantity of material greater than five times the lowest annual limit on intake specified in Appendix B of 10 CFR 20.1001 through 20.2402 (2017), which is incorporated by reference, for the material; and

  (iii) has access to the area restricted for a reason other than to allow radionuclides with a half-life of less than 24 hours to decay prior to decontamination; or

  (b) an event in which equipment is disabled or fails to function as designed when:

  (i) the equipment is required by rule or license condition to prevent releases exceeding regulatory limits, to prevent exposures to radiation and radioactive materials exceeding regulatory limits, or to mitigate the consequences of an accident;

  (ii) the equipment is required by rule or license condition to be available and operable; and

  (iii) no redundant equipment is available and operable to perform the required safety function; or

  (c) an event that requires unplanned medical treatment at a medical facility of an individual with spreadable radioactive contamination on the individual's clothing or body; or

  (d) an unplanned fire or explosion damaging licensed material or a device, container, or equipment containing licensed material when:

  (i) the quantity of material involved is greater than five times the lowest annual limit on intake specified in Appendix B of 10 CFR 20.1001 through 20.2402 (2017), which is incorporated by reference, for the material; and

  (ii) the damage affects the integrity of the licensed material or its container.

  (3) Preparation and submission of reports. Reports made by licensees in response to the requirements of Section R313-19-50 must be made as follows:

  (a) For radioactive materials, other than special nuclear material, licensees shall make reports required by Subsections R313-19-50(1) and (2) by telephone to the Director. To the extent that the information is available at the time of notification, the information provided in these reports must include:

  (i) the caller's name and call back telephone number;

  (ii) a description of the event, including date and time;

  (iii) the exact location of the event;

  (iv) the radionuclides, quantities, and chemical and physical form of the licensed material involved; and

  (v) available personnel radiation exposure data.

  (b) For special nuclear materials, licensees shall make reports required by Subsections R313-19-50(1) and (2) by telephone to the Director. To the extent that the information is available at the time of notification, the information provided in these reports must include:

  (i) the caller's name, position title, and call-back telephone number;

  (ii) the date, time, and exact location of the event; and

  (iii) a description of the event, including:

  (A) radiological or chemical hazards involved, including isotopes, quantities, and chemical and physical form of any material released; and

  (B) actual or potential health and safety consequences to the workers, the public, and the environment, including relevant chemical and radiation data for actual personnel exposures to radiation or radioactive materials or hazardous chemicals produced from radioactive materials (e.g., level of radiation exposure, concentration of chemicals, and duration of exposure).

  (c) Written report for materials other than special nuclear materials. A licensee who makes a report required by Subsections R313-19-50(1) or (2) shall submit a written follow-up report within 30 days of the initial report. Written reports prepared pursuant to other rules may be submitted to fulfill this requirement if the reports contain all of the necessary information and the appropriate distribution is made. These written reports shall be sent to the Director. The report shall include the following:

  (i) A description of the event, including the probable cause and the manufacturer and model number, if applicable, of equipment that failed or malfunctioned;

  (ii) the exact location of the event;

  (iii) the radionuclides, quantities, and chemical and physical form of the licensed material involved;

  (iv) date and time of the event;

  (v) corrective actions taken or planned and results of evaluations or assessments; and

  (vi) the extent of exposure of individuals to radiation or radioactive materials without identification of individuals by name.

  (d) Written report for special nuclear material. A licensee who makes a report required by Subsections R313-19-50(1) or (2) shall submit a written follow-up report within 30 days of the initial report. Written reports prepared pursuant to other rules may be submitted to fulfill this requirement if the reports contain all of the necessary information and the appropriate distribution is made. These written reports shall be sent to the Director. The report shall include the following:

  (i) the complete applicable information required by Subsection R313-19-50(3)(b);

  (ii) the probable cause of the event, including all factors that contributed to the event and the manufacturer and model number (if applicable) of any equipment that failed or malfunctioned; and

  (iii) corrective actions taken or planned to prevent occurrence of similar or identical events in the future and the results of any evaluations or assessments.


R313-19-61. Modification, Revocation, and Termination of Licenses
Latest version.

(1) The terms and conditions of all licenses shall be subject to amendment, revision, or modification or the license may be suspended or revoked by reason of amendments to the Act, or by reason of rules, and orders issued by the Director.

(2) Licenses may be revoked, suspended, or modified, in whole or in part, for any material false statement in the application or any statement of fact required under provisions of the Act, or because of conditions revealed by the application or statement of fact or any report, record, or inspection or other means which would warrant the Director to refuse to grant a license on an original application, or for violation of, or failure to observe any of the terms and conditions of the Act, or of the license, or of any rule, or order of the Director.

(3) Administrative reviews, modifications, revocations or terminations of licenses will be in accordance with Title 19, Chapter 3.

(4) The Director may terminate a specific license upon written request submitted by the licensee to the Director.


R313-19-70. Exempt Concentrations of Radioactive Materials
Latest version.

Refer to Subsection R313-19-13(2)(a)


  TABLE


                                 Column I

                               Concentration Column II

Element Material Concentration

(Atomic Normally Used Liquid (uCi/ml)

Number) Radionuclide As Gas (uCi/ml) Solid (uCi/g)

Antimony (51) Sb-122 3 E-4

                   Sb-124 2 E-4

                   Sb-125 1 E-3

Argon (18) Ar-37 1 E-3

                   Ar-41 4 E-7

Arsenic (33) As-73 5 E-3

                   As-74 5 E-4

                   As-76 2 E-4

                   As-77 8 E-4

Barium (56) Ba-131 2 E-3

                   Ba-140 3 E-4

Beryllium (4) Be-7 2 E-2

Bismuth (83) Bi-206 4 E-4

Bromine (35) Br-82 4 E-7 3 E-3

Cadmium (48) Cd-109 2 E-3

                   Cd-115m 3 E-4

                   Cd-115 3 E-4

Calcium (20) Ca-45 9 E-5

                   Ca-47 5 E-4

Carbon (6) C-14 1 E-6 8 E-3

Cerium (58) Ce-141 9 E-4

                   Ce-143 4 E-4

                   Ce-144 1 E-4

Cesium (55) Cs-131 2 E-2

                   Cs-134m 6 E-2

                   Cs-134 9 E-5

Chlorine (17) Cl-38 9 E-7 4 E-3

Chromium (24) Cr-51 2 E-2

Cobalt (27) Co-57 5 E-3

                   Co-58 1 E-3

                   Co-60 5 E-4

Copper (29) Cu-64 3 E-3

Dysprosium (66) Dy-165 4 E-3

                   Dy-166 4 E-4

Erbium (68) Er-169 9 E-4

                   Er-171 1 E-3

Europium (63) Eu-152 6 E-4

                   (T = 9.2 h)

                   Eu-155 2 E-3

Fluorine (9) F-18 2 E-6 8 E-3

Gadolinium (64) Gd-153 2 E-3

                   Gd-159 8 E-4

Gallium (31) Ga-72 4 E-4

Germanium (32) Ge-71 2 E-2

Gold (79) Au-196 2 E-3

                   Au-198 5 E-4

                   Au-199 2 E-3

Hafnium (72) Hf-181 7 E-4

Hydrogen (1) H-3 5 E-6 3 E-2

Indium (49) In-113m 1 E-2

                   In-114m 2 E-4

Iodine (53) I-126 3 E-9 2 E-5

                   I-131 3 E-9 2 E-5

                   I-132 8 E-8 6 E-4

                   I-133 1 E-8 7 E-5

                   I-134 2 E-7 1 E-3

Iridium (77) Ir-190 2 E-3

                   Ir-192 4 E-4

                   Ir-194 3 E-4

Iron (26) Fe-55 8 E-3

                   Fe-59 6 E-4

Krypton (36) Kr-85m 1 E-6

                   Kr-85 3 E-6

Lanthanum (57) La-140 2 E-4

Lead (82) Pb-203 4 E-3

Lutetium (71) Lu-177 1 E-3

Manganese (25) Mn-52 3 E-4

                   Mn-54 1 E-3

                   Mn-56 1 E-3

Mercury (80) Hg-197m 2 E-3

                   Hg-197 3 E-3

                   Hg-203 2 E-4

Molybdenum (42) Mo-99 2 E-3

Neodymium (60) Nd-147 6 E-4

                   Nd-149 3 E-3

Nickel (28) Ni-65 1 E-3

Niobium Nb-95 1 E-3

  (Columbium)(41) Nb-97 9 E-3

Osmium (76) Os-185 7 E-4

                   Os-191m 3 E-2

                   Os-191 2 E-3

                   Os-193 6 E-4

Palladium (46) Pd-103 3 E-3

                   Pd-109 9 E-4

Phosphorus (15) P-32 2 E-4

Platinum (78) Pt-191 1 E-3

                   Pt-193m 1 E-2

                   Pt-197m 1 E-2

                   Pt-197 1 E-3

Potassium (19) K-42 3 E-3

Praseodymium (59) Pr-142 3 E-4

                   Pr-143 5 E-4

Promethium (61) Pm-147 2 E-3

                   Pm-149 4 E-3

Rhenium (75) Re-183 6 E-4

                   Re-186 9 E-3

                   Re-188 6 E-4

Rhodium (45) Rh-103m 1 E-1

                   Rh-105 1 E-3

Rubidium (37) Rb-86 7 E-4

Ruthenium (44) Ru-97 4 E-4

                   Ru-103 8 E-4

                   Ru-105 1 E-3

                   Ru-106 1 E-4

Samarium (62) Sm-153 8 E-4

Scandium (21) Sc-46 4 E-4

                   Sc-47 9 E-4

                   Sc-48 3 E-4

Selenium (34) Se-75 3 E-3

Silicon (14) Si-31 9 E-3

Silver (47) Ag-105 1 E-3

                   Ag-110m 3 E-4

                   Ag-111 4 E-4

Sodium (11) Na-24 2 E-3

Strontium (38) Sr-85 1 E-4

                   Sr-89 1 E-4

                   Sr-91 7 E-4

                   Sr-92 7 E-4

Sulfur (16) S-35 9 E-8 6 E-4

Tantalum (73) Ta-182 4 E-4

Technetium (43) Tc-96m 1 E-1

                   Tc-96 1 E-3

Tellurium (52) Te-125m 2 E-3

                   Te-127m 6 E-4

                   Te-127 3 E-3

                   Te-129m 3 E-4

                   Te-131m 6 E-4

                   Te-132 3 E-4

Terbium (65) Tb-160 4 E-4

Thallium (81) Tl-200 4 E-3

                   Tl-201 3 E-3

                   Tl-202 1 E-3

                   Tl-204 1 E-3

Thulium (69) Tm-170 5 E-4

                   Tm-171 5 E-3

Tin (50) Sn-113 9 E-4

                   Sn-125 2 E-4

Tungsten W-181 4 E-3

  (Wolfram)(74) W-187 7 E-4

Vanadium (23) V-48 3 E-4

Xenon (54) Xe-131m 4 E-6

                   Xe-133 3 E-6

                   Xe-135 1 E-6

Ytterbium (70) Yb-175 1 E-3

Yttrium (39) Y-90 2 E-4

                   Y-91m 3 E-2

                   Y-91 3 E-4

                   Y-92 6 E-4

                   Y-93 3 E-4

Zinc (30) Zn-65 1 E-3

                   Zn-69m 7 E-4

                   Zn-69 2 E-2

Zirconium (40) Zr-95 6 E-4

                   Zr-97 2 E-4

Beta or gamma

emitting

radioactive

material not

listed above

with half-life

less than 3 years 1 E-10 1 E-6


     (1) In expressing the concentrations in Section R313-19-70, the activity stated is that of the parent radionuclide and takes into account the radioactive decay products, because many radionuclides disintegrate into radionuclides which are also radioactive.

     (2) For purposes of Subsection R313-19-13(2)(a) where there is involved a combination of radionuclides, the limit for the combination should be derived as follows: Determine for each radionuclide in the product the ratio between the radioactivity concentration present in the product and the exempt radioactivity concentration established in Section R313-19-70 for the specific radionuclide when not in combination. The sum of the ratios may not exceed one or unity.

     (3) To convert microcuries (uCi) to SI units of kilobecquerels (kBq), multiply the above values by 37.

  

R313-19-71. Exempt Quantities of Radioactive Materials
Latest version.

Refer to Subsection R313-19-13(2)(b)


  TABLE


     RADIOACTIVE MATERIAL MICROCURIES


     Antimony-122 (Sb-122) 100

     Antimony-124 (Sb-124) 10

     Antimony-125 (Sb-125) 10

     Arsenic-73 (As-73) 100

     Arsenic-74 (As-74) 10

     Arsenic-76 (As-76) 10

     Arsenic-77 (As-77) 100

     Barium-131 (Ba-131) 10

     Barium-133 (Ba-133) 10

     Barium-140 (Ba-140) 10

     Bismuth-210 (Bi-210) 1

     Bromine-82 (Br-82) 10

     Cadmium-109 (Cd-109) 10

     Cadmium-115m (Cd-115m) 10

     Cadmium-115 (Cd-115) 100

     Calcium-45 (Ca-45) 10

     Calcium-47 (Ca-47) 10

     Carbon-14 (C-14) 100

     Cerium-141 (Ce-141) 100

     Cerium-143 (Ce-143) 100

     Cerium-144 (Ce-144) 1

     Cesium-129 (Cs-129) 100

     Cesium-131 (Cs-131) 1,000

     Cesium-134m (Cs-134m) 100

     Cesium-134 (Cs-134) 1

     Cesium-135 (Cs-135) 10

     Cesium-136 (Cs-136) 10

     Cesium-137 (Cs-137) 10

     Chlorine-36 (Cl-36) 10

     Chlorine-38 (Cl-38) 10

     Chromium-51 (Cr-51) 1,000

     Cobalt-57 (Co-57) 100

     Cobalt-58m (Co-58m) 10

     Cobalt-58 (Co-58) 10

     Cobalt-60 (Co-60) 1

     Copper-64 (Cu-64) 100

     Dysprosium-165 (Dy-165) 10

     Dysprosium-166 (Dy-166) 100

     Erbium-169 (Er-169) 100

     Erbium-171 (Er-171) 100

     Europium-152 (Eu-152) 9.2h 100

     Europium-152 (Eu-152) 13 yr 1

     Europium-154 (Eu-154) 1

     Europium-155 (Eu-155) 10

     Fluorine-18 (F-18) 1,000

     Gadolinium-153 (Gd-153) 10

     Gadolinium-159 (Gd-159) 100

     Gallium-67 (Ga-67) 100

     Gallium-72 (Ga-72) 10

     Germanium-68 (Ge-68) 10

     Germanium-71 (Ge-71) 100

     Gold-195 (Au 195) 10

     Gold-198 (Au-198) 100

     Gold-199 (Au-199) 100

     Hafnium-181 (Hf-181) 10

     Holmium-166 (Ho-166) 100

     Hydrogen-3 (H-3) 1,000

     Indium-111 (In-111) 100

     Indium-113m (In-113m) 100

     Indium-114m (In-114m) 10

     Indium-115m (In-115m) 100

     Indium-115 (In-115) 10

     Iodine-123 (I-123) 100

     Iodine-125 (I-125) 1

     Iodine-126 (I-126) 1

     Iodine-129 (I-129) 0.1

     Iodine-131 (I-131) 1

     Iodine-132 (I-132) 10

     Iodine-133 (I-133) 1

     Iodine-134 (I-134) 10

     Iodine-135 (I-135) 10

     Iridium-192 (Ir-192) 10

     Iridium-194 (Ir-194) 100

     Iron-52 (Fe-52) 10

     Iron-55 (Fe-55) 100

     Iron-59 (Fe-59) 10

     Krypton-85 (Kr-85) 100

     Krypton-87 (Kr-87) 10

     Lanthanum-140 (La-140) 10

     Lutetium-177 (Lu-177) 100

     Manganese-52 (Mn-52) 10

     Manganese-54 (Mn-54) 10

     Manganese-56 (Mn-56) 10

     Mercury-197m (Hg-197m) 100

     Mercury-197 (Hg-197) 100

     Mercury-203 (Hg-203) 10

     Molybdenum-99 (Mo-99) 100

     Neodymium-147 (Nd-147) 100

     Neodymium-149 (Nd-149) 100

     Nickel-59 (Ni-59) 100

     Nickel-63 (Ni-63) 10

     Nickel-65 (Ni-65) 100

     Niobium-93m (Nb-93m) 10

     Niobium-95 (Nb-95) 10

     Niobium-97 (Nb-97) 10

     Osmium-185 (Os-185) 10

     Osmium-191m (Os-191m) 100

     Osmium-191 (Os-191) 100

     Osmium-193 (Os-193) 100

     Palladium-103 (Pd-103) 100

     Palladium-109 (Pd-109) 100

     Phosphorus-32 (P-32) 10

     Platinum-191 (Pt-191) 100

     Platinum-193m (Pt-193m) 100

     Platinum-193 (Pt-193) 100

     Platinum-197m (Pt-197m) 100

     Platinum-197 (Pt-197) 100

     Polonium-210 (Po-210) 0.1

     Potassium-42 (K-42) 10

     Potassium-43 (K-43) 10

     Praseodymium-142 (Pr-142) 100

     Praseodymium-143 (Pr-143) 100

     Promethium-147 (Pm-147) 10

     Promethium-149 (Pm-149) 10

     Rhenium-186 (Re-186) 100

     Rhenium-188 (Re-188) 100

     Rhodium-103m (Rh-103m) 100

     Rhodium-105 (Rh-105) 100

     Rubidium-81 (Rb-81) 10

     Rubidium-86 (Rb-86) 10

     Rubidium-87 (Rb-87) 10

     Ruthenium-97 (Ru-97) 100

     Ruthenium-103 (Ru-103) 10

     Ruthenium-105 (Ru-105) 10

     Ruthenium-106 (Ru-106) 1

     Samarium-151 (Sm-151) 10

     Samarium-153 (Sm-153) 100

     Scandium-46 (Sc-46) 10

     Scandium-47 (Sc-47) 100

     Scandium-48 (Sc-48) 10

     Selenium-75 (Se-75) 10

     Silicon-31 (Si-31) 100

     Silver-105 (Ag-105) 10

     Silver-110m (Ag-110m) 1

     Silver-111 (Ag-111) 100

     Sodium-22 (Na-22) 10

     Sodium-24 (Na-24) 10

     Strontium-85 (Sr-85) 10

     Strontium-89 (Sr-89) 1

     Strontium-90 (Sr-90) 0.1

     Strontium-91 (Sr-91) 10

     Strontium-92 (Sr-92) 10

     Sulfur-35 (S-35) 100

     Tantalum-182 (Ta-182) 10

     Technetium-96 (Tc-96) 10

     Technetium-97m (Tc-97m) 100

     Technetium-97 (Tc-97) 100

     Technetium-99m (Tc-99m) 100

     Technetium-99 (Tc-99) 10

     Tellurium-125m (Te-125m) 10

     Tellurium-127m (Te-127m) 10

     Tellurium-127 (Te-127) 100

     Tellurium-129m (Te-129m) 10

     Tellurium-129 (Te-129) 100

     Tellurium 131m (Te-131m) 10

     Tellurium-132 (Te-132) 10

     Terbium-160 (Tb-160) 10

     Thallium-200 (Tl-200) 100

     Thallium-201 (Tl-201) 100

     Thallium-202 (Tl-202) 100

     Thallium-204 (Tl-204) 10

     Thulium-170 (Tm-170) 10

     Thulium-171 (Tm-171) 10

     Tin-113 (Sn-113) 10

     Tin-125 (Sn-125) 10

     Tungsten-181 (W-181) 10

     Tungsten-185 (W-185) 10

     Tungsten-187 (W-187) 100

     Vanadium-48 (V-48) 10

     Xenon-131m (Xe-131m) 1,000

     Xenon-133 (Xe-133) 100

     Xenon-135 (Xe-135) 100

     Ytterbium-175 (Yb-175) 100

     Yttrium-87 (Y-87) 10

     Yttrium-88 (Y-88) 10

     Yttrium-90 (Y-90) 10

     Yttrium-91 (Y-91) 10

     Yttrium-92 (Y-92) 100

     Yttrium-93 (Y-93) 100

     Zinc-65 (Zn-65) 10

     Zinc-69m (Zn-69m) 100

     Zinc-69 (Zn-69) 1,000

     Zirconium-93 (Zr-93) 10

     Zirconium-95 (Zr-95) 10

     Zirconium-97 (Zr-97) 10

     Any radioactive

     material not listed

     above other than

     alpha emitting

     radioactive material. 0.1


     (1) To convert microcuries (uCi) to SI units of kilobecquerels (kBq), multiply the above values by 37.

  

R313-19-100. Transportation
Latest version.

  For purposes of Section R313-19-100, 10 CFR 71.0(c), 71.1(a), 71.3, 71.4, 71.13, 71.14(a), 71.15, 71.17, 71.19(a), 71.19(b), 71.19(c), 71.20 through 71.23, 71.47, 71.83 through 71.89, 71.97, 71.101(a), 71.101(b), 71.101(c)(1), 71.101(g), 71.105, 71.127 through 71.137, and Appendix A to Part 71 (2014) are incorporated by reference with the following clarifications or exceptions:

  (1) The exclusion of the following:

  (a) In 10 CFR 71.4 the following definitions:

  (i) "close reflection by water";

  (ii) "licensed material";

  (iii) "optimum interspersed hydrogenous moderation";

  (iv) "spent nuclear fuel or spent fuel"; and

  (v) "state."

  (2) The substitution of the following date reference:

  (a) "October 1, 2011" for "October 1, 2008".

  (3) The substitution of the following rule references:

  (a) "R313-36 (incorporating 10 CFR 34.31(b) by reference)" for "Sec. 34.31(b) of this chapter" as found in 10 CFR 71.101(g);

  (b) "R313-15-502" for reference to "10 CFR 20.1502";

  (c) "R313-14" for reference to "10 CFR Part 2 Subpart B";

  (d) "Rule R313-32, 10 CFR Part 35," for reference to "10 CFR part 35";

  (e) "R313-15-906(5)" for reference to "10 CFR 20.1906(e)";

  (f) "R313-19-100(5)" for "Sec.71.5";

  (g) "10 CFR 71.101(a), 71.101(b), 71.101(c)(1), 71.101(g), 71.105, and 71.127 through 71.137" for "subpart H of this part" or for "subpart H" except in 10 CFR 71.17(b), 71.20(b), 71.21(b), 71.22(b), 71.23(b);

  (h) "10 CFR 71.0(c), 71.1(a), 71.3, 71.4, 71.17(c)(2), 71.20(c)(2), 71.21(d)(2), 71.83 through 71.89, 71.97, 71.101(a), 71.101(b), 71.101(c)(1), 71.101(g), 71.105, and 71.127 through 71.137" for "subparts A, G, and H of this part";

  (i) "10 CFR 71.47" for "subparts E and F of this part"; and

  (j) "10 CFR 71.101(a), 71.101(b), 71.101(c)(1), 71.101(g), 71.105, and 71.127 through 71.137" for "Sec. Sec. 71.101 through 71.137."

  (4) The substitution of the following terms:

  (a) "Director" for:

  (i) "Commission" in 10 CFR 71.0(c), 71.17(a), 71.20(a), 71.21(a), 71.22(a), 71.23(a), and 71.101(c)(1);

  (ii) "Director, Division of Nuclear Safety, Office of Nuclear Security and Incident Response" in 10 CFR 71.97(c)(1), and 71.97(f)(1);

  (iii) "Director, Office of State Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001" in 10 CFR 71.97(c)(3)(iii);

  (iv) "NRC" in 10 CFR 71.101(f);

  (b) "Director, the U.S. Nuclear Regulatory Commission, or an Agreement State" for "Commission" in 10 CFR 71.3;

  (c) "The Governor of Utah" for:

  (i) "the governor of a State" in 71.97(a);

  (ii) "each appropriate governor" in 10 CFR 71.97(c)(1);

  (iii) "the governor" in 10 CFR 71.97(c)(3);

  (iv) "the governor of the state" in 10 CFR 71.97(e);

  (v) "the governor of each state" in 10 CFR 71.97(f)(1);

  (vi) "a governor" in 10 CFR 71.97(e);

  (d) "State of Utah" for "State" in 71.97(a), 71.97(b)(2), and 71.97(d)(4);

  (e) "the Governor of Utah's" for:

  (i) "the governor's" in 10 CFR 71.97(a), 71.97(c)(3), 71.97(c)(3)(iii), 71.97(e), and 71.97(f)(1);

  (ii) "governor's" in 10 CFR 71.97(c)(1), and 71.97(e);

  (f) "Specific or general" for "NRC" in 10 CFR 71.0(c);

  (g) "The Director at the address specified in R313-12-110" for reference to "ATTN: Document Control Desk, Director, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards" in 10 CFR 71.101(c)(1);

  (h) "Each" for "Using an appropriate method listed in Sec. 71.1(a), each" in 10 CFR 71.101(c)(1);

  (i) "The material must be contained in a Type A package meeting the requirements of 49 CFR 173.417(a)." for "The fissile material need not be contained in a package which meets the standards of subparts E and F of this part; however, the material must be contained in a Type A package. The Type A package must also meet the DOT requirements of 49 CFR 173.417(a)." as found in 10 CFR 71.22(a) and 71.23(a);

  (j) "Licensee" for "licensee, certificate holder, and applicant for a COC"; and

  (k) "Licensee is" for reference to "licensee, certificate holder, and applicant for a COC are."

  (5) Transportation of licensed material

  (a) Each licensee who transports licensed material outside the site of usage, as specified in the license issued by the Director, the U.S. Nuclear Regulatory Commission or an Agreement State, or where transport is on public highways, or who delivers licensed material to a carrier for transport, shall comply with the applicable requirements of the U.S. Department of Transportation regulations in 49 CFR parts 107, 171 through 180, and 390 through 397 (2009), appropriate to the mode of transport.

  (i) The licensee shall particularly note DOT regulations in the following areas:

  (A) Packaging--49 CFR part 173: subparts A (49 CFR 173.1 through 49 CFR 173.13), B (49 CFR 173.21 through 49 CFR 173.40), and I (49 CFR 173.401 through 49 CFR 173.477).

  (B) Marking and labeling--49 CFR part 172: subpart D (49 CFR 172.300 through 49 CFR 172.338); and 49 CFR 172.400 through 49 CFR 172.407 and 49 CFR 172.436 through 49 CFR 172.441 of subpart E.

  (C) Placarding--49 CFR part 172: subpart F (49 CFR 172.500 through 49 CFR 172.560), especially 49 CFR 172.500 through 49 CFR 172.519 and 49 CFR 172.556; and appendices B and C.

  (D) Accident reporting--49 CFR part 171: 49 CFR 171.15 and 171.16.

  (E) Shipping papers and emergency information--49 CFR part 172: subparts C (49 CFR 172.200 through 49 CFR 172.205) and G (49 CFR 172.600 through 49 CFR 172.606).

  (F) Hazardous material employee training--49 CFR part 172: subpart H (49 CFR 172.700 through 49 CFR 172.704).

  (G) Security plans--49 CFR part 172: subpart I (49 CFR 172.800 through 49 CFR 172.804).

  (H) Hazardous material shipper/carrier registration--49 CFR part 107: subpart G (49 CFR 107.600 through 49 CFR 107.606).

  (ii) The licensee shall also note DOT regulations pertaining to the following modes of transportation:

  (A) Rail--49 CFR part 174: subparts A through D (49 CFR 174.1 through 49 CFR 174.86) and K (49 CFR 174.700 through 49 CFR 174.750).

  (B) Air--49 CFR part 175.

  (C) Vessel--49 CFR part 176: subparts A through F (49 CFR 176.1 through 49 CFR 176.99) and M (49 CFR 176.700 through 49 CFR 107.720).

  (D) Public Highway--49 CFR part 177 and parts 390 through 397.

  (b) If DOT regulations are not applicable to a shipment of licensed material, the licensee shall conform to the standards and requirements of the DOT specified in paragraph (a) of this section to the same extent as if the shipment or transportation were subject to DOT regulations. A request for modification, waiver, or exemption from those requirements, and any notification referred to in those requirements, must be filed with, or made to, the Director, P.O. Box 144850, Salt Lake City, Utah 84114-4850.