ML23241A914

t180-13 Effective 2021-04-05 Highlighted

ML23241A914
Person / Time
Issue date:	08/23/2023
From:	Solomon Sahle NRC/NMSS/DMSST/ASPB
To:	Harisis B State of NE, Dept of Heath & Human Services Systems
References
Download: ML23241A914 (1)

Text

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 TITLE 180 CONTROL OF RADIATION CHAPTER 13 TRANSPORTATION OF RADIOACTIVE MATERIAL 001. SCOPE AND AUTHORITY. The regulations in this Chapter establish requirements for packaging, preparation for shipment, and transportation of radioactive material. The regulations are authorized by and implement the Nebraska Radiation Control Act, Nebraska Revised Statute (Neb. Rev. Stat.) §§ 71-3501 to 71-3520. 10 Code of Federal Regulations (CFR) as published on January 1, 2006 and 49 CFR as published October 1, 2006 and referred throughout this Chapter are incorporated by reference and available for viewing at the Department of Health and Human Services, Public Health Division, Radiological Health, 301 Centennial Mall South, 3rd Floor, Lincoln, Nebraska 68509-5026. The regulations in 180 Nebraska Administrative Code (NAC) 13 apply to any licensee authorized by specific or general license issued by this Department to receive, possess, use, or transfer licensed material, if the licensee delivers that material to a carrier for transport, transport the material outside the site of usage as specified in the Departments license, or transport that material on public highways. No provision of 180 NAC 13 authorizes possession of licensed material.

002. DEFINITIONS. As used in 180 NAC 13, the following definitions apply:

002.01 CERTIFICATE HOLDER. A certificate holder is a person who has been issued a certificate of compliance or other package approval by the U.S. Nuclear Regulatory Commission (NRC).

002.02 CERTIFICATE OF COMPLIANCE (COC). A certificate of compliance (COC) is a Certificate issued by the U.S. Nuclear Regulatory Commission (NRC) under 10 CFR 71 Subpart D which approves the design of a package for the transportation of radioactive material.

002.03 CLOSE REFLECTION BY WATER. Close reflection by water is the immediate contact by water of sufficient thickness for maximum reflection of neutrons.

002.04 CLOSED TRANSPORT VEHICLE. A closed transport vehicle is a transport vehicle equipped with a securely attached exterior enclosure that during normal transportation restricts the access of unauthorized persons to the cargo space containing the radioactive material. The enclosure may be either temporary or permanent but must limit access from top, sides, and ends. In the case of packaged materials, it may be of the "see-through" type.

002.05 CONSIGNMENT. A consignment is the shipment of a package, groups of packages, or load of radioactive material offered by a shipper for transport.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 002.06 CONTAMINATION. Contamination is the presence of a radioactive substance on a surface in quantities in excess of 0.4 becquerel (Bq)/cm2 (1x10-5 microcurie (µCi)/cm2) for beta and gamma emitters and low toxicity alpha emitters, or 0.04 Bq/cm2 (1x10-6 µCi/cm2) for all other alpha emitters.

(A) Fixed contamination means contamination that cannot be removed from a surface during normal conditions of transport.

(B) Non-fixed contamination means contamination that can be removed from a surface during normal conditions of transport.

002.07 CONTAINMENT SYSTEM. A containment system is the assembly of packaging components intended to retain the radioactive material during transport.

002.08 CONVEYANCE. Conveyance means any of the following:

(A) For transport by public highway or rail any transport vehicle or large freight container; (B) For transport by water any vessel, or any hold, compartment, or defined deck area of a vessel including any transport vehicle on board the vessel; and (C) For transport by aircraft any aircraft.

002.09 CRITICALITY SAFETY INDEX (CSI). The criticality safety index (CSI) is the dimensionless number, rounded up to the next tenth, assigned to and placed on the label of a fissile material package, to designate the degree of control of accumulation of packages, overpacks or freight containers containing fissile material during transportation. Determination of the criticality safety index is described in 180 NAC 13-011 and 13-012, and 10 CFR 71.59.

The criticality safety index for an overpack, freight container, consignment or conveyance containing fissile material packages is the arithmetic sum of the criticality safety indices of all the fissile material packages contained within the overpack, freight container, consignment or conveyance.

002.10 DEUTERIUM. For the purposes of 180 NAC 13-004.04 and 13-011, deuterium and any deuterium compounds, including heavy water, in which the ratio of deuterium atoms to hydrogen atoms exceeds 1:5000 is deuterium.

002.11 DOT. DOT means the U.S. Department of Transportation.

002.12 EXCLUSIVE USE. Exclusive use means the sole use of a conveyance by a single consignor for which all initial, intermediate, and final loading and unloading are carried out in according to the direction of the consignor or consignee. The consignor and the carrier must ensure that any loading or unloading performed by personnel having radiological training and resources appropriate for safe handling of the consignment. The consignor must issue specific instructions, in writing, for maintenance of exclusive use shipment controls and include them with the shipping paper information provided to the carrier by the consignor.

002.13 FISSILE MATERIAL. Plutonium-239, plutonium-241, uranium-233, uranium-235, or any combination of these radionuclides is fissile material. Fissile material means the fissile nuclides themselves, not material containing fissile nuclides. Unirradiated natural uranium and depleted uranium and natural uranium or depleted uranium that has been irradiated in thermal reactors only, are not included in this definition. Department jurisdiction extends only to "special nuclear material in quantities not sufficient to form a critical mass" as defined in 180

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 NAC 1-002. Certain exclusions from fissile material control are provided in 180 NAC 13-004.04.

002.14 GRAPHITE. For the purposes of 180 NAC 13-004.04 and 13-011, graphite means graphite with a boron equivalent content less than 5 parts per million and density greater than 1.5 grams per cubic centimeter.

002.15 HIGHWAY ROUTE CONTROLLED QUANTITY (HRCQ). A highway route controlled quantity (HRCQ) is the quantity within a single package which exceeds:

(A) 3,000 times the A1 value of the radionuclides as specified in 49 CFR 173.435 for special form Class 7 (radioactive) material; (B) 3,000 times the A2 value of the radionuclides as specified in 49 CFR 173.435 for normal form Class 7 (radioactive) material; or (C) 1,000 TBq (27,000 curie (Ci)), whichever is least.

002.16 LOW SPECIFIC ACTIVITY (LSA) MATERIAL. Low specific activity (LSA) material is radioactive material with limited specific activity which is nonfissile or is excepted under 180 NAC 13-004.04, and which satisfies the descriptions and limits set forth below. Shielding materials surrounding the Low Specific Activity (LSA) material may not be considered in determining the estimated average specific activity of the package contents. Low Specific Activity (LSA) material must be in one of three groups:

002.16(A) LOW SPECIFIC ACTIVITY (LSA) I. The following criteria applies to low specific activity (LSA) I:

(i) Uranium and thorium ores, concentrates of uranium and thorium ores, and other ores containing naturally occurring radioactive radionuclides that are intended to be processed for the use of these radionuclides; (ii) Natural uranium, depleted uranium, natural thorium or their compounds or mixtures, provided they are unirradiated and in solid or liquid form; (iii) Radioactive material other than fissile material, for which the A2 value is unlimited; or (iv) Other radioactive material in which the activity is distributed throughout and the estimated average specific activity does not exceed 30 times the value for exempt material activity concentration determined according to Appendix 13-A.

002.16(B) LOW SPECIFIC ACTIVITY (LSA) II. The following criteria applies to low specific activity (LSA) II:

(i) Water with tritium concentration up to 0.8 TBq/liter (20.0 Ci/liter); or (ii) Other radioactive material in which the activity is distributed throughout, and the average specific activity does not exceed 10-4 A2/g for solids and gases, and 10 5 A2/g for liquids.

002.16(C) LOW SPECIFIC ACTIVITY (LSA) III SOLIDS. Low specific activity (LSA) III solids are solids excluding powders, that satisfy the requirements of 10 CFR 71.77 in which:

(i) The radioactive material is distributed throughout a solid or a collection of solid objects, or is essentially uniformly distributed in a solid compact binding agent; and

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 (ii) The radioactive material is relatively insoluble, or it is intrinsically contained in a relatively insoluble material, so that, even under loss of packaging, the loss of radioactive material per package leaching, when placed in water for 7 days, would not exceed 0.1 A2; and (iii) The estimated average specific activity of the solid, excluding any shielding material, does not exceed 2 E-3 A2/g.

002.17 LOW TOXICITY ALPHA EMITTERS. Low toxicity alpha emitters are natural uranium, depleted uranium, natural thorium; uranium-235, uranium-238, thorium-232, thorium-228 or thorium-230 when contained in ores or physical or chemical concentrates or tailings; or alpha emitters with a half-life of less than 10 days.

002.18 NATURAL THORIUM. Natural thorium is thorium with the naturally occurring distribution of thorium isotopes, essentially 100 weight percent thorium-232.

002.19 NORMAL FORM RADIOACTIVE MATERIAL. Normal form radioactive material is radioactive material which has not been demonstrated to qualify as special form radioactive material as defined 180 NAC 1-002.

002.20 OPTIMUM INTERSPERSED HYDROGENOUS MODERATION. Optimum interspersed hydrogenous moderation means the presence of hydrogenous material between packages to such an extent that the maximum nuclear reactivity results.

002.21 PACKAGE. A package is the packaging together with its radioactive contents as presented for transport.

(A) Fissile material package or Type AF package, Type BF package, Type B(U)F package or Type B(M)F package means a fissile material packaging together with its fissile material contents.

(B) Type A package means a Type A packaging together with its radioactive contents. A type A package is defined and must comply with the U.S. Department of Transportation (DOT) regulations in 49 CFR 173.

(C) Type B package means a Type B packaging together with its radioactive contents.

On approval, a Type B package design is designated by U.S. Nuclear Regulatory Commission (NRC) as B(U) unless the package has a maximum normal operating pressure or more than 700 Kilopascal Pressure Unit (kPa) (100 lb/in2) gauge or pressure relief device that would allow the release of radioactive material to the environment under the tests specified in 10 CFR Part 71.73 (hypothetical accident conditions), in which it will receive a designation B(M). B(U) refers to the need for unilateral approval of international shipments; B(M) refers to the need for multilateral approval of international shipments. There is no distinction made in how packages with these designations may be used in domestic transportation. To determine their distinction for international transportation, see U.S. Department of Transportation (DOT) regulations, 49 CFR 173. A Type B package approved before September 6,1983, was designated only as Type B. Limitations on its use are specified 10 CFR 71.19.

002.22 PACKAGING. Packaging is the assembly of components necessary to ensure compliance with the packaging requirements of 180 NAC 13. It may consist of one or more

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 receptacles, absorbent materials, spacing structures, thermal insulation, radiation shielding, and devices for cooling or absorbing mechanical shocks. The vehicle, tie down system, and auxiliary equipment may be designated as part of the packaging.

002.23 SPECIFIC ACTIVITY OF A RADIONUCLIDE. The specific activity of a radionuclide is the radioactivity of a radionuclide per unit mass of that nuclide. The specific activity of a material in which the radionuclide is essentially uniformly distributed is the radioactivity per unit mass of the material.

002.24 SURFACE CONTAMINATED OBJECT (SCO). A surface contaminated object (SCO) is a solid object that is not itself classed as radioactive material, but which has radioactive material distributed on any of its surfaces. Surface Contaminated Object (SCO) must be in one of two groups with surface activity not exceeding the following limits:

002.24(A) SURFACE CONTAMINATED OBJECT (SCO)-I. A surface contaminated object (SCO)-I is a solid object on which:

(i) The non-fixed contamination on the accessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 4 Bq /cm2 (10-4

µCi/cm2) for beta and gamma and low toxicity alpha emitters, or 0.4 Bq /cm2 (10-5

µCi/cm2) for all other alpha emitters; (ii) The fixed contamination on the accessible surface averaged over 300 cm2, or the area of the surface if less than 300 cm2, does not exceed 4E+4 Bq/cm2 (1.0

µCi/cm2) for beta and gamma and low toxicity alpha emitters, or 4E+3 Bq /cm2 (0.1

µCi/cm2) for all other alpha emitters; and (iii) The non fixed contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 4E+4 Bq/cm2 (1.0 µCi /cm2) for beta and gamma and low toxicity alpha emitters, or 4E+3 Bq /cm2 (0.1 µCi/cm2) for all other alpha emitters.

002.24(B) SURFACE CONTAMINATED OBJECT (SCO)-II. A surface Contaminated Object (SCO)-II is a solid object on which the limits for Surface Contaminated Object (SCO)-I are exceeded and on which:

(i) The non fixed contamination on the accessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 400 Bq/cm2 (10-2

µCi/cm2) or beta and gamma and low toxicity alpha emitters or 40 Bq/cm2 (10-3

µCi/cm2) for all other alpha emitters; (ii) The fixed contamination on the accessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 8E+5 Bq/cm2 (20

µCi/cm2) for beta and gamma and low toxicity alpha emitters, or 8E+4 Bq/cm2 (2

µCi/cm2) for all other alpha emitters; (iii) The non fixed contamination plus the fixed contamination on the inaccessible surface averaged over 300 cm2 (or the area of the surface if less than 300 cm2) does not exceed 8E+5 Bq/cm2 (20 µCi/cm2) for beta and gamma and low toxicity alpha emitters, or 8E+4 Bq/cm2 (2 µCi/cm2) for all other alpha emitters.

002.25 TRANSPORT INDEX. The transport index is a dimensionless number, rounded up to the next tenth, placed on the label of a package, to designate the degree of control to be exercised by the carrier during transportation. The transport index is the number determined

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 by multiplying the maximum radiation level in millisievert (mSv) per hour at 1 meter (3.3 feet) from the external surface of the package by 100, equivalent to the maximum radiation level in millirem (mrem) per hour at 1 meter (3.3 feet).

002.26 TYPE A QUANTITY. A type A quantity is a quantity of radioactive material, the aggregate radioactivity of which does not exceed A1 for special form radioactive material, or A2, for normal form radioactive material, where A1 and A2 are given in Appendix 13-A, Table A-1, or may be determined by procedures described in Appendix 13-A.

002.27 TYPE B QUANTITY. A type B quantity is a quantity of radioactive material greater than a Type A quantity.

002.28 UNIRRADIATED URANIUM. Unirradiated uranium is uranium containing not more than 2 x 103 Bq of plutonium per gram of uranium-235, not more than 9 x 106 Bq of fission products per gram of uranium-235, and not more than 5 x 10-3 g of uranium-236 per gram of uranium-235.

002.29 URANIUM - NATURAL, DEPLETED, ENRICHED. Natural uranium, depleted uranium and enriched uranium are:

002.29(A) NATURAL URANIUM. Natural uranium is uranium, which may be chemically separated, with the naturally occurring distribution of uranium isotopes, approximately 0.711 weight percent uranium-235, and the remainder by weight essentially uranium-238.

002.29(B) DEPLETED URANIUM. Depleted uranium is uranium containing less uranium-235 than the naturally occurring distribution of uranium isotopes.

002.29(C) ENRICHED URANIUM. Enriched uranium is uranium containing more uranium-235 than the naturally occurring distribution of uranium isotopes.

003. REQUIREMENT FOR LICENSE. Except as authorized in a general or specific license issued by the Department, or as exempted in 180 NAC 13-004, no licensee may:

(A) Deliver radioactive material to a carrier for transport; or (B) Transport radioactive material.

004. EXEMPTIONS. The following are exempt from the requirements of this chapter.

004.01 COMMON AND CONTRACT CARRIERS. Common and contract carriers, freight forwarders, and warehouse workers which are subject to the requirements of the U.S.

Department of Transportation (DOT) in 49 CFR 170 through 189 or the U.S. Postal Service in the Postal Service Domestic Mail Manual, incorporated by reference, at 39 CFR 111.1 (1997) and set out as Attachment 1 of this chapter, are exempt from the requirements of this section to the extent that they transport or store radioactive material in the regular course of their carriage for others or storage incident previously mentioned. Common and contract carriers who are not subject to the requirements of the U.S. Department of Transportation (DOT) or U.S. Postal Service are subject to 180 NAC 13-003 and other applicable requirements of these regulations.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 004.02 EXEMPTION OF PHYSICIANS. Any physician licensed by the State of Nebraska to dispense drugs in the practice of medicine is exempt from 180 NAC 13-003 with respect to transport by the physician of radioactive material for use in the practice of medicine. However, any physician operating under this exemption must be licensed under 180 NAC 7 or equivalent U.S. Nuclear Regulatory Commission (NRC) or Agreement State regulations.

004.03 EXEMPTION FOR LOW-LEVEL MATERIALS. Any licensee is exempt from the requirements of 180 NAC 13 with respect to shipment or carriage of the following low-level materials:

(A) Natural material and ores containing naturally occurring radionuclides that are either in their natural state, or have only been processed for purposes other than for the extraction of the radionuclides, and which are not intended to be processed for the use of these radionuclides, provided the activity concentration of the material does not exceed 10 times the values specified in Appendix 13-A, Table A-2 or Table A-3; (B) Materials for which the activity concentration is not greater than the activity concentration values specified in Appendix 13-A, Table A-2 or Table A-3 or for which the consignment activity is not greater than the limit for an exempt consignment found in Appendix 13-A, Table A-2 or Table A-3; and (C) Non-radioactive solid objects with radioactive substances present on any surfaces in quantities not in excess of the levels cited in the definition of contamination in 180 NAC 13-002.

004.04 EXEMPTION FROM CLASSIFICATION AS FISSILE MATERIAL. Fissile material meeting the requirements of at least one of the items of 180 NAC 13-004.04(A) through (F) are exempt from classification as fissile material and from the fissile material package standards of 10 CFR 71.55 and 71.59, but are subject to all other requirements of 180 NAC 13, except as listed below:

(A) Individual package containing 2 grams or less fissile material; (B) Individual or bulk packaging containing 15 grams or less of fissile material provided the package has at least 200 grams of solid nonfissile material for every gram of fissile material. Lead, beryllium, graphite, and hydrogenous material enriched in deuterium may be present in the package but must not be included in determining the required mass for solid nonfissile material; (C) Packages containing:

(i) Low concentrations of solid fissile material commingled with solid nonfissile material, provided that:

(1) There is at least 2000 grams of solid nonfissile material for every gram of fissile material; and (2) There is no more than 180 grams of fissile material distributed within 360 kg of contiguous nonfissile material; and (ii) Lead, beryllium, graphite, and hydrogenous material enriched in deuterium may be present in the package but must not be included in determining the required mass of solid nonfissile material; (D) Uranium enriched in uranium-235 to a maximum of 1% by weight, and with total plutonium and uranium-233 content of up to 1% of the mass of uranium-235, provided that the mass of any beryllium, graphite, and hydrogenous material enriched in deuterium constitutes less than 5% of the uranium mass, and that the fissile material

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 is distributed homogeneously and does not form a lattice arrangement within the package; (E) Liquid solutions of uranyl nitrate enriched in uranium-235 to a maximum of 2% by mass, with a total plutonium and uranium-233 content not exceeding 0.002% of the mass of uranium, and with a minimum nitrogen to uranium atomic ratio (N/U) of 2.

The material must be contained in at least a U.S. Department of Transportation (DOT)

Type A package; and (F) Packages containing, individually, a total plutonium mass of not more than 1000 grams, of which not more than 20% by mass may consist of plutonium-239, plutonium-241, or any combination of these radionuclides.

005. TRANSPORTATION OF LICENSED MATERIAL. This section addresses the transportation of licensed material.

005.01 U.S. DEPARTMENT OF TRANSPORTATION COMPLIANCE. Each licensee who transports licensed material outside of the site of usage, as specified in the Department license, or where transport is on public highways, or who delivers licensed material to a carrier for transport, must comply with the applicable requirements of the U.S. Department of Transportation (DOT) regulation in 49 CFR part 107, 171 through 180 and 390 through 397 appropriate to mode of transport. The licensee must:

(A) Comply with the applicable U.S. Department of Transportation (DOT) regulations in the following areas:

(i) PACKAGING. The packing requirements in 49 CFR Part 173: Subparts A and B and I; (ii) MARKING AND LABELING. The marking and labeling requirements in 49 CFR Part 172: Subpart D, §§ 172.400 through 172.407, §§ 172.436 through 172.441, of Subpart E; (iii) PLACARDING. The placarding requirements in 49 CFR Part 172: Subpart F, especially §§ 172.500 through 172.519, 172.556, and Appendices B and C; (iv) ACCIDENT REPORTING. The accident reporting requirements in 49 CFR Part 171: §§ 171.15 and 171.16; (v) SHIPPING PAPERS AND EMERGENCY INFORMATION. The shipping papers and emergency information requirements in 49 CFR Part 172: Subparts C and G;

(vi) HAZARDOUS MATERIAL EMPLOYEE TRAINING. The hazardous material employee training requirements in 49 CFR Part 172: Subpart H; (vii) HAZARDOUS MATERIAL SHIPPER AND CARRIER REGISTRATION. The hazardous material shipper and carrier registration requirements in 49 CFR Part 107: Subpart G; and (viii) SECURITY PLANS. The security plan requirements in 49 CFR Part 172; Subpart I.

(B) Comply with applicable U.S. Department of Transportation (DOT) regulations pertaining to the following modes of transportation:

(i) RAIL. The rail requirements in 49 CFR Part 174: Subparts A through D and K; (ii) AIR. The air requirements in 49 CFR Part 175; (iii) VESSEL. The vessel requirements in 49 CFR Part 176: Subparts A through F and M; and

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 (iv) PUBLIC HIGHWAY. The public highway requirements in 49 CFR Part 177 and Parts 390 through 397; and (C) Assure that any special instructions needed to safely open the package are sent to or have been made available to the consignee according to 180 NAC 4-038.

005.02 CODE OF FEDERAL REGULATIONS COMPLIANCE. If, for any reason, the regulations of the U.S. Department of Transportation (DOT) are not applicable to a shipment of licensed material, the licensee must conform to the standards and requirements of 49 CFR Parts 107, 171 through 180 and 390 through 397 appropriate to the mode of transport to the same extent as if the shipment was subject to the 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 Department.

006. GENERAL LICENSES FOR CARRIERS. This section applies to general licenses for carriers.

006.01 GENERAL LICENSE ISSUED. A general license is hereby issued to any common or contract carrier not exempt under 180 NAC 13-004 to receive, possess, transport, and store radioactive material in the regular course of their carriage for others or storage incident previously mentioned, provided the transportation and storage is according to the applicable requirements, appropriate to the mode of transport, of the U.S. Department of Transportation (DOT) to the extent that such requirements relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting.

006.02 PRIVATE CARRIERS. A general license is hereby issued to any private carrier to transport radioactive material, provided the transportation is according to the applicable requirements, appropriate to the mode of transport, of the U.S. Department of Transportation (DOT) to the extent that such requirements relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting. Notification of incidents must be filed with, or made to, the Department as prescribed in 49 CFR, regardless of and in addition to notification made to U.S. Department of Transportation (DOT) or other agencies.

006.03 EXEMPTIONS. Persons who transport radioactive material according to the general licenses in 180 NAC 13-006.01 or 13-006.02 are exempt from the requirements of 180 NAC 4 and 10 to the extent that they transport radioactive material.

007. GENERAL LICENSE: U.S. NUCLEAR REGULATORY COMMISSION APPROVED PACKAGES. This section addresses U.S. Nuclear Regulatory Commission (NRC) approved packages.

007.01 GENERAL LICENSE ISSUED. A general license is hereby issued to any licensee of the Department to transport, or to deliver to a carrier for transport, licensed material in a package for which a license, or other approval has been issued by the U.S. Nuclear Regulatory Commission (NRC).

007.02 APPROVED QUALITY ASSURANCE PROGRAM. This general license applies only to a licensee who has a quality assurance program approved by the Department as satisfying the provisions of 180 NAC 13-021.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 007.03 APPLICABILITY. This general license applies only to a licensee who:

(A) Has a copy of the specific license, or other approval by the U.S. Nuclear Regulatory Commission (NRC) of the package and has the drawings and other documents referenced in the approval relating to the use and maintenance of the packaging and to the actions to be taken prior to shipment; (B) Complies with the terms and conditions of the license, certificate, or other approval by the Nuclear Regulatory Commission (NRC), as applicable, the requirements of 180 NAC 13, and 10 CFR Part 71, Subpart G, 71.91(a)(5) and (7), 71.91(b), 71.93, and 71.95(b)(c) and (d); and 10 CFR Part 71, Subpart H, 71.101(c)(2) and (d), (e) and (f), 71.103(d), (e) and (f), 71.105(a) and (b), and 71.107 through 71.125.

(C) Submits in writing before the first use of the package to: ATTN: Document Control Desk, Director, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards, using an appropriate method listed in 10 CFR 71.1(a), the licensee's name and license number and the package identification number specified in the package approval.

007.04 PACKAGE APPROVAL. The general license in 180 NAC 13-007.01 applies only when the package approval authorizes use of the package under this general license.

007.05 TYPE B OR FISSILE MATERIAL PACKAGE. For a Type B or fissile material package, the design of which was approved before April 1, 1996 the general license is subject to the additional restrictions of 10 CFR 71.19.

008. RESERVED.

009. RESERVED.

010. GENERAL LICENSE: USE OF FOREIGN APPROVED PACKAGE. This section addresses the use of foreign approved package.

010.01 GENERAL LICENSE ISSUED. A general license is issued to any licensee of the Department to transport, or to deliver to a carrier for transport, licensed material in a package the design of which has been approved in a foreign national competent authority certificate which has been revalidated by the U.S. Department of Transportation (DOT) as meeting the applicable requirements of 49 CFR 171.23.

010.02 APPROVED QUALITY ASSURANCE PROGRAM. Except as otherwise provided in this section, the general license applies only to a licensee who has a quality assurance program approved by the Department as satisfying the applicable provisions of 10 CFR 71, subpart H.

010.03 SHIPMENTS MADE TO OR FROM LOCATIONS OUTSIDE THE UNITED STATES.

This general license applies only to shipments made to or from locations outside the United States.

010.04 APPLICABILITY. This general license applies only to a licensee who:

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 (A) Has a copy of the applicable certificate, the revalidation, and the drawings and other documents referenced in the certificate relating to the use and maintenance of the packaging and to the actions to be taken prior to shipment; and (B) Complies with the terms and conditions of the certificate and revalidation and with the applicable requirements of 180 NAC 13.

011. GENERAL LICENSE: FISSILE MATERIAL. This section addresses the general licensing of fissile material.

011.01 GENERAL LICENSE ISSUED. A general license is issued to any licensee to transport fissile material, or to deliver fissile material to a carrier for transport, if the material is shipped according to 180 NAC 13-011. The fissile material need not be contained in a package which meets the standards of 10 CFR 71 subparts E and F; however the material must be contained in a Type A package. The Type A package must also meet the U.S. Department of Transportation (DOT) requirements of 49 CFR 173.417(a).

011.02 APPROVED QUALITY ASSURANCE PROGRAM. The general license applies only to a licensee who has a quality assurance program approved by the Department.

011.03 PACKAGE CONTENTS. The general license applies only when a packages contents:

(A) Contains less than a Type A quantity of fissile material; and (B) Contain less than 500 total grams of beryllium, graphite, or hydrogenous material enriched in deuterium.

011.04 CRITICALITY SAFETY INDEX (CSI) LABELING. The general license applies only to packages containing fissile material that are labeled with a Criticality Safety Index (CSI) which:

(A) Has been determined according to 180 NAC 13-011.05; (B) Has a value less than or equal to 10; and (C) For a shipment of multiple packages containing fissile material, the sum of the Criticality Safety Indexes (CSI) must be less than or equal to 50 (for shipment on a nonexclusive use conveyance) and less than or equal to 100 (for shipment on an exclusive use conveyance).

011.05 CRITICALITY SAFETY INDEX (CSI) DETERMINATION. This section addresses how to determine the Criticality Safety Index (CSI) of fissile material.

(A) The value for the Criticality Safety Index (CSI) must be greater than or equal to the number calculated by the following equation:

The calculated Criticality Safety Index (CSI) must be rounded up to the first decimal place; (B) The values of X, Y, and Z used in the Criticality Safety Index (CSI) equation must be taken from Table 13-1 or Table 13-2, as appropriate;

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 (C) If Table 13-2 is used to obtain the value of X, then the values for the terms in the equation for uranium-233 and plutonium must be assumed to be zero; and (D) Table 13-1 values for X, Y, and Z must be used to determine the Criticality Safety Index (CSI) if:

(i) Uranium-233 is present in the package; (ii) The mass of the plutonium exceeds 1% of the mass of uranium-235; (iii) The uranium is unknown uranium-235 enrichment or greater than 24 weight percent enrichment; or (iv) Substances having a moderating effectiveness (that is, an average hydrogen density greater that H2O, certain hydrocarbon oils or plastics, are present in any form, except as polyethylene used for packing or wrapping.

TABLE 13-1 Mass Limits for General License Packages Containing Mixed Quantities of Fissile Material or Uranium-235 of Unknown Enrichment per 180 NAC 13-011.05 Fissile material mass Fissile material mass mixed with moderating mixed with substances having an moderating average hydrogen substances having Fissile material density less than or equal an average hydrogen to H2O (grams) density greater than H2Oa (grams) 235U (X) 60 38 233U (Y) 43 27 239 Pu or 241 Pu (Z) 37 24 a When mixtures of moderating substances are present, the lower mass limits must be used if more than 15% of the moderating substance has an average hydrogen density greater than H2O.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 TABLE 13-2 Mass Limits for General License Packages Containing Uranium-235 Of Known Enrichment per 180 NAC 13-011 Uranium enrichment in weight Fissile material mass of percent of uranium-235 not uranium-235 U(X) (grams) exceeding 24 60 20 63 15 67 11 72 10 76 9.5 78 9 81 8.5 82 8 85 7.5 88 7 90 6.5 93 6 97 5.5 102 5 108 4.5 114 4 120 3.5 132 3 150 2.5 180 2 246 1.5 408 1.35 480 1 1,020 0.92 1,800

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 012. GENERAL LICENSE: PLUTONIUM-BERYLLIUM SPECIAL FORM MATERIAL. This section addresses the general licensing of plutonium-beryllium special form material.

012.01 GENERAL LICENSE ISSUANCE. A general license is hereby issued to any licensee to transport fissile material, or to deliver fissile material in the form of plutonium-beryllium (Pu-Be) special form sealed sources, or to deliver Pu-Be sealed sources to a carrier for transport, if the material is shipped according to this subsection. This material need not be contained in package which meets the standards of 10 CFR 71 subpart E and F; however the material must be contained in a Type A package. The Type A package must also meet the U.S.

Department of Transportation (DOT) requirements of 40 CFR 173.417(a).

012.02 GENERAL LICENCE REQUIREMENTS. This general license applies only when all of the following requirements are met:

(A) The package contains no more than a Type A quantity of radioactive material; and (B) Contain less than 1000 g of plutonium, provided that: plutonium-239, plutonium-241, or any combination of these radionuclides, constitutes less than 240g of the total quantity of plutonium in the package.

012.03 APPROVED QUALITY ASSURANCE PROGRAM. The general license applies only to a licensee who has a quality assurance program approved by the Department.

012.04 CRITICALITY SAFETY INDEX (CSI) LABELING. The general license applies only to packages labeled with a Criticality Safety Index (CSI) which:

(A) Has been determined per 180 NAC 13-012.05; (B) Has a value less than or equal to 100; and (C) For a shipment of multiple packages containing Pu-Be sealed sources, the sum of the Criticality Safety Indexes (CSI) must be less than or equal to 50 (for shipment on a nonexclusive use conveyance) and less than or equal to 100 (for shipment on an exclusive use conveyance).

012.05 CRITICALITY SAFETY INDEX (CSI) DETERMINATION. This section addresses how to determine the Criticality Safety Index (CSI) of plutonium-beryllium special form material.

(A) The value for the Criticality Safety Index (CSI) must be greater than or equal to the number calculated by the following equation:

(B) The calculated Criticality Safety Index (CSI) must be rounded up to the first decimal place.

013. ASSUMPTIONS AS TO UNKNOWN PROPERTIES. When the isotopic abundance, mass, concentration, degree of irradiation, degree of moderation, or other pertinent property of fissile material in any package is not known, the licensee must package the fissile material as if the unknown properties have credible values that will cause the maximum neutron multiplication.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 014. PRELIMINARY DETERMINATIONS. Prior to the first use of any pack aging for the shipment of licensed material the licensee must find out whether the determinations in 10 CFR 71.85 (a) -

(c) have been made.

015. ROUTINE DETERMINATIONS. Prior to each shipment of licensed material, the licensee must ensure that the package with its contents satisfies the applicable requirements of 180 NAC 13-015 and of the licensee as follows.

015.01 PROPER PACKAGING. The package is proper for the contents to be shipped.

015.02 UNIMPAIRED PHYSICAL CONDITION. The package is in unimpaired physical condition except for superficial defects such as marks or dents.

015.03 CLOSURE DEVICES. Each closure device of the packaging, including any required gasket, is properly installed and secured and free of defects.

015.04 LIQUIDS. Any system for containing liquid is adequately sealed and has adequate space or other specified provision for expansion of the liquid.

015.05 PRESSURE RELIEF DEVICES. Any pressure relief device is operable and set according to written procedures.

015.06 LOADING AND CLOSURE. The package has been loaded and closed according to written procedures.

015.07 MODERATORS AND NEUTRON ABSORBERS. For fissile material, any moderator or neutron absorber, if required, is present and in proper condition.

015.08 PACKAGE STRUCTURE REQUIREMENTS. Any structural part of the package which could be used to lift or tie down the package during transport is rendered inoperable for that purpose unless it satisfies design requirements specified in 10 CFR 71.45.

015.09 PACKAGE EXTERNAL SURFACE LEVELS OF REMOVABLE RADIOACTIVE CONTAMINATION. The level of removable radioactive contamination on the external surfaces of each package offered for shipment is as low as reasonably achievable (ALARA).

The level of removable radioactive contamination may be determined by wiping an area of 300 square centimeters of the surface concerned with an absorbent material, using moderate pressure, and measuring the activity on the wiping material. Sufficient measurements must be taken in the most appropriate locations to yield a representative assessment of the removable contamination levels. Except as provided in 180 NAC 13-015.09(A), the amount of radioactivity measured on any single wiping material, when averaged over the surface wiped, must not exceed the limits given in TABLE 13-3 of 180 NAC 13-015 at any time during transport. Other methods of assessment of equal or greater efficiency may be used. When other methods are used, the detection efficiency of the method used must be taken into account and in no case may the removable contamination on the external surfaces of the package exceed 10 times the limits listed in TABLE 13-3.

(A) In the case of packages transported as exclusive use shipments by rail or highway only, the removable radioactive contamination at any time during transport must not

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 exceed 10 times the levels prescribed in 180 NAC 13-015.09. The levels at the beginning of transport must not exceed the levels in 180 NAC 13-015.09; 015.10 EXTERNAL RADIATION LEVELS AROUND THE PACKAGE AND AROUND THE VEHICLE. External radiation levels around the package and around the vehicle, if applicable, will not exceed 2 mSv/h (200 mrem/hr) at any point on the external surface of the package at any time during transportation. The transport index must not exceed 10.

015.11 PACKAGE EXTERNAL RADIATION LEVEL REQUIREMENTS FOR TRANSPORTATION BY LAND OR WATER. For a package transported in exclusive use by rail, highway or water, radiation levels external to the package may exceed the limits specified in 180 NAC 13-015.09 but must not exceed any of the following:

(A) 2 mSv/h (200 mrem/hr) on the accessible external surface of the package unless the following conditions are met, in which case the limit is 10 mSv/h (1000 mrem/hr);

(i) The shipment is made in a closed transport vehicle; (ii) Provisions are made to secure the package so that its position within the vehicle remains fixed during transportation; and (iii) There are no loading or unloading operations between the beginning and end of the transportation.

(B) 2 mSv/h (200 mrem/hr) at any point on the outer surface of the vehicle, including the top and underside of the vehicle, or, in the case of a flatbed style vehicle, at any point on the vertical planes projected from the outer edges of the vehicle, on the upper surface of the load, or enclosure, if used, and on the lower external surface of the vehicle; (C) 0.1 mSv/h (10 mrem/hr) at any point 2 meters from the vertical planes represented by the outer lateral surfaces of the vehicle, or, in the case of a flatbed style vehicle, at any point 2 meters from the vertical planes projected from the outer edges of the vehicle; and (D) 0.02 mSv/h (2 mrem/hr) in any normally occupied positions of the vehicle, except that this provision does not apply to private motor carriers when persons occupying these positions are provided with special health supervision, personnel radiation exposure monitoring devices, and training according to 180 NAC 10-003.

015.12 MAINTENANCE OF THE EXCLUSIVE USE SHIPMENT CONTROLS. For shipments made under the provisions of 180 NAC 13-015.11, the shipper must provide specific written instructions to the carrier for maintenance of the exclusive use shipment controls. The instructions must be included with the shipping paper information.

015.13 WRITTEN INSTRUCTIONS REQUIRED FOR EXCLUSIVE USE SHIPMENTS. The written instructions required for exclusive use shipments must be sufficient so that, when followed, they will cause the carrier to avoid actions that will unnecessarily delay delivery or unnecessarily result in increased radiation levels or radiation exposures to transport workers or member of the general public.

015.14 ACCESSIBLE PACKAGE SURFACE TEMPERATURES. A package must be prepared for transport so that in still air at 100 degrees Fahrenheit (38 degrees Celsius) and in the shade, no accessible surface of a package would have a temperature exceeding 122 degrees Fahrenheit (50 degrees Celsius) in a nonexclusive use shipment or 185 degrees

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 Fahrenheit (85 degrees Celsius) in an exclusive use shipment. Accessible package surface temperatures must not exceed these limits at any time during transportation.

015.15 CONTINUOUS VENTILATION. A package may not incorporate a feature intended to allow continuous venting during transport.

TABLE 13-3 Removable External Radioactive Contamination Wipe Limits Contaminant Maximum Permissible Limits Bq /cm2 µCi /cm2 dpm /cm2 Beta and gamma 0.41 1.0 E-5 22 emitters and low toxicity alpha emitters All other alpha 0.04 1.0 E-6 2.2 emitting radionuclides 016. AIR TRANSPORT OF PLUTONIUM. This section addresses the air transport of plutonium.

016.01 ADDITIONAL REQUIREMENTS. Despite the provisions of any general licenses and despite any exemptions stated directly in this Section or included indirectly by citation of the U.S. Department of Transportation (DOT) regulations, as may be applicable, the licensee must assure that plutonium in any form is not transported by air, or delivered to a carrier for air transport, unless:

(A) The plutonium is contained in a medical device designed for individual human application; (B) The plutonium is contained in a material in which the specific activity is less than or equal to the activity concentration values for plutonium specified in Appendix 13-A, Table A-2, in which the radioactivity is essentially uniformly distributed; (C) The plutonium is shipped in a single package containing no more than an A2 quantity of plutonium in any isotope or form and is shipped according to 180 NAC 13-005; or (D) The plutonium is shipped in a package specifically authorized for the shipment of plutonium by air in the Certificate of Compliance for that package issued by the U.S.

Nuclear Regulatory Commission (NRC).

016.02 INTERPRETATION OF REQUIREMENTS. Nothing in 180 NAC 13-016.01 is to be interpreted as removing or diminishing the requirements of 10 CFR 73.24.

016.03 U.S. DEPARTMENT OF TRANSPORTATION COMPLIANCE. For a shipment of plutonium by air which is subject to 180 NAC 13-016.01, (D), the licensee must, through special arrangement with the carrier, require compliance with 49 CFR 175.704, the U.S.

Department of Transportation (DOT) regulations applicable to the air transport of plutonium.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 017. OPENING INSTRUCTIONS. Before delivery of a package to a carrier for transport, the licensee must ensure that any special instructions needed to safely open the package have been sent to, or otherwise made available to, the consignee for the consignees use according to 180 NAC 4-038.

018. SHIPMENT RECORDS. Shipment records must be retained as follows.

018.01 RECORD REQUIREMENTS. Each licensee must maintain for a period of three years after shipment a record of each shipment of licensed material not exempt under 180 NAC 13-004.03, showing, where applicable:

(A) Identification of the packaging by model number and serial number; (B) Verification that the packaging, as shipped, has no significant defects; (C) Volume and identification of coolant; (D) Type and quantity of licensed material in each package, and the total quantity of each shipment; (E) Date of the shipment; (F) Name and address of the transferee; (G) Address to which the shipment was made; and (H) Results of the determinations required by 180 NAC 13-015 and by the conditions of the package approval.

018.02 RECORD AVAILIBILITY. The licensee must make available for inspection, upon reasonable notice, all records required by these regulations. Records are only valid if stamped, initialed, or signed and dated by authorized personnel, or otherwise authenticated.

018.03 RECORD MAINTENANCE. The licensee must maintain sufficient written records to furnish evidence of the quality of packaging. The records to be maintained include results of the determinations required by 10 CFR 71.85 (a) - (c); design, fabrication, and assembly records; results of reviews, inspections, tests, and audits; results of monitoring work performance and materials analyses; and results of maintenance, modification, and repair activities. Inspection, test, and audit records must identify the inspector or data recorder, the type of observation, the results, the acceptability, and the action taken in connection with any deficiencies noted. These records must be retained for 3 years after the life of the packaging to which they apply.

019. REPORTS. The licensee must report to the Department within 30 days:

(A) Any instance in which there is significant reduction in the effectiveness of any packaging during use; (B) Details of any defects with safety significance in the packaging after first use, with the means employed to repair the defects and prevent their recurrence; or (C) Instances in which the conditions of approval in the Certificate of Compliance were not observed in making a shipment.

020. ADVANCE NOTIFICATION OF TRANSPORT OF NUCLEAR WASTE. The requirements for advance notification of transport of nuclear waste area as follows.

020.01 REQUIREMENTS. As specified in 180 NAC 13-020.02, 13-20.03 and 13-020.04, each licensee must:

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 (A) Provide advance notification to the governor of a State, or the governor's designee, of the shipment of licensed material, within or across the boundary of the State, before the transport, or delivery to a carrier, for transport, of licensed material outside the confines of the licensee's plant or other place of use or storage.

(B) Provide advance notification to the Tribal official of participating Tribes referenced in 180 NAC 13-020.03, or the official's designee, of the shipment of licensed material, within or across the boundary of the Tribe's reservation, before the transport, or delivery to a carrier, for transport, of licensed material outside the confines of the licensee's plant or other place of use or storage.

020.02 CONDITIONS FOR ADVANCE NOTIFICATION. Advance notification is also required in 180 NAC 13 for the shipment of licensed material, other than irradiated fuel, meeting the following three conditions:

(A) The nuclear waste is required to be in Type B packaging for transportation; (B) The nuclear waste is being transported into, within, or through, a state enroute to a disposal facility or to a collection point for transport to a disposal facility; and (C) The quantity of licensed material in a single package exceeds:

(i) 3000 times the A1 value of the radionuclides as specified in Appendix 13-A, Table I for special form radioactive material; (ii) 3000 times the A2 value of the radionuclides as specified in Appendix 13-A, Table I for normal form radioactive material; or (iii) 1000 TBq (27,000 Ci).

020.03 ADVANCE NOTIFICATION REQUIRED INFORMATION. Each advance notification required by 180 NAC 13-020.01 must contain the following information:

(A) The name, address, and telephone number of the shipper, carrier, and receiver of the shipment; (B) A description of the nuclear waste contained in the shipment as required by 49 CFR 172.202 and 172.203(d);

(C) The point of origin of the shipment and the seven day period during which departure of the shipment is estimated to occur; (D) The seven day period during which arrival of the shipment at state boundaries or Tribal reservation boundaries is estimated to occur; (E) The destination of the shipment, and the seven day period during which arrival of the shipment is estimated to occur; and (F) A point of contact with a telephone number for current shipment information.

020.04 PROCEDURES FOR SUBMITTING ADVANCE NOTIFICATION. The notification required by 180 NAC 13-020.01 must:

(A) Be made in writing to:

(i) The office of each appropriate governor, or governor's designee; (ii) The office of each appropriate Tribal official or Tribal officials designee and (iii) To the U.S. Nuclear Regulatory Director, Division of Nuclear Security, Office of Nuclear Security and Incident Response; (B) Be postmarked at least seven days before the beginning of the seven day period during which departure of the shipment is estimated to occur if delivered by mail.

(C) Reach the office of the governor, or governor's designee, or the Tribal official or Tribal officials designee at least four days before the beginning of the seven day period

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 during which departure of the shipment is estimated to occur, if the notification is delivered by any other means than mail.

(i) A list of names and mailing addresses of the governors' designees receiving advance notification of transportation of nuclear waste was published in the Federal Register on June 30, 1995 (60 FR 34306).

(ii) Contact information for each State, including telephone and mailing addresses of governors and governors designees, and participating Tribes, including telephone and mailing addresses of Tribal officials and Tribal officials designees, is available on the U.S. Nuclear Regulatory Commission (NRC) Web site at:

https://scp.nrc.gov/special/designee.pdf.

(iii) A list of the names and mailing addresses of the governors' designees and Tribal officials designees of participating Tribes is available on request from the Director, Division of Intergovernmental Liaison and Rulemaking, Office of Federal and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

(iv) The licensee must retain a copy of the notification as a record for 3 years.

020.05 REVISION NOTICE. A licensee who finds that schedule information previously furnished to a governor or governor's designee or a Tribal official or Tribal officials designee, according to 180 NAC 13-020, will not be met, must telephone a responsible individual in the office of the governor of the State or of the governor's designee or the Tribal official or the Tribal officials designee and inform that individual of the extent of the delay beyond the schedule originally reported. The licensee must maintain for three years a record of the name of the individual contacted.

020.06 CANCELLATION NOTICE. Procedures for submitting a cancellation notice are as follows.

020.06(A) NOTICE AND RETENTION PERIOD. Each licensee who cancels an irradiated reactor fuel or nuclear waste shipment for which advance notification has been sent must send a cancellation notice to the governor of each State or to the governors designee previously notified, each Tribal official or to the Tribal officials designee previously notified, and the Director, Office of Nuclear Security and Incident Response. A copy of the notice must be retained by the licensee for three years.

020.06(B) IDENTIFICATION. The licensee must state in the notice that it is a cancellation and identify the advance notification that is being canceled. The licensee must retain a copy of the notice as a record for three years.

021. QUALITY ASSURANCE REQUIREMENTS. This section describes quality assurance requirements applying to design, purchase, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, operation, maintenance, repair, and modification of components of packaging that are important to safety.

021.01 QUALITY ASSURANCE. As used in this section, "quality assurance" comprises all those planned and systematic actions necessary to provide adequate confidence that a system or component will perform satisfactorily in service. Quality assurance includes quality control, which comprises those quality assurance actions related to control of the physical

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 characteristics and quality of the material or component to predetermined requirements. Each licensee is responsible for satisfying the quality assurance requirements that apply to its use of a packaging for the shipment of licensed material subject to this section.

021.02 ESTABLISHMENT OF PROGRAM. Unless otherwise authorized by the Department, each licensee must establish, maintain, and execute a quality assurance program satisfying each of the applicable criteria of 10 CFR 71.101 through 71.137 and satisfying any specific provisions that are applicable to the licensee's activities including procurement of packaging.

The licensee must execute the applicable criteria in a graded approach to an extent that is equivalent with the quality assurance requirement's importance to safety.

021.03 APPROVAL OF PROGRAM. Before the use of any package for the shipment of licensed material subject to this section, each licensee must obtain Departmental approval of its quality assurance program. Each licensee must file a description of its quality assurance program, including a discussion of which requirements of this section are applicable and how they will be satisfied, by submitting the description to: ATTN: Nebraska Department of Health and Human Services, Office of Radiological Health, 301 Centennial Mall South. P.O. Box 95026, Lincoln, NE 68509-5026.

021.04 MATERIAL AND COMPONENT IDENTIFICATION. The licensee must identify the material and components to be covered by the quality assurance program.

021.05 QUALITY ASSURANCE PROGRAM PROCEDURES. Each licensee must document the quality assurance program by written procedures or instructions and must carry out the program according to those procedures throughout the period during which packaging is used.

021.06 QUALITY ASSURANCE PROGRAM APPROVAL. Prior to the use of any package for the shipment of radioactive material, each licensee must obtain approval by the Department of its quality assurance program.

021.07 WRITTEN RECORDS. The licensee must maintain sufficient written records to demonstrate compliance with the quality assurance program. Records of quality assurance pertaining to the use of a package for shipment of radioactive material must be maintained for a period of three years after shipment.

021.08 RADIOGRAPHY CONTAINERS. The licensee must maintain a program for transport container inspection and maintenance limited to radiographic exposure devices, source changer, or packages transporting these devices and meeting the requirements of 180 NAC 5-011 or equivalent Agreement State or U.S. Nuclear Regulatory Commission (NRC) requirements.

021.09 QUALITY ASSURANCE PROGRAM DELEGATION. The licensee must be responsible for the establishment and execution of the quality assurance program. The licensee may delegate to others, such as contractors, agents, or consultants, the work of establishing and executing the quality assurance program, or any part of the quality assurance program, but must retain responsibility for the program. The licensee m clearly establish and delineate, in writing, the authority and duties of persons and organizations performing activities affecting the safety-related functions of structures, systems, and components. These

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 activities include performing the functions associated with attaining quality objectives and the quality assurance functions. While the term licensee is used in these criteria, the requirements are applicable to whatever design, fabrication, assembly, and testing of the package is accomplished with respect to a package before the time a package approval is issued.

021.10 QUALITY ASSURANCE FUNCTIONS. The quality assurance functions are:

(A) Assuring that an appropriate quality assurance program is established and effectively executed; and (B) Verifying, by procedures such as checking, auditing, and inspection, that activities affecting the safety-related functions have been performed correctly.

021.11 AUTHORITY AND ORGANIZATIONAL FREEDOM. The persons and organizations performing quality assurance functions must have sufficient authority and organizational freedom to:

(A) Identify quality problems; (B) Initiate, recommend, or provide solutions; and (C) Verify implementation of solutions.

021.12 HANDLING, STORAGE, AND SHIPPING CONTROL. The licensee must establish measures to control, according to instructions, the handling, storage, shipping, cleaning, and preservation of materials and equipment to be used in packaging to prevent damage or deterioration. When necessary for particular products, special protective environments, such as inert gas atmosphere, and specific moisture content and temperature levels must be specified and provided.

021.13 INSPECTION, TEST, AND OPERATING STATUS. The licensee must:

(A) Establish measures to indicate, by the use of markings such as stamps, tags, labels, routing cards, or other suitable means, the status of inspections and tests performed upon individual items of the packaging. These measures must provide for the identification of items that have satisfactorily passed required inspections and tests, where necessary to preclude inadvertent bypassing of the inspections and tests; and (B) Establish measures to identify the operating status of components of the packaging, such as tagging valves and switches, to prevent inadvertent operation.

021.14 NONCONFORMING MATERIALS, PARTS, OR COMPONENTS. The licensee must establish measures to control materials, parts, or components that do not conform to the licensees requirements to prevent their inadvertent use or installation. These measures must include, as appropriate, procedures for identification, documentation, segregation, disposition, and notification to affected organization. Nonconforming items must be reviewed and accepted, rejected, repaired, or reworked according to documented procedures.

021.15 CORRECTIVE ACTIONS. The licensee must establish measures to assure that conditions adverse to quality, such as deficiencies, deviations, defective material and equipment, and nonconformances, are prompt identified and corrected. In the case of significant condition adverse to quality, the measures must assure that the cause of the condition is determined and corrective action taken to preclude repetition. The identification of the significant condition adverse to quality, the cause of the condition, and the corrective action taken must be documented and reported to appropriate levels of management.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 021.16 QUALITY ASSURANCE RECORDS. The licensee must maintain sufficient written records to describe the activities affecting quality. These records must include changes to the quality assurance program as required by 180 NAC 13-022. The records must include the instruction, procedures, and drawings to prescribe quality assurance activities and must include closely related specifications such as required qualification of personnel, procedures, and equipment. The records must include the instructions or procedures, which establish a records retention program that is consistent with applicable regulations and designates factors such as duration, location, and assigned responsibility. The licensee must retain these records for three years beyond the date which the licensee last engage in the activity for which the quality assurance program was developed. If any portion of the written procedures or instruction is superseded, the licensee must retain the superseded material for three years after it is superseded.

021.17 AUDITS. The licensee must carry out a comprehensive system of planned and periodic audits to verify compliance with all aspects of the quality assurance program and to determine the effectiveness of the program. The audits must be performed according to written procedures or checklists by appropriately trained personnel not having direct responsibilities in the areas being audited. Audited results must be documented and reviewed by management having responsibility in the area audited. Follow-up action, including reaudit of deficient areas, must be taken where indicated.

021.18 COMPLEXITY AND PROPOSED USE OF THE PACKAGE AND ITS COMPONENTS. The licensee must base the requirements and procedures of its quality assurance program on the following considerations concerning the complexity and proposed use of the package and its components:

(A) The impact of malfunction or failure of the item to safety; (B) The design and fabrication complexity or uniqueness of the item; (C) The need for special controls and surveillance over processes and equipment; (D) The degree to which functional compliance can be demonstrated by inspection or test; and (E) The quality history and degree of standardization of the item.

021.19 INDOCTRINATION AND TRAINING. The licensee must provide for indoctrination and training of personnel performing activities affecting quality, as necessary to assure that suitable proficiency is achieved and maintained. The licensee must review the status and adequacy of the quality assurance program at established intervals. Management of other organizations participating in the quality assurance program must review regularly the status and adequacy of that part of the quality assurance program they are executing.

022. CHANGES TO QUALITY ASSURANCE PROGRAM. This section addresses changes to the quality assurance program.

022.01 QUALITY ASSURANCE PROGRAM PROPOSED CHANGE SUBMISSION. Each quality assurance program approval holder must submit a description of a proposed change to its Department-approved quality assurance program that will reduce commitments in the program description as approved by the Department. The quality assurance program approval holder must not implement the change before receiving Department approval.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 022.01(A) DESCRIPTION REQUIREMENTS. The description of a proposed change to the Department-approved quality assurance program must identify the change, the reason for the change, and the basis for concluding that the revised program incorporating the change continues to satisfy the applicable requirements of 13-021.

022.02 CHANGE OF A PREVIOUSLY APPROVED QUALITY ASSURANCE PROGRAM.

Each quality assurance program approval holder may change a previously approved quality assurance program without prior Department approval, if the change does not reduce the commitments in the quality assurance program previously approved by the Department.

Changes to the quality assurance program that do not reduce the commitments must be submitted to the Department every 24 months. In addition to quality assurance program changes involving administrative improvements and clarifications, spelling corrections, and nonsubstantive changes to punctuation or editorial items, the following changes are not considered reductions in commitment:

(A) The use of a quality assurance standard approved by the Department that is more recent than the quality assurance standard in the licensees current quality assurance program at the time of the change; (B) The use of generic organizational position titles that clearly denote the position function, supplemented as necessary by descriptive text, rather than specific titles, provided that there is no substantive change to either the functions of the position or reporting responsibilities; (C) The use of generic organizational charts to indicate functional relationships, authorities, and responsibilities, or alternatively, the use of descriptive text, provided that there is no substantive change to the functional relationships, authorities, or responsibilities; (D) The elimination of quality assurance program information that duplicates language in quality assurance regulatory guides and quality assurance standards to which the quality assurance program approval holder has committed to on record; and (E) Organizational revisions that ensure that persons and organizations performing quality assurance functions continue to have the requisite authority and organizational freedom, including sufficient independence from cost and schedule when opposed to safety considerations.

022.03 RECORDING QUALITY ASSURANCE PROGRAM CHANGES. Each quality assurance program approval holder must maintain records of quality assurance program changes.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A DETERMINATION OF A1 AND A2 I. Values of A1 and A2 for individual radionuclides, which are the bases for many activity limits elsewhere in these regulations, are given in Table A-1. The curie (Ci) values specified are obtained by converting from the Terabecquerel (TBq) value. The curie values are expressed to three significant figures to assure that the difference in the TBq and Ci quantities is one tenth of one percent or less. Where values of A1 or A2 are unlimited, it is for radiation control purposes only. For nuclear criticality safety, some materials are subject to controls placed on fissile material.

II. a. For individual radionuclides whose identities are known, but which are not listed in Table A-1, the A1 and A2 values contained in Appendix 13-A, Table A-3 may be used. Otherwise the licensee must obtain prior Department approval of the A1 and A2 values for radionuclides not listed in Table A-1, before shipping the material.

b. For individual radionuclides whose identities are known, but which are not listed in Table A-2, the exempt material activity concentration and exempt consignment activity values contained in Appendix 13-A, Table A-3 may be used. Otherwise, the licensee must obtain prior Department approval of the exempt material activity concentration and exempt consignment activity values for radionuclides not listed in Table A-2, before shipping the material.

c. The licensee must submit requests for prior approval, described under paragraphs II.a. and II.b. of this Appendix, to the Department, according to 180 NAC 1-012.

III. In the calculations of A1 and A2 for a radionuclide not in Table A-1, a single radioactive decay chain, in which radionuclides are present in their naturally occurring proportions, and in which no daughter radionuclide has a half-life either longer than 10 days, or longer than that of the parent radionuclide, must be considered as a single radionuclide, and the activity to be taken into account, and the A1 and A2 value to be applied must be those corresponding to the parent nuclide of that chain. In the case of radioactive decay chains in which any daughter radionuclide has a half-life either longer than 10 days, or greater than that of the parent radionuclide, the parent and those daughter radionuclides must be considered as mixtures of different nuclides.

IV. For mixtures of radionuclides whose identities and respective activities are known, the following conditions apply:

a. For special form radioactive material, the maximum quantity transported in a Type A package is as follows:

B(i)

A (i) 1 i

1 Where B(i) is the activity of radionuclide i in special form, and A1(i) is the A1 value for radionuclide i.

b. For normal form radioactive material, the maximum quantity transported in a Type A package is a follows:

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 B(i)

A (i) 1 i 2 where B(i) is the activity of radionuclide i in normal form, and A2(i) is the A2 value for radionuclide i.

c. If the package contains both special and normal form radioactive material, the activity that may be transported in a Type A package is as follows:

Bi C j A (i) A (j) 1 i 1 j 2 where B(i) is the activity of radionuclide i as special form radioactive material, A1 (i) is the A1 value for radionuclide i, C(j) is the activity of radionuclide j as normal form radioactive material, and A2 (j) is the A2 value for radionuclide j.

d. Alternatively, the A1 value for mixtures of special form material may be determined as follows:

1 A1 for mixture f(i) i A1(i) where f(i) is the fraction of activity for radionuclide i in the mixture, and A2(i) is the appropriate A1 value for radionuclide i.

e. Alternatively, the A2 value for mixtures of normal form material may be determined as follows:

1 A2 for mixture f(i) i A2(i)

Where f(i) is the fraction of activity of radionuclide i in the mixture, and A2(i) is the appropriate A2 value for radionuclide i.

APPENDIX 13-A

f. The exempt activity concentration for mixtures of nuclides may be determined as follows:

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 1

Exempt activity concentration for mixture =

f(i) i [A](i)

Where f(i) is the fraction of activity concentration of radionuclide i in the mixture, and [A](i) is the activity concentration for exempt material containing radionuclide i.

g. The activity limit for an exempt consignment for mixtures of radionuclides may be determined as follows:

1 Exempt consignment activity limit for mixture =

f(i) i A(i)

Where f(i) is the fraction of activity of radionuclide i in the mixture, and A(i) is the activity limit for exempt consignments for radionuclide i.

V. a. When the identity of each radionuclide is known, but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped and the lowest A1 or A2 value, as appropriate, for the radionuclides in each group may be used in applying the formulas in paragraph IV. Groups may be based on the total alpha activity and the total beta, gamma activity when these are known, using the lowest A1 or A2 values for the alpha emitters and beta, gamma emitters.

b. When the identity of each radionuclide is known but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped and the lowest

[A] (activity concentration for exempt material) or A (activity limit for exempt consignment) value, as appropriate, for the radionuclides in each group may be used in applying the formulas in paragraph IV of this appendix. Groups may be based on the total alpha activity and the total beta, gamma activity when these are known, using the lowest [A] or A values for the alpha emitters and beta, gamma emitters, respectively.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A A1 AND A2 VALUES FOR RADIONUCLIDES Symbol of Element and Specific activity radionuclide atomic number A1 (TBq) A1 (Ci)b A2 (TBq) A2 (Ci)b (TBq/g) (Ci/g)

Ac-225 (a) Actinium (89) 8.0X10-1 2.2X101 6.0X10-3 1.6X10-1 2.1X103 5.8X104 Ac-227 (a) 9.0X10-1 2.4X101 9.0X10-5 2.4X10-3 2.7 7.2X101 Ac-228 6.0X10-1 1.6X101 5.0X10-1 1.4X101 8.4X10 4 2.2X106 Ag-105 Silver (47) 2.0 5.4X101 2.0 5.4X101 1.1X10 3 3.0X104 Ag-108m (a) 7.0X10-1 1.9X101 7.0X10-1 1.9X101 9.7X10 -1 2.6X101 Ag-110m (a) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 1.8X10 2 4.7X103 Ag-111 2.0 5.4X101 6.0X10-1 1.6X101 5.8X10 3 1.6X105 Al-26 Aluminum (13) 1.0X10-1 2.7 1.0X10-1 2.7 7.0X10 -4 1.9X10-2 Am-241 Americium (95) 1.0X101 2.7X102 1.0X10-3 2.7X10-2 1.3X10 -1 3.4 Am-242m (a) 1.0X101 2.7X102 1.0X10-3 2.7X10-2 3.6X10-1 1.0X101 Am-243 (a) 5.0 1.4X102 1.0X10-3 2.7X10-2 7.4X10 -3 2.0X10-1 Ar-37 Argon (18) 4.0X101 1.1X103 4.0X101 1.1X103 3.7X10 3 9.9X104 Ar-39 4.0X101 1.1X103 2.0X101 5.4X102 1.3 3.4X101 Ar-41 3.0X10-1 8.1 3.0X10-1 8.1 1.5X10 6 4.2X107 As-72 Arsenic (33) 3.0X10-1 8.1 3.0X10-1 8.1 6.2X10 4 1.7X106 As-73 4.0X101 1.1X103 4.0X101 1.1X103 8.2X10 2 2.2X104 As-74 1.0 2.7X101 9.0X10-1 2.4X101 3.7X10 3 9.9X104 As-76 3.0X10-1 8.1 3.0X10-1 8.1 5.8X10 4 1.6X106 As-77 2.0X101 5.4X102 7.0X10-1 1.9X101 3.9X10 4 1.0X106 At-211 (a) Astatine (85) 2.0X101 5.4X102 5.0X10-1 1.4X101 7.6X10 4 2.1X106 Au-193 Gold (79) 7.0 1.9X102 2.0 5.4X101 3.4X10 4 9.2X105 Au-194 1.0 2.7X101 1.0 2.7X101 1.5X10 4 4.1X105 Au-195 Gold (79) 1.0X101 2.7X102 6.0 1.6X102 1.4X102 3.7X103 Au-198 1.0 2.7X101 6.0X10-1 1.6X101 9.0X103 2.4X105 Au-199 1.0X101 2.7X102 6.0X10-1 1.6X101 7.7X103 2.1X105 Ba-131 (a) Barium (56) 2.0 5.4X101 2.0 5.4X101 3.1X103 8.4X104 Ba-133 3.0 8.1X101 3.0 8.1X101 9.4 2.6X102 Ba-133m 2.0X101 5.4X102 6.0X10-1 1.6X101 2.2X104 6.1X105 Ba-140 (a) 5.0X10-1 1.4X101 3.0X10-1 8.1 2.7X103 7.3X104 Be-7 Beryllium (4) 2.0X101 5.4X102 2.0X101 5.4X102 1.3X104 3.5X105 Be-10 4.0X101 1.1X103 6.0X10-1 1.6X101 8.3X10-4 2.2X10-2 Bi-205 Bismuth (83) 7.0X10-1 1.9X101 7.0X10-1 1.9X101 1.5X10-3 4.2X104 Bi-206 3.0X10-1 8.1 3.0X10-1 8.1 3.8X103 1.0X105 Bi-207 7.0X10-1 1.9X101 7.0X10-1 1.9X101 1.9 5.2X101 Bi-210 1.0 2.7X101 6.0X10-1 1.6X101 4.6X103 1.2X105 Bi-210m (a) 6.0X10-1 1.6X101 2.0X10-2 5.4X10-1 2.1X10-5 5.7X10-4 Bi-212 (a) 7.0X10-1 1.9X101 6.0X10-1 1.6X101 5.4X105 1.5X107 Bk-247 Berkelium (97) 8.0 2.2X102 8.0X10-4 2.2X10-2 3.8X10-2 1.0 Bk-249 (a) 4.0X101 1.1X103 3.0X10-1 8.1 6.1X101 1.6X103 Br-76 Bromine (35) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 9.4X104 2.5X106 Br-77 3.0 8.1X101 3.0 8.1X101 2.6X10 4 7.1X105 Br-82 4.0X10-1 1.1X101 4.0X10-1 1.1X101 4.0X10 4 1.1X106 C-11 Carbon (6) 1.0 2.7X101 6.0X10-1 1.6X101 3.1X10 7 8.4X108 C-14 4.0X101 1.1X103 3.0 8.1X101 1.6X10 -1 4.5 Ca-41 Calcium (20) Unlimited Unlimited Unlimited Unlimited 3.1X10-3 8.5X10-2 Ca-45 4.0X101 1.1X103 1.0 2.7X101 6.6X102 1.8X104 Ca-47 (a) 3.0 8.1X101 3.0X10-1 8.1 2.3X104 6.1X105 Cd-109 Cadmium (48) 3.0X101 8.1X102 2.0 5.4X101 9.6X101 2.6X103 Cd-113m 4.0X101 1.1X103 5.0X10-1 1.4X101 8.3 2.2X102

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A A1 AND A2 VALUES FOR RADIONUCLIDES Symbol of Element and Specific activity radionuclide atomic number A1 (TBq) A1 (Ci)b A2 (TBq) A2 (Ci)b (TBq/g) (Ci/g)

Cd-115 (a) 3.0 8.1X101 4.0X10-1 1.1X101 1.9X104 5.1X105 Cd-115m 5.0X10-1 1.4X101 5.0X10-1 1.4X101 9.4X102 2.5X104 Ce-139 Cerium (58) 7.0 1.9X102 2.0 5.4X101 2.5X10 2 6.8X103 Ce-141 2.0X101 5.4X102 6.0X10-1 1.6X101 1.1X10 3 2.8X104 Ce-143 9.0X10-1 2.4X101 6.0X10-1 1.6X101 2.5X10 4 6.6X105 Ce-144 (a) 2.0X10-1 5.4 2.0X10-1 5.4 1.2X10 2 3.2X103 Cf-248 Californium (98) 4.0X101 1.1X103 6.0X10-3 1.6X10-1 5.8X10 1 1.6X103 Cf-249 3.0 8.1X101 8.0X10-4 2.2X10-2 1.5X10 -1 4.1 Cf-250 2.0X101 5.4X102 2.0X10-3 5.4X10-2 4.0 1.1X102 Cf-251 7.0 1.9X102 7.0X10-4 1.9X10-2 5.9X10 -2 1.6 Cf-252 (h) 1.0x10-1 2.7 3.0X10-3 8.1X10-2 2.0X101 5.4X102 Cf-253 (a) 4.0X101 1.1X103 4.0X10-2 1.1 1.1X103 2.9X104 Cf-254 1.0X10-3 2.7X10-2 1.0X10-3 2.7X10-2 3.1X102 8.5X103 Cl-36 Chlorine (17) 1.0X101 2.7X102 6.0X10-1 1.6X101 1.2X10-3 3.3X10-2 Cl-38 2.0X10-1 5.4 2.0X10-1 5.4 4.9X106 1.3X108 Cm-240 Curium (96) 4.0X101 1.1X103 2.0X10-2 5.4X10-1 7.5X102 2.0X104 Cm-241 2.0 5.4X101 1.0 2.7X101 6.1X102 1.7X104 Cm-242 4.0X101 1.1X103 1.0X10-2 2.7X10-1 1.2X102 3.3X103 Cm-243 9.0 2.4X102 1.0X10-3 2.7X10-2 1.9X10-3 5.2X101 Cm-244 2.0X101 5.4X102 2.0X10-3 5.4X10-2 3.0 8.1X101 Cm-245 9.0 2.4X102 9.0X10-4 2.4X10-2 6.4X10-3 1.7X10-1 Cm-246 9.0 2.4X102 9.0X10-4 2.4X10-2 1.1X10-2 3.1X10-1 Cm-247 (a) 3.0 8.1X101 1.0X10-3 2.7X10-2 3.4X10-6 9.3X10-5 Cm-248 2.0X10-2 5.4X10-1 3.0X10-4 8.1X10-3 1.6X10 -4 4.2X10-3 Co-55 Cobalt (27) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 1.1X10 5 3.1X106 Co-56 3.0X10-1 8.1 3.0X10-1 8.1 1.1X10 3 3.0X104 Co-57 1.0X101 2.7X102 1.0X101 2.7X102 3.1X10 2 8.4X103 Co-58 1.0 2.7X101 1.0 2.7X101 1.2X10 3 3.2X104 Co-58m 4.0X101 1.1X103 4.0X101 1.1X103 2.2X10 5 5.9X106 Co-60 4.0X10-1 1.1X101 4.0X10-1 1.1X101 4.2X10 1 1.1X103 Cr-51 Chromium (24) 3.0X101 8.1X102 3.0X101 8.1X102 3.4X10 3 9.2X104 Cs-129 Cesium (55) 4.0 1.1X102 4.0 1.1X102 2.8X10 4 7.6X105 Cs-131 3.0X101 8.1X102 3.0X101 8.1X102 3.8X10 3 1.0X105 Cs-132 1.0 2.7X101 1.0 2.7X101 5.7X10 3 1.5X105 Cs-134 7.0X10-1 1.9X101 7.0X10-1 1.9X101 4.8X10 1 1.3X103 Cs-134m 4.0X101 1.1X103 6.0X10-1 1.6X101 3.0X10 5 8.0X106 Cs-135 4.0X101 1.1X103 1.0 2.7X101 4.3X10 -5 1.2X10-3 Cs-136 5.0X10-1 1.4X101 5.0X10-1 1.4X101 2.7X10 3 7.3X104 Cs-137 (a) 2.0 5.4X101 6.0X10-1 1.6X101 3.2 8.7X101 Cu-64 Copper (29) 6.0 1.6X102 1.0 2.7X101 1.4X10 5 3.9X106 Cu-67 1.0X101 2.7X102 7.0X10-1 1.9X101 2.8X10 4 7.6X105 Dy-159 Dysprosium (66) 2.0X101 5.4X102 2.0X101 5.4X102 2.1X10 2 5.7X103 Dy-165 9.0X10-1 2.4X101 6.0X10-1 1.6X101 3.0X10 5 8.2X106 Dy-166 (a) 9.0X10-1 2.4X101 3.0X10-1 8.1 8.6X10 3 2.3X105 Er-169 Erbium (68) 4.0X101 1.1X103 1.0 2.7X101 3.1X10 3 8.3X104 Er-171 8.0X10-1 2.2X101 5.0X10-1 1.4X101 9.0X10 4 2.4X106 Eu-147 Europium (63) 2.0 5.4X101 2.0 5.4X101 1.4X10 3 3.7X104 Eu-148 5.0X10-1 1.4X101 5.0X10-1 1.4X101 6.0X10 2 1.6X104 Eu-149 2.0X101 5.4X102 2.0X101 5.4X102 3.5X10 2 9.4X103 Eu-150 (short lived) 2.0 5.4X101 7.0X10-1 1.9X101 6.1X10 4 1.6X106

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A A1 AND A2 VALUES FOR RADIONUCLIDES Symbol of Element and Specific activity radionuclide atomic number A1 (TBq) A1 (Ci)b A2 (TBq) A2 (Ci)b (TBq/g) (Ci/g)

Eu-150 (long lived) 7 x 10-1 1.9X101 7.0X10-1 1.9X101 6.1X104 1.6X106 Eu-152 1.0 2.7X101 1.0 2.7X101 6.5 1.8X102 Eu-152m 8.0X10-1 2.2X101 8.0X10-1 2.2X101 8.2X10 4 2.2X106 Eu-154 9.0X10-1 2.4X101 6.0X10-1 1.6X101 9.8 2.6X102 Eu-155 2.0X101 5.4X102 3.0 8.1X101 1.8X10 1 4.9X102 Eu-156 7.0X10-1 1.9X101 7.0X10-1 1.9X101 2.0X10 3 5.5X104 F-18 Fluorine (9) 1.0 2.7X101 6.0X10-1 1.6X101 3.5X10 6 9.5X107 Fe-52 (a) Iron (26) 3.0X10-1 8.1 3.0X10-1 8.1 2.7X10 5 7.3X106 Fe-55 4.0X101 1.1X103 4.0X101 1.1X103 8.8X10 1 2.4X103 Fe-59 9.0X10-1 2.4X101 9.0X10-1 2.4X101 1.8X10 3 5.0X104 Fe-60 (a) 4.0X101 1.1X103 2.0X10-1 5.4 7.4X10 -4 2.0X10-2 Ga-67 Gallium (31) 7.0 1.9X102 3.0 8.1X101 2.2X10 4 6.0X105 Ga-68 5.0X10-1 1.4X101 5.0X10-1 1.4X101 1.5X10 6 4.1X107 Ga-72 4.0X10-1 1.1X101 4.0X10-1 1.1X101 1.1X10 5 3.1X106 Gd-146 (a) Gadolinium (64) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 6.9X10 2 1.9X104 Gd-148 2.0X101 5.4X102 2.0X10-3 5.4X10-2 1.2 3.2X101 Gd-153 1.0X101 2.7X102 9.0 2.4X102 1.3X10 2 3.5X103 Gd-159 3.0 8.1X101 6.0X10-1 1.6X101 3.9X10 4 1.1X106 Ge-68 (a) Germanium (32) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 2.6X10 2 7.1X103 Ge-71 4.0X101 1.1X103 4.0X101 1.1X103 5.8X10 3 1.6X105 Ge-77 3.0X10-1 8.1 3.0X10-1 8.1 1.3X10 5 3.6X106 Hf-172 (a) Hafnium (72) 6.0X10-1 1.6X101 6.0X10-1 1.6X101 4.1X10 1 1.1X103 Hf-175 3.0 8.1X101 3.0 8.1X101 3.9X102 1.1X104 Hf-181 2.0 5.4X101 5.0X10-1 1.4X101 6.3X10 2 1.7X104

-6 Hf-182 Unlimited Unlimited Unlimited Unlimited 8.1X10 2.2X10-4 Hg-194 (a) Mercury (80) 1.0 2.7X101 1.0 2.7X101 1.3X10 -1 3.5 Hg-195m (a) 3.0 8.1X101 7.0X10-1 1.9X101 1.5X104 4.0X105 Hg-197 2.0X101 5.4X102 1.0X101 2.7X102 9.2X103 2.5X105 Hg-197m 1.0X101 2.7X102 4.0X10-1 1.1X101 2.5X10 4 6.7X105 Hg-203 5.0 1.4X102 1.0 2.7X101 5.1X102 1.4X104 Ho-166 Holmium (67) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 2.6X104 7.0X105 Ho-166m 6.0X10-1 1.6X101 5.0X10-1 1.4X101 6.6X10-2 1.8 I-123 Iodine (53) 6.0 1.6X102 3.0 8.1X101 7.1X104 1.9X106 I-124 1.0 2.7X101 1.0 2.7X101 9.3X103 2.5X105 I-125 2.0X101 5.4X102 3.0 8.1X101 6.4X102 1.7X104 I-126 2.0 5.4X101 1.0 2.7X101 2.9X103 8.0X104 I-129 Unlimited Unlimited Unlimited Unlimited 6.5X10-6 1.8X10-4 I-131 3.0 8.1X101 7.0X10-1 1.9X101 4.6X103 1.2X105 I-132 4.0X10-1 1.1X101 4.0X10-1 1.1X101 3.8X105 1.0X107 I-133 7.0X10-1 1.9X101 6.0X10-1 1.6X101 4.2X104 1.1X106 I-134 3.0X10-1 8.1 3.0X10-1 8.1 9.9X10 5 2.7X107 I-135 (a) 6.0X10-1 1.6X101 6.0X10-1 1.6X101 1.3X10 5 3.5X106 In-111 Indium (49) 3.0 8.1X101 3.0 8.1X101 1.5X10 4 4.2X105 In-113m 4.0 1.1X102 2.0 5.4X101 6.2X10 5 1.7X107 In-114m (a) 1.0X101 2.7X102 5.0X10-1 1.4X101 8.6X10 2 2.3X104 In-115m 7.0 1.9X102 1.0 2.7X101 2.2X10 5 6.1X106 Ir-189 (a) Iridium (77) 1.0X101 2.7X102 1.0X101 2.7X102 1.9X10 3 5.2X104 Ir-190 7.0X10-1 1.9X101 7.0X10-1 1.9X101 2.3X10 3 6.2X104 Ir-192 (c) 1.0 c 2.7X101 6.0X10-1 1.6X101 3.4X10 2 9.2X103 Ir-194 3.0X10-1 8.1 3.0X10-1 8.1 3.1X10 4 8.4X105

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A A1 AND A2 VALUES FOR RADIONUCLIDES Symbol of Element and Specific activity radionuclide atomic number A1 (TBq) A1 (Ci)b A2 (TBq) A2 (Ci)b (TBq/g) (Ci/g)

K-40 Potassium (19) 9.0X10-1 2.4X101 9.0X10-1 2.4X101 2.4X10-7 6.4X10-6 K-42 2.0X10-1 5.4 2.0X10-1 5.4 2.2X105 6.0X106 K-43 7.0X10-1 1.9X101 6.0X10-1 1.6X101 1.2X10 5 3.3X106 Kr-79 Krypton (36) 4.0 1.1x102 2.0 5.4x101 4.2x10 4 1.1x106 Kr-81 4.0X101 1.1X103 4.0X101 1.1X103 7.8X10 -4 2.1X10-2 Kr-85 1.0X101 2.7X102 1.0X101 2.7X102 1.5X10 1 3.9X102 Kr-85m 8.0 2.2X102 3.0 8.1X101 3.0X10 5 8.2X106 Kr-87 2.0X10-1 5.4 2.0X10-1 5.4 1.0X10 6 2.8X107 La-137 Lanthanum (57) 3.0X101 8.1X102 6.0 1.6X102 1.6X10 -3 4.4X10-2 La-140 4.0X10-1 1.1X101 4.0X10-1 1.1X101 2.1X10 4 5.6X105 Lu-172 Lutetium (71) 6.0X10-1 1.6X101 6.0X10-1 1.6X101 4.2X10 3 1.1X105 Lu-173 8.0 2.2X102 8.0 2.2X102 5.6X10 1 1.5X103 Lu-174 9.0 2.4X102 9.0 2.4X102 2.3X10 1 6.2X102 Lu-174m 2.0X101 5.4X102 1.0X101 2.7X102 2.0X10 2 5.3X103 Lu-177 3.0X101 8.1X102 7.0X10-1 1.9X101 4.1X10 3 1.1X105 Mg-28 (a) Magnesium (12) 3.0X10-1 8.1 3.0X10-1 8.1 2.0X10 5 5.4X106 Mn-52 Manganese (25) 3.0X10-1 8.1 3.0X10-1 8.1 1.6X10 4 4.4X105

-5 Mn-53 Unlimited Unlimited Unlimited Unlimited 6.8X10 1.8X10-3 Mn-54 1.0 2.7X101 1.0 2.7X101 2.9X10 2 7.7X103 Mn-56 3.0X10-1 8.1 3.0X10-1 8.1 8.0X10 5 2.2X107 Mo-93 Molybdenum (42) 4.0X101 1.1X103 2.0X101 5.4X102 4.1X10 -2 1.1 Mo-99 a h 1.0 2.7X101 6.0X10-1 1.6X101 1.8X104 4.8X105 N-13 Nitrogen (7) 9.0X10-1 2.4X101 6.0X10-1 1.6X101 5.4X107 1.5X109 Na-22 Sodium (11) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 2.3X10 2 6.3X103 Na-24 2.0X10-1 5.4 2.0X10-1 5.4 3.2X10 5 8.7X106 Nb-93m Niobium (41) 4.0X101 1.1X103 3.0X101 8.1X102 8.8 2.4X102 Nb-94 7.0X10-1 1.9X101 7.0X10-1 1.9X101 6.9X10 -3 1.9X10-1 Nb-95 1.0 2.7X101 1.0 2.7X101 1.5X10 3 3.9X104 Nb-97 9.0X10-1 2.4X101 6.0X10-1 1.6X101 9.9X10 5 2.7X107 Nd-147 Neodymium (60) 6.0 1.6X102 6.0X10-1 1.6X101 3.0X10 3 8.1X104 Nd-149 6.0X10-1 1.6X101 5.0X10-1 1.4X101 4.5X10 5 1.2X107

-3 Ni-59 Nickel (28) Unlimited Unlimited Unlimited Unlimited 3.0X10 8.0X10-2 Ni-63 4.0X101 1.1X103 3.0X101 8.1X102 2.1 5.7X101 Ni-65 4.0X10-1 1.1X101 4.0X10-1 1.1X101 7.1X10 5 1.9X107 Np-235 Neptunium (93) 4.0X101 1.1X103 4.0X101 1.1X103 5.2X10 1 1.4X103 Np-236 (short-lived) 2.0X101 5.4X102 2.0 5.4X101 4.7X10 -4 1.3X10-2 Np-236 (long-lived) 9.0X100 2.4X102 2.0x10-2 5.4X10-1 4.7X10-4 1.3X10-2 Np-237 2.0X101 5.4X102 2.0X10-3 5.4X10-2 2.6X10-5 7.1X10-4 Np-239 7.0 1.9X102 4.0X10-1 1.1X101 8.6X103 2.3X105 Os-185 Osmium (76) 1.0 2.7X101 1.0 2.7X101 2.8X102 7.5X103 Os-191 1.0X101 2.7X102 2.0 5.4X101 1.6X103 4.4X104 Os-191m 4.0X101 1.1X103 3.0X101 8.1X102 4.6X104 1.3X106 Os-193 2.0 5.4X101 6.0X10-1 1.6X101 2.0X104 5.3X105 Os-194 (a) 3.0X10-1 8.1 3.0X10-1 8.1 1.1X101 3.1X102 P-32 Phosphorus (15) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 1.1X104 2.9X105 P-33 4.0X101 1.1X103 1.0 2.7X101 5.8X103 1.6X105 Pa-230 (a) Protactinium (91) 2.0 5.4X101 7.0X10-2 1.9 1.2X103 3.3X104 Pa-231 4.0 1.1X102 4.0X10-4 1.1X10-2 1.7X10 -3 4.7X10-2 Pa-233 5.0 1.4X102 7.0X10-1 1.9X101 7.7X10 2 2.1X104 Pb-201 Lead (82) 1.0 2.7X101 1.0 2.7X101 6.2X10 4 1.7X106

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A A1 AND A2 VALUES FOR RADIONUCLIDES Symbol of Element and Specific activity radionuclide atomic number A1 (TBq) A1 (Ci)b A2 (TBq) A2 (Ci)b (TBq/g) (Ci/g)

Pb-202 4.0X101 1.1X103 2.0X101 5.4X102 1.2X10-4 3.4X10-3 Pb-203 4.0 1.1X102 3.0 8.1X101 1.1X104 3.0X105

-6 Pb-205 Unlimited Unlimited Unlimited Unlimited 4.5X10 1.2X10-4 Pb-210 (a) 1.0 2.7X101 5.0X10-2 1.4 2.8 7.6X101 Pb-212 (a) 7.0X10-1 1.9X101 2.0X10-1 5.4 5.1X10 4 1.4X106 Pd-103 (a) Palladium (46) 4.0X101 1.1X103 4.0X101 1.1X103 2.8X10 3 7.5X104

-5 Pd-107 Unlimited Unlimited Unlimited Unlimited 1.9X10 5.1X10-4 Pd-109 2.0 5.4X101 5.0X10-1 1.4X101 7.9X10 4 2.1X106 Pm-143 Promethium (61) 3.0 8.1X101 3.0 8.1X101 1.3X10 2 3.4X103 Pm-144 7.0X10-1 1.9X101 7.0X10-1 1.9X101 9.2X10 1 2.5X103 Pm-145 3.0X101 8.1X102 1.0X101 2.7X102 5.2 1.4X102 Pm-147 4.0X101 1.1X103 2.0 5.4X101 3.4X10 1 9.3X102 Pm-148m (a) 8.0X10-1 2.2X101 7.0X10-1 1.9X101 7.9X10 2 2.1X104 Pm-149 2.0 5.4X101 6.0X10-1 1.6X101 1.5X10 4 4.0X105 Pm-151 2.0 5.4X101 6.0X10-1 1.6X101 2.7X10 4 7.3X105 Po-210 Polonium (84) 4.0X101 1.1X103 2.0X10-2 5.4X10-1 1.7X10 2 4.5X103 Pr-142 Praseodymium 4.0X10-1 1.1X101 4.0X10-1 1.1X101 4.3X10 4 1.2X106 Pr-143 (59) 3.0 8.1X101 6.0X10-1 1.6X101 2.5X10 3 6.7X104 Pt-188 (a) Platinum (78) 1.0 2.7X101 8.0X10-1 2.2X101 2.5X10 3 6.8X104 Pt-191 4.0 1.1X102 3.0 8.1X101 8.7X10 3 2.4X105 Pt-193 4.0X101 1.1X103 4.0X101 1.1X103 1.4 3.7X101 Pt-193m 4.0X101 1.1X103 5.0X10-1 1.4X101 5.8X10 3 1.6X105 Pt-195m 1.0X101 2.7X102 5.0X10-1 1.4X101 6.2X10 3 1.7X105 Pt-197 2.0X101 5.4X102 6.0X10-1 1.6X101 3.2X10 4 8.7X105 Pt-197m 1.0X101 2.7X102 6.0X10-1 1.6X101 3.7X10 5 1.0X107 Pu-236 Plutonium (94) 3.0X101 8.1X102 3.0X10-3 8.1X10-2 2.0X10 1 5.3X102 Pu-237 2.0X101 5.4X102 2.0X101 5.4X102 4.5X10 2 1.2X104 Pu-238 1.0X101 2.7X102 1.0X10-3 2.7X10-2 6.3X10-1 1.7X101 Pu-239 1.0X101 2.7X102 1.0X10-3 2.7X10-2 2.3X10-3 6.2X10-2 Pu-240 1.0X101 2.7X102 1.0X10-3 2.7X10-2 8.4X10-3 2.3X10-1 Pu-241 (a) 4.0X101 1.1X103 6.0X10-2 1.6 3.8 1.0X102 Pu-242 1.0X101 2.7X102 1.0X10-3 2.7X10-2 1.5X10-4 3.9X10-3 Pu-244 (a) 4.0X10-1 1.1X101 1.0X10-3 2.7X10-2 6.7X10-7 1.8X10-5 Ra-223 (a) Radium (88) 4.0X10-1 1.1X101 7.0X10-3 1.9X10-1 1.9X103 5.1X104 Ra-224 (a) 4.0X10-1 1.1X101 2.0X10-2 5.4X10-1 5.9X103 1.6X105 Ra-225 (a) 2.0X10-1 5.4 4.0X10-3 1.1X10-1 1.5X103 3.9X104 Ra-226 (a) 2.0X10-1 5.4 3.0X10-3 8.1X10-2 3.7X10-2 1.0 Ra-228 (a) 6.0X10-1 1.6X101 2.0X10-2 5.4X10-1 1.0X101 2.7X102 Rb-81 Rubidium (37) 2.0 5.4X101 8.0X10-1 2.2X101 3.1X105 8.4X106 Rb-83 (a) 2.0 5.4X101 2.0 5.4X101 6.8X10 2 1.8X104 Rb-84 1.0 2.7X101 1.0 2.7X101 1.8X10 3 4.7X104 Rb-86 5.0X10-1 1.4X101 5.0X10-1 1.4X101 3.0X10 3 8.1X104

-9 Rb-87 Unlimited Unlimited Unlimited Unlimited 3.2X10 8.6X10-8 6

Rb(nat) Unlimited Unlimited Unlimited Unlimited 6.7X10 1.8X108 Re-184 Rhenium (75) 1.0 2.7X101 1.0 2.7X101 6.9X10 2 1.9X104 Re-184m 3.0 8.1X101 1.0 2.7X101 1.6X10 2 4.3X103 Re-186 2.0 5.4X101 6.0X10-1 1.6X101 6.9X10 3 1.9X105

-9 Re-187 Unlimited Unlimited Unlimited Unlimited 1.4X10 3.8X10-8 Re-188 4.0X10-1 1.1X101 4.0X10-1 1.1X101 3.6X10 4 9.8X105 Re-189 (a) 3.0 8.1X101 6.0X10-1 1.6X101 2.5X10 4 6.8X105

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A A1 AND A2 VALUES FOR RADIONUCLIDES Symbol of Element and Specific activity radionuclide atomic number A1 (TBq) A1 (Ci)b A2 (TBq) A2 (Ci)b (TBq/g) (Ci/g)

Re(nat) Unlimited Unlimited Unlimited Unlimited 0.0 2.4X10-8 Rh-99 Rhodium (45) 2.0 5.4X101 2.0 5.4X101 3.0X103 8.2X104 Rh-101 4.0 1.1X102 3.0 8.1X101 4.1X10 1 1.1X103 Rh-102 5.0X10-1 1.4X101 5.0X10-1 1.4X101 4.5X10 1 1.2X103 Rh-102m 2.0 5.4X101 2.0 5.4X101 2.3X10 2 6.2X103 Rh-103m 4.0X101 1.1X103 4.0X101 1.1X103 1.2X10 6 3.3X107 Rh-105 1.0X101 2.7X102 8.0X10-1 2.2X101 3.1X10 4 8.4X105 Rn-222 (a) Radon (86) 3.0X10-1 8.1 4.0X10-3 1.1X10-1 5.7X10 3 1.5X105 Ru-97 Ruthenium (44) 5.0 1.4X102 5.0 1.4X102 1.7X10 4 4.6X105 Ru-103 (a) 2.0 5.4X101 2.0 5.4X101 1.2X10 3 3.2X104 Ru-105 1.0 2.7X101 6.0X10-1 1.6X101 2.5X10 5 6.7X106 Ru-106 (a) 2.0X10-1 5.4 2.0X10-1 5.4 1.2X10 2 3.3X103 S-35 Sulphur (16) 4.0X101 1.1X103 3.0 8.1X101 1.6X10 3 4.3X104 Sb-122 Antimony (51) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 1.5X10 4 4.0X105 Sb-124 6.0X10-1 1.6X101 6.0X10-1 1.6X101 6.5X10 2 1.7X104 Sb-125 2.0 5.4X101 1.0 2.7X101 3.9X10 1 1.0X103 Sb-126 4.0X10-1 1.1X101 4.0X10-1 1.1X101 3.1X10 3 8.4X104 Sc-44 Scandium (21) 5.0X10-1 1.4X101 5.0X10-1 1.4X101 6.7X10 5 1.8X107 Sc-46 5.0X10-1 1.4X101 5.0X10-1 1.4X101 1.3X10 3 3.4X104 Sc-47 1.0X101 2.7X102 7.0X10-1 1.9X101 3.1X10 4 8.3X105 Sc-48 3.0X10-1 8.1 3.0X10-1 8.1 5.5X10 4 1.5X106 Se-75 Selenium (34) 3.0 8.1X101 3.0 8.1X101 5.4X10 2 1.5X104 Se-79 4.0X101 1.1X103 2.0 5.4X101 2.6X10 -3 7.0X10-2 Si-31 Silicon (14) 6.0X10-1 1.6X101 6.0X10-1 1.6X101 1.4X10 6 3.9X107 Si-32 4.0X101 1.1X103 5.0X10-1 1.4X101 3.9 1.1X102 Sm-145 Samarium (62) 1.0X101 2.7X102 1.0X101 2.7X102 9.8X10 1 2.6X103

-1 Sm-147 Unlimited Unlimited Unlimited Unlimited 8.5X10 2.3X10-8 Sm-151 4.0X101 1.1X103 1.0X101 2.7X102 9.7X10 -1 2.6X101 Sm-153 9.0 2.4X102 6.0X10-1 1.6X101 1.6X10 4 4.4X105 Sn-113 (a) Tin (50) 4.0 1.1X102 2.0 5.4X101 3.7X10 2 1.0X104 Sn-117m 7.0 1.9X102 4.0X10-1 1.1X101 3.0X10 3 8.2X104 Sn-119m 4.0X101 1.1X103 3.0X101 8.1X102 1.4X102 3.7X103 Sn-121m (a) 4.0X101 1.1X103 9.0X10-1 2.4X101 2.0 5.4X101 Sn-123 8.0X10-1 2.2X101 6.0X10-1 1.6X101 3.0X102 8.2X103 Sn-125 4.0X10-1 1.1X101 4.0X10-1 1.1X101 4.0X103 1.1X105 Sn-126 (a) 6.0X10-1 1.6X101 4.0X10-1 1.1X101 1.0X10-3 2.8X10-2 Sr-82 (a) Strontium (38) 2.0X10-1 5.4 2.0X10-1 5.4 2.3X103 6.2X104 Sr-85 2.0 5.4X101 2.0 5.4X101 8.8X102 2.4X104 Sr-85m 5.0 1.4X102 5.0 1.4X102 1.2X106 3.3X107 Sr-87m 3.0 8.1X101 3.0 8.1X101 4.8X105 1.3X107 Sr-89 6.0X10-1 1.6X101 6.0X10-1 1.6X101 1.1X103 2.9X104 Sr-90 (a) 3.0X10-1 8.1 3.0X10-1 8.1 5.1 1.4X102 Sr-91 (a) 3.0X10-1 8.1 3.0X10-1 8.1 1.3X105 3.6X106 Sr-92 (a) 1.0 2.7X101 3.0X10-1 8.1 4.7X105 1.3X107 T(H-3) Tritium (1) 4.0X101 1.1X103 4.0X101 1.1X103 3.6X102 9.7X103 Ta-178 (long-lived) Tantalum (73) 1.0 2.7X101 8.0X10-1 2.2X101 4.2X106 1.1X108 Ta-179 3.0X101 8.1X102 3.0X101 8.1X102 4.1X101 1.1X103 Ta-182 9.0X10-1 2.4X101 5.0X10-1 1.4X101 2.3X10 2 6.2X103 Tb-157 Terbium (65) 4.0X101 1.1X103 4.0X101 1.1X103 5.6X10 -1 1.5X101 Tb-158 1.0 2.7X101 1.0 2.7X101 5.6X10 -1 1.5X101

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A A1 AND A2 VALUES FOR RADIONUCLIDES Symbol of Element and Specific activity radionuclide atomic number A1 (TBq) A1 (Ci)b A2 (TBq) A2 (Ci)b (TBq/g) (Ci/g)

Tb-160 1.0 2.7X101 6.0X10-1 1.6X101 4.2X102 1.1X104 Tc-95m (a) Technetium (43) 2.0 5.4X101 2.0 5.4X101 8.3X102 2.2X104 Tc-96 4.0X10-1 1.1X101 4.0X10-1 1.1X101 1.2X10 4 3.2X105 Tc-96m (a) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 1.4X10 6 3.8X107

-5 Tc-97 Unlimited Unlimited Unlimited Unlimited 5.2X10 1.4X10-3 Tc-97m 4.0X101 1.1X103 1.0 2.7X101 5.6X10 2 1.5X104 Tc-98 8.0X10-1 2.2X101 7.0X10-1 1.9X101 3.2X10 -5 8.7X10-4 Tc-99 4.0X101 1.1X103 9.0X10-1 2.4X101 6.3X10 -4 1.7X10-2 Tc-99m 1.0X101 2.7X102 4.0 1.1X102 1.9X10 5 5.3X106 Te-121 Tellurium (52) 2.0 5.4X101 2.0 5.4X101 2.4X10 3 6.4X104 Te-121m 5.0 1.4X102 3.0 8.1X101 2.6X10 2 7.0X103 Te-123m 8.0 2.2X102 1.0 2.7X101 3.3X10 2 8.9X103 Te-125m 2.0X101 5.4X102 9.0X10-1 2.4X101 6.7X10 2 1.8X104 Te-127 2.0X101 5.4X102 7.0X10-1 1.9X101 9.8X10 4 2.6X106 Te-127m (a) 2.0X101 5.4X102 5.0X10-1 1.4X101 3.5X10 2 9.4X103 Te-129 7.0X10-1 1.9X101 6.0X10-1 1.6X101 7.7X10 5 2.1X107 Te-129m (a) 8.0X10-1 2.2X101 4.0X10-1 1.1X101 1.1X10 3 3.0X104 Te-131m (a) 7.0X10-1 1.9X101 5.0X10-1 1.4X101 3.0X10 4 8.0X105 Te-132 (a) 5.0X10-1 1.4X101 4.0X10-1 1.1X101 1.1X10 4 3.0X105 Th-227 Thorium (90) 1.0X101 2.7X102 5.0X10-3 1.4X10-1 1.1X10 3 3.1X104 Th-228 (a) 5.0X10-1 1.4X101 1.0X10-3 2.7X10-2 3.0X10 1 8.2X102 Th-229 5.0 1.4X102 5.0X10-4 1.4X10-2 7.9X10 -3 2.1X10-1 Th-230 1.0X101 2.7X102 1.0X10-3 2.7X10-2 7.6X10 -4 2.1X10-2 Th-231 4.0X101 1.1X103 2.0X10-2 5.4X10-1 2.0X10 4 5.3X105

-9 Th-232 Unlimited Unlimited Unlimited Unlimited 4.0X10 1.1X10-7 Th-234 (a) 3.0X10-1 8.1 3.0X10-1 8.1 8.6X102 2.3X104 Th(nat) Unlimited Unlimited Unlimited Unlimited 8.1X10-9 2.2X10-7 Ti-44 (a) Titanium (22) 5.0X10-1 1.4X101 4.0X10-1 1.1X101 6.4 1.7X102 Tl-200 Thallium (81) 9.0X10-1 2.4X101 9.0X10-1 2.4X101 2.2X104 6.0X105 Tl-201 1.0X101 2.7X102 4.0 1.1X102 7.9X103 2.1X105 Tl-202 2.0 5.4X101 2.0 5.4X101 2.0X103 5.3X104 Tl-204 1.0X101 2.7X102 7.0X10-1 1.9X101 1.7X101 4.6X102 Tm-167 Thulium (69) 7.0 1.9X102 8.0X10-1 2.2X101 3.1X103 8.5X104 Tm-170 3.0 8.1X101 6.0X10-1 1.6X101 2.2X102 6.0X103 Tm-171 4.0X101 1.1X103 4.0X101 1.1X103 4.0X101 1.1X103 U-230 (fast lung Uranium (92) 4.0X101 1.1X103 1.0X10-1 2.7 1.0X103 2.7X104 absorption) (a)(d)

U-230 (medium 4.0X101 1.1X103 4.0X10-3 1.1X10-1 1.0X103 2.7X104 lung absorption)

(a)(e)

U-230 (slow lung 3.0X101 8.1X102 3.0X10-3 8.1X10-2 1.0X103 2.7X104 absorption) (a)(f)

U-232 (fast lung 4.0X101 1.1X103 1.0X10-2 2.7X10-1 8.3X10-1 2.2X101 absorption) (d)

U-232 (medium 4.0X101 1.1X103 7.0X10-3 1.9X10-1 8.3X10-1 2.2X101 lung absorption) (e)

U-232 (slow lung 1.0X101 2.7X102 1.0X10-3 2.7X10-2 8.3X10-1 2.2X101 absorption) (f)

U-233 (fast lung 4.0X101 1.1X103 9.0X10-2 2.4 3.6X10-4 9.7X10-3 absorption) (d)

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A A1 AND A2 VALUES FOR RADIONUCLIDES Symbol of Element and Specific activity radionuclide atomic number A1 (TBq) A1 (Ci)b A2 (TBq) A2 (Ci)b (TBq/g) (Ci/g)

U-233 (medium 4.0X101 1.1X103 2.0X10-2 5.4X10-1 3.6X10-4 9.7X10-3 lung absorption) (e)

U-233 (slow lung 4.0X101 1.1X103 6.0X10-3 1.6X10-1 3.6X10-4 9.7X10-3 absorption) (f)

U-234 (fast lung 4.0X101 1.1X103 9.0X10-2 2.4 2.3X10-4 6.2X10-3 absorption) (d)

U-234 (medium 4.0X101 1.1X103 2.0X10-2 5.4X10-1 2.3X10-4 6.2X10-3 lung absorption) (e)

U-234 (slow lung 4.0X101 1.1X103 6.0X10-3 1.6X10-1 2.3X10-4 6.2X10-3 absorption) (f)

U-235 (all lung Unlimited Unlimited Unlimited Unlimited 8.0X10-8 2.2X10-6 absorption types)

(a),(d),(e),(f)

U-236 (fast lung Unlimited Unlimited Unlimited Unlimited 2.4X10-6 6.5X10-5 absorption) (d)

U-236 (medium 4.0x101 1.1X103 2.0x10-2 5.4X10-1 2.4X10-6 6.5X10-5 lung absorption) (e)

U-236 (slow lung 4.0x101 1.1X103 6.0x10-3 1.6X10-1 2.4X10-6 6.5X10-5 absorption) (f)

U-238 (all lung Unlimited Unlimited Unlimited Unlimited 1.2X10-8 3.4X10-7 absorption types)

(d),(e),(f)

U (nat) Unlimited Unlimited Unlimited Unlimited 2.6X10-8 7.1X10-7 U (enriched to 20% Unlimited Unlimited Unlimited Unlimited 49 CFR 49 CFR or less)(g) 173.434 173.434 U (dep) Unlimited Unlimited Unlimited Unlimited 49 CFR 49 CFR 173.434 173.434 V-48 Vanadium (23) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 6.3X103 1.7X105 V-49 4.0X101 1.1X103 4.0X101 1.1X103 3.0X102 8.1X103 W-178 (a) Tungsten (74) 9.0 2.4X102 5.0 1.4X102 1.3X103 3.4X104 W-181 3.0X101 8.1X102 3.0X101 8.1X102 2.2X102 6.0X103 W-185 4.0X101 1.1X103 8.0X10-1 2.2X101 3.5X102 9.4X103 W-187 2.0 5.4X101 6.0X10-1 1.6X101 2.6X104 7.0X105 W-188 (a) 4.0X10-1 1.1X101 3.0X10-1 8.1 3.7X102 1.0X104 Xe-122 (a) Xenon (54) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 4.8X104 1.3X106 Xe-123 2.0 5.4X101 7.0X10-1 1.9X101 4.4X105 1.2X107 Xe-127 4.0 1.1X102 2.0 5.4X101 1.0X103 2.8X104 Xe-131m 4.0X101 1.1X103 4.0X101 1.1X103 3.1X103 8.4X104 Xe-133 2.0X101 5.4X102 1.0X101 2.7X102 6.9X103 1.9X105 Xe-135 3.0 8.1X101 2.0 5.4X101 9.5X104 2.6X106 Y-87 (a) Yttrium (39) 1.0 2.7X101 1.0 2.7X101 1.7X104 4.5X105 Y-88 4.0X10-1 1.1X101 4.0X10-1 1.1X101 5.2X102 1.4X104 Y-90 3.0X10-1 8.1 3.0X10-1 8.1 2.0X104 5.4X105 Y-91 6.0X10-1 1.6X101 6.0X10-1 1.6X101 9.1X102 2.5X104 Y-91m 2.0 5.4X101 2.0 5.4X101 1.5X106 4.2X107 Y-92 2.0X10-1 5.4 2.0X10-1 5.4 3.6X105 9.6X106 Y-93 3.0X10-1 8.1 3.0X10-1 8.1 1.2X105 3.3X106 Yb-169 Ytterbium (79) 4.0 1.1X102 1.0 2.7X101 8.9X102 2.4X104 Yb-175 3.0X101 8.1X102 9.0X10-1 2.4X101 6.6X103 1.8X105 Zn-65 Zinc (30) 2.0 5.4X101 2.0 5.4X101 3.0X102 8.2X103 Zn-69 3.0 8.1X101 6.0X10-1 1.6X101 1.8X106 4.9X107 Zn-69m (a) 3.0 8.1X101 6.0X10-1 1.6X101 1.2X105 3.3X106

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A A1 AND A2 VALUES FOR RADIONUCLIDES Symbol of Element and Specific activity radionuclide atomic number A1 (TBq) A1 (Ci)b A2 (TBq) A2 (Ci)b (TBq/g) (Ci/g)

Zr-88 Zirconium (40) 3.0 8.1X101 3.0 8.1X101 6.6X102 1.8X104 Zr-93 Unlimited Unlimited Unlimited Unlimited 9.3X10-5 2.5X10-3 Zr-95 (a) 2.0 5.4X101 8.0X10-1 2.2X101 7.9X102 2.1X104 Zr-97 (a) 4.0X10-1 1.1X101 4.0X10-1 1.1X101 7.1X104 1.9X106 NOTES:

(a) A1 and/or A2 values include contributions from daughter nuclides with half-lives less than 10 days, as listed in the following:

Mg-28 Al-28 Ca-47 Sc-47 Ti-44 Sc-44 Fe-52 Mn-52m Fe-60 Co-60m Zn-69m Zn-69 Ge-68 Ga-68 Rb-83 Kr-83m Sr-82 Rb-82 Sr-90 Y-90 Sr-91 Y-91m Sr-92 Y-92 Y-87 Sr-87m Zr-95 Nb-95m Zr-97 Nb-97m, Nb-97 Mo-99 Tc-99m Tc-95m Tc-95 Tc-96m Tc-96 Ru-103 Rh-103m Ru-106 Rh-106 Pd-103 Rh-103m Ag-108m Ag-108 Ag-110m Ag-110 Cd-115 In-115m In-114m In-114 Sn-113 In-113m Sn-121m Sn-121 Sn-126 Sb-126m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-132 I-135 Xe-135m Xe-122 I-122 Cs-137 Ba-137m Ba-131 Cs-131 Ba-140 La-140 Ce-144 Pr-144m, Pr-144 Pm-148m Pm-148 Gd-146 Eu-146 Dy-166 Ho-166 Hf-172 Lu-172 W-178 Ta-178 W-188 Re-188 Re-189 Os-189m Os-194 Ir-194 Ir-189 Os-189m Pt-188 Ir-188 Hg-194 Au-194

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 Hg-195m Hg-195 Pb-210 Bi-210 Pb-212 Bi-212, Tl-208, Po-212 Bi-210m Tl-206 Bi-212 Tl-208, Po-212 At-211 Po-211 Rn-222 Po-218, Pb-214, At-218, Bi-214, Po-214 Ra-223 Rn-219, Po-215, Pb-211, Bi-211, Po-211, Tl-207 Ra-224 Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 Ra-225 Ac-225, Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209 Ra-226 Rn-222, Po-218, Pb-214, At-218, Bi-214, Po-214 Ra-228 Ac-228 Ac-225 Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209 Ac-227 Fr-223 Th-228 Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212 Th-234 Pa-234m, Pa-234 Pa-230 Ac-226, Th-226, Fr-222, Ra-222, Rn-218, Po-214 U-230 Th-226, Ra-222, Rn-218, Po-214 U-235 Th-231 Pu-241 U-237 Pu-244 U-240, Np-240m Am-242m Am-242, Np-238 Am-243 Np-239 Cm-247 Pu-243 Bk-249 Am-245 Cf-253 Cm-249 (b) The values of A1 and/or A2 in Curies (Ci) are approximate and for information only; the regulatory standard units are Terabecquerel (TBq), (see Appendix 13-A - Determination of A1 and/or A2, Section 1)

(c) The activity of Ir-192 in special form may be determined from a measurement of the rate of decay or a measurement of the radiation level at a prescribed distance from the source.

(d) These values apply only to compounds of uranium that take the chemical form of UF6, UO2F2 and UO2(NO3)2 in both normal and accident conditions of transport.

(e) These values apply only to compounds of uranium that take the chemical form of UO3, UF4, UCl4 and hexavalent compounds in both normal and accident conditions of transport.

(f) These values apply to all compounds of uranium other than those specified in notes (d) and (e) of this table.

(g) These values apply to unirradiated uranium only.

(h) A2 = 0.74 TBq (20 Ci) for Mo-99 for domestic use.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES Activity Activity Activity limit Activity limit for Symbol of Element and concentration for concentration for for exempt exempt radionuclide atomic number exempt material exempt material consignment consignment (Bq/g) (Ci/g) (Bq) (Ci)

Ac-225 (a) Actinium (89) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Ac-227 (a) 1.0X10-1 2.7X10-12 1.0X103 2.7X10-8 Ac-228 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ag-105 Silver (47) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ag-108m (b) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ag-110m 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ag-111 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Al-26 Aluminum (13) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Am-241 Americium (95) 1.0 2.7X10-11 1.0X104 2.7X10-7 Am-242m (b) 1.0 2.7X10-11 1.0X104 2.7X10-7 Am-243 (b) 1.0 2.7X10-11 1.0X103 2.7X10-8 Ar-37 Argon (18) 1.0X106 2.7X10-5 1.0X108 2.7X10-3 Ar-39 1.0X107 2.7X10-4 1.0X104 2.7X10-7 Ar-41 1.0X102 2.7X10-9 1.0X109 2.7X10-2 As-72 Arsenic (33) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 As-73 1.0X103 2.7X10-8 1.0X107 2.7X10-4 As-74 1.0X101 2.7X10-10 1.0X106 2.7X10-5 As-76 1.0X102 2.7X10-9 1.0X105 2.7X10-6 As-77 1.0X103 2.7X10-8 1.0X106 2.7X10-5 At-211 (a) Astatine (85) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Au-193 Gold (79) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Au-194 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Au-195 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Au-198 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Au-199 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ba-131 (a) Barium (56) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ba-133 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ba-133m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ba-140 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Be-7 Beryllium (4) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Be-10 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Bi-205 Bismuth (83) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Bi-206 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Bi-207 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Bi-210 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Bi-210m 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Bi-212 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Bk-247 Berkelium (97) 1.0 2.7X10-11 1.0X104 2.7X10-7 Bk-249 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Br-76 Bromine (35) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Br-77 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Br-82 1.0X101 2.7X10-10 1.0X106 2.7X10-5 C-11 Carbon (6) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 C-14 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Ca-41 Calcium (20) 1.0X105 2.7X10-6 1.0X107 2.7X10-4 Ca-45 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Ca-47 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Cd-109 Cadmium (48) 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Cd-113m 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Cd-115 1.0X102 2.7X10-9 1.0X106 2.7X10-5

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 Cd-115m 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Ce-139 Cerium (58) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ce-141 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Ce-143 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ce-144 (b) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Cf-248 Californium (98) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cf-249 1.0 2.7X10-11 1.0X103 2.7X10-8 Cf-250 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cf-251 1.0 2.7X10-11 1.0X103 2.7X10-8 Cf-252 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cf-253 (a) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Cf-254 1.0 2.7X10-11 1.0X103 2.7X10-8 Cl-36 Chlorine (17) 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Cl-38 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Cm-240 Curium (96) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Cm-241 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Cm-242 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Cm-243 1.0 2.7X10-11 1.0X104 2.7X10-7 Cm-244 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cm-245 1.0 2.7X10-11 1.0X103 2.7X10-8 Cm-246 1.0 2.7X10-11 1.0X103 2.7X10-8 Cm-247 (a) 1.0 2.7X10-11 1.0X104 2.7X10-7 Cm-248 1.0 2.7X10-11 1.0X103 2.7X10-8 Co-55 Cobalt (27) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Co-56 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Co-57 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Co-58 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Co-58m 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Co-60 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Cr-51 Chromium (24) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Cs-129 Cesium (55) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Cs-131 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Cs-132 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Cs-134 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cs-134m 1.0X103 2.7X10-8 1.0X105 2.7X10-6 Cs-135 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Cs-136 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Cs-137 (b) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Cu-64 Copper (29) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Cu-67 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Dy-159 Dysprosium (66) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Dy-165 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Dy-166 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Er-169 Erbium (68) 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Er-171 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Eu-147 Europium (63) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Eu-148 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Eu-149 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Eu-150 (short lived) 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Eu-150 (long lived) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Eu-152 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Eu-152 m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Eu-154 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Eu-155 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Eu-156 1.0X101 2.7X10-10 1.0X106 2.7X10-5 F-18 Fluorine (9) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Fe-52 (a) Iron (26) 1.0X101 2.7X10-10 1.0X106 2.7X10-5

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 Fe-55 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Fe-59 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Fe-60 (a) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Ga-67 Gallium (31) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ga-68 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Ga-72 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Gd-146 (a) Gadolinium (64) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Gd-148 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Gd-153 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Gd-159 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Ge-68 (a) Germanium (32) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Ge-71 1.0X104 2.7X10-7 1.0X108 2.7X10-3 Ge-77 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Hf-172 (a) Hafnium (72) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Hf-175 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Hf-181 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Hf-182 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Hg-194 (a) Mercury (80) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Hg-195m (a) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Hg-197 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Hg-197m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Hg-203 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Ho-166 Holmium (67) 1.0X103 2.7X10-8 1.0X105 2.7X10-6 Ho-166m 1.0X101 2.7X10-10 1.0X106 2.7X10-5 I-123 Iodine (53) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 I-124 1.0X101 2.7X10-10 1.0X106 2.7X10-5 I-125 1.0X103 2.7X10-8 1.0X106 2.7X10-5 I-126 1.0X102 2.7X10-9 1.0X106 2.7X10-5 I-129 1.0X102 2.7X10-9 1.0X105 2.7X10-6 I-131 1.0X102 2.7X10-9 1.0X106 2.7X10-5 I-132 1.0X101 2.7X10-10 1.0X105 2.7X10-6 I-133 1.0X101 2.7X10-10 1.0X106 2.7X10-5 I-134 1.0X101 2.7X10-10 1.0X105 2.7X10-6 I-135 (a) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 In-111 Indium (49) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 In-113m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 In-114m (a) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 In-115m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ir-189 (a) Iridium (77) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Ir-190 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ir-192 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Ir-194 1.0X102 2.7X10-9 1.0X105 2.7X10-6 K-40 Potassium (19) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 K-42 1.0X102 2.7X10-9 1.0X106 2.7X10-5 K-43 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Kr-79 Krypton (36) 1.0x103 2.7x10-8 1.0x105 2.7x10-6 Kr-81 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Kr-85 1.0X105 2.7X10-6 1.0X104 2.7X10-7 Kr-85m 1.0X103 2.7X10-8 1.0X1010 2.7X10-1 Kr-87 1.0X102 2.7X10-9 1.0X109 2.7X10-2 La-137 Lanthanum (57) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 La-140 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Lu-172 Lutetium (71) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Lu-173 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Lu-174 1.0X102 2.7X10-9 1.0X107 2.7X10-4

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 Lu-174m 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Lu-177 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Mg-28 (a) Magnesium (12) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Mn-52 Manganese (25) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Mn-53 1.0X104 2.7X10-7 1.0X109 2.7X10-2 Mn-54 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Mn-56 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Mo-93 Molybdenum (42) 1.0X103 2.7X10-8 1.0X108 2.7X10-3 Mo-99 (a) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 N-13 Nitrogen (7) 1.0X102 2.7X10-9 1.0X109 2.7X10-2 Na-22 Sodium (11) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Na-24 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Nb-93m Niobium (41) 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Nb-94 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Nb-95 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Nb-97 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Nd-147 Neodymium (60) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Nd-149 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ni-59 Nickel (28) 1.0X104 2.7X10-7 1.0X108 2.7X10-3 Ni-63 1.0X105 2.7X10-6 1.0X108 2.7X10-3 Ni-65 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Np-235 Neptunium (93) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Np-236 (short-lived) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Np-236 (long-lived) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Np-237 (b) 1.0 2.7X10-11 1.0X103 2.7X10-8 Np-239 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Os-185 Osmium (76) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Os-191 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Os-191m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Os-193 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Os-194 1.0X102 2.7X10-9 1.0X105 2.7X10-6 P-32 Phosphorus (15) 1.0X103 2.7X10-8 1.0X105 2.7X10-6 P-33 1.0X105 2.7X10-6 1.0X108 2.7X10-3 Pa-230 (a) Protactinium (91) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Pa-231 1.0 2.7X10-11 1.0X103 2.7X10-8 Pa-233 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Pb-201 Lead (82) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Pb-202 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Pb-203 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Pb-205 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Pb-210 (b) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Pb-212 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Pd-103 (a) Palladium (46) 1.0X103 2.7X10-8 1.0X108 2.7X10-3 Pd-107 1.0X105 2.7X10-6 1.0X108 2.7X10-3 Pd-109 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Pm-143 Promethium (61) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Pm-144 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Pm-145 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Pm-147 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Pm-148m (a) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Pm-149 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Pm-151 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Po-210 Polonium (84) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Pr-142 Praseodymium (59) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Pr-143 1.0X104 2.7X10-7 1.0X106 2.7X10-5

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 Pt-188 (a) Platinum (78) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Pt-191 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Pt-193 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Pt-193m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Pt-195m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Pt-197 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Pt-197m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Pu-236 Plutonium (94) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Pu-237 .0X103 2.7X10-8 1.0X107 2.7X10-4 Pu-238 1.0 2.7X10-11 1.0X104 2.7X10-7 Pu-239 1.0 2.7X10-11 1.0X104 2.7X10-7 Pu-240 1.0 2.7X10-11 1.0X103 2.7X10-8 Pu-241 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Pu-242 1.0 2.7X10-11 1.0X104 2.7X10-7 Pu-244 1.0 2.7X10-11 1.0X104 2.7X10-7 Ra-223 (b) Radium (88) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Ra-224 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Ra-225 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Ra-226 (b) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Ra-228 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Rb-81 Rubidium (37) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Rb-83 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Rb-84 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Rb-86 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Rb-87 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Rb(nat) 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Re-184 Rhenium (75) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Re-184m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Re-186 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Re-187 1.0X106 2.7X10-5 1.0X109 2.7X10-2 Re-188 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Re-189 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Re(nat) 1.0X106 2.7X10-5 1.0X109 2.7X10-2 Rh-99 Rhodium (45) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Rh-101 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Rh-102 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Rh-102m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Rh-103m 1.0X104 2.7X10-7 1.0X108 2.7X10-3 Rh-105 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Rn-222 (b) Radon (86) 1.0X101 2.7X10-10 1.0X108 2.7X10-3 Ru-97 Ruthenium (44) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Ru-103 (a) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Ru-105 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ru-106 (b) 1.0X102 2.7X10-9 1.0X105 2.7X10-6 S-35 Sulphur (16) 1.0X105 2.7X10-6 1.0X108 2.7X10-3 Sb-122 Antimony (51) 1.0X102 2.7X10-9 1.0X104 2.7X10-7 Sb-124 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Sb-125 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sb-126 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Sc-44 Scandium (21) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Sc-46 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Sc-47 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sc-48 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Se-75 Selenium (34) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Se-79 1.0X104 2.7X10-7 1.0X107 2.7X10-4

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 Si-31 Silicon (14) 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Si-32 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Sm-145 Samarium (62) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Sm-147 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Sm-151 1.0X104 2.7X10-7 1.0X108 2.7X10-3 Sm-153 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sn-113 (a) Tin (50) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Sn-117m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sn-119m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Sn-121m (a) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Sn-123 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Sn-125 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Sn-126 (a) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Sr-82 (a) Strontium (38) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Sr-85 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sr-85m 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Sr-87m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Sr-89 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Sr-90 (b) 1.0X102 2.7X10-9 1.0X104 2.7X10-7 Sr-91 1.0X101 2.7X10-10 1.0X105 2.7X10-6 Sr-92 1.0X101 2.7X10-10 1.0X106 2.7X10-5 T(H-3) Tritium (1) 1.0X106 2.7X10-5 1.0X109 2.7X10-2 Ta-178 (long-lived) Tantalum (73) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Ta-179 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Ta-182 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Tb-157 Terbium (65) 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Tb-158 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Tb-160 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Tc-95m Technetium (43) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Tc-96 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Tc-96m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Tc-97 1.0X103 2.7X10-8 1.0X108 2.7X10-3 Tc-97m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Tc-98 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Tc-99 1.0X104 2.7X10-7 1.0X107 2.7X10-4 Tc-99m 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Te-121 Tellurium (52) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Te-121m 1.0X102 2.7X10-9 1.0x106 2.7x10-5 Te-123m 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Te-125m 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Te-127 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Te-127m (a) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Te-129 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Te-129m (a) 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Te-131m (a) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Te-132 (a) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Th-227 Thorium (90) 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Th-228 (b) 1.0 2.7X10-11 1.0X104 2.7X10-7 Th-229 (b) 1.0 2.7X10-11 1.0X103 2.7X10-8 Th-230 1.0 2.7X10-11 1.0X104 2.7X10-7 Th-231 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Th-232 1.0X101 2.7X10-10 1.0X104 2.7X10-7 Th-234 (b) 1.0X103 2.7X10-8 1.0X105 2.7X10-6 Th (nat) (b) 1.0 2.7X10-11 1.0X103 2.7X10-8 Ti-44 Titanium (22) 1.0X101 2.7X10-10 1.0X105 2.7X10-6

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 Tl-200 Thallium (81) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Tl-201 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Tl-202 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Tl-204 1.0X104 2.7X10-7 1.0X104 2.7X10-7 Tm-167 Thulium (69) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Tm-170 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Tm-171 1.0X104 2.7X10-7 1.0X108 2.7X10-3 U-230 (fast lung Uranium (92) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 absorption) (b),(d)

U-230 (medium lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption) (e)

U-230 (slow lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption) (f)

U-232 (fast lung 1.0 2.7X10-11 1.0X103 2.7X10-8 absorption) (b),(d)

U-232 (medium lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption) (e)

U-232 (slow lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption) (f)

U-233 (fast lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption) (d)

U-233 (medium lung 1.0X102 2.7X10-9 1.0X105 2.7X10-6 absorption) (e)

U-233 (slow lung 1.0X101 2.7X10-10 1.0X105 2.7X10-6 absorption) (f)

U-234 (fast lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption) (d)

U-234 (medium lung 1.0X102 2.7X10-9 1.0X105 2.7X10-6 absorption) (e)

U-234 (slow lung 1.0X101 2.7X10-10 1.0X105 2.7X10-6 absorption) (f)

U-235 (all lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption types)

(b),(d),(e),(f)

U-236 (fast lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption) (d)

U-236 (medium lung 1.0X102 2.7X10-10 1.0X105 2.7X10-7 absorption) (e)

U-236 (slow lung 1.0X101 2.7X10-9 1.0X104 2.7X10-6 absorption) (f)

U-238 (all lung 1.0X101 2.7X10-10 1.0X104 2.7X10-7 absorption types)

(b),(d),(e),(f)

U (nat) (b) 1.0 2.7X10-11 1.0X103 2.7X10-8 U (enriched to 20% 1.0 2.7X10-11 1.0X103 2.7X10-8 or less)(g)

U (dep) 1.0 2.7X10-11 1.0X103 2.7X10-8 V-48 Vanadium (23) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 V-49 1.0X104 2.7X10-7 1.0X107 2.7X10-4 W-178 Tungsten (74) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 W-181 1.0X103 2.7X10-8 1.0X107 2.7X10-4 W-185 1.0X104 2.7X10-7 1.0X107 2.7X10-4 W-187 1.0X102 2.7X10-9 1.0X106 2.7X10-5 W-188 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Xe-122 Xenon (54) 1.0X102 2.7X10-9 1.0X109 2.7X10-2 Xe-123 1.0X102 2.7X10-9 1.0X109 2.7X10-2

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 Xe-127 1.0X103 2.7X10-8 1.0X105 2.7X10-6 Xe-131m 1.0X104 2.7X10-7 1.0X104 2.7X10-7 Xe-133 1.0X103 2.7X10-8 1.0X104 2.7X10-7 Xe-135 1.0X103 2.7X10-8 1.0X1010 2.7X10-1 Y-87 Yttrium (39) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Y-88 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Y-90 1.0X103 2.7X10-8 1.0X105 2.7X10-6 Y-91 1.0X103 2.7X10-8 1.0X106 2.7X10-5 Y-91m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Y-92 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Y-93 1.0X102 2.7X10-9 1.0X105 2.7X10-6 Yb-169 Ytterbium (79) 1.0X102 2.7X10-9 1.0X107 2.7X10-4 Yb-175 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Zn-65 Zinc (30) 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Zn-69 1.0X104 2.7X10-7 1.0X106 2.7X10-5 Zn-69m 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Zr-88 Zirconium (40) 1.0X102 2.7X10-9 1.0X106 2.7X10-5 Zr-93 (b) 1.0X103 2.7X10-8 1.0X107 2.7X10-4 Zr-95 1.0X101 2.7X10-10 1.0X106 2.7X10-5 Zr-97 (b) 1.0X101 2.7X10-10 1.0X105 2.7X10-6 NOTES:

(a) [Reserved]

(b) Parent nuclides and their progeny included in secular equilibrium are listed in the following:

Sr-90 Y-90 Zr-93 Nb-93m Zr-97 Nb-97 Ru-106 Rh-106 Cs-137 Ba-137m Ce-144 Pr-144 Ba-140 La-140 Bi-212 Tl-208 (0.36), Po-212 (0.64)

Pb-210 Bi-210, Po-210 Pb-212 Bi-212, Tl-208 (0.36), Po-212 (0.64)

Rn-222 Po-218, Pb-214, Bi-214, Po-214 Ra-223 Rn-219, Po-215, Pb-211, Bi-211, Tl-207 Ra-224 Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)

Ra-226 Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210 Ra-228 Ac-228 Th-228 Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36),

Po-212 (0.64)

Th-229 Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213, Pb-209 Th-nat Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)

Th-234 Pa-234m U-230 Th-226, Ra-222, Rn-218, Po-214

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 U-232 Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36),

Po-212 (0.64)

U-235 Th-231 U-238 Th-234, Pa-234m U-nat Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210 Np-237 Pa-233 Am-242m Am-242 Am-243 Np-239 (c) [Reserved]

(d) These values apply only to compounds of uranium that take the chemical form of UF6, UO2F2 and UO2(NO3)2 in both normal and accident conditions of transport.

(e) These values apply only to compounds of uranium that take the chemical form of UO3, UF4, UCl4 and hexavalent compounds in both normal and accident conditions of transport.

(f) These values apply to all compounds of uranium other than those specified in notes (d) and (e) of this table.

(g) These values apply to unirradiated uranium only.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE -A-3: GENERAL VALUES FOR A1 AND A2 A2 Activity Activity CONTENTS A1 concentration Activity limits Activity limits concentration for exempt for exempt for exempt for exempt TBq Ci TBq Ci material material consignments consignments (Bq/g) (Ci/g) (Bq) (Ci)

Only beta- or gamma-emitting nuclides are known 1 x 10-1 2.7 x 100 2 x 10-2 5.4 x 10-1 1 x 10-1 2.7 x 10-10 1 x 10-4 2.7 x 10-7 to be present Only alpha-emitting nuclides 2 x 10-1 5.4 x 100 9 x 10-5 2.4 x 10-3 1 x 10-1 2.7 x 10-12 1 x 103 2.7 x 10-8 are known to be present. a No relevant data are 1 x 10-3 2.7 x 10-2 9 x 10-5 2.4 x 10-3 1 x 10-1 2.7 x 10-12 1 x 103 2.7 x 10-8 available

a. If beta or gamma emitting nuclides are known to be present, the A1 value of 0.1TBq (2.7 Ci) should be used.

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 APPENDIX 13-A, TABLE A-4: ACTIVITY-MASS RELATIONSHIPS FOR URANIUM Uranium Enrichment*- Specific Activity weight % U-235 present TBq/g Ci/g 0.45 1.8 E-8 5.0 E-7 0.72 2.6 E-8 7.1 E-7 1.0 2.8 E-8 7.6 E-7 1.5 3.7 E-8 1.0 E-6 5.0 1.0 E-7 2.7 E-6 10.0 1.8 E-7 4.8 E-6 20.0 3.7 E-7 1.0 E-5 35.0 7.4 E-7 2.0 E-5 50.0 9.3 E-7 2.5 E-5 90.0 2.2 E-6 5.8 E-5 93.0 2.6 E-6 7.0 E-5 95.0 3.4 E-6 9.1 E-5

• The figures for uranium include representative values for the activity of the uranium-234 that is concentrated during the

EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13 ATTACHMENT 1 39 CFR Part 111, §111.1

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EFFECTIVE NEBRASKA DEPARTMENT OF 04-25-2021 HEALTH AND HUMAN SERVICES 180 NAC 13

[Code of Federal Regulations]

[Title 39, Volume 1]

[Revised as of January 1, 2008]

From the U.S. Government Printing Office via GPO Access

[CITE: 39 CFR 111.1]

[Page 26]

TITLE 39--POSTAL SERVICE CHAPTER I--UNITED STATES POSTAL SERVICE PART 111_GENERAL INFORMATION ON POSTAL SERVICE--Table of Contents Sec. 111.1 Mailing Standards of the United States Postal Service, Domestic Mail Manual; incorporated by reference of regulations governing domestic mail services.

Sec. 111.1 Mailing Standards of the United States Postal Service, Domestic Mail Manual; incorporation by reference of regulations governing domestic mail services.

111.2 Availability of the Mailing Standards of the United States Postal Service, Domestic Mail Manual.

111.3 Amendments to the Mailing Standards of the United States Postal Service, Domestic Mail Manual.

111.4 Approval of the Director of the Federal Register.

111.5 [Reserved]

Authority: 5 U.S.C. 552(a); 13 U.S.C. 301-307; 18 U.S.C. 1692-1737; 39 U.S.C. 101, 401, 403, 404, 414, 416, 3001-3011, 3201-3219, 3403-3406, 3621, 3626, 3632, 3633, and 5001.

Source: 44 FR 39852, July 6, 1979, unless otherwise noted.

Section 552(a) of title 5, U.S.C., relating to the public information requirements of the Administrative Procedure Act, provides in pertinent part that ``* *

• matter reasonably available to the class of persons affected thereby is deemed published in the Federal Register when incorporated by reference therein with the approval of the Director of the Federal Register. In conformity with that provision, and with 39 U.S.C.

section 410(b)(1), and as provided in this part, the U.S. Postal Service hereby incorporates by reference in this part, the Mailing Standards of the United States Postal Service, Domestic Mail Manual, a loose leaf document published and maintained by the Postal Service.

[62 FR 14827, Mar. 28, 1997, as amended at 69 FR 59139, Oct. 4, 2004; 70 FR 14535, Mar. 23, 2005]