Compilation of Rules and Regulations of the State of Georgia
Department 391 - RULES OF GEORGIA DEPARTMENT OF NATURAL RESOURCES
Chapter 391-3 - ENVIRONMENTAL PROTECTION
Subject 391-3-17 - RADIOACTIVE MATERIALS
Rule 391-3-17-.06 - Transportation of Radioactive Material

Universal Citation: GA Rules and Regs r 391-3-17-.06

Current through Rules and Regulations filed through September 23, 2024

(1) General.

(a) Purpose. The Regulations in this Rule, 391-3-17-.06, establish requirements for packaging, preparation for shipment, and transportation of radioactive material.

(b) Scope. This Rule applies to any licensee authorized by specific or general license issued by the Director, Agreement State, or NRC to receive, possess, use, or transfer licensed material to a carrier for transport of the material outside the site of usage as specified in the license, or transports that material on public highways or public access roads. No provision of this part authorizes possession of licensed material.

(2) Requirement for License. No person shall transport radioactive material or deliver radioactive material to a carrier for transport except as authorized in a general or specific license issued by the Director or as exempted in (4).

(3) Definitions. As used in this Rule, the following definitions apply:

(a) "A1" and "A2" mean, respectively, the maximum activity of special form radioactive material (A1) and the maximum activity of radioactive material, other than special form material, LSA, and SCO material (A2), permitted in a Type A package.

(b) "Carrier" means a person engaged in the transportation of passengers or property by land or water as a common, contract, or private carrier, or by civil aircraft.

(c) "Certificate holder" means a person who has been issued a certificate of compliance or other package approval by the U.S. Nuclear Regulatory Commission.

(d) "Certificate of Compliance (CoC)" means the certificate issued by the U.S Nuclear Regulatory Commission, which approves the design of a package for the transportation of radioactive material.

(e) "Close reflection by water" means immediate contact by water of sufficient thickness for maximum reflection of neutrons.

(f) "Closed transport vehicle" means 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 shall limit access from top, sides, and ends. In the case of packaged materials, it may be of the "see-through" type.

(g) "Consignment" means each shipment of a package or groups of packages or load of radioactive material offered by a shipper for transport.

(h) "Containment system" means the assembly components of the packaging intended to retain the radioactive material during transport.

(i) "Conveyance" means:
1. For transport by public highway or rail any transport vehicle or large freight container;

2. 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

3. For transport by any aircraft.

(j) "Criticality Safety Index (CSI)" means 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 391-3-17-.06(11) and (12) 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.

(k) "Deuterium" means deuterium and any deuterium compounds, including heavy water, in which the ratio of deuterium atoms to hydrogen atoms exceeds 1:5,000.

(l) "DOT" means the U.S. Department of Transportation.

(m) "Exclusive use" means the sole use of a conveyance by a single consignor and for which all initial, intermediate, and final loading and unloading are carried out in accordance with the direction of the consignor or consignee. The consignor and the carrier must ensure that any loading or unloading is 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.1

(n) "Fissile material" means the radionuclides uranium-233, uranium-235, plutonium-239, and plutonium-241, or any combination of these radionuclides. Fissile material means the fissile nuclides themselves, not material containing fissile nuclides. Neither natural nor depleted uranium is fissile material.2 Unirradiated natural uranium or depleted uranium that has been irradiated in thermal reactors only are not included in this definition. Certain exclusions from fissile material controls are provided in 10 CFR 71.15.

(o) "Graphite" means graphite with a boron equivalent content less than five (5) parts per million and density greater than 1.5 grams per cubic centimeter.

(p) "Indian Tribe" means an Indian or Alaska Native Tribe, band, nation, pueblo, village, or community that the Secretary of the Interior acknowledges to exist as an Indian Tribe pursuant to the Federally Recognized Indian Tribe List Act of 1994, 25 U.S.C. 479a.

(q) "Licensed material" means byproduct, source, or special nuclear material received, possessed, used, or transferred under a general or specific license issued by the U.S. Nuclear Regulatory Commission or an Agreement State pursuant to the regulations in 10 CFR or this Chapter, respectively.

(r) "Low specific activity material" means radioactive material with limited specific activity which is nonfissile or is excepted under 391-3-17-.06(4)(f), and which satisfies the descriptions and limits set forth below. Shielding materials surrounding the LSA material may not be considered in determining the estimated average specific activity of the package contents. The LSA material must be in one of three groups:
1. LSA-I
(i) Uranium and thorium ores, concentrates of uranium and thorium ores, and other ores containing naturally occurring radionuclides that are intended to be processed for the use of these radionuclides; or

(ii) Natural uranium, depleted uranium, natural thorium or their compounds or mixtures, provided they are unirradiated and in solid or liquid form; or

(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 in accordance with 391-3-17-.06(23).

2. LSA-II
(i) Water with tritium concentration up to 20.0 Ci/L (0.8 TBq/liter); or

(ii) Other radioactive material in which the activity is distributed throughout and the estimated average specific activity does not exceed 10-4 A2/g for solids and gases, and 10-5 A2/g for liquids.

3. LSA-III. Solids (e.g., consolidated wastes, activated materials), 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 (such as concrete, bitumen, ceramic, etc);

(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 by leaching, when placed in water for seven days, would not exceed 0.1 A2; and

(iii) The estimated average specific activity of the solid, excluding any shielding material, does not exceed 2x10-3 A2/g.

(s) "Low toxicity alpha emitters" means 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.

(t) "Maximum normal operating pressure" means the maximum gauge pressure that would develop in the containment system in a period of one year under the heat condition specified in 10 CFR 71.71(c)(1), in the absence of venting, external cooling by an ancillary system, or operational controls during transport.

(u) "Natural thorium" means thorium with the naturally occurring distribution of thorium isotopes (essentially 100 weight percent thorium-232).

(v) "Normal form radioactive material" means radioactive material that has not been demonstrated to qualify as "special form radioactive material."

(w) "Nuclear waste" means a quantity of source, byproduct or special nuclear material3 required to be in US Nuclear Regulatory Commission-approved specification packaging while transported to, through or across a state boundary to a disposal site, or to a collection point for transport to a disposal site.

(x) "Optimum interspersed hydrogenous moderation" means the presence of hydrogenous material between packages to such an extent that the maximum nuclear reactivity results.

(y) "Package" means the packaging together with its radioactive contents as presented for transport.
1. "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.

2. "Type A package" means a Type A packaging together with its radioactive contents. A Type A package is defined and must comply with the DOT regulations in 49 CFR Part 173.

3. "Type B package" means a Type B packaging together with its radioactive contents. On approval, a Type B package design is designated by NRC as B(U) unless the package has a maximum normal operating pressure of more than 700 kPa (100 lb/in2) gauge or a pressure relief device that would allow the release of radioactive material to the environment under the tests specified in 10 CFR Part 71 (hypothetical accident conditions), in which case 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 DOT regulations in 49 CFR Part 173. A Type B package approved before September 6, 1983, was designated only as Type B. Limitations on its use are specified in .06(8).

(z) "Packaging" means the assembly of components necessary to ensure compliance with the packaging requirements of this Rule. It may consist of one or more 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.

(aa) "Regulations of the U.S. Department of Transportation" means the regulations in 49 CFR Parts 100-189 and Parts 390-397.

(bb) "Regulations of the U.S. Nuclear Regulatory Commission" means the regulations in 10 CFR 71 for purposes of this Rule.

(cc) "Special form radioactive material" means radioactive material that satisfies the following conditions:
1. It is either a single solid piece or is contained in a sealed capsule that can be opened only by destroying the capsule;

2. The piece or capsule has at least one dimension not less than 5 millimeters (0.2 in.); and

3. It satisfies the requirements specified by the Nuclear Regulatory Commission in 10 CFR 71.75. A special form encapsulation designed in accordance with the requirements of 10 CFR 71.4 in effect on June 30, 1983 (see 10 CFR 71, revised as of January 1, 1983), and constructed prior to July 1, 1985, may continue to be used. A special form encapsulation designed in accordance with the Nuclear Regulatory Commission requirements in 10 CFR 71.4 in effect on March 31, 1996 (see 10 CFR 71, revised as of January 1, 1996), and constructed prior to April 1, 1998, may continue to be used. A special form material that was successfully tested before September 10, 2015 in accordance with the requirements of 10 CFR 71.75(d) in effect before September 10, 2015 may continue to be used. Any other special form must meet requirements of this definition applicable at the time of its design or construction.

(dd) "Specific activity" of a radionuclide means 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.

(ee) "Spent nuclear fuel or Spent fuel" means fuel that has been withdrawn from a nuclear reactor following irradiation, has undergone at least one (1) year's decay since being used as a source of energy in a power reactor, and has not been chemically separated into its constituent elements by reprocessing. Spent fuel includes the special nuclear material, byproduct material, source material, and other radioactive materials associated with fuel assemblies.

(ff) "Surface Contaminated Object (SCO)" means a solid object that is not itself classed as radioactive material, but which has radioactive material distributed on any of its surfaces. SCO must be in one of two groups with surface activity not exceeding the following limits:
1. SCO-I: 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 10-4 microcurie/cm2 (4 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 10-5 microcurie/cm2 (0.4 Bq/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 1.0 microcurie/cm2 (4x104 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 0.1 microcurie/cm2 (4x103 Bq/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 1.0 microcurie/cm2 (4x104 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 0.1 microcurie/cm2 (4x103 Bq/cm2) for all other alpha emitters.

2. SCO-II: A solid object on which the limits for 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 10-2 microcurie/cm2 (400 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 10-3 microcurie/cm2 (40 Bq/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 20 microcurie/cm2 (8x105 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 2 microcurie/cm2 (8x104 Bq/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 20 microcurie/cm2 (8x105 Bq/cm2) for beta and gamma and low toxicity alpha emitters, or 2 microcurie/cm2 (8x104 Bq/cm2) for all other alpha emitters.

(gg) "Transport index" means the dimension-less 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 transportation index is the number expressing the maximum radiation level in millirem per hour at 1 meter from the external surface of the package.

(hh) "Tribal official" means the highest ranking individual that represents Tribal leadership, such as the Chief, President, or Tribal Council leadership.

(ii) "Type A package" means a packaging that, together with its radioactive contents limited to A1 or A2 as appropriate, meets the requirements of 49 CFR 173.410 and 173.412 and is designed to retain the integrity of containment and shielding required by this Rule under normal conditions of transport as demonstrated by the tests set forth in 49 CFR 173.465 or 173.466, as appropriate.

(jj) "Type A quantity" means 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 Table 4, "A1 and A2 Values for Radionuclides" or may be determined by procedures described in (23) of this Rule.

(kk) "Type B package" is defined in Rule 391-3-17-.01(2)(ttt).

(ll) "Type B packaging" means a packaging designed to retain the integrity of containment and shielding when subjected to the normal conditions of transport and hypothetical accident test conditions set forth in 10 CFR Part 71.

(mm) "Type B quantity" means a quantity of radioactive material greater than a Type A quantity.

(nn) "Unirradiated uranium" means uranium containing not more than 2x103 Bq of plutonium per gram of uranium-235, not more than 9x106 Bq of fission products per gram of uranium-235, and not more than 5x10-3 grams of uranium-236 per gram of uranium-235.

(oo) "Uranium-natural, depleted, enriched" means:
1. Natural uranium means 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).

2. Depleted uranium means uranium containing less uranium-235 than the naturally occurring distribution of uranium isotopes.

3. Enriched uranium means uranium containing more uranium-235 than the naturally occurring distribution of uranium isotopes.

(pp) "Contamination" means the presence of a radioactive substance on a surface in quantities in excess of 0.4 Bq/cm2 (1x10-5 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.
1. Fixed contamination means contamination that cannot be removed from a surface during normal conditions of transport

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

(4) Exemptions.

(a) Common and contract carriers, freight forwarders, and warehousemen who 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 Manual (Domestic Mail Manual), Section C-023.9.0, and the U.S. Postal Service, are exempt from the requirements of this Rule and as stated in 10 CFR 30.13 to the extent that they transport or store radioactive material in the regular course of their carriage for others or storage incident thereto. Common and contract carriers who are not subject to the requirements of the U.S. Department of Transportation or U.S. Postal Service are subject to (2) of this Rule and other applicable requirements of these Regulations.

(b) Any licensee is exempt from the requirements of this Rule to the extent that the licensee delivers to a carrier for transport a package containing radioactive material having a specific activity not greater than 0.002 microcurie per gram (70 Bq/gm).

(c) Any physician licensed by Georgia to dispense drugs in the practice of medicine is exempt from Rule .06 with respect to transport by the physician of licensed material for use in the practice of medicine. However, any physician operating under this exemption must be licensed under Rule .05.

(d) A licensee is exempt from the requirements of Rule .06 with respect to shipment or carriage of the following low-level materials:
1. 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 use of these radionuclides, provided the activity concentration of the material does not exceed 10 times the applicable radionuclide activity concentration values specified in Table 5 and 7.

2. Materials for which the activity concentration is not greater than the activity concentration values specified in Table 5 and 7, or for which the consignment activity is not greater than the limit for an exempt consignment found in Table 5 and 7.

3. 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 391-3-17-.06(3)(pp).

(e) A licensee is exempt from the requirements of Rule .06, other than .06(5) and .06(17), with respect to shipment or carriage of the following packages, providing the packages do not contain any fissile material, or the material is exempt from classification as fissile material in .06(4)(f):
1. A package that contains no more than a Type A quantity of radioactive material;

2. A package transported within the United States that contains no more than 20 Ci (0.74 TBq) of special form plutonium-244; or

3. A package contains LSA or SCO radioactive material, provided that the LSA or SCO material has an external radiation dose of less than or equal to 1 rem/hr (10 mSv/hr) at a distance of 3 meters from the unshielded material or that the package contains only LSA-I or SCO-I material.

(f) Fissile material meeting the requirements of at least one of the following six paragraphs in this part 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 this part, except as noted.
1. Individual package containing two (2) grams or less of fissile material.

2. Individual or bulk packaging containing fifteen (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.

3. Low concentrations of solid fissile material commingled with solid nonfissile material, provided that (i) there is at least 2,000 grams of solid nonfissile material for every gram of fissile material, and (ii) there is no more than 180 grams of fissile material distributed within 360 kg of contiguous nonfissile 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.

4. Uranium enriched in uranium-235 to a maximum of one (1) percent by weight, and with a total plutonium and uranium-233 content of up to one (1) percent of the mass of uranium-235, provided that the mass of any beryllium, graphite, and hydrogenous material enriched in deuterium constitutes less than five (5) percent of the uranium mass, and that the fissile material is distributed homogeneously and does not form a lattice arrangement within the package.

5. Liquid solutions of uranyl nitrate enriched in uranium-235 to a maximum of two (2) percent by mass, with a total plutonium and uranium-233 content not exceeding 0.002 percent 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 DOT Type A package.

6. Packages containing, individually, a total plutonium mass of not more than 1,000 grams, of which not more than twenty (20) percent by mass may consist of plutonium-239, plutonium-241, or any combination of these radionuclides.

(5) Transportation of Licensed Material.

(a) Each licensee who transports licensed material outside the site of usage, as specified in a Division license, or where transport is on public highway, or public access road, or who delivers licensed material to a carrier for transport, shall:
1. Comply with the applicable requirements, appropriate to the mode of transport, of the regulations of the US Department of Transportation (DOT).
(i) The licensee shall particularly note DOT regulations in the following areas:
(I) Packaging - 49 CFR Part 173, Subparts A and B and I.

(II) Marking and Labeling - 49 CFR Part 172 : Subpart D, and §§ 49 CFR 172.400 through 172.407, §§ 172.436 through 172.440 of Subpart E.

(III) Placarding - 49 CFR Part 172 : Subpart F, especially §§ 172.500 through 172.519, 172.556 and Appendices B and C.

(IV) Accident Reporting - 49 CFR Part 171: §§ 171.15 and 171.16.

(V) Shipping Papers and Emergency Information - 49 CFR Part 172, Subpart C and Subpart G.

(VI) Hazardous material employee training - 49 CFR Part 172: Subpart H.

(VII) Security Plans - 49 CFR Part 172: Subpart I.

(VIII) Hazardous material shipper/carrier registration - 49 CFR Part 107 : Subpart G.

(ii) The licensee shall also note DOT regulations pertaining to the following modes of transportation:
(I) Rail - 49 CFR Part 174, Subparts A through D and K.

(II) Air - 49 CFR Part 175.

(III) Vessel - 49 CFR Part 176, Subparts A through F and M.

(IV) Public Highway - 49 CFR Part 177 and Parts 390 through 397.

2. Assure that any special instructions needed to safely open the package are sent to or have been made available to the consignee in accordance with Rule 391-3-17-.03(12)(f).

(b) If, for any reason, the regulations of the DOT are not applicable to a shipment of licensed material, the licensee shall conform to the standards and requirements of 49 CFR Parts 170-189 appropriate to the mode of transport to the same extent as if the shipment was subject to the regulations.

(6) General Licenses for Carriers.

(a) A general license is hereby issued to any common or contract carrier not exempt under (4) to receive, possess, transport, and store radioactive material in the regular course of their carriage for others or storage incident thereto, provided the transportation and storage is in accordance with the applicable requirements, appropriate to the mode of transport, of the DOT insofar as such requirements relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting.4

(b) A general license is hereby issued to any private carrier to transport radioactive material, provided the transportation is in accordance with the applicable requirements, appropriate to the mode of transport, of the DOT insofar as such requirements relate to the loading and storage of packages, placarding of the transporting vehicle, and incident reporting.

(c) Persons who transport radioactive material pursuant to the general licenses in (6)(a) or (b) are exempt from the requirements of Rules 391-3-17-.03 and .07 to the extent that they transport radioactive material.

(7) General License: NRC-Approved Packages.

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

(b) Each licensee issued a general license under .06(7)(a) shall:
1. Possess a copy of the specific license, certificate of compliance, or other approval of the package and 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;

2. Comply with the terms and conditions of the license, certificate, or other approval by the Nuclear Regulatory Commission, as applicable, and the applicable requirements of this Rule;

3. Submit in writing before the first use of the package to: ATTN: Document Control Desk, Director, Division of Fuel Management, Office of Nuclear Material Safety and Safeguards, using an appropriate method listed in 10 CFR 71.71(a), the licensee's name and license number and the package identification number specified in the package approval.

(c) This general license applies only to a licensee who has a quality assurance program required by the Georgia Department of Natural Resources Radioactive Materials Program satisfying the provisions of (22).

(d) The general license in (7)(a) applies only when the package approval authorizes use of the package under this general license.

(e) For a Type B or fissile material package the design of which was approved by NRC before April 1, 1996 the general license is subject to additional restrictions of 10 CFR 71.19.

(8) [Reserved].

(9) General License: DOT Specification Container.

(a) A general license is issued to any licensee of the Division to transport, or to deliver to a carrier for transport, licensed material in a specification container for fissile material or for a Type B quantity of radioactive material as specified in 49 CFR Parts 173 and 178.

(b) This general license applies only to a licensee who:
1. Has a copy of the specification;

2. Complies with the terms and conditions of the specification and the applicable requirements of this Rule; and

3. Has a quality assurance program required by (22).

(c) The general license in (9)(a) is subject to the limitation that the specification container may not be used for a shipment to a location outside the United States, except by multilateral approval, as defined in DOT regulations at 49 CFR 173.403.

(10) General License: Use of Foreign-Approved Package.

(a) A general license is issued to any licensee of the Division 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 DOT as meeting the applicable requirements of 49 CFR 171.23.

(b) This general license applies only to international shipments.

(c) This general license applies only to a licensee who:
1. 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;

2. Complies with the terms and conditions of the certificate and revalidation and with the applicable requirements of this Rule; and

3. Has a quality assurance program approved by the Georgia Department of Natural Resources, Environmental Protection Division, Radioactive Materials Program satisfying the requirements of (22).

(11) General License: Fissile Material, Limited Quantity per Package.

(a) A general license is hereby issued to any licensee to transport fissile material, or to deliver fissile material to a carrier for transport, if the material is shipped in accordance with this section. The material must be contained in a Type A package. The Type A package must also meet the DOT requirements of 49 CFR 173.417(a).

(b) This general license applies only to a licensee who has a quality assurance program required by (22).

(c) This general license applies only when a package contains no more than a Type A quantity of fissile material and contains less than 500 grams total of beryllium, graphite, or hydrogenous material enriched in deuterium.

(d)
1.

This general license applies only to packages containing fissile material that are labeled with a Criticality Safety Index (CSI), defined as

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where the values of X, Y, and Z used in the CSI equation must be taken from Tables 1 or 2, as appropriate. If Table 2 is used to obtain the value of X, then the values for the terms for uranium-233 and plutonium must be assumed to be zero. Table 1 values for X, Y, and Z must be used to determine the CSI if:

i. Uranium-233 is present in the package;

ii. The mass of plutonium exceeds one (1) percent of the mass of uranium-235;

iii. The uranium is of unknown uranium-235 enrichment or greater than 24 weight percent enrichment; or

iv. Substances having a moderating effectiveness (i.e., an average hydrogen density greater than water) (e.g., certain hydrocarbon oils or plastics) are present in any form, except as polyethylene used for packing or wrapping.

2. In all cases, the Criticality Safety Index must be rounded up to one decimal place and may not exceed 10.0.

3. For a shipment of multiple packages containing fillies material, the sum of the CSIs must be less than or equal to 50 (for shipment on a non-exclusive use conveyance) and less than or equal to 100 (for shipment on an exclusive use conveyance).

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Table 1

Fissile Material

Fissile Material mass mixed with moderating substances having an average hydrogen density less than or equal to water (in grams)

Fissile Material mass mixed with moderating substances having an average hydrogen density greater than water(a) (in grams)

235U (X)

60

38

233U (Y)

43

27

239Pu or 241Pu (Z)

37

24
(a) - When mixtures of moderating substances are present, the lower mass limits shall be used if more than 15 percent of the moderating substances has an average hydrogen density greater than water.

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Table 2

Mass Limits for General License Packages Containing Uranium-235 of Known Enrichment

Uranium Enrichment in weight percent of 235U not exceeding

Fissile Material mass of 235U (X)

(in grams)

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*

*- Pursuant to the Division's agreement with the USNRC, jurisdiction extends only to 350 grams of uranium-235.

______________________________________________________

(12) General License: Plutonium-Beryllium Special Form Material.

(a) A general license is hereby issued to any licensee to transport 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 in accordance with this section. The material must be contained in a Type A package. The Type A package must also meet the DOT requirements of 49 CFR 173.417(a).

(b) This general license applies only when all of the following requirements are met:
1. The package contains no more than a Type A quantity of radioactive material.

2. The package contains less than 1,000 grams of plutonium, provided that: plutonium-239, plutonium-241, or any combination of these radionuclides, constitutes less than 240 grams of the total quantity of plutonium in the package.

(c)
1. This general license applies only to packages that are labeled with a Criticality Safety Index, calculated by:

CSI = (10 / 24) x (grams 239Pu + grams 241Pu)

where the CSI value is less than or equal to 100 and must be rounded up to the first decimal place.

2. For a shipment of multiple packages containing Pu-Be sealed sources, the sum of the CSIs 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).

(d) The general license has a quality assurance program required by (22).

(13) Assumptions as to Unknown Properties of Fissile Material. 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 shall package the fissile material as if the unknown properties had credible values that will cause the maximum neutron multiplication.

(14) External Radiation Standards For All Packages.

(a) Except as provided in (14)(b), each package of radioactive materials offered for transportation must be designed and prepared for shipment so that under conditions normally incident to transportation the radiation level does not exceed 200 mrem/hr (2 mSv/hr) at any point on the external surface of the package, and the transport index does not exceed 10.

(b) A package that exceeds the radiation level limits specified in (14)(a) must be transported by exclusive use shipment only, and the radiation levels for such shipment must not exceed the following during transportation:
1. 200 mrem/hr (2 mSv/hr) on the external surface of the package, unless the following conditions are met, in which case the limit is 1,000 mrem/hr (10 mSv/hr):
(i) The shipment is made in a closed transport vehicle;

(ii) The package is secured within the vehicle so that its position remains fixed during transportation; and

(iii) There are no loading or unloading operations between the beginning and end of the transportation;

2. 200 mrem/hr (2 mSv/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 flat-bed 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; and

3. 10 mrem/hr (0.1 mSv/hr) at any point two (2) meters (80 inches) from the outer lateral surfaces of the vehicle (excluding the top and underside of the vehicle); or in the case of a flat-bed style vehicle, at any point two (2) meters (6.6 feet) from the vertical planes projected by the outer edges of the vehicle (excluding the top and underside of the vehicle); and

4. 2 mrem/hr (0.02 mSv/hr) in any normally occupied space, except that this provision does not apply to private carriers, if exposed personnel under their control wear radiation dosimetry devices in conformance with Rule 391-3-17-.03(8)(b).

(c) For shipments made under the provisions of (14)(b), the shipper will 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.

(d) 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 members of the general public.

(15) Preliminary Determinations. Prior to the first use of any packaging for the shipment of radioactive material:

(a) The licensee shall ascertain that the determinations in 10 CFR 71.85(a) through (c) have been made.

(16) Routine Determinations. Prior to each shipment of licensed material, the licensee shall determine that:

(a) The package is proper for the contents to be shipped;

(b) The package is in unimpaired physical condition except for superficial defects such as marks or dents;

(c) Each closure device of the packaging, including any required gasket, is properly installed and secured and free of defects;

(d) Any system for containing liquid is adequately sealed and has adequate space or other specified provision for expansion of the liquid;

(e) Any pressure relief device is operable and set in accordance with written procedures;

(f) The package has been loaded and closed in accordance with written procedures;

(g) For fissile material, any moderator or neutron absorber, if required, is present and in proper condition;

(h) 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 by 10 CFR 71.45;

(i) The level of non-fixed radioactive contamination on the external surfaces of each package offered for shipment is as low as reasonably achievable.
1. The level of non-fixed 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 (16)(i)2., the amount of radioactivity measured on any single wiping material, when averaged over the surface wiped, must not exceed the limits given in Table 3 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 3.

2. In the case of packages transported as exclusive use shipments by rail or highway only, the non-fixed radioactive contamination at any time during transport must not exceed 10 times the levels prescribed in (16)(i)1. The levels at the beginning of transport must not exceed the levels in (16)(i)1.;

_____________________________________________________

Table 3

Maximum Permissible limits

Contaminant

µCi/cm2

dpm/cm2

Bq/cm2

Beta-/gamma-emitting radionuclides; and low toxicity alpha emitters................

10-5

22

0.4

All other alpha-emitting radionuclides..........................................

10-6

2.2

0.04

______________________________________________________

(j) External radiation levels around the package and around the vehicle, if applicable, will not exceed 200 millirem per hour (2 mSv/hr) at any point on the external surface of the package at any time during transportation. The transport index shall not exceed 10.

(k) For package transported as exclusive use by rail, highway, or water, radiation levels external to the package may exceed the limits specified in (16)(j). but shall not exceed any of the following:
1. 200 millirem per hour (2 mSv/hr) on the accessible external surface of the package unless the following conditions are met, in which case the limit is 1,000 millirem per hour (10 mSv/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;

2. 200 millirem per hour (2 mSv/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 flat-bed style vehicle with a personnel barrier5, 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;

3. 10 millirem per hour (0.1 mSv/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 flat-bed style vehicle, at any point 2 meters from the vertical planes projected from the outer edges of the vehicle; and

4. 2 millirem per hour (0.02 mSv/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 in accordance with 391-3-17-.07(3) of this Chapter; and

(l) 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 Fahrenheit (85 degrees Celsius) in an exclusive use shipment. Accessible package surface temperatures shall not exceed these limits at any time during transportation.

(m) A package may not incorporate a feature intended to allow continuous venting during transport.

(17) Air Transport of Plutonium. Notwithstanding the provisions of any general licenses and notwithstanding any exemptions stated directly in this Rule or included indirectly by citation of the DOT regulations, as may be applicable, the licensee shall 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 not greater than the activity concentration values for plutonium as specified in Table 7, and 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 in accordance with (5); or

(d) The plutonium is shipped in a package specifically authorized, in the certificate of compliance, issued by the Nuclear Regulatory Commission, for the shipment of plutonium by air and the licensee requires, through special arrangement with the carrier, compliance with 49 CFR 175.704, the US Department of Transportation regulations applicable to the air transport of plutonium.

(18) Opening instructions. Before delivery of a package to a carrier for transport, the licensee shall ensure that any special instructions needed to safely open the package have been sent to, or otherwise made available to, the consignee for the consignee's use in accordance with Rule 391-3-17-.03(12)(f).

(19) Shipment Records. Each licensee shall maintain for a period of three years after shipment a record of each shipment of licensed material not exempt under (4), showing, where applicable:

(a) Identification of the packaging by model number;

(b) Verification that there were no significant defects in the packaging, as shipped;

(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 (16) and the conditions of the package approval.

(i) The licensee shall make available to the Division for inspection, upon reasonable notice, all records required by this part. Records are only valid if stamped, initialed, or signed and dated by authorized personnel, or otherwise authenticated.

(j) The licensee shall maintain sufficient written records to furnish evidence of the quality of packaging. The records to be maintained include results of the determinations required by 391-3-17-.06(15) and 10 CFR 71.85; 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.

(k) For each item of irradiated fissile material -
1. Identification by model number and serial number;

2. Irradiation and decay history to the extent appropriate to demonstrate that its nuclear and thermal characteristics comply with license conditions; and

3. Any abnormal or unusual condition relevant to radiation safety;

(l) For fissile packages and for Type B packages, any special controls exercised.

(20) Reports. The licensee shall report to the Division within 30 days:

(a) Any instance in which there is significant reduction in the effectiveness of any authorized packaging during use; and

(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.

(21) Advance Notification of Transport of Nuclear Waste.

(a) As specified in paragraphs (b), (c), and (d) of this section, each licensee shall provide advance notification to the governor of a State, or the governor's designee6, 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.
1. As specified in paragraphs (b), (c), and (d) of this section, after June 11, 2013, each licensee shall provide advance notification to the Tribal official of participating Tribes referenced in paragraph (d)3.(iii) of this section, 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.

(b) Advance notification is also required when:
1. The licensed material is required to be in Type B packaging for transportation;

2. The licensed material is being transported into, within, or through, a state en route to a disposal facility or to a collection point for transport to a disposal facility; and

3. The quantity of licensed material in a single package exceeds the least of the following:
(i) 3000 times the A1 value of the radionuclides as specified in Table 7, for special form radioactive material;

(ii) 3000 times the A2 value of the radionuclides as specified in Table 7 for normal form radioactive material; or

(iii) 27,000 Ci (1000 TBq);

(c) Each advance notification required by .06(21)(a) shall contain the following information:
1. The name, address, and telephone number of the shipper, carrier, and receiver of the shipment;

2. A description of the nuclear waste contained in the shipment as required by 49 CFR 172.202 and 172.203(d);

3. The point of origin of the shipment and the seven-day period during which departure of the shipment is estimated to occur;

4. The seven-day period during which arrival of the shipment at state boundaries or Tribal reservation boundaries is estimated to occur;

5. The destination of the shipment, and the seven-day period during which arrival of the shipment is estimated to occur; and

6. A point of contact with a telephone number for current shipment information.

(d) Procedures for Submitting Advance Notification:
1. The notification required by .06(21)(a) shall be made in writing to the office of each appropriate governor, or governor's designee, to the office of each appropriate Tribal official or Tribal official's designee, and to the Division.

2. A notification delivered by mail must be postmarked at least seven days before the beginning of the seven-day period during which departure of the shipment is estimated to occur.

3. A notification delivered by any other means than mail must reach the office of the governor or of the governor's designee or the Tribal official or Tribal official's designee at least four days before the beginning of the seven-day period during which departure of the shipment is estimated to occur.
(i) [Reserved]

(ii) The list of governor's designees and Tribal official's designees of participating Tribes will be published annually in the Federal Register on or about June 30th to reflect any changes in information.

(iii) A list of the names and mailing addresses of the governors' designees and Tribal officials' designees of participating Tribes, including telephone and mailing addresses of Tribal official's designees, is available on the NRC Web site at: https://scp.nrc.gov/special/designee.pdf.

4. A copy of the notification shall be retained by the licensee for three years.

(e) A licensee who finds that schedule information previously furnished to a governor or governor's designee or a Tribal official or Tribal official's designee, in accordance with this section, will not be met, shall 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 official's designee and inform that individual of the extent of the delay beyond the schedule originally reported. The licensee shall maintain a record of the name of the individual contacted for three years.

(f) Each licensee who cancels a nuclear waste shipment for which advance notification has been sent shall send a cancellation notice to the governor of each State or to the governor's designee previously notified, each Tribal official or to the Tribal official's designee previously notified, and to the Division.
1. The licensee shall state in the notice that it is a cancellation and identify the advance notification that is being cancelled. The licensee shall retain a copy of the notice as a record for 3 years.

(22) Quality Assurance Requirements.

This paragraph 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. As used in this paragraph, "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 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 subpart.

(a) Unless otherwise authorized by the Division, each licensee shall establish, maintain, and execute a quality assurance program to verify by procedures such as checking, auditing, and inspection that deficiencies, deviations, and defective material and equipment relating to the shipment of packages containing radioactive material are promptly identified and corrected.

(b) The licensee shall identify the material and components to be covered by the quality assurance program.

(c) Each licensee shall document the quality assurance program by written procedures or instructions and shall carry out the program in accordance with those procedures throughout the period during which packaging is used.

(d) Prior to the use of any package for the shipment of radioactive material, each licensee shall obtain approval by the Division of its quality assurance program.

(e) The licensee shall 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 shall be maintained for a period of three years after shipment.

(f) Radiography containers. A program for transport container inspection and maintenance limited to radiographic exposure devices, source changers, or packages transporting these devices and meeting the requirements of rule 391-3-17-.04(11)(d) and (e) or equivalent NRC or Agreement State requirement, is deemed to satisfy the requirements of 391-3-17-.06(7) and .06(22)(g).

(g) Establishment of program. Each licensee shall establish, maintain, and execute a quality assurance program satisfying each of the applicable criteria of 391-3-17-.06(22) and satisfying any specific provisions that are applicable to the licensee's activities including procurement of packaging. The licensee shall execute the applicable criteria in a graded approach to an extent that is commensurate with the quality assurance requirement's importance to safety.

(h) Approval of program.
1. Before the use of any package for the shipment of licensed material subject to this paragraph, each licensee shall obtain Division approval of its quality assurance program. Using an appropriate method listed in 391-3-17-.06(22), each licensee shall file a description of its quality assurance program, including a discussion of which requirements of this subpart are applicable and how they will be satisfied, by submitting the description to: Georgia Department of Natural Resources/Environmental Protection Division, Radioactive Materials Program, at 4244 International Parkway, Suite 120, Atlanta, Georgia 30354.

(i) Quality Assurance Organization
1. The licensee shall 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 shall retain responsibility for the program. These activities include performing the functions associated with attaining quality objectives and the quality assurance functions.

2. The quality assurance functions are:
(i) Assuring that an appropriate quality assurance program is established and effectively executed; and

(ii) Verifying, by procedures such as checking, auditing, and inspection, that activities affecting the functions that are important to safety have been correctly performed.

(j) Changes to Quality Assurance Programs
1. Each quality assurance program approval holder shall submit, in accordance with the requirements of 391-3-17-.01(13) and 391-3-17-.06(19), a description of a proposed change to its Georgia Department of Natural Resources Radioactive Materials Program approved quality assurance program that will reduce commitments in the program description as approved by the Georgia Department of Natural Resources Radioactive Materials Program. The quality assurance program approval holder shall not implement the change before receiving Georgia Department of Natural Resources Radioactive Materials Program approval.
(i) The description of a proposed change to the Georgia Department of Natural Resources Radioactive Materials Program 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 391-3-17-.06(22).

(ii) [Reserved]

2. Each quality assurance program approval holder may change a previously approved quality assurance program without prior Georgia Department of Natural Resources Radioactive Materials Program approval, if the change does not reduce the commitments in the quality assurance program previously approved by the Georgia Department of Natural Resources Radioactive Materials Program. Changes to the quality assurance program that do not reduce the commitments shall be submitted to the Georgia Department of Natural Resources Radioactive Materials Program every 24 months, in accordance with 391-3-17-.01(13). In addition to quality assurance program changes involving administrative improvements and clarifications, spelling corrections, and non-substantive changes to punctuation or editorial items, the following changes are not considered reductions in commitment:
(i) The use of a quality assurance standard approved by the Georgia Department of Natural Resources Radioactive Materials Program that is more recent than the quality assurance standard in the applicant's current quality assurance program at the time of the change;

(ii) 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;

(iii) 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;

(iv) 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

(v) 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.

3. Each quality assurance program approval holder shall maintain records of quality assurance program changes.

(k) Quality Assurance Records
1. The licensee shall maintain sufficient written records to describe the activities affecting quality. These records must include changes to the quality assurance program as required by 391-3-17-.06(22)(j), the instructions, procedures, and drawings required by 10 CFR 71.111 to prescribe quality assurance activities, and closely related specifications such as required qualifications of personnel, procedures, and equipment. The records must include the instructions or procedures that establish a records retention program that is consistent with applicable regulations and designates factors such as duration, location, and assigned responsibility. The licensee shall retain these records for 3 years beyond the date when the licensee last engage in the activity for which the quality assurance program was developed. If any portion of the quality assurance program, written procedures or instructions is superseded, the licensee shall retain the superseded material for 3 years after it is superseded.

(23) Determination of A1 and A2.

(a) Values of A1 and A2 for individual radionuclides, which are the bases for many activity limits elsewhere in these regulations, are given in Table 4. 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.

(b)
1. For individual radionuclides whose identities are known but are not listed in Table 4, the A1 and A2 values contained in Table 5 may be used. Otherwise, the licensee shall obtain prior Division approval of the A1 and A2 values for radionuclides not listed in Table 4, before shipping the material

2. For individual radionuclides whose identities are known but are not listed in Table 7, the exempt material activity concentration and exempt consignment activity values contained in Table 5 may be used. Otherwise, the licensee shall obtain prior Division approval of the exempt material activity concentration and exempt consignment activity values for radionuclides not listed in Table 7, before shipping the material.

(c) In calculations of A1 and A2 for a radionuclide not in Table 4, a single radioactive decay chain, in which radionuclides are present in their naturally occurring proportions, and in which no daughter nuclide has a half-life either longer than 10 days, or longer than that of the parent nuclide, shall be considered as a single radionuclide, and the activity to be taken into account, and the A1 and A2 value to be applied shall be those corresponding to the parent nuclide of that chain. In the case of radioactive decay chains in which any daughter nuclide has a half-life either longer than ten days, or greater than of the parent nuclide, the parent and those daughters nuclides shall be considered as a mixture of different nuclides.

(d) Mixtures of radionuclides.
1. For mixture of radionuclides whose identities and respective activities are known, following conditions apply:
(i) For a special form radioactive material, the maximum quantity transported in a Type A package is as follows:

Click here to view

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

(ii) For normal form radioactive material, the maximum quantity transported in a Type A package is as follows:

Click here to view

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

(iii) 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:

Click here to view

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.

(iv) Alternatively, the A1 value for mixtures of special form material may be determined as follows:

A1 for mixture =

Click here to view

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

(v) Alternatively, the A2 value for mixtures of normal form material may be determined as follows:

A2 for mixture =

Click here to view

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.

(e) The exempt activity concentration for mixtures of radionuclides may be determined as follows:

Exempt activity concentration for mixture =

Click here to view

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

(f) The activity limit for an exempt consignment for mixtures of radionuclides may be determined as follows:

Exempt consignment activity limit for mixture =

Click here to view

where f(i) is the fraction of activity of radionuclide i in the mixture and [A] is the activity limit for exempt consignments for radionuclide i.

(g)
1. 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 formulas above. 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.

2. 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 391-3-17-.06(23). 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.

Table 4- A1 and A2 VALUES FOR RADIONUCLIDES

Symbol of radionuclide

Element and atomic number

A1 (TBq)

A1(Ci)b

A2 (TBq)

A2(Ci)b

Specific activity

(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

8.4X104

2.2X106

Ag-105

Silver (47)

2.0

5.4X101

2.0

5.4X101

1.1X103

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

1.8X102

4.7X103

Ag-111

2.0

5.4X101

6.0X10-1

1.6X101

5.8X103

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

3.7X103

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

1.5X106

4.2X107

As-72

Arsenic (33)

3.0X10-1

8.1

3.0X10-1

8.1

6.2X104

1.7X106

As-73

4.0X101

1.1X103

4.0X101

1.1X103

8.2X102

2.2X104

As-74

1.0

2.7X101

9.0X10-1

2.4X101

3.7X103

9.9X104

As-76

3.0X10-1

8.1

3.0X10-1

8.1

5.8X104

1.6X106

As-77

2.0X101

5.4X102

7.0X10-1

1.9X101

3.9X104

1.0X106

At-211 (a)

Astatine (85)

2.0X101

5.4X102

5.0X10-1

1.4X101

7.6X104

2.1X106

Au-193

Gold (79)

7.0

1.9X102

2.0

5.4X101

3.4X104

9.2X105

Au-194

1.0

2.7X101

1.0

2.7X101

1.5X104

4.1X105

Au-195

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

1.5X103

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

2.6X104

7.1X105

Br-82

4.0X10-1

1.1X101

4.0X10-1

1.1X101

4.0X104

1.1X106

C-11

Carbon (6)

1.0

2.7X101

6.0X10-1

1.6X101

3.1X107

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

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

2.5X102

6.8X103

Ce-141

2.0X101

5.4X102

6.0X10-1

1.6X101

1.1X103

2.8X104

Ce-143

9.0X10-1

2.4X101

6.0X10-1

1.6X101

2.5X104

6.6X105

Ce-144 (a)

2.0X10-1

5.4

2.0X10-1

5.4

1.2X102

3.2X103

Cf-248

Californium (98)

4.0X101

1.1X103

6.0X10-3

1.6X10-1

5.8X101

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

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

1.1X105

3.1X106

Co-56

3.0X10-1

8.1

3.0X10-1

8.1

1.1X103

3.0X104

Co-57

1.0X101

2.7X102

1.0X101

2.7X102

3.1X102

8.4X103

Co-58

1.0

2.7X101

1.0

2.7X101

1.2X103

3.2X104

Co-58m

4.0X101

1.1X103

4.0X101

1.1X103

2.2X105

5.9X106

Co-60

4.0X10-1

1.1X101

4.0X10-1

1.1X101

4.2X101

1.1X103

Cr-51

Chromium (24)

3.0X101

8.1X102

3.0X101

8.1X102

3.4X103

9.2X104

Cs-129

Cesium (55)

4.0

1.1X102

4.0

1.1X102

2.8X104

7.6X105

Cs-131

3.0X101

8.1X102

3.0X101

8.1X102

3.8X103

1.0X105

Cs-132

1.0

2.7X101

1.0

2.7X101

5.7X103

1.5X105

Cs-134

7.0X10-1

1.9X101

7.0X10-1

1.9X101

4.8X101

1.3X103

Cs-134m

4.0X101

1.1X103

6.0X10-1

1.6X101

3.0X105

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

2.7X103

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

1.4X105

3.9X106

Cu-67

1.0X101

2.7X102

7.0X10-1

1.9X101

2.8X104

7.6X105

Dy-159

Dysprosium (66)

2.0X101

5.4X102

2.0X101

5.4X102

2.1X102

5.7X103

Dy-165

9.0X10-1

2.4X101

6.0X10-1

1.6X101

3.0X105

8.2X106

Dy-166 (a)

9.0X10-1

2.4X101

3.0X10-1

8.1

8.6X103

2.3X105

Er-169

Erbium (68)

4.0X101

1.1X103

1.0

2.7X101

3.1X103

8.3X104

Er-171

8.0X10-1

2.2X101

5.0X10-1

1.4X101

9.0X104

2.4X106

Eu-147

Europium (63)

2.0

5.4X101

2.0

5.4X101

1.4X103

3.7X104

Eu-148

5.0X10-1

1.4X101

5.0X10-1

1.4X101

6.0X102

1.6X104

Eu-149

2.0X101

5.4X102

2.0X101

5.4X102

3.5X102

9.4X103

Eu-150 (short lived)

2.0

5.4X101

7.0X10-1

1.9X101

6.1X104

1.6X106

Eu-150 (long lived)

7.0X10-1

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

8.2X104

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

1.8X101

4.9X102

Eu-156

7.0X10-1

1.9X101

7.0X10-1

1.9X101

2.0X103

5.5X104

F-18

Fluorine (9)

1.0

2.7X101

6.0X10-1

1.6X101

3.5X106

9.5X107

Fe-52 (a)

Iron (26)

3.0X10-1

8.1

3.0X10-1

8.1

2.7X105

7.3X106

Fe-55

4.0X101

1.1X103

4.0X101

1.1X103

8.8X101

2.4X103

Fe-59

9.0X10-1

2.4X101

9.0X10-1

2.4X101

1.8X103

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

2.2X104

6.0X105

Ga-68

5.0X10-1

1.4X101

5.0X10-1

1.4X101

1.5X106

4.1X107

Ga-72

4.0X10-1

1.1X101

4.0X10-1

1.1X101

1.1X105

3.1X106

Gd-146 (a)

Gadolinium (64)

5.0X10-1

1.4X101

5.0X10-1

1.4X101

6.9X102

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

1.3X102

3.5X103

Gd-159

3.0

8.1X101

6.0X10-1

1.6X101

3.9X104

1.1X106

Ge-68 (a)

Germanium (32)

5.0X10-1

1.4X101

5.0X10-1

1.4X101

2.6X102

7.1X103

Ge-71

4.0X101

1.1X103

4.0X101

1.1X103

5.8X103

1.6X105

Ge-77

3.0X10-1

8.1

3.0X10-1

8.1

1.3X105

3.6X106

Hf-172 (a)

Hafnium (72)

6.0X10-1

1.6X101

6.0X10-1

1.6X101

4.1X101

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

6.3X102

1.7X104

Hf-182

Unlimited

Unlimited

Unlimited

Unlimited

8.1X10-6

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

2.5X104

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

9.9X105

2.7X107

I-135 (a)

6.0X10-1

1.6X101

6.0X10-1

1.6X101

1.3X105

3.5X106

In-111

Indium (49)

3.0

8.1X101

3.0

8.1X101

1.5X104

4.2X105

In-113m

4.0

1.1X102

2.0

5.4X101

6.2X105

1.7X107

In-114m (a)

1.0X101

2.7X102

5.0X10-1

1.4X101

8.6X102

2.3X104

In-115m

7.0

1.9X102

1.0

2.7X101

2.2X105

6.1X106

Ir-189 (a)

Iridium (77)

1.0X101

2.7X102

1.0X101

2.7X102

1.9X103

5.2X104

Ir-190

7.0X10-1

1.9X101

7.0X10-1

1.9X101

2.3X103

6.2X104

Ir-192

c1.0

c2.7X101

6.0X10-1

1.6X101

3.4X102

9.2X103

Ir-194

3.0X10-1

8.1

3.0X10-1

8.1

3.1X104

8.4X105

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

1.2X105

3.3X106

Kr-79

Krypton (36)

4.0

1.1X102

2.0

5.4X101

4.2X104

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

1.5X101

3.9X102

Kr-85m

8.0

2.2X102

3.0

8.1X101

3.0X105

8.2X106

Kr-87

2.0X10-1

5.4

2.0X10-1

5.4

1.0X106

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

2.1X104

5.6X105

Lu-172

Lutetium (71)

6.0X10-1

1.6X101

6.0X10-1

1.6X101

4.2X103

1.1X105

Lu-173

8.0

2.2X102

8.0

2.2X102

5.6X101

1.5X103

Lu-174

9.0

2.4X102

9.0

2.4X102

2.3X101

6.2X102

Lu-174m

2.0X101

5.4X102

1.0X101

2.7X102

2.0X102

5.3X103

Lu-177

3.0X101

8.1X102

7.0X10-1

1.9X101

4.1X103

1.1X105

Mg-28 (a)

Magnesium (12)

3.0X10-1

8.1

3.0X10-1

8.1

2.0X105

5.4X106

Mn-52

Manganese (25)

3.0X10-1

8.1

3.0X10-1

8.1

1.6X104

4.4X105

Mn-53

Unlimited

Unlimited

Unlimited

Unlimited

6.8X10-5

1.8X10-3

Mn-54

1.0

2.7X101

1.0

2.7X101

2.9X102

7.7X103

Mn-56

3.0X10-1

8.1

3.0X10-1

8.1

8.0X105

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

2.3X102

6.3X103

Na-24

2.0X10-1

5.4

2.0X10-1

5.4

3.2X105

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

1.5X103

3.9X104

Nb-97

9.0X10-1

2.4X101

6.0X10-1

1.6X101

9.9X105

2.7X107

Nd-147

Neodymium (60)

6.0

1.6X102

6.0X10-1

1.6X101

3.0X103

8.1X104

Nd-149

6.0X10-1

1.6X101

5.0X10-1

1.4X101

4.5X105

1.2X107

Ni-59

Nickel (28)

Unlimited

Unlimited

Unlimited

Unlimited

3.0X10-3

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

7.1X105

1.9X107

Np-235

Neptunium (93)

4.0X101

1.1X103

4.0X101

1.1X103

5.2X101

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

7.7X102

2.1X104

Pb-201

Lead (82)

1.0

2.7X101

1.0

2.7X101

6.2X104

1.7X106

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

Pb-205

Unlimited

Unlimited

Unlimited

Unlimited

4.5X10-6

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

5.1X104

1.4X106

Pd-103 (a)

Palladium (46)

4.0X101

1.1X103

4.0X101

1.1X103

2.8X103

7.5X104

Pd-107

Unlimited

Unlimited

Unlimited

Unlimited

1.9X10-5

5.1X10-4

Pd-109

2.0

5.4X101

5.0X10-1

1.4X101

7.9X104

2.1X106

Pm-143

Promethium (61)

3.0

8.1X101

3.0

8.1X101

1.3X102

3.4X103

Pm-144

7.0X10-1

1.9X101

7.0X10-1

1.9X101

9.2X101

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

3.4X101

9.3X102

Pm-148m (a)

8.0X10-1

2.2X101

7.0X10-1

1.9X101

7.9X102

2.1X104

Pm-149

2.0

5.4X101

6.0X10-1

1.6X101

1.5X104

4.0X105

Pm-151

2.0

5.4X101

6.0X10-1

1.6X101

2.7X104

7.3X105

Po-210

Polonium (84)

4.0X101

1.1X103

2.0X10-2

5.4X10-1

1.7X102

4.5X103

Pr-142

Praseodymium (59)

4.0X10-1

1.1X101

4.0X10-1

1.1X101

4.3X104

1.2X106

Pr-143

3.0

8.1X101

6.0X10-1

1.6X101

2.5X103

6.7X104

Pt-188 (a)

Platinum (78)

1.0

2.7X101

8.0X10-1

2.2X101

2.5X103

6.8X104

Pt-191

4.0

1.1X102

3.0

8.1X101

8.7X103

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

5.8X103

1.6X105

Pt-195m

1.0X101

2.7X102

5.0X10-1

1.4X101

6.2X103

1.7X105

Pt-197

2.0X101

5.4X102

6.0X10-1

1.6X101

3.2X104

8.7X105

Pt-197m

1.0X101

2.7X102

6.0X10-1

1.6X101

3.7X105

1.0X107

Pu-236

Plutonium (94)

3.0X101

8.1X102

3.0X10-3

8.1X10-2

2.0X101

5.3X102

Pu-237

2.0X101

5.4X102

2.0X101

5.4X102

4.5X102

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

6.8X102

1.8X104

Rb-84

1.0

2.7X101

1.0

2.7X101

1.8X103

4.7X104

Rb-86

5.0X10-1

1.4X101

5.0X10-1

1.4X101

3.0X103

8.1X104

Rb-87

Unlimited

Unlimited

Unlimited

Unlimited

3.2X10-9

8.6X10-8

Rb(nat)

Unlimited

Unlimited

Unlimited

Unlimited

6.7X106

1.8X108

Re-184

Rhenium (75)

1.0

2.7X101

1.0

2.7X101

6.9X102

1.9X104

Re-184m

3.0

8.1X101

1.0

2.7X101

1.6X102

4.3X103

Re-186

2.0

5.4X101

6.0X10-1

1.6X101

6.9X103

1.9X105

Re-187

Unlimited

Unlimited

Unlimited

Unlimited

1.4X10-9

3.8X10-8

Re-188

4.0X10-1

1.1X101

4.0X10-1

1.1X101

3.6X104

9.8X105

Re-189 (a)

3.0

8.1X101

6.0X10-1

1.6X101

2.5X104

6.8X105

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

4.1X101

1.1X103

Rh-102

5.0X10-1

1.4X101

5.0X10-1

1.4X101

4.5X101

1.2X103

Rh-102m

2.0

5.4X101

2.0

5.4X101

2.3X102

6.2X103

Rh-103m

4.0X101

1.1X103

4.0X101

1.1X103

1.2X106

3.3X107

Rh-105

1.0X101

2.7X102

8.0X10-1

2.2X101

3.1X104

8.4X105

Rn-222 (a)

Radon (86)

3.0X10-1

8.1

4.0X10-3

1.1X10-1

5.7X103

1.5X105

Ru-97

Ruthenium (44)

5.0

1.4X102

5.0

1.4X102

1.7X104

4.6X105

Ru-103 (a)

2.0

5.4X101

2.0

5.4X101

1.2X103

3.2X104

Ru-105

1.0

2.7X101

6.0X10-1

1.6X101

2.5X105

6.7X106

Ru-106 (a)

2.0X10-1

5.4

2.0X10-1

5.4

1.2X102

3.3X103

S-35

Sulphur (16)

4.0X101

1.1X103

3.0

8.1X101

1.6X103

4.3X104

Sb-122

Antimony (51)

4.0X10-1

1.1X101

4.0X10-1

1.1X101

1.5X104

4.0X105

Sb-124

6.0X10-1

1.6X101

6.0X10-1

1.6X101

6.5X102

1.7X104

Sb-125

2.0

5.4X101

1.0

2.7X101

3.9X101

1.0X103

Sb-126

4.0X10-1

1.1X101

4.0X10-1

1.1X101

3.1X103

8.4X104

Sc-44

Scandium (21)

5.0X10-1

1.4X101

5.0X10-1

1.4X101

6.7X105

1.8X107

Sc-46

5.0X10-1

1.4X101

5.0X10-1

1.4X101

1.3X103

3.4X104

Sc-47

1.0X101

2.7X102

7.0X10-1

1.9X101

3.1X104

8.3X105

Sc-48

3.0X10-1

8.1

3.0X10-1

8.1

5.5X104

1.5X106

Se-75

Selenium (34)

3.0

8.1X101

3.0

8.1X101

5.4X102

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

1.4X106

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

9.8X101

2.6X103

Sm-147

Unlimited

Unlimited

Unlimited

Unlimited

8.5X10-10

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

1.6X104

4.4X105

Sn-113 (a)

Tin (50)

4.0

1.1X102

2.0

5.4X101

3.7X102

1.0X104

Sn-117m

7.0

1.9X102

4.0X10-1

1.1X101

3.0X103

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

2.3X102

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

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

1.2X104

3.2X105

Tc-96m (a)

4.0X10-1

1.1X101

4.0X10-1

1.1X101

1.4X106

3.8X107

Tc-97

Unlimited

Unlimited

Unlimited

Unlimited

5.2X10-5

1.4X10-3

Tc-97m

4.0X101

1.1X103

1.0

2.7X101

5.6X102

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

1.9X105

5.3X106

Te-121

Tellurium (52)

2.0

5.4X101

2.0

5.4X101

2.4X103

6.4X104

Te-121m

5.0

1.4X102

3.0

8.1X101

2.6X102

7.0X103

Te-123m

8.0

2.2X102

1.0

2.7X101

3.3X102

8.9X103

Te-125m

2.0X101

5.4X102

9.0X10-1

2.4X101

6.7X102

1.8X104

Te-127

2.0X101

5.4X102

7.0X10-1

1.9X101

9.8X104

2.6X106

Te-127m (a)

2.0X101

5.4X102

5.0X10-1

1.4X101

3.5X102

9.4X103

Te-129

7.0X10-1

1.9X101

6.0X10-1

1.6X101

7.7X105

2.1X107

Te-129m (a)

8.0X10-1

2.2X101

4.0X10-1

1.1X101

1.1X103

3.0X104

Te-131m (a)

7.0X10-1

1.9X101

5.0X10-1

1.4X101

3.0X104

8.0X105

Te-132 (a)

5.0X10-1

1.4X101

4.0X10-1

1.1X101

1.1X104

3.0X105

Th-227

Thorium (90)

1.0X101

2.7X102

5.0X10-3

1.4X10-1

1.1X103

3.1X104

Th-228 (a)

5.0X10-1

1.4X101

1.0X10-3

2.7X10-2

3.0X101

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

2.0X104

5.3X105

Th-232

Unlimited

Unlimited

Unlimited

Unlimited

4.0X10-9

1.1X10-7

Th-234 (a)

3.0X10-1

8.1

3.0X10-1

8.1

8.6X102

2.3X104

Th (natural)

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 absorption) (a)(d)

Uranium (92)

4.0X101

1.1X103

1.0X10-1

2.7

1.0X103

2.7X104

U-230 (medium lung absorption) (a) (e)

4.0X101

1.1X103

4.0X10-3

1.1X10-1

1.0X103

2.7X104

U-230 (slow lung absorption) (a)(f)

3.0X101

8.1X102

3.0X10-3

8.1X10-2

1.0X103

2.7X104

U-232 (fast lung absorption) (d)

4.0X101

1.1X103

1.0X10-2

2.7X10-1

8.3X10-1

2.2X101

U-232 (medium lung absorption) (e)

4.0X101

1.1X103

7.0X10-3

1.9X10-1

8.3X10-1

2.2X101

U-232 (slow lung absorption) (f)

1.0X101

2.7X102

1.0X10-3

2.7X10-2

8.3X10-1

2.2X101

U-233 (fast lung absorption) (d)

4.0X101

1.1X103

9.0X10-2

2.4

3.6X10-4

9.7X10-3

U-233 (medium lung absorption) (e)

4.0X101

1.1X103

2.0X10-2

5.4X10-1

3.6X10-4

9.7X10-3

U-233 (slow lung absorption) (f)

4.0X101

1.1X103

6.0X10-3

1.6X10-1

3.6X10-4

9.7X10-3

U-234 (fast lung absorption) (d)

4.0X101

1.1X103

9.0X10-2

2.4

2.3X10-4

6.2X10-3

U-234 (medium lung absorption) (e)

4.0X101

1.1X103

2.0X10-2

5.4X10-1

2.3X10-4

6.2X10-3

U-234 (slow lung absorption) (f)

4.0X101

1.1X103

6.0X10-3

1.6X10-1

2.3X10-4

6.2X10-3

U-235 (all lung absorption types) (a), (d),(e),(f)

Unlimited

Unlimited

Unlimited

Unlimited

8.0X10-8

2.2X10-6

U-236 (fast lung absorption) (d)

Unlimited

Unlimited

Unlimited

Unlimited

2.4X10-6

6.5X10-5

U-236 (medium lung absorption) (e)

4.0X101

1.1X103

2.0X10-2

5.4X10-1

2.4X10-6

6.5X10-5

U-236 (slow lung absorption) (f)

4.0X101

1.1X103

6.0X10-3

1.6X10-1

2.4X10-6

6.5X10-5

U-238 (all lung absorption types) (d),(e),(f)

Unlimited

Unlimited

Unlimited

Unlimited

1.2X10-8

3.4X10-7

U (natural)

Unlimited

Unlimited

Unlimited

Unlimited

2.6X10-8

7.1X10-7

U (enriched to 20% or less) (g)

Unlimited

Unlimited

Unlimited

Unlimited

See Table 6

See Table 6

U (dep)

Unlimited

Unlimited

Unlimited

Unlimited

See Table

See Table

V-48

Vanadium (23)

4.0X10-1

1.1X101

4.0X10-1

1.1X101

66.3X103

51.7X105

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 (70)

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

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

a A1 and/or A2 values include contributions from daughter nuclides with half-lives less than 10 days as listed in Table 4-A.

bThe values of A1 and A2 in Curies (Ci) are approximate and for information only; the regulatory standard units are Terabecquerels (TBq).

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.

TABLE 4-A- DAUGHTER NUCLIDES WITH HALF-LIVES LESS THAN 10 DAYS

Parent Nuclide

Daughter Nuclide(s)

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

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

TABLE 5 - GENERAL VALUES FOR A1 AND A2

Contents

A1

A2

Activity concentration for exempt material (Bq/g)

Activity concentration for exempt material (Ci/g)

Activity limits for exempt consignments (Bq)

Activity limits for exempt consignments (Ci)

(TBq)

(Ci)

(TBq)

(Ci)

Only beta or gamma emitting radionuclides are known to be present

1 x 10-1

2.7 x 100

2 x 10 -2

5.4 x 10-1

1 x 101

2.7 x10-10

1 x 104

2.7 x10-7

Alpha emitting nuclides, but no neutron emitters, are known to be presenta

2 x 10-1

5.4 x 100

9 x 10-5

2.4 x 10-3

1 x 10-1

2.7 x10-12

1 x 103

2.7 x10-8

Neutron emitting nuclides are known to be present or no relevant data are available

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

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

TABLE 6 - ACTIVITY-MASS RELATIONSHIPS FOR URANIUM

Uranium Enrichment1 wt % U-235 present

Specific Activity

TBq/g

Ci/g

0.45

1.8 x 10-8

5.0 x 10-7

0.72

2.6 x 10-8

7.1 x 10-7

1

2.8 x 10-8

7.6 x 10-7

1.5

3.7 x 10-8

1.0 x 10-6

5

1.0 x 10-7

2.7 x 10-6

10

1.8 x 10-7

4.8 x 10-6

20

3.7 x 10-7

1.0 x 10-5

35

7.4 x 10-7

2.0 x 10-5

50

9.3 x 10-7

2.5 x 10-5

90

2.2 x 10-6

5.8 x 10-5

93

2.6 x 10-6

7.0 x 10-5

95

3.4 x 10-6

9.1 x 10-5

1 The figures for uranium include representative values for the activity of the uranium-234 that is concentrated during the enrichment process.

Table 7 - EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES

Symbol of radionuclide

Element and atomic number

Activity concentration for exempt material (Bq/g)

Activity concentration for exempt material (Ci/g)

Activity limit for exempt consignment (Bq)

Activity limit for exempt consignment (Ci)

Ac-225

Actinium (89)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

Ac-227

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

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

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

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

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

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-152m

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

Iron (26)

1.0X101

2.7X10-10

1.0X106

2.7X10-5

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

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

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

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

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

Mercury (80)

1.0X101

2.7X10-10

1.0X106

2.7X10-5

Hg-195m

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

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

1.0X102

2.7X10-9

1.0X106

2.7X10-5

In-115m

1.0X102

2.7X10-9

1.0X106

2.7X10-5

Ir-189

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

1.0X101

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

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

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

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

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

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

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

Pt-188

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

1.0X103

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 (b)

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

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

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

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

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

1.0X101

2.7X10-10

1.0X105

2.7X10-6

Sr-82

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

1.0X103

2.7X10-8

1.0X107

2.7X10-4

Te-129

1.0X102

2.7X10-9

1.0X106

2.7X10-5

Te-129m

1.0X103

2.7X10-8

1.0X106

2.7X10-5

Te-131m

1.0X101

2.7X10-10

1.0X106

2.7X10-5

Te-132

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

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 absorption) (b),(d)

Uranium (92)

1.0X101

2.7X10-10

1.0X105

2.7X10-6

U-230 (medium lung absorption) (e)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

U-230 (slow lung absorption) (f)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

U-232 (fast lung absorption) (b),(d)

1.0

2.7X10-11

1.0X103

2.7X10-8

U-232 (medium lung absorption) (e)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

U-232 (slow lung absorption) (f)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

U-233 (fast lung absorption) (d)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

U-233 (medium lung absorption) (e)

1.0X102

2.7X10-9

1.0X105

2.7X10-6

U-233 (slow lung absorption) (f)

1.0X101

2.7X10-10

1.0X105

2.7X10-6

U-234 (fast lung absorption) (d)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

U-234 (medium lung absorption) (e)

1.0X102

2.7X10-9

1.0X105

2.7X10-6

U-234 (slow lung absorption) (f)

1.0X101

2.7X10-10

1.0X105

2.7X10-6

U-235 (all lung absorption types) (b),(d),(e),(f)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

U-236 (fast lung absorption) (d)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

U-236 (medium lung absorption) (e)

1.0X102

2.7X10-9

1.0X105

2.7X10-6

U-236 (slow lung absorption) (f)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

U-238 (all lung absorption types) (b),(d),(e),(f)

1.0X101

2.7X10-10

1.0X104

2.7X10-7

U (natural) (b)

1.0

2.7X10-11

1.0X103

2.7X10-8

U (enriched to 20% or less) (g)

1.0

2.7X10-11

1.0X103

2.7X10-8

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

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 (70)

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

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

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.

O.C.G.A. § 31-13-1 et seq.

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