[Code of Federal Regulations]
[Title 10, Volume 2]
[Revised as of January 1, 2008]
From the U.S. Government Printing Office via GPO Access
[CITE: 10CFR71]

[Page 325-382]
 
                            TITLE 10--ENERGY
 
          CHAPTER I--NUCLEAR REGULATORY COMMISSION (CONTINUED)
 
PART 71_PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL

                      Subpart A_General Provisions

Sec.
71.0 Purpose and scope.
71.1 Communications and records.
71.2 Interpretations.
71.3 Requirement for license.
71.4 Definitions.
71.5 Transportation of licensed material.
71.6 Information collection requirements: OMB approval.
71.7 Completeness and accuracy of information.
71.8 Deliberate misconduct.
71.9 Employee protection.
71.10 Public inspection of application.
71.11 [Reserved]

                          Subpart B_Exemptions

71.12 Specific exemptions.
71.13 Exemption of physicians.
71.14 Exemption for low-level materials.
71.15 Exemption from classification as fissile material.
71.16 [Reserved]

                       Subpart C_General Licenses

71.17 General license: NRC-approved package.
71.18 [Reserved]
71.19 Previously approved package.
71.20 General license: DOT specification container.
71.21 General license: Use of foreign approved package.
71.22 General license: Fissile material.
71.23 General license: Plutonium-beryllium special form material.
71.24-71.25 [Reserved]

               Subpart D_Application for Package Approval

71.31 Contents of application.
71.33 Package description.
71.35 Package evaluation.

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71.37 Quality assurance.
71.38 Renewal of a certificate of compliance or quality assurance 
          program approval.
71.39 Requirement for additional information.

                  Subpart E_Package Approval Standards

71.41 Demonstration of compliance.
71.43 General standards for all packages.
71.45 Lifting and tie-down standards for all packages.
71.47 External radiation standards for all packages.
71.51 Additional requirements for Type B packages.
71.53 [Reserved]
71.55 General requirements for fissile material packages.
71.57 [Reserved]
71.59 Standards for arrays of fissile material packages.
71.61 Special requirements for Type B packages containing more than 
          10\5\A<INF>2</INF>.
71.63 Special requirement for plutonium shipments.
71.64 Special requirements for plutonium air shipments.
71.65 Additional requirements.

           Subpart F_Package, Special Form, and LSA-III Tests

71.71 Normal conditions of transport.
71.73 Hypothetical accident conditions.
71.74 Accident conditions for air transport of plutonium.
71.75 Qualification of special form radioactive material.
71.77 Qualification of LSA-III Material.

               Subpart G_Operating Controls and Procedures

71.81 Applicability of operating controls and procedures.
71.83 Assumptions as to unknown properties.
71.85 Preliminary determinations.
71.87 Routine determinations.
71.88 Air transport of plutonium.
71.89 Opening instructions.
71.91 Records.
71.93 Inspection and tests.
71.95 Reports.
71.97 Advance notification of shipment of irradiated reactor fuel and 
          nuclear waste.
71.99 Violations.
71.100 Criminal penalties.

                       Subpart H_Quality Assurance

71.101 Quality assurance requirements.
71.103 Quality assurance organization.
71.105 Quality assurance program.
71.107 Package design control.
71.109 Procurement document control.
71.111 Instructions, procedures, and drawings.
71.113 Document control.
71.115 Control of purchased material, equipment, and services.
71.117 Identification and control of materials, parts, and components.
71.119 Control of special processes.
71.121 Internal inspection.
71.123 Test control.
71.125 Control of measuring and test equipment.
71.127 Handling, storage, and shipping control.
71.129 Inspection, test, and operating status.
71.131 Nonconforming materials, parts, or components.
71.133 Corrective action.
71.135 Quality assurance records.
71.137 Audits.

Appendix A to Part 71--Determination of A<INF>1</INF> and A<INF>2</INF>

    Authority: Secs. 53, 57, 62, 63, 81, 161, 182, 183, 68 Stat. 930, 
932, 933, 935, 948, 953, 954, as amended, sec. 1701, 106 Stat. 2951, 
2952, 2953 (42 U.S.C. 2073, 2077, 2092, 2093, 2111, 2201, 2232, 2233, 
2297f); secs. 201, as amended, 202, 206, 88 Stat.1242, as amended, 1244, 
1246 (42 U.S.C. 5841, 5842, 5846); sec. 1704, 112 Stat. 2750 (44 U.S.C. 
3504 note).
    Section 71.9 also issued under Pub. L. 95-601, sec. 10, 92 Stat. 
2951, as amended by Pub. L. 102-486, sec. 2902, 106 Stat. 3123 (42 
U.S.C. 5851).
    Section 71.97 also issued under sec. 301, Pub. L. 96-295, 94 Stat. 
789-790.

    Source: 60 FR 50264, Sept. 28, 1995, unless otherwise noted.

                      Subpart A_General Provisions

    Source: 69 FR 3786, Jan. 26, 2004, unless otherwise noted.

Sec.  71.0  Purpose and scope.

    (a) This part establishes--
    (1) Requirements for packaging, preparation for shipment, and 
transportation of licensed material; and
    (2) Procedures and standards for NRC approval of packaging and 
shipping procedures for fissile material and for a quantity of other 
licensed material in excess of a Type A quantity.
    (b) The packaging and transport of licensed material are also 
subject to other parts of this chapter (e.g., 10 CFR parts 20, 21, 30, 
40, 70, and 73) and to the regulations of other agencies (e.g., the U.S. 
Department of Transportation

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(DOT) and the U.S. Postal Service) \1\ having jurisdiction over means of 
transport. The requirements of this part are in addition to, and not in 
substitution for, other requirements.
---------------------------------------------------------------------------

    \1\ Postal Service manual (Domestic Mail Manual), Section 124, which 
is incorporated by reference at 39 CFR 111.1.
---------------------------------------------------------------------------

    (c) The regulations in this part apply to any licensee authorized by 
specific or general license issued by the Commission to receive, 
possess, use, or transfer licensed material, if the licensee delivers 
that material to a carrier for transport, transports the material 
outside the site of usage as specified in the NRC license, or transports 
that material on public highways. No provision of this part authorizes 
possession of licensed material.
    (d)(1) Exemptions from the requirement for license in Sec.  71.3 are 
specified in Sec.  71.14. General licenses for which no NRC package 
approval is required are issued in Sec. Sec.  71.20 through 71.23. The 
general license in Sec.  71.17 requires that an NRC certificate of 
compliance or other package approval be issued for the package to be 
used under this general license.
    (2) Application for package approval must be completed in accordance 
with subpart D of this part, demonstrating that the design of the 
package to be used satisfies the package approval standards contained in 
subpart E of this part, as related to the tests of subpart F of this 
part.
    (3) A licensee transporting licensed material, or delivering 
licensed material to a carrier for transport, shall comply with the 
operating control requirements of subpart G of this part; the quality 
assurance requirements of subpart H of this part; and the general 
provisions of subpart A of this part, including DOT regulations 
referenced in Sec.  71.5.
    (e) The regulations of this part apply to any person holding, or 
applying for, a certificate of compliance, issued pursuant to this part, 
for a package intended for the transportation of radioactive material, 
outside the confines of a licensee's facility or authorized place of 
use.
    (f) The regulations in this part apply to any person required to 
obtain a certificate of compliance, or an approved compliance plan, 
pursuant to part 76 of this chapter, if the person delivers radioactive 
material to a common or contract carrier for transport or transports the 
material outside the confines of the person's plant or other authorized 
place of use.
    (g) This part also gives notice to all persons who knowingly provide 
to any licensee, certificate holder, quality assurance program approval 
holder, applicant for a license, certificate, or quality assurance 
program approval, or to a contractor, or subcontractor of any of them, 
components, equipment, materials, or other goods or services, that 
relate to a licensee's, certificate holder's, quality assurance program 
approval holder's, or applicant's activities subject to this part, that 
they may be individually subject to NRC enforcement action for violation 
of Sec.  71.8.

Sec.  71.1  Communications and records.

    (a) Except where otherwise specified, all communications and reports 
concerning the regulations in this part and applications filed under 
them should be sent by mail addressed: ATTN: Document Control Desk, 
Director, Spent Fuel Project Office, Office of Nuclear Material Safety 
and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, by hand delivery to the NRC's offices at 11555 Rockville 
Pike, Rockville, Maryland; or, where practicable, by electronic 
submission, for example, via Electronic Information Exchange, or CD-ROM. 
Electronic submissions must be made in a manner that enables the NRC to 
receive, read, authenticate, distribute, and archive the submission, and 
process and retrieve it a single page at a time. Detailed guidance on 
making electronic submissions can be obtained by visiting the NRC's Web 
site at http://www.nrc.gov/site-help/e-submittals.html, by calling (301) 
415-0439, by e-mail to EIE@nrc.gov, or by writing the Office of 
Information Services, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001. The guidance discusses, among other topics, the formats the 
NRC can accept, the use of electronic signatures, and the treatment of 
nonpublic information. If the submission date falls on a Saturday, 
Sunday, or a

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Federal holiday, the next Federal working day becomes the official due 
date.
    (b) Each record required by this part must be legible throughout the 
retention period specified by each Commission regulation. The record may 
be the original or a reproduced copy or a microform provided that the 
copy or microform is authenticated by authorized personnel and that the 
microform is capable of producing a clear copy throughout the required 
retention period. The record may also be stored in electronic media with 
the capability for producing legible, accurate, and complete records 
during the required retention period. Records such as letters, drawings, 
and specifications must include all pertinent information such as 
stamps, initials, and signatures. The licensee shall maintain adequate 
safeguards against tampering with and loss of records.

[69 FR 3786, Jan. 26, 2004; 69 FR 58038, Sept. 29, 2004]

Sec.  71.2  Interpretations.

    Except as specifically authorized by the Commission in writing, no 
interpretation of the meaning of the regulations in this part by any 
officer or employee of the Commission, other than a written 
interpretation by the General Counsel, will be recognized to be binding 
upon the Commission.

Sec.  71.3  Requirement for license.

    Except as authorized in a general license or a specific license 
issued by the Commission, or as exempted in this part, no licensee may--
    (a) Deliver licensed material to a carrier for transport; or
    (b) Transport licensed material.

Sec.  71.4  Definitions.

    The following terms are as defined here for the purpose of this 
part. To ensure compatibility with international transportation 
standards, all limits in this part are given in terms of dual units: The 
International System of Units (SI) followed or preceded by U.S. standard 
or customary units. The U.S. customary units are not exact equivalents 
but are rounded to a convenient value, providing a functionally 
equivalent unit. For the purpose of this part, either unit may be used.
    A1 means the maximum activity of special form radioactive material 
permitted in a Type A package. This value is either listed in Appendix 
A, Table A-1, of this part, or may be derived in accordance with the 
procedures prescribed in Appendix A of this part.
    A2 means the maximum activity of radioactive material, other than 
special form material, LSA, and SCO material, permitted in a Type A 
package. This value is either listed in Appendix A, Table A-1, of this 
part, or may be derived in accordance with the procedures prescribed in 
Appendix A of this part.
    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.
    Certificate holder means a person who has been issued a certificate 
of compliance or other package approval by the Commission.
    Certificate of Compliance (CoC) means the certificate issued by the 
Commission under subpart D of this part which approves the design of a 
package for the transportation of radioactive material.
    Close reflection by water means immediate contact by water of 
sufficient thickness for maximum reflection of neutrons.
    Consignment means each shipment of a package or groups of packages 
or load of radioactive material offered by a shipper for transport.
    Containment system means the assembly of components of the packaging 
intended to retain the radioactive material during transport.
    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.
    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

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package, to designate the degree of control of accumulation of packages 
containing fissile material during transportation. Determination of the 
criticality safety index is described in Sec. Sec.  71.22, 71.23, and 
71.59.
    Deuterium means, for the purposes of Sec. Sec.  71.15 and 71.22, 
deuterium and any deuterium compounds, including heavy water, in which 
the ratio of deuterium atoms to hydrogen atoms exceeds 1:5000.
    DOT means the U.S. Department of Transportation.
    Exclusive use means the sole use by a single consignor of a 
conveyance 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.
    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. Unirradiated natural uranium 
and depleted uranium and natural uranium or depleted uranium, that has 
been irradiated in thermal reactors only, are not included in this 
definition. Certain exclusions from fissile material controls are 
provided in Sec.  71.15.
    Graphite means, for the purposes of Sec. Sec.  71.15 and 71.22, 
graphite with a boron equivalent content less than 5 parts per million 
and density greater than 1.5 grams per cubic centimeter.
    Licensed material means byproduct, source, or special nuclear 
material received, possessed, used, or transferred under a general or 
specific license issued by the Commission pursuant to the regulations in 
this chapter.
    Low Specific Activity (LSA) material means radioactive material with 
limited specific activity which is nonfissile or is excepted under Sec.  
71.15, 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. 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 radioactive 
radionuclides which are not intended to be processed for the use of 
these radionuclides;
    (ii) Solid unirradiated natural uranium or depleted uranium or 
natural thorium or their solid or liquid compounds or mixtures;
    (iii) Radioactive material for which the A<INF>2</INF> 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 Appendix A.
    (2) LSA--II.
    (i) Water with tritium concentration up to 0.8 TBq/liter (20.0 Ci/
liter); or
    (ii) Other material in which the activity is distributed throughout 
and the average specific activity does not exceed 10<SUP>-4</SUP> 
A<INF>2</INF>/g for solids and gases, and 10<SUP>-5</SUP> A<INF>2</INF>/
g for liquids.
    (3) LSA--III. Solids (e.g., consolidated wastes, activated 
materials), excluding powders, that satisfy the requirements of Sec.  
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 7 days, would not exceed 0.1 
A<INF>2</INF>; and
    (iii) The estimated average specific activity of the solid does not 
exceed 2 x 10<SUP>-3</SUP> A<INF>2</INF>/g.

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    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.
    Maximum normal operating pressure means the maximum gauge pressure 
that would develop in the containment system in a period of 1 year under 
the heat condition specified in Sec.  71.71(c)(1), in the absence of 
venting, external cooling by an ancillary system, or operational 
controls during transport.
    Natural thorium means thorium with the naturally occurring 
distribution of thorium isotopes (essentially 100 weight percent 
thorium-232).
    Normal form radioactive material means radioactive material that has 
not been demonstrated to qualify as ``special form radioactive 
material.''
    Optimum interspersed hydrogenous moderation means the presence of 
hydrogenous material between packages to such an extent that the maximum 
nuclear reactivity results.
    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 lbs/in\2\) gauge or a pressure relief 
device that would allow the release of radioactive material to the 
environment under the tests specified in Sec.  71.73 (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 Sec.  71.19.
    Packaging means the assembly of components necessary to ensure 
compliance with the packaging requirements of this part. 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.
    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 
mm (0.2 in); and
    (3) It satisfies the requirements of Sec.  71.75. A special form 
encapsulation designed in accordance with the requirements of Sec.  71.4 
in effect on June 30, 1983 (see 10 CFR part 71, revised as of January 1, 
1983), and constructed before July 1, 1985, and a special form 
encapsulation designed in accordance with the requirements of Sec.  71.4 
in effect on March 31, 1996 (see 10 CFR part 71, revised as of January 
1, 1983), and constructed before April 1, 1998, may continue to be used. 
Any other special form encapsulation must meet the specifications of 
this definition.
    Specific activity of a radionuclide means the radioactivity of the 
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.
    Spent nuclear fuel or Spent fuel means fuel that has been withdrawn 
from a nuclear reactor following irradiation, has undergone at least 1 
year's decay since being used as a source of energy in a power reactor, 
and has not been

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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.
    State means a State of the United States, the District of Columbia, 
the Commonwealth of Puerto Rico, the Virgin Islands, Guam, American 
Samoa, and the Commonwealth of the Northern Mariana Islands.
    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 nonfixed contamination on the accessible surface averaged 
over 300 cm\2\ (or the area of the surface if less than 300 cm\2\) does 
not exceed 4 Bq/cm\2\ (10<SUP>-4</SUP> microcurie/cm\2\) for beta and 
gamma and low toxicity alpha emitters, or 0.4 Bq/cm\2\ (10<SUP>-5</SUP> 
microcurie/cm\2\) for all other alpha emitters;
    (ii) The fixed contamination on the accessible surface averaged over 
300 cm\2\ (or the area of the surface if less than 300 cm\2\) does not 
exceed 4 x 10\4\ Bq/cm\2\ (1.0 microcurie/cm\2\) for beta and gamma and 
low toxicity alpha emitters, or 4 x 10\3\ Bq/cm\2\ (0.1 microcurie/
cm\2\) for all other alpha emitters; and
    (iii) The nonfixed contamination plus the fixed contamination on the 
inaccessible surface averaged over 300 cm\2\ (or the area of the surface 
if less than 300 cm\2\) does not exceed 4 x 10\4\ Bq/cm\2\ (1 
microcurie/cm\2\) for beta and gamma and low toxicity alpha emitters, or 
4 x 10\3\ Bq/cm\2\ (0.1 microcurie/cm\2\) 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 nonfixed contamination on the accessible surface averaged 
over 300 cm\2\ (or the area of the surface if less than 300 cm\2\) does 
not exceed 400 Bq/cm\2\ (10<SUP>-2</SUP> microcurie/cm\2\) for beta and 
gamma and low toxicity alpha emitters or 40 Bq/cm\2\ (10<SUP>-3</SUP> 
microcurie/cm\2\) for all other alpha emitters;
    (ii) The fixed contamination on the accessible surface averaged over 
300 cm\2\ (or the area of the surface if less than 300 cm\2\) does not 
exceed 8 x 10\5\ Bq/cm\2\ (20 microcuries/cm\2\) for beta and gamma and 
low toxicity alpha emitters, or 8 x 10\4\ Bq/cm\2\ (2 microcuries/cm\2\) 
for all other alpha emitters; and
    (iii) The nonfixed contamination plus the fixed contamination on the 
inaccessible surface averaged over 300 cm\2\ (or the area of the surface 
if less than 300 cm\2\) does not exceed 8 x 10\5\ Bq/cm\2\ (20 
microcuries/cm\2\) for beta and gamma and low toxicity alpha emitters, 
or 8 x 10\4\ Bq/cm\2\ (2 microcuries/cm\2\) for all other alpha 
emitters.
    Transport index (TI) means the dimensionless number (rounded up to 
the next tenth) placed on the label of a package, to designate the 
degree of control to be exercised by the carrier during transportation. 
The transport index is the number determined by multiplying the maximum 
radiation level in millisievert (mSv) per hour at 1 meter (3.3 ft) from 
the external surface of the package by 100 (equivalent to the maximum 
radiation level in millirem per hour at 1 meter (3.3 ft)).
    Type A quantity means a quantity of radioactive material, the 
aggregate radioactivity of which does not exceed A<INF>1</INF> for 
special form radioactive material, or A<INF>2</INF>, for normal form 
radioactive material, where A<INF>1</INF> and A<INF>2</INF> are given in 
Table A-1 of this part, or may be determined by procedures described in 
Appendix A of this part.
    Type B quantity means a quantity of radioactive material greater 
than a Type A quantity.
    Unirradiated uranium means uranium containing not more than 2 x 
10\3\ Bq of plutonium per gram of uranium-235, not more than 9 x 10\6\ 
Bq of fission products per gram of uranium-235, and not more than 5 x 
10<SUP>-3</SUP> g of uranium-236 per gram of uranium-235.
    Uranium--natural, depleted, enriched:
    (1) Natural uranium means uranium with the naturally occurring 
distribution of uranium isotopes (approximately 0.711 weight percent 
uranium-235, and the remainder by weight essentially uranium-238).

[[Page 332]]

    (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.

[69 FR 3786, Jan. 26, 2004; 69 FR 58038, Sept. 29, 2004]

Sec.  71.5  Transportation of licensed material.

    (a) Each licensee who transports licensed material outside the site 
of usage, as specified in the NRC license, or where transport is on 
public highways, or who delivers licensed material to a carrier for 
transport, shall comply with the applicable requirements of the DOT 
regulations in 49 CFR parts 107, 171 through 180, and 390 through 397, 
appropriate to the mode of transport.
    (1) The licensee shall particularly note DOT regulations in the 
following areas:
    (i) Packaging--49 CFR part 173: subparts A, B, and I.
    (ii) Marking and labeling--49 CFR part 172: subpart D; and 
Sec. Sec.  172.400 through 172.407 and Sec. Sec.  172.436 through 
172.441 of subpart E.
    (iii) Placarding--49 CFR part 172: subpart F, especially Sec. Sec.  
172.500 through 172.519 and 172.556; and appendices B and C.
    (iv) Accident reporting--49 CFR part 171: Sec. Sec.  171.15 and 
171.16.
    (v) Shipping papers and emergency information--49 CFR part 172: 
subparts C and 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.
    (2) 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.
    (b) If DOT regulations are not applicable to a shipment of licensed 
material, the licensee shall conform to the standards and requirements 
of the DOT specified in paragraph (a) of this section to the same extent 
as if the shipment or transportation were subject to DOT regulations. A 
request for modification, waiver, or exemption from those requirements, 
and any notification referred to in those requirements, must be filed 
with, or made to, the Director, Office of Nuclear Material Safety and 
Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.

[69 FR 3786, Jan. 26, 2004; 69 FR 58038, Sept. 29, 2004]

Sec.  71.6  Information collection requirements: OMB approval.

    (a) The Nuclear Regulatory Commission has submitted the information 
collection requirements contained in this part to the Office of 
Management and Budget (OMB) for approval as required by the Paperwork 
Reduction Act (44 U.S.C. 3501 et seq.). The NRC may not conduct or 
sponsor, and a person is not required to respond to, a collection of 
information unless it displays a currently valid OMB control number. OMB 
has approved the information collection requirements contained in this 
part under control number 3150-0008.
    (b) The approved information collection requirements contained in 
this part appear in Sec. Sec.  71.5, 71.7, 71.9, 71.12, 71.17, 71.19, 
71.20, 71.22, 71.23, 71.31, 71.33, 71.35, 71.37, 71.38, 71.39, 71.41, 
71.47, 71.85, 71.87, 71.89, 71.91, 71.93, 71.95, 71.97, 71.101, 71.103, 
71.105, 71.107, 71.109, 71.111, 71.113, 71.115, 71.117, 71.119, 71.121, 
71.123, 71.125, 71.127, 71.129, 71.131, 71.133, 71.135, 71.137, and 
Appendix A, Paragraph II.

Sec.  71.7  Completeness and accuracy of information.

    (a) Information provided to the Commission by a licensee, 
certificate holder, or an applicant for a license or CoC; or information 
required by statute or by the Commission's regulations, orders, license 
or CoC conditions, to be maintained by the licensee or certificate 
holder, must be complete and accurate in all material respects.

[[Page 333]]

    (b) Each licensee, certificate holder, or applicant for a license or 
CoC must notify the Commission of information identified by the 
licensee, certificate holder, or applicant for a license or CoC as 
having, for the regulated activity, a significant implication for public 
health and safety or common defense and security. A licensee, 
certificate holder, or an applicant for a license or CoC violates this 
paragraph only if the licensee, certificate holder, or applicant for a 
license or CoC fails to notify the Commission of information that the 
licensee, certificate holder, or applicant for a license or CoC has 
identified as having a significant implication for public health and 
safety or common defense and security. Notification must be provided to 
the Administrator of the appropriate Regional Office within 2 working 
days of identifying the information. This requirement is not applicable 
to information which is already required to be provided to the 
Commission by other reporting or updating requirements.

Sec.  71.8  Deliberate misconduct.

    (a) This section applies to any--
    (1) Licensee;
    (2) Certificate holder;
    (3) Quality assurance program approval holder;
    (4) Applicant for a license, certificate, or quality assurance 
program approval;
    (5) Contractor (including a supplier or consultant) or 
subcontractor, to any person identified in paragraph (a)(4) of this 
section; or
    (6) Employees of any person identified in paragraphs (a)(1) through 
(a)(5) of this section.
    (b) A person identified in paragraph (a) of this section who 
knowingly provides to any entity, listed in paragraphs (a)(1) through 
(a)(5) of this section, any components, materials, or other goods or 
services that relate to a licensee's, certificate holder's, quality 
assurance program approval holder's, or applicant's activities subject 
to this part may not:
    (1) Engage in deliberate misconduct that causes or would have 
caused, if not detected, a licensee, certificate holder, quality 
assurance program approval holder, or any applicant to be in violation 
of any rule, regulation, or order; or any term, condition or limitation 
of any license, certificate, or approval issued by the Commission; or
    (2) Deliberately submit to the NRC, a licensee, a certificate 
holder, quality assurance program approval holder, an applicant for a 
license, certificate or quality assurance program approval, or a 
licensee's, applicant's, certificate holder's, or quality assurance 
program approval holder's contractor or subcontractor, information that 
the person submitting the information knows to be incomplete or 
inaccurate in some respect material to the NRC.
    (c) A person who violates paragraph (b)(1) or (b)(2) of this section 
may be subject to enforcement action in accordance with the procedures 
in 10 CFR part 2, subpart B.
    (d) For the purposes of paragraph (b)(1) of this section, deliberate 
misconduct by a person means an intentional act or omission that the 
person knows:
    (1) Would cause a licensee, certificate holder, quality assurance 
program approval holder, or applicant for a license, certificate, or 
quality assurance program approval to be in violation of any rule, 
regulation, or order; or any term, condition, or limitation of any 
license or certificate issued by the Commission; or
    (2) Constitutes a violation of a requirement, procedure, 
instruction, contract, purchase order, or policy of a licensee, 
certificate holder, quality assurance program approval holder, 
applicant, or the contractor or subcontractor of any of them.

Sec.  71.9  Employee protection.

    (a) Discrimination by a Commission licensee, certificate holder, an 
applicant for a Commission license or a CoC, or a contractor or 
subcontractor of any of these, against an employee for engaging in 
certain protected activities, is prohibited. Discrimination includes 
discharge and other actions that relate to compensation, terms, 
conditions, or privileges of employment. The protected activities are 
established in section 211 of the Energy Reorganization Act of 1974, as 
amended, and in general are related to the administration or enforcement 
of a requirement imposed

[[Page 334]]

under the Atomic Energy Act of 1954, as amended, or the Energy 
Reorganization Act of 1974, as amended.
    (1) The protected activities include, but are not limited to:
    (i) Providing the Commission or his or her employer information 
about alleged violations of either of the statutes named in paragraph 
(a) of this section or possible violations of requirements imposed under 
either of those statutes;
    (ii) Refusing to engage in any practice made unlawful under either 
of the statutes named in paragraph (a) of this section or under these 
requirements if the employee has identified the alleged illegality to 
the employer;
    (iii) Requesting the Commission to institute action against his or 
her employer for the administration or enforcement of these 
requirements;
    (iv) Testifying in any Commission proceeding, or before Congress, or 
at any Federal or State proceeding regarding any provision (or proposed 
provision) of either of the statutes named in paragraph (a) of this 
section; and
    (v) Assisting or participating in, or is about to assist or 
participate in, these activities.
    (2) These activities are protected even if no formal proceeding is 
actually initiated as a result of the employee's assistance or 
participation.
    (3) This section has no application to any employee alleging 
discrimination prohibited by this section who, acting without direction 
from his or her employer (or the employer's agent), deliberately causes 
a violation of any requirement of the Energy Reorganization Act of 1974, 
as amended, or the Atomic Energy Act of 1954, as amended.
    (b) Any employee who believes that he or she has been discharged or 
otherwise discriminated against by any person for engaging in protected 
activities specified in paragraph (a)(1) of this section may seek a 
remedy for the discharge or discrimination through an administrative 
proceeding in the Department of Labor. The administrative proceeding 
must be initiated within 180 days after an alleged violation occurs. The 
employee may do this by filing a complaint alleging the violation with 
the Department of Labor, Employment Standards Administration, Wage and 
Hour Division. The Department of Labor may order reinstatement, back 
pay, and compensatory damages.
    (c) A violation of paragraph (a), (e), or (f) of this section by a 
Commission licensee, certificate holder, applicant for a Commission 
license or a CoC, or a contractor or subcontractor of any of these may 
be grounds for:
    (1) Denial, revocation, or suspension of the license or the CoC;
    (2) Imposition of a civil penalty on the licensee, applicant, or a 
contractor or subcontractor of the licensee or applicant; or
    (3) Other enforcement action.
    (d) Actions taken by an employer, or others, which adversely affect 
an employee may be predicated upon nondiscriminatory grounds. The 
prohibition applies when the adverse action occurs because the employee 
has engaged in protected activities. An employee's engagement in 
protected activities does not automatically render him or her immune 
from discharge or discipline for legitimate reasons or from adverse 
action dictated by nonprohibited considerations.
    (e)(1) Each licensee, certificate holder, and applicant for a 
license or CoC must prominently post the current revision of NRC Form 3, 
``Notice to Employees,'' referenced in Sec.  19.11(c) of this chapter. 
This form must be posted at locations sufficient to permit employees 
protected by this section to observe a copy on the way to or from their 
place of work. The premises must be posted not later than 30 days after 
an application is docketed and remain posted while the application is 
pending before the Commission, during the term of the license or CoC, 
and for 30 days following license or CoC termination.
    (2) Copies of NRC Form 3 may be obtained by writing to the Regional 
Administrator of the appropriate U.S. Nuclear Regulatory Commission 
Regional Office listed in Appendix D to part 20 of this chapter or by 
calling the NRC Publishing Services Branch at 301-415-5877.
    (f) No agreement affecting the compensation, terms, conditions, or 
privileges of employment, including an agreement to settle a complaint 
filed

[[Page 335]]

by an employee with the Department of Labor pursuant to section 211 of 
the Energy Reorganization Act of 1974, as amended, may contain any 
provision which would prohibit, restrict, or otherwise discourage an 
employee from participating in a protected activity as defined in 
paragraph (a)(1) of this section including, but not limited to, 
providing information to the NRC or to his or her employer on potential 
violations or other matters within NRC's regulatory responsibilities.

[69 FR 3786, Jan. 26, 2004, as amended at 72 FR 63975, Nov. 14, 2007]

Sec.  71.10  Public inspection of application.

    Applications for approval of a package design under this part, which 
are submitted to the Commission, may be made available for public 
inspection, in accordance with provisions of parts 2 and 9 of this 
chapter. This includes an application to amend or revise an existing 
package design, any associated documents and drawings submitted with the 
application, and any responses to NRC requests for additional 
information.

Sec.  71.11  [Reserved]

                          Subpart B_Exemptions

    Source: 69 FR 3786, Jan. 26, 2004, unless otherwise noted.

Sec.  71.12  Specific exemptions.

    On application of any interested person or on its own initiative, 
the Commission may grant any exemption from the requirements of the 
regulations in this part that it determines is authorized by law and 
will not endanger life or property nor the common defense and security.

Sec.  71.13  Exemption of physicians.

    Any physician licensed by a State to dispense drugs in the practice 
of medicine is exempt from Sec.  71.5 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 10 CFR part 35 or the equivalent Agreement State regulations.

Sec.  71.14  Exemption for low-level materials.

    (a) A licensee is exempt from all the requirements of this part with 
respect to shipment or carriage of the following low-level materials:
    (1) Natural material and ores containing naturally occurring 
radionuclides that are not intended to be processed for use of these 
radionuclides, provided the activity concentration of the material does 
not exceed 10 times the values specified in Appendix A, Table A-2, of 
this part.
    (2) Materials for which the activity concentration is not greater 
than the activity concentration values specified in Appendix A, Table A-
2 of this part, or for which the consignment activity is not greater 
than the limit for an exempt consignment found in Appendix A, Table A-2, 
of this part.
    (b) A licensee is exempt from all the requirements of this part, 
other than Sec. Sec.  71.5 and 71.88, with respect to shipment or 
carriage of the following packages, provided the packages do not contain 
any fissile material, or the material is exempt from classification as 
fissile material under Sec.  71.15:
    (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 0.74 TBq (20 Ci) of special form plutonium-244; or
    (3) The package contains only LSA or SCO radioactive material, 
provided--
    (i) That the LSA or SCO material has an external radiation dose of 
less than or equal to 10 mSv/h (1 rem/h), at a distance of 3 m from the 
unshielded material; or
    (ii) That the package contains only LSA-I or SCO-I material.

Sec.  71.15  Exemption from classification as fissile material.

    Fissile material meeting the requirements of at least one of the 
paragraphs (a) through (f) of this section are exempt from 
classification as fissile material and from the fissile material package 
standards of Sec. Sec.  71.55 and 71.59, but are subject to all other 
requirements of this part, except as noted.
    (a) Individual package containing 2 grams or less fissile material.

[[Page 336]]

    (b) Individual or bulk packaging containing 15 grams or less of 
fissile material provided the package has at least 200 grams of solid 
nonfissile material for every gram of fissile material. Lead, beryllium, 
graphite, and hydrogenous material enriched in deuterium may be present 
in the package but must not be included in determining the required mass 
for solid nonfissile material.
    (c)(1) Low concentrations of solid fissile material commingled with 
solid nonfissile material, provided that:
    (i) There is at least 2000 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.
    (2) Lead, beryllium, graphite, and hydrogenous material enriched in 
deuterium may be present in the package but must not be included in 
determining the required mass of solid nonfissile material.
    (d) Uranium enriched in uranium-235 to a maximum of 1 percent by 
weight, and with total plutonium and uranium-233 content of up to 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 5 percent of the uranium mass.
    (e) Liquid solutions of uranyl nitrate enriched in uranium-235 to a 
maximum of 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.
    (f) Packages containing, individually, a total plutonium mass of not 
more than 1000 grams, of which not more than 20 percent by mass may 
consist of plutonium-239, plutonium-241, or any combination of these 
radionuclides.

Sec.  71.16  [Reserved]

                       Subpart C_General Licenses

    Source: 69 FR 3786, Jan. 26, 2004, unless otherwise noted.

Sec.  71.17  General license: NRC-approved package.

    (a) A general license is issued to any licensee of the Commission to 
transport, or to deliver to a carrier for transport, licensed material 
in a package for which a license, certificate of compliance (CoC), or 
other approval has been issued by the NRC.
    (b) This general license applies only to a licensee who has a 
quality assurance program approved by the Commission as satisfying the 
provisions of subpart H of this part.
    (c) This general license applies only to a licensee who--
    (1) Has a copy of the CoC, or other approval of the package, and has 
the drawings and other documents referenced in the approval relating to 
the use and maintenance of the packaging and to the actions to be taken 
before shipment;
    (2) Complies with the terms and conditions of the license, 
certificate, or other approval, as applicable, and the applicable 
requirements of subparts A, G, and H of this part; and
    (3) Before the licensee's first use of the package, submits in 
writing to: ATTN: Document Control Desk, Director, Spent Fuel Project 
Office, Office of Nuclear Material Safety and Safeguards, using an 
appropriate method listed in Sec.  71.1(a), the licensee's name and 
license number and the package identification number specified in the 
package approval.
    (d) This general license 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 the additional restrictions of Sec.  71.19.

Sec.  71.18  [Reserved]

Sec.  71.19  Previously approved package.

    (a) A Type B package previously approved by NRC, but not designated 
as B(U), B(M), B(U)F, or B(M)F in the identification number of the NRC 
CoC, or Type AF packages approved by the NRC prior to September 6, 1983, 
may be used under the general license of Sec.  71.17

[[Page 337]]

with the following additional conditions:
    (1) Fabrication of the packaging was satisfactorily completed by 
August 31, 1986, as demonstrated by application of its model number in 
accordance with Sec.  71.85(c);
    (2) A serial number that uniquely identifies each packaging which 
conforms to the approved design is assigned to, and legibly and durably 
marked on, the outside of each packaging; and
    (3) Paragraph (a) of this section expires October 1, 2008.
    (b) A Type B(U) package, a Type B(M) package, or a fissile material 
package, previously approved by the NRC but without the designation ``-
85'' in the identification number of the NRC CoC, may be used under the 
general license of Sec.  71.17 with the following additional conditions:
    (1) Fabrication of the package is satisfactorily completed by April 
1, 1999, as demonstrated by application of its model number in 
accordance with Sec.  71.85(c);
    (2) A package used for a shipment to a location outside the United 
States is subject to multilateral approval as defined in DOT regulations 
at 49 CFR 173.403; and
    (3) A serial number which uniquely identifies each packaging which 
conforms to the approved design is assigned to and legibly and durably 
marked on the outside of each packaging.
    (c) A Type B(U) package, a Type B(M) package, or a fissile material 
package previously approved by the NRC with the designation ``-85'' in 
the identification number of the NRC CoC, may be used under the general 
license of Sec.  71.17 with the following additional conditions:
    (1) Fabrication of the package must be satisfactorily completed by 
December 31, 2006, as demonstrated by application of its model number in 
accordance with Sec.  71.85(c); and
    (2) After December 31, 2003, a package used for a shipment to a 
location outside the United States is subject to multilateral approval 
as defined in DOT regulations at 49 CFR 173.403.
    (d) NRC will approve modifications to the design and authorized 
contents of a Type B package, or a fissile material package, previously 
approved by NRC, provided--
    (1) The modifications of a Type B package are not significant with 
respect to the design, operating characteristics, or safe performance of 
the containment system, when the package is subjected to the tests 
specified in Sec. Sec.  71.71 and 71.73;
    (2) The modifications of a fissile material package are not 
significant, with respect to the prevention of criticality, when the 
package is subjected to the tests specified in Sec. Sec.  71.71 and 
71.73; and
    (3) The modifications to the package satisfy the requirements of 
this part.
    (e) NRC will revise the package identification number to designate 
previously approved package designs as B, BF, AF, B(U), B(M), B(U)F, 
B(M)F, B(U)-85, B(U)F-85, B(M)-85, B(M)F-85, or AF-85 as appropriate, 
and with the identification number suffix ``-96'' after receipt of an 
application demonstrating that the design meets the requirements of this 
part.

[69 FR 3786, Jan. 26, 2004; 69 FR 6139, Feb. 10, 2004]

    Effective Date Note: At 69 FR 3786, Jan. 26, 2004, as corrected at 
69 FR 6139, Feb. 10, 2004, Sec.  71.19 was revised, effective Oct. 1, 
2004. Paragraph (a) of this section will expire on Oct. 1, 2008.

Sec.  71.20  General license: DOT specification container.

    (a) A general license is issued to any licensee of the Commission 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 DOT regulations at 49 
CFR parts 173 and 178.
    (b) This general license applies only to a licensee who has a 
quality assurance program approved by the Commission as satisfying the 
provisions of subpart H of this part.
    (c) This general license applies only to a licensee who--
    (1) Has a copy of the specification; and
    (2) Complies with the terms and conditions of the specification and 
the applicable requirements of subparts A, G, and H of this part.

[[Page 338]]

    (d) This general license 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.
    (e) This section expires October 1, 2008.

[69 FR 3786, Jan. 26, 2004]

    Effective Date Note: At 69 FR 3786, Sec.  71.20 was revised, 
effective Oct. 1, 2004 to Oct. 1, 2008.

Sec.  71.21  General license: Use of foreign approved package.

    (a) A general license is issued to any licensee of the Commission 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, that has been revalidated by 
DOT as meeting the applicable requirements of 49 CFR 171.12.
    (b) Except as otherwise provided in this section, the general 
license applies only to a licensee who has a quality assurance program 
approved by the Commission as satisfying the applicable provisions of 
subpart H of this part.
    (c) This general license applies only to shipments made to or from 
locations outside the United States.
    (d) 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 before shipment; and
    (2) Complies with the terms and conditions of the certificate and 
revalidation, and with the applicable requirements of subparts A, G, and 
H of this part. With respect to the quality assurance provisions of 
subpart H of this part, the licensee is exempt from design, 
construction, and fabrication considerations.

Sec.  71.22  General license: Fissile material.

    (a) A general license is issued to any licensee of the Commission 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 fissile material need not be contained in a package which 
meets the standards of subparts E and F of this part; however, the 
material must be contained in a Type A package. The Type A package must 
also meet the DOT requirements of 49 CFR 173.417(a).
    (b) The general license applies only to a licensee who has a quality 
assurance program approved by the Commission as satisfying the 
provisions of subpart H of this part.
    (c) The general license applies only when a package's contents:
    (1) Contain no more than a Type A quantity of radioactive material; 
and
    (2) Contain less than 500 total grams of beryllium, graphite, or 
hydrogenous material enriched in deuterium.
    (d) The general license applies only to packages containing fissile 
material that are labeled with a CSI which:
    (1) Has been determined in accordance with paragraph (e) of this 
section;
    (2) Has a value less than or equal to 10; and
    (3) For a shipment of multiple packages containing fissile material, 
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).
    (e)(1) The value for the CSI must be greater than or equal to the 
number calculated by the following equation:
[GRAPHIC] [TIFF OMITTED] TR26JA04.012


[[Page 339]]


    (2) The calculated CSI must be rounded up to the first decimal 
place;
    (3) The values of X, Y, and Z used in the CSI equation must be taken 
from Tables 71-1 or 71-2, as appropriate;
    (4) If Table 71-2 is used to obtain the value of X, then the values 
for the terms in the equation for uranium-233 and plutonium must be 
assumed to be zero; and
    (5) Table 71-1 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 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 H<INF>2</INF>O) (e.g., certain hydrocarbon 
oils or plastics) are present in any form, except as polyethylene used 
for packing or wrapping.

  Table 71-1--Mass Limits for General License Packages Containing Mixed
 Quantities of Fissile Material or Uranium-235 of Unknown Enrichment per
                             Sec.   71.22(e)
------------------------------------------------------------------------
                                   Fissile material    Fissile material
                                    mass mixed with     mass mixed with
                                      moderating          moderating
                                   substances having   substances having
        Fissile material              an average          an average
                                   hydrogen density    hydrogen density
                                  less than or equal   greater than H2Oa
                                    to H2O (grams)          (grams)
------------------------------------------------------------------------
\235\ U (X).....................                 60                  38
\233\ U (Y).....................                 43                  27
\239\ Pu or \241\ Pu (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
  substance has an average hydrogen density greater than H2O.


Table 71-2--Mass Limits for General License Packages Containing Uranium-
               235 of Known Enrichment per Sec.   71.22(e)
------------------------------------------------------------------------
                                                               Fissile
                                                              material
    Uranium enrichment in weight percent of \235\ U not        mass of
                         exceeding                           \235\ U (X)
                                                               (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
------------------------------------------------------------------------


[69 FR 3786, Jan. 26, 2004; 69 FR 58038, Sept. 29, 2004]

Sec.  71.23  General license: Plutonium-beryllium special form material.

    (a) A general license is issued to any licensee of the Commission 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. This material need not be contained in a package which 
meets the standards of subparts E and F of this part; however, the 
material must be contained in a Type A package. The Type A package must 
also meet the DOT requirements of 49 CFR 173.417(a).
    (b) The general license applies only to a licensee who has a quality 
assurance program approved by the Commission as satisfying the 
provisions of subpart H of this part.
    (c) The general license applies only when a package's contents:
    (1) Contain no more than a Type A quantity of radioactive material; 
and
    (2) Contain less than 1000 g of plutonium, provided that: plutonium-
239, plutonium-241, or any combination of these radionuclides, 
constitutes less

[[Page 340]]

than 240 g of the total quantity of plutonium in the package.
    (d) The general license applies only to packages labeled with a CSI 
which:
    (1) Has been determined in accordance with paragraph (e) of this 
section;
    (2) Has a value less than or equal to 100; and
    (3) 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).
    (e)(1) The value for the CSI must be greater than or equal to the 
number calculated by the following equation:
[GRAPHIC] [TIFF OMITTED] TR26JA04.013

    (2) The calculated CSI must be rounded up to the first decimal 
place.

[69 FR 3786, Jan. 26, 2004; 69 FR 58038, Sept. 29, 2004]

Sec. Sec.  71.24-71.25  [Reserved]

               Subpart D_Application for Package Approval

Sec.  71.31  Contents of application.

    (a) An application for an approval under this part must include, for 
each proposed packaging design, the following information:
    (1) A package description as required by Sec.  71.33;
    (2) A package evaluation as required by Sec.  71.35; and
    (3) A quality assurance program description, as required by Sec.  
71.37, or a reference to a previously approved quality assurance 
program.
    (b) Except as provided in Sec.  71.13, an application for 
modification of a package design, whether for modification of the 
packaging or authorized contents, must include sufficient information to 
demonstrate that the proposed design satisfies the package standards in 
effect at the time the application is filed.
    (c) The applicant shall identify any established codes and standards 
proposed for use in package design, fabrication, assembly, testing, 
maintenance, and use. In the absence of any codes and standards, the 
applicant shall describe and justify the basis and rationale used to 
formulate the package quality assurance program.

Sec.  71.33  Package description.

    The application must include a description of the proposed package 
in sufficient detail to identify the package accurately and provide a 
sufficient basis for evaluation of the package. The description must 
include--
    (a) With respect to the packaging--
    (1) Classification as Type B(U), Type B(M), or fissile material 
packaging;
    (2) Gross weight;
    (3) Model number;
    (4) Identification of the containment system;
    (5) Specific materials of construction, weights, dimensions, and 
fabrication methods of--
    (i) Receptacles;
    (ii) Materials specifically used as nonfissile neutron absorbers or 
moderators;
    (iii) Internal and external structures supporting or protecting 
receptacles;
    (iv) Valves, sampling ports, lifting devices, and tie-down devices; 
and
    (v) Structural and mechanical means for the transfer and dissipation 
of heat; and
    (6) Identification and volumes of any receptacles containing 
coolant.
    (b) With respect to the contents of the package--
    (1) Identification and maximum radioactivity of radioactive 
constituents;
    (2) Identification and maximum quantities of fissile constituents;
    (3) Chemical and physical form;
    (4) Extent of reflection, the amount and identity of nonfissile 
materials

[[Page 341]]

used as neutron absorbers or moderators, and the atomic ratio of 
moderator to fissile constituents;
    (5) Maximum normal operating pressure;
    (6) Maximum weight;
    (7) Maximum amount of decay heat; and
    (8) Identification and volumes of any coolants.

Sec.  71.35  Package evaluation.

    The application must include the following:
    (a) A demonstration that the package satisfies the standards 
specified in subparts E and F of this part;
    (b) For a fissile material package, the allowable number of packages 
that may be transported in the same vehicle in accordance with Sec.  
71.59; and
    (c) For a fissile material shipment, any proposed special controls 
and precautions for transport, loading, unloading, and handling and any 
proposed special controls in case of an accident or delay.

Sec.  71.37  Quality assurance.

    (a) The applicant shall describe the quality assurance program (see 
Subpart H of this part) for the design, fabrication, assembly, testing, 
maintenance, repair, modification, and use of the proposed package.
    (b) The applicant shall identify any specific provisions of the 
quality assurance program that are applicable to the particular package 
design under consideration, including a description of the leak testing 
procedures.

Sec.  71.38  Renewal of a certificate of compliance or quality assurance 
          program approval.

    (a) Except as provided in paragraph (b) of this section, each 
Certificate of Compliance or Quality Assurance Program Approval expires 
at the end of the day, in the month and year stated in the approval.
    (b) In any case in which a person, not less than 30 days before the 
expiration of an existing Certificate of Compliance or Quality Assurance 
Program Approval issued pursuant to the part, has filed an application 
in proper form for renewal of either of those approvals, the existing 
Certificate of Compliance or Quality Assurance Program Approval for 
which the renewal application was filed shall not be deemed to have 
expired until final action on the application for renewal has been taken 
by the Commission.
    (c) In applying for renewal of an existing Certificate of Compliance 
or Quality Assurance Program Approval, an applicant may be required to 
submit a consolidated application that incorporates all changes to its 
program that, are incorporated by reference in the existing approval or 
certificate, into as few referenceable documents as reasonably 
achievable.

Sec.  71.39  Requirement for additional information.

    The Commission may at any time require additional information in 
order to enable it to determine whether a license, certificate of 
compliance, or other approval should be granted, renewed, denied, 
modified, suspended, or revoked.

                  Subpart E_Package Approval Standards

Sec.  71.41  Demonstration of compliance.

    (a) The effects on a package of the tests specified in Sec.  71.71 
(``Normal conditions of transport''), and the tests specified in Sec.  
71.73 (``Hypothetical accident conditions''), and Sec.  71.61 (``Special 
requirements for Type B packages containing more than 10\5\ 
A<INF>2</INF>''), must be evaluated by subjecting a specimen or scale 
model to a specific test, or by another method of demonstration 
acceptable to the Commission, as appropriate for the particular feature 
being considered.
    (b) Taking into account the type of vehicle, the method of securing 
or attaching the package, and the controls to be exercised by the 
shipper, the Commission may permit the shipment to be evaluated together 
with the transporting vehicle.
    (c) Environmental and test conditions different from those specified 
in Sec. Sec.  71.71 and 71.73 may be approved by the Commission if the 
controls proposed to be exercised by the shipper are demonstrated to be 
adequate to provide equivalent safety of the shipment.

[[Page 342]]

    (d) Packages for which compliance with the other provisions of these 
regulations is impracticable shall not be transported except under 
special package authorization. Provided the applicant demonstrates that 
compliance with the other provisions of the regulations is impracticable 
and that the requisite standards of safety established by these 
regulations have been demonstrated through means alternative to the 
other provisions, a special package authorization may be approved for 
one-time shipments. The applicant shall demonstrate that the overall 
level of safety in transport for these shipments is at least equivalent 
to that which would be provided if all the applicable requirements had 
been met.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3794, Jan. 26, 2004; 
69 FR 58039, Sept. 29, 2004]

Sec.  71.43  General standards for all packages.

    (a) The smallest overall dimension of a package may not be less than 
10 cm (4 in).
    (b) The outside of a package must incorporate a feature, such as a 
seal, that is not readily breakable and that, while intact, would be 
evidence that the package has not been opened by unauthorized persons.
    (c) Each package must include a containment system securely closed 
by a positive fastening device that cannot be opened unintentionally or 
by a pressure that may arise within the package.
    (d) A package must be made of materials and construction that assure 
that there will be no significant chemical, galvanic, or other reaction 
among the packaging components, among package contents, or between the 
packaging components and the package contents, including possible 
reaction resulting from inleakage of water, to the maximum credible 
extent. Account must be taken of the behavior of materials under 
irradiation.
    (e) A package valve or other device, the failure of which would 
allow radioactive contents to escape, must be protected against 
unauthorized operation and, except for a pressure relief device, must be 
provided with an enclosure to retain any leakage.
    (f) A package must be designed, constructed, and prepared for 
shipment so that under the tests specified in Sec.  71.71 (``Normal 
conditions of transport'') there would be no loss or dispersal of 
radioactive contents, no significant increase in external surface 
radiation levels, and no substantial reduction in the effectiveness of 
the packaging.
    (g) A package must be designed, constructed, and prepared for 
transport so that in still air at 38[deg]C (100[deg]F) and in the shade, 
no accessible surface of a package would have a temperature exceeding 
50[deg]C (122[deg]F) in a nonexclusive use shipment, or 85[deg]C 
(185[deg]F) in an exclusive use shipment.
    (h) A package may not incorporate a feature intended to allow 
continuous venting during transport.

Sec.  71.45  Lifting and tie-down standards for all packages.

    (a) Any lifting attachment that is a structural part of a package 
must be designed with a minimum safety factor of three against yielding 
when used to lift the package in the intended manner, and it must be 
designed so that failure of any lifting device under excessive load 
would not impair the ability of the package to meet other requirements 
of this subpart. Any other structural part of the package that could be 
used to lift the package must be capable of being rendered inoperable 
for lifting the package during transport, or must be designed with 
strength equivalent to that required for lifting attachments.
    (b) Tie-down devices:
    (1) If there is a system of tie-down devices that is a structural 
part of the package, the system must be capable of withstanding, without 
generating stress in any material of the package in excess of its yield 
strength, a static force applied to the center of gravity of the package 
having a vertical component of 2 times the weight of the package with 
its contents, a horizontal component along the direction in which the 
vehicle travels of 10 times the weight of the package with its contents, 
and a horizontal component in the transverse direction of 5 times the 
weight of the package with its contents.

[[Page 343]]

    (2) Any other structural part of the package that could be used to 
tie down the package must be capable of being rendered inoperable for 
tying down the package during transport, or must be designed with 
strength equivalent to that required for tie-down devices.
    (3) Each tie-down device that is a structural part of a package must 
be designed so that failure of the device under excessive load would not 
impair the ability of the package to meet other requirements of this 
part.

Sec.  71.47  External radiation standards for all packages.

    (a) Except as provided in paragraph (b) of this section, 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 2 mSv/h 
(200 mrem/h) 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 
paragraph (a) of this section must be transported by exclusive use 
shipment only, and the radiation levels for such shipment must not 
exceed the following during transportation:
    (1) 2 mSv/h (200 mrem/h) on the external surface of the package, 
unless the following conditions are met, in which case the limit is 10 
mSv/h (1000 mrem/h):
    (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) 2 mSv/h (200 mrem/h) 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) 0.1 mSv/h (10 mrem/h) at any point 2 meters (80 in) 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 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) 0.02 mSv/h (2 mrem/h) 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 10 CFR 20.1502.
    (c) For shipments made under the provisions of paragraph (b) of this 
section, the shipper shall 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.

Sec.  71.51  Additional requirements for Type B packages.

    (a) A Type B package, in addition to satisfying the requirements of 
Sec. Sec.  71.41 through 71.47, must be designed, constructed, and 
prepared for shipment so that under the tests specified in:
    (1) Section 71.71 (``Normal conditions of transport''), there would 
be no loss or dispersal of radioactive contents--as demonstrated to a 
sensitivity of 10<SUP>-6</SUP> A<INF>2</INF> per hour, no significant 
increase in external surface radiation levels, and no substantial 
reduction in the effectiveness of the packaging; and
    (2) Section 71.73 (``Hypothetical accident conditions''), there 
would be no escape of krypton-85 exceeding 10 A<INF>2</INF> in 1 week, 
no escape of other radioactive material exceeding a total amount 
A<INF>2</INF> in 1 week, and no external radiation dose rate exceeding 
10 mSv/h (1 rem/h) at 1 m (40 in) from the external surface of the 
package.
    (b) Where mixtures of different radionuclides are present, the 
provisions of appendix A, paragraph IV of this part

[[Page 344]]

shall apply, except that for Krypton-85, an effective A<INF>2</INF> 
value equal to 10 A<INF>2</INF> may be used.
    (c) Compliance with the permitted activity release limits of 
paragraph (a) of this section may not depend on filters or on a 
mechanical cooling system.
    (d) For packages which contain radioactive contents with activity 
greater than 10\5\ A<INF>2</INF>, the requirements of Sec.  71.61 must 
be met.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3794, Jan. 26, 2004; 
69 FR 58039, Sept. 29, 2004]

Sec.  71.53  [Reserved]

Sec.  71.55  General requirements for fissile material packages.

    (a) A package used for the shipment of fissile material must be 
designed and constructed in accordance with Sec. Sec.  71.41 through 
71.47. When required by the total amount of radioactive material, a 
package used for the shipment of fissile material must also be designed 
and constructed in accordance with Sec.  71.51.
    (b) Except as provided in paragraph (c) or (g) of this section, a 
package used for the shipment of fissile material must be so designed 
and constructed and its contents so limited that it would be subcritical 
if water were to leak into the containment system, or liquid contents 
were to leak out of the containment system so that, under the following 
conditions, maximum reactivity of the fissile material would be 
attained:
    (1) The most reactive credible configuration consistent with the 
chemical and physical form of the material;
    (2) Moderation by water to the most reactive credible extent; and
    (3) Close full reflection of the containment system by water on all 
sides, or such greater reflection of the containment system as may 
additionally be provided by the surrounding material of the packaging.
    (c) The Commission may approve exceptions to the requirements of 
paragraph (b) of this section if the package incorporates special design 
features that ensure that no single packaging error would permit 
leakage, and if appropriate measures are taken before each shipment to 
ensure that the containment system does not leak.
    (d) A package used for the shipment of fissile material must be so 
designed and constructed and its contents so limited that under the 
tests specified in Sec.  71.71 (``Normal conditions of transport'')--
    (1) The contents would be subcritical;
    (2) The geometric form of the package contents would not be 
substantially altered;
    (3) There would be no leakage of water into the containment system 
unless, in the evaluation of undamaged packages under Sec.  71.59(a)(1), 
it has been assumed that moderation is present to such an extent as to 
cause maximum reactivity consistent with the chemical and physical form 
of the material; and
    (4) There will be no substantial reduction in the effectiveness of 
the packaging, including:
    (i) No more than 5 percent reduction in the total effective volume 
of the packaging on which nuclear safety is assessed;
    (ii) No more than 5 percent reduction in the effective spacing 
between the fissile contents and the outer surface of the packaging; and
    (iii) No occurrence of an aperture in the outer surface of the 
packaging large enough to permit the entry of a 10 cm (4 in) cube.
    (e) A package used for the shipment of fissile material must be so 
designed and constructed and its contents so limited that under the 
tests specified in Sec.  71.73 (``Hypothetical accident conditions''), 
the package would be subcritical. For this determination, it must be 
assumed that:
    (1) The fissile material is in the most reactive credible 
configuration consistent with the damaged condition of the package and 
the chemical and physical form of the contents;
    (2) Water moderation occurs to the most reactive credible extent 
consistent with the damaged condition of the package and the chemical 
and physical form of the contents; and
    (3) There is full reflection by water on all sides, as close as is 
consistent with the damaged condition of the package.

[[Page 345]]

    (f) For fissile material package designs to be transported by air:
    (1) The package must be designed and constructed, and its contents 
limited so that it would be subcritical, assuming reflection by 20 cm 
(7.9 in) of water but no water inleakage, when subjected to sequential 
application of:
    (i) The free drop test in Sec.  71.73(c)(1);
    (ii) The crush test in Sec.  71.73(c)(2);
    (iii) A puncture test, for packages of 250 kg or more, consisting of 
a free drop of the specimen through a distance of 3 m (120 in) in a 
position for which maximum damage is expected at the conclusion of the 
test sequence, onto the upper end of a solid, vertical, cylindrical, 
mild steel probe mounted on an essentially unyielding, horizontal 
surface. The probe must be 20 cm (7.9 in) in diameter, with the striking 
end forming the frustum of a right circular cone with the dimensions of 
30 cm height, 2.5 cm top diameter, and a top edge rounded to a radius of 
not more than 6 mm (0.25 in). For packages less than 250 kg, the 
puncture test must be the same, except that a 250 kg probe must be 
dropped onto the specimen which must be placed on the surface; and
    (iv) The thermal test in Sec.  71.73(c)(4), except that the duration 
of the test must be 60 minutes.
    (2) The package must be designed and constructed, and its contents 
limited, so that it would be subcritical, assuming reflection by 20 cm 
(7.9 in) of water but no water inleakage, when subjected to an impact on 
an unyielding surface at a velocity of 90 m/s normal to the surface, at 
such orientation so as to result in maximum damage. A separate, 
undamaged specimen can be used for this evaluation.
    (3) Allowance may not be made for the special design features in 
paragraph (c) of this section, unless water leakage into or out of void 
spaces is prevented following application of the tests in paragraphs 
(f)(1) and (f)(2) of this section, and subsequent application of the 
immersion test in Sec.  71.73(c)(5).
    (g) Packages containing uranium hexafluoride only are excepted from 
the requirements of paragraph (b) of this section provided that:
    (1) Following the tests specified in Sec.  71.73 (``Hypothetical 
accident conditions''), there is no physical contact between the valve 
body and any other component of the packaging, other than at its 
original point of attachment, and the valve remains leak tight;
    (2) There is an adequate quality control in the manufacture, 
maintenance, and repair of packagings;
    (3) Each package is tested to demonstrate closure before each 
shipment; and
    (4) The uranium is enriched to not more than 5 weight percent 
uranium-235.

[60 FR 50264, Sept. 28, 1995; 61 FR 28724, June 6, 1996, as amended at 
69 FR 3794, Jan. 26, 2004]

Sec.  71.57  [Reserved]

Sec.  71.59  Standards for arrays of fissile material packages.

    (a) A fissile material package must be controlled by either the 
shipper or the carrier during transport to assure that an array of such 
packages remains subcritical. To enable this control, the designer of a 
fissile material package shall derive a number ``N'' based on all the 
following conditions being satisfied, assuming packages are stacked 
together in any arrangement and with close full reflection on all sides 
of the stack by water:
    (1) Five times ``N'' undamaged packages with nothing between the 
packages would be subcritical;
    (2) Two times ``N'' damaged packages, if each package were subjected 
to the tests specified in Sec.  71.73 (``Hypothetical accident 
conditions'') would be subcritical with optimum interspersed hydrogenous 
moderation; and
    (3) The value of ``N'' cannot be less than 0.5.
    (b) The CSI must be determined by dividing the number 50 by the 
value of ``N'' derived using the procedures specified in paragraph (a) 
of this section. The value of the CSI may be zero provided that an 
unlimited number of packages are subcritical, such that the value of 
``N'' is effectively equal to infinity under the procedures specified in 
paragraph (a) of this section. Any CSI

[[Page 346]]

greater than zero must be rounded up to the first decimal place.
    (c) For a fissile material package which is assigned a CSI value--
    (1) Less than or equal to 50, that package may be shipped by a 
carrier in a nonexclusive use conveyance, provided the sum of the CSIs 
is limited to less than or equal to 50.
    (2) Less than or equal to 50, that package may be shipped by a 
carrier in an exclusive use conveyance, provided the sum of the CSIs is 
limited to less than or equal to 100.
    (3) Greater than 50, that package must be shipped by a carrier in an 
exclusive use conveyance, provided the sum of the CSIs is limited to 
less than or equal to 100.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3795, Jan. 26, 2004]

Sec.  71.61  Special requirements for Type B packages containing more 
          than 10[bds5]A[bdi2].

    A Type B package containing more than 10\5\A<INF>2</INF> must be 
designed so that its undamaged containment system can withstand an 
external water pressure of 2 MPa (290 psi) for a period of not less than 
1 hour without collapse, buckling, or inleakage of water.

[69 FR 3795, Jan. 26, 2004]

Sec.  71.63  Special requirement for plutonium shipments.

    Shipments containing plutonium must be made with the contents in 
solid form, if the contents contain greater than 0.74 TBq (20 Ci) of 
plutonium.

[69 FR 3795, Jan. 26, 2004]

Sec.  71.64  Special requirements for plutonium air shipments.

    (a) A package for the shipment of plutonium by air subject to Sec.  
71.88(a)(4), in addition to satisfying the requirements of Sec. Sec.  
71.41 through 71.63, as applicable, must be designed, constructed, and 
prepared for shipment so that under the tests specified in--
    (1) Section 71.74 (``Accident conditions for air transport of 
plutonium'')--
    (i) The containment vessel would not be ruptured in its post-tested 
condition, and the package must provide a sufficient degree of 
containment to restrict accumulated loss of plutonium contents to not 
more than an A<INF>2</INF> quantity in a period of 1 week;
    (ii) The external radiation level would not exceed 10 mSv/h (1 rem/
h) at a distance of 1 m (40 in) from the surface of the package in its 
post-tested condition in air; and
    (iii) A single package and an array of packages are demonstrated to 
be subcritical in accordance with this part, except that the damaged 
condition of the package must be considered to be that which results 
from the plutonium accident tests in Sec.  71.74, rather than the 
hypothetical accident tests in Sec.  71.73; and
    (2) Section 71.74(c), there would be no detectable leakage of water 
into the containment vessel of the package.
    (b) With respect to the package requirements of paragraph (a), there 
must be a demonstration or analytical assessment showing that--
    (1) The results of the physical testing for package qualification 
would not be adversely affected to a significant extent by--
    (i) The presence, during the tests, of the actual contents that will 
be transported in the package; and
    (ii) Ambient water temperatures ranging from 0.6[deg]C (+33[deg]F) 
to 38[deg]C (+100[deg]F) for those qualification tests involving water, 
and ambient atmospheric temperatures ranging from -40[deg]C (-40[deg]F) 
to +54[deg]C (+130[deg]F) for the other qualification tests.
    (2) The ability of the package to meet the acceptance standards 
prescribed for the accident condition sequential tests would not be 
adversely affected if one or more tests in the sequence were deleted.

Sec.  71.65  Additional requirements.

    The Commission may, by rule, regulation, or order, impose 
requirements on any licensee, in addition to those established in this 
part, as it deems necessary or appropriate to protect public health or 
to minimize danger to life or property.

[[Page 347]]

         Subpart F_Package, Special Form, and LSA-III Tests \2\
---------------------------------------------------------------------------

    \2\ The package standards related to the tests in this subpart are 
contained in subpart E of this part.
---------------------------------------------------------------------------

Sec.  71.71  Normal conditions of transport.

    (a) Evaluation. Evaluation of each package design under normal 
conditions of transport must include a determination of the effect on 
that design of the conditions and tests specified in this section. 
Separate specimens may be used for the free drop test, the compression 
test, and the penetration test, if each specimen is subjected to the 
water spray test before being subjected to any of the other tests.
    (b) Initial conditions. With respect to the initial conditions for 
the tests in this section, the demonstration of compliance with the 
requirements of this part must be based on the ambient temperature 
preceding and following the tests remaining constant at that value 
between -29[deg]C (-20[deg]F) and +38[deg]C (+100[deg]F) which is most 
unfavorable for the feature under consideration. The initial internal 
pressure within the containment system must be considered to be the 
maximum normal operating pressure, unless a lower internal pressure 
consistent with the ambient temperature considered to precede and follow 
the tests is more unfavorable.
    (c) Conditions and tests--(1) Heat. An ambient temperature of 
38[deg]C (100[deg]F) in still air, and insolation according to the 
following table:

                             Insolation Data
------------------------------------------------------------------------
                                             Total insolation for a 12-
       Form and location of surface           hour period (g cal/cm\2\
------------------------------------------------------------------------
Flat surfaces transported horizontally:
    Base..................................  None
    Other surfaces........................  800
Flat surfaces not transported horizontally  200
Curved surfaces...........................  400
------------------------------------------------------------------------

    (2) Cold. An ambient temperature of -40[deg]C (-40[deg]F) in still 
air and shade.
    (3) Reduced external pressure. An external pressure of 25 kPa (3.5 
lbf/in\2\) absolute.
    (4) Increased external pressure. An external pressure of 140 kPa (20 
lbf/in\2\) absolute.
    (5) Vibration. Vibration normally incident to transport.
    (6) Water spray. A water spray that simulates exposure to rainfall 
of approximately 5 cm/h (2 in/h) for at least 1 hour.
    (7) Free drop. Between 1.5 and 2.5 hours after the conclusion of the 
water spray test, a free drop through the distance specified below onto 
a flat, essentially unyielding, horizontal surface, striking the surface 
in a position for which maximum damage is expected.

              Criteria for Free Drop Test (Weight/Distance)
------------------------------------------------------------------------
                    Package weight                          Free drop
-------------------------------------------------------     distance
                                                       -----------------
            Kilograms                    (Pounds)        Meters   (Feet)
------------------------------------------------------------------------
Less than 5,000..................  (Less than 11,000).      1.2      (4)
5,000 to 10,000..................  (11,000 to 22,000).      0.9      (3)
10,000 to 15,000.................  (22,000 to 33,100).      0.6      (2)
More than 15,000.................  (More than 33,100).      0.3      (1)
------------------------------------------------------------------------

    (8) Corner drop. A free drop onto each corner of the package in 
succession, or in the case of a cylindrical package onto each quarter of 
each rim, from a height of 0.3 m (1 ft) onto a flat, essentially 
unyielding, horizontal surface. This test applies only to fiberboard, 
wood, or fissile material rectangular packages not exceeding 50 kg (110 
lbs) and fiberboard, wood, or fissile material cylindrical packages not 
exceeding 100 kg (220 lbs).
    (9) Compression. For packages weighing up to 5000 kg (11,000 lbs), 
the package must be subjected, for a period of 24 hours, to a 
compressive load applied uniformly to the top and bottom of the package 
in the position in which the package would normally be transported. The 
compressive load must be the greater of the following:
    (i) The equivalent of 5 times the weight of the package; or
    (ii) The equivalent of 13 kPa (2 lbf/in\2\) multiplied by the 
vertically projected area of the package.
    (10) Penetration. Impact of the hemispherical end of a vertical 
steel cylinder of 3.2 cm (1.25 in) diameter and 6 kg (13 lbs) mass, 
dropped from a height of 1 m (40 in) onto the exposed surface of the 
package that is expected to be most vulnerable to puncture. The long 
axis of the cylinder must be perpendicular to the package surface.

[[Page 348]]

Sec.  71.73  Hypothetical accident conditions.

    (a) Test procedures. Evaluation for hypothetical accident conditions 
is to be based on sequential application of the tests specified in this 
section, in the order indicated, to determine their cumulative effect on 
a package or array of packages. An undamaged specimen may be used for 
the water immersion tests specified in paragraph (c)(6) of this section.
    (b) Test conditions. With respect to the initial conditions for the 
tests, except for the water immersion tests, to demonstrate compliance 
with the requirements of this part during testing, the ambient air 
temperature before and after the tests must remain constant at that 
value between -29[deg]C (-20[deg]F) and +38[deg]C (+100[deg]F) which is 
most unfavorable for the feature under consideration. The initial 
internal pressure within the containment system must be the maximum 
normal operating pressure, unless a lower internal pressure, consistent 
with the ambient temperature assumed to precede and follow the tests, is 
more unfavorable.
    (c) Tests. Tests for hypothetical accident conditions must be 
conducted as follows:
    (1) Free Drop. A free drop of the specimen through a distance of 9 m 
(30 ft) onto a flat, essentially unyielding, horizontal surface, 
striking the surface in a position for which maximum damage is expected.
    (2) Crush. Subjection of the specimen to a dynamic crush test by 
positioning the specimen on a flat, essentially unyielding horizontal 
surface so as to suffer maximum damage by the drop of a 500-kg (1100-lb) 
mass from 9 m (30 ft) onto the specimen. The mass must consist of a 
solid mild steel plate 1 m (40 in) by 1 m (40 in) and must fall in a 
horizontal attitude. The crush test is required only when the specimen 
has a mass not greater than 500 kg (1100 lb), an overall density not 
greater than 1000 kg/m \3\ (62.4 lb/ft \3\) based on external dimension, 
and radioactive contents greater than 1000 A<INF>2</INF> not as special 
form radioactive material. For packages containing fissile material, the 
radioactive contents greater than 1000 A<INF>2</INF> criterion does not 
apply.
    (3) Puncture. A free drop of the specimen through a distance of 1 m 
(40 in) in a position for which maximum damage is expected, onto the 
upper end of a solid, vertical, cylindrical, mild steel bar mounted on 
an essentially unyielding, horizontal surface. The bar must be 15 cm (6 
in) in diameter, with the top horizontal and its edge rounded to a 
radius of not more than 6 mm (0.25 in), and of a length as to cause 
maximum damage to the package, but not less than 20 cm (8 in) long. The 
long axis of the bar must be vertical.
    (4) Thermal. Exposure of the specimen fully engulfed, except for a 
simple support system, in a hydrocarbon fuel/air fire of sufficient 
extent, and in sufficiently quiescent ambient conditions, to provide an 
average emissivity coefficient of at least 0.9, with an average flame 
temperature of at least 800[deg]C (1475[deg]F) for a period of 30 
minutes, or any other thermal test that provides the equivalent total 
heat input to the package and which provides a time averaged 
environmental temperature of 800[deg]C. The fuel source must extend 
horizontally at least 1 m (40 in), but may not extend more than 3 m (10 
ft), beyond any external surface of the specimen, and the specimen must 
be positioned 1 m (40 in) above the surface of the fuel source. For 
purposes of calculation, the surface absorptivity coefficient must be 
either that value which the package may be expected to possess if 
exposed to the fire specified or 0.8, whichever is greater; and the 
convective coefficient must be that value which may be demonstrated to 
exist if the package were exposed to the fire specified. Artificial 
cooling may not be applied after cessation of external heat input, and 
any combustion of materials of construction, must be allowed to proceed 
until it terminates naturally.
    (5) Immersion--fissile material. For fissile material subject to 
Sec.  71.55, in those cases where water inleakage has not been assumed 
for criticality analysis, immersion under a head of water of at least 
0.9 m (3 ft) in the attitude for which maximum leakage is expected.
    (6) Immersion--all packages. A separate, undamaged specimen must be 
subjected to water pressure equivalent to immersion under a head of 
water of

[[Page 349]]

at least 15 m (50 ft). For test purposes, an external pressure of water 
of 150 kPa (21.7 lbf/in\2\) gauge is considered to meet these 
conditions.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3795, Jan. 26, 2004]

Sec.  71.74  Accident conditions for air transport of plutonium.

    (a) Test conditions--Sequence of tests. A package must be physically 
tested to the following conditions in the order indicated to determine 
their cumulative effect.
    (1) Impact at a velocity of not less than 129 m/sec (422 ft/sec) at 
a right angle onto a flat, essentially unyielding, horizontal surface, 
in the orientation (e.g., side, end, corner) expected to result in 
maximum damage at the conclusion of the test sequence.
    (2) A static compressive load of 31,800 kg (70,000 lbs) applied in 
the orientation expected to result in maximum damage at the conclusion 
of the test sequence. The force on the package must be developed between 
a flat steel surface and a 5 cm (2 in) wide, straight, solid, steel bar. 
The length of the bar must be at least as long as the diameter of the 
package, and the longitudinal axis of the bar must be parallel to the 
plane of the flat surface. The load must be applied to the bar in a 
manner that prevents any members or devices used to support the bar from 
contacting the package.
    (3) Packages weighing less than 227 kg (500 lbs) must be placed on a 
flat, essentially unyielding, horizontal surface, and subjected to a 
weight of 227 kg (500 lbs) falling from a height of 3 m (10 ft) and 
striking in the position expected to result in maximum damage at the 
conclusion of the test sequence. The end of the weight contacting the 
package must be a solid probe made of mild steel. The probe must be the 
shape of the frustum of a right circular cone, 30 cm (12 in) long, 20 cm 
(8 in) in diameter at the base, and 2.5 cm (1 in) in diameter at the 
end. The longitudinal axis of the probe must be perpendicular to the 
horizontal surface. For packages weighing 227 kg (500 lbs) or more, the 
base of the probe must be placed on a flat, essentially unyielding 
horizontal surface, and the package dropped from a height of 3 m (10 ft) 
onto the probe, striking in the position expected to result in maximum 
damage at the conclusion of the test sequence.
    (4) The package must be firmly restrained and supported such that 
its longitudinal axis is inclined approximately 45[deg] to the 
horizontal. The area of the package that made first contact with the 
impact surface in paragraph (a)(1) of this section must be in the 
lowermost position. The package must be struck at approximately the 
center of its vertical projection by the end of a structural steel angle 
section falling from a height of at least 46 m (150 ft). The angle 
section must be at least 1.8 m (6 ft) in length with equal legs at least 
13 cm (5 in) long and 1.3 cm (0.5 in) thick. The angle section must be 
guided in such a way as to fall end-on, without tumbling. The package 
must be rotated approximately 90[deg] about its longitudinal axis and 
struck by the steel angle section falling as before.
    (5) The package must be exposed to luminous flames from a pool fire 
of JP-4 or JP-5 aviation fuel for a period of at least 60 minutes. The 
luminous flames must extend an average of at least 0.9 m (3 ft) and no 
more than 3 m (10 ft) beyond the package in all horizontal directions. 
The position and orientation of the package in relation to the fuel must 
be that which is expected to result in maximum damage at the conclusion 
of the test sequence. An alternate method of thermal testing may be 
substituted for this fire test, provided that the alternate test is not 
of shorter duration and would not result in a lower heating rate to the 
package. At the conclusion of the thermal test, the package must be 
allowed to cool naturally or must be cooled by water sprinkling, 
whichever is expected to result in maximum damage at the conclusion of 
the test sequence.
    (6) Immersion under at least 0.9 m (3 ft) of water.
    (b) Individual free-fall impact test. (1) An undamaged package must 
be physically subjected to an impact at a velocity not less than the 
calculated terminal free-fall velocity, at mean sea level, at a right 
angle onto a flat, essentially unyielding, horizontal surface, in the 
orientation (e.g., side, end, corner) expected to result in maximum 
damage.

[[Page 350]]

    (2) This test is not required if the calculated terminal free-fall 
velocity of the package is less than 129 m/sec (422 ft/sec), or if a 
velocity not less than either 129 m/sec (422 ft/sec) or the calculated 
terminal free-fall velocity of the package is used in the sequential 
test of paragraph (a)(1) of this section.
    (c) Individual deep submersion test. An undamaged package must be 
physically submerged and physically subjected to an external water 
pressure of at least 4 MPa (600 lbs/in \2\).

Sec.  71.75  Qualification of special form radioactive material.

    (a) Special form radioactive materials must meet the test 
requirements of paragraph (b) of this section. Each solid radioactive 
material or capsule specimen to be tested must be manufactured or 
fabricated so that it is representative of the actual solid material or 
capsule that will be transported, with the proposed radioactive content 
duplicated as closely as practicable. Any differences between the 
material to be transported and the test material, such as the use of 
non-radioactive contents, must be taken into account in determining 
whether the test requirements have been met. In addition:
    (1) A different specimen may be used for each of the tests;
    (2) The specimen may not break or shatter when subjected to the 
impact, percussion, or bending tests;
    (3) The specimen may not melt or disperse when subjected to the heat 
test;
    (4) After each test, leaktightness or indispersibility of the 
specimen must be determined by a method no less sensitive than the 
leaching assessment procedure prescribed in paragraph (c) of this 
section. For a capsule resistant to corrosion by water, and which has an 
internal void volume greater than 0.1 milliliter, an alternative to the 
leaching assessment is a demonstration of leaktightness of 
x10<SUP>-4</SUP> torr-liter/s (1.3xx10<SUP>-4</SUP> atm-cm\3\/s) based 
on air at 25[deg]C (77[deg]F) and one atmosphere differential pressure 
for solid radioactive content, or x10<SUP>-6</SUP> torr-liter/s 
(1.3xx10<SUP>-6</SUP> atm-cm\3\/s) for liquid or gaseous radioactive 
content; and
    (5) A specimen that comprises or simulates radioactive material 
contained in a sealed capsule need not be subjected to the leaktightness 
procedure specified in this section, provided it is alternatively 
subjected to any of the tests prescribed in ISO/TR4826-1979(E), ``Sealed 
radioactive sources leak test methods'' which is available from the 
American National Standards Institute, 1430 Broadway, New York, N.Y. 
10018.
    (b) Test methods--(1) Impact Test. The specimen must fall onto the 
target from a height of 9 m (30 ft) or greater in the orientation 
expected to result in maximum damage. The target must be a flat, 
horizontal surface of such mass and rigidity that any increase in its 
resistance to displacement or deformation, on impact by the specimen, 
would not significantly increase the damage to the specimen.
    (2) Percussion Test. (i) The specimen must be placed on a sheet of 
lead that is supported by a smooth solid surface, and struck by the flat 
face of a steel billet so as to produce an impact equivalent to that 
resulting from a free drop of 1.4 kg (3 lbs) through 1 m (40 in);
    (ii) The flat face of the billet must be 25 millimeters (mm) (1 
inch) in diameter with the edges rounded off to a radius of 3 mm <plus-
minus<ls-thn-eq> 0.3 mm(.12 in <plus-minus<ls-thn-eq> 0.012 in);
    (iii) The lead must be hardness number 3.5 to 4.5 on the Vickers 
scale and thickness 25 mm (1 in) or greater, and must cover an area 
greater than that covered by the specimen;
    (iv) A fresh surface of lead must be used for each impact; and
    (v) The billet must strike the specimen so as to cause maximum 
damage.
    (3) Bending test. (i) This test applies only to long, slender 
sources with a length of 10 cm (4 inches) or greater and a length to 
width ratio of 10 or greater;
    (ii) The specimen must be rigidly clamped in a horizontal position 
so that one half of its length protrudes from the face of the clamp;
    (iii) The orientation of the specimen must be such that the specimen 
will suffer maximum damage when its free end is struck by the flat face 
of a steel billet;
    (iv) The billet must strike the specimen so as to produce an impact 
equivalent to that resulting from a free

[[Page 351]]

vertical drop of 1.4 kg (3 lbs) through 1 m (40 in); and
    (v) The flat face of the billet must be 25 mm (1 inch) in diameter 
with the edges rounded off to a radius of 3 mm <plus-minus<ls-thn-eq> 
0.3 mm (.12 in <plus-minus<ls-thn-eq> 0.012 in).
    (4) Heat test. The specimen must be heated in air to a temperature 
of not less than 800[deg]C (1475[deg]F), held at that temperature for a 
period of 10 minutes, and then allowed to cool.
    (c) Leaching assessment methods. (1) For indispersible solid 
material--
    (i) The specimen must be immersed for 7 days in water at ambient 
temperature. The water must have a pH of 6-8 and a maximum conductivity 
of 10 micromho per centimeter at 20[deg] (68[deg]F);
    (ii) The water with specimen must then be heated to a temperature of 
50[deg]C <plus-minus<ls-thn-eq> 5[deg]C (122[deg]F <plus-
minus<ls-thn-eq> 9[deg]F) and maintained at this temperature for 4 
hours.
    (iii) The activity of the water must then be determined;
    (iv) The specimen must then be stored for at least 7 days in still 
air of relative humidity not less than 90 percent at 30[deg]C 
(86[deg]F);
    (v) The specimen must then be immersed in water under the same 
conditions as in paragraph (c)(1)(i) of this section, and the water with 
specimen must be heated to 50[deg]C <plus-minus<ls-thn-eq> 5[deg]C 
(122[deg]F <plus-minus<ls-thn-eq> 9[deg]F) and maintained at that 
temperature for 4 hours;
    (vi) The activity of the water must then be determined. The sum of 
the activities determined here and in paragraph (c)(1)(iii) of this 
section must not exceed 2 kilobecquerels (kBq) (0.05 microcurie 
([micro]Ci)).
    (2) For encapsulated material--
    (i) The specimen must be immersed in water at ambient temperature. 
The water must have a pH of 6-8 and a maximum conductivity of 10 
micromho per centimeter;
    (ii) The water and specimen must be heated to a temperature of 
50[deg]C <plus-minus<ls-thn-eq> 5[deg]C (122[deg]F <plus-
minus<ls-thn-eq> 9[deg]F) and maintained at this temperature for 4 
hours;
    (iii) The activity of the water must then be determined;
    (iv) The specimen must then be stored for at least 7 days in still 
air at a temperature of 30[deg]C (86[deg]F) or greater;
    (v) The process in paragraph (c)(2)(i), (ii), and (iii) of this 
section must be repeated; and
    (vi) The activity of the water must then be determined. The sum of 
the activities determined here and in paragraph (c)(2)(iii) of this 
section must not exceed 2 kilobecquerels (kBq) (0.05 microcurie 
([micro]Ci)).
    (d) A specimen that comprises or simulates radioactive material 
contained in a sealed capsule need not be subjected to--
    (1) The impact test and the percussion test of this section, 
provided that the specimen is alternatively subjected to the Class 4 
impact test prescribed in ISO 2919-1980(e), ``Sealed Radioactive Sources 
Classification'' (see Sec.  71.75(a)(5) for statement of availability); 
and
    (2) The heat test of this section, provided the specimen is 
alternatively subjected to the Class 6 temperature test specified in the 
International Organization for Standardization document ISO 2919-
1980(e), ``Sealed Radioactive Sources Classification.''

Sec.  71.77  Qualification of LSA-III Material.

    (a) LSA-III material must meet the test requirements of paragraph 
(b) of this section. Any differences between the specimen to be tested 
and the material to be transported must be taken into account in 
determining whether the test requirements have been met.
    (b) Leaching Test. (1) The specimen, representing no less than the 
entire contents of the package, must be immersed for 7 days in water at 
ambient temperature;
    (2) The volume of water to be used in the test must be sufficient to 
ensure that at the end of the test period the free volume of the 
unabsorbed and unreacted water remaining will be at least 10% of the 
volume of the specimen itself;
    (3) The water must have an initial pH of 6-8 and a maximum 
conductivity 10 micromho/cm at 20[deg]C (68[deg]F); and
    (4) The total activity of the free volume of water must be measured 
following the 7 day immersion test and must not exceed 0.1 
A<INF>2</INF>.

[[Page 352]]

               Subpart G_Operating Controls and Procedures

Sec.  71.81  Applicability of operating controls and procedures.

    A licensee subject to this part, who, under a general or specific 
license, transports licensed material or delivers licensed material to a 
carrier for transport, shall comply with the requirements of this 
subpart G, with the quality assurance requirements of subpart H of this 
part, and with the general provisions of subpart A of this part.

Sec.  71.83  Assumptions as to unknown properties.

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

Sec.  71.85  Preliminary determinations.

    Before the first use of any packaging for the shipment of licensed 
material--
    (a) The licensee shall ascertain that there are no cracks, pinholes, 
uncontrolled voids, or other defects that could significantly reduce the 
effectiveness of the packaging;
    (b) Where the maximum normal operating pressure will exceed 35 kPa 
(5 lbf/in\2\) gauge, the licensee shall test the containment system at 
an internal pressure at least 50 percent higher than the maximum normal 
operating pressure, to verify the capability of that system to maintain 
its structural integrity at that pressure; and
    (c) The licensee shall conspicuously and durably mark the packaging 
with its model number, serial number, gross weight, and a package 
identification number assigned by NRC. Before applying the model number, 
the licensee shall determine that the packaging has been fabricated in 
accordance with the design approved by the Commission.

Sec.  71.87  Routine determinations.

    Before each shipment of licensed material, the licensee shall ensure 
that the package with its contents satisfies the applicable requirements 
of this part and of the license. 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 that could be used to lift or 
tie down the package during transport is rendered inoperable for that 
purpose, unless it satisfies the design requirements of Sec.  71.45;
    (i) The level of non-fixed (removable) radioactive contamination on 
the external surfaces of each package offered for shipment is as low as 
reasonably achievable, and within the limits specified in DOT 
regulations in 49 CFR 173.443;
    (j) External radiation levels around the package and around the 
vehicle, if applicable, will not exceed the limits specified in Sec.  
71.47 at any time during transportation; and
    (k) Accessible package surface temperatures will not exceed the 
limits specified in Sec.  71.43(g) at any time during transportation.

Sec.  71.88  Air transport of plutonium.

    (a) Notwithstanding the provisions of any general licenses and 
notwithstanding any exemptions stated directly in this part or included 
indirectly by citation of 49 CFR chapter I, as may be applicable, the 
licensee shall assure that plutonium in any form, whether for import, 
export, or domestic shipment, is not transported by air or delivered to 
a carrier for air transport unless:

[[Page 353]]

    (1) The plutonium is contained in a medical device designed for 
individual human application; or
    (2) The plutonium is contained in a material in which the specific 
activity is less than or equal to the activity concentration values for 
plutonium specified in Appendix A, Table A-2, of this part, and in which 
the radioactivity is essentially uniformly distributed; or
    (3) The plutonium is shipped in a single package containing no more 
than an A<INF>2</INF> quantity of plutonium in any isotope or form, and 
is shipped in accordance with Sec.  71.5; or
    (4) The plutonium is shipped in a package specifically authorized 
for the shipment of plutonium by air in the Certificate of Compliance 
for that package issued by the Commission.
    (b) Nothing in paragraph (a) of this section is to be interpreted as 
removing or diminishing the requirements of Sec.  73.24 of this chapter.
    (c) For a shipment of plutonium by air which is subject to paragraph 
(a)(4) of this section, the licensee shall, through special arrangement 
with the carrier, require compliance with 49 CFR 175.704, U.S. 
Department of Transportation regulations applicable to the air transport 
of plutonium.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3795, Jan. 26, 2004]

Sec.  71.89  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 10 CFR 20.1906(e).

Sec.  71.91  Records.

    (a) Each licensee shall maintain, for a period of 3 years after 
shipment, a record of each shipment of licensed material not exempt 
under Sec.  71.10, showing where applicable--
    (1) Identification of the packaging by model number and serial 
number;
    (2) Verification that there are no significant defects in the 
packaging, as shipped;
    (3) Volume and identification of coolant;
    (4) Type and quantity of licensed material in each package, and the 
total quantity of each shipment;
    (5) For each item of irradiated fissile material--
    (i) Identification by model number and serial number;
    (ii) Irradiation and decay history to the extent appropriate to 
demonstrate that its nuclear and thermal characteristics comply with 
license conditions; and
    (iii) Any abnormal or unusual condition relevant to radiation 
safety;
    (6) Date of the shipment;
    (7) For fissile packages and for Type B packages, any special 
controls exercised;
    (8) Name and address of the transferee;
    (9) Address to which the shipment was made; and
    (10) Results of the determinations required by Sec.  71.87 and by 
the conditions of the package approval.
    (b) Each certificate holder shall maintain, for a period of 3 years 
after the life of the packaging to which they apply, records identifying 
the packaging by model number, serial number, and date of manufacture.
    (c) The licensee, certificate holder, and an applicant for a CoC, 
shall make available to the Commission 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.
    (d) The licensee, certificate holder, and an applicant for a CoC 
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 Sec.  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

[[Page 354]]

years after the life of the packaging to which they apply.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3795, Jan. 26, 2004]

Sec.  71.93  Inspection and tests.

    (a) The licensee, certificate holder, and applicant for a CoC shall 
permit the Commission, at all reasonable times, to inspect the licensed 
material, packaging, premises, and facilities in which the licensed 
material or packaging is used, provided, constructed, fabricated, 
tested, stored, or shipped.
    (b) The licensee, certificate holder, and applicant for a CoC shall 
perform, and permit the Commission to perform, any tests the Commission 
deems necessary or appropriate for the administration of the regulations 
in this chapter.
    (c) The certificate holder and applicant for a CoC shall notify the 
NRC, in accordance with Sec.  71.1, 45 days in advance of starting 
fabrication of the first packaging under a CoC. This paragraph applies 
to any packaging used for the shipment of licensed material which has 
either--
    (1) A decay heat load in excess of 5 kW; or
    (2) A maximum normal operating pressure in excess of 103 kPa (15 
lbf/in \2\) gauge.

[69 FR 3796, Jan. 26, 2004]

Sec.  71.95  Reports.

    (a) The licensee, after requesting the certificate holder's input, 
shall submit a written report to the Commission of--
    (1) Instances in which there is a significant reduction in the 
effectiveness of any NRC-approved Type B or Type AF packaging during 
use; or
    (2) Details of any defects with safety significance in any NRC-
approved Type B or fissile material packaging, after first use.
    (3) Instances in which the conditions of approval in the Certificate 
of Compliance were not observed in making a shipment.
    (b) The licensee shall submit a written report to the Commission of 
instances in which the conditions in the certificate of compliance were 
not followed during a shipment.
    (c) Each licensee shall submit, in accordance with Sec.  71.1, a 
written report required by paragraph (a) or (b) of this section within 
60 days of the event or discovery of the event. The licensee shall also 
provide a copy of each report submitted to the NRC to the applicable 
certificate holder. Written reports prepared under other regulations may 
be submitted to fulfill this requirement if the reports contain all the 
necessary information, and the appropriate distribution is made. Using 
an appropriate method listed in Sec.  71.1(a), the licensee shall report 
to: ATTN: Document Control Desk, Director, Spent Fuel Project Office, 
Office of Nuclear Material Safety and Safeguards. These written reports 
must include the following:
    (1) A brief abstract describing the major occurrences during the 
event, including all component or system failures that contributed to 
the event and significant corrective action taken or planned to prevent 
recurrence.
    (2) A clear, specific, narrative description of the event that 
occurred so that knowledgeable readers conversant with the requirements 
of part 71, but not familiar with the design of the packaging, can 
understand the complete event. The narrative description must include 
the following specific information as appropriate for the particular 
event.
    (i) Status of components or systems that were inoperable at the 
start of the event and that contributed to the event;
    (ii) Dates and approximate times of occurrences;
    (iii) The cause of each component or system failure or personnel 
error, if known;
    (iv) The failure mode, mechanism, and effect of each failed 
component, if known;
    (v) A list of systems or secondary functions that were also affected 
for failures of components with multiple functions;
    (vi) The method of discovery of each component or system failure or 
procedural error;
    (vii) For each human performance-related root cause, a discussion of 
the cause(s) and circumstances;
    (viii) The manufacturer and model number (or other identification) 
of

[[Page 355]]

each component that failed during the event; and
    (ix) For events occurring during use of a packaging, the quantities 
and chemical and physical form(s) of the package contents.
    (3) An assessment of the safety consequences and implications of the 
event. This assessment must include the availability of other systems or 
components that could have performed the same function as the components 
and systems that failed during the event.
    (4) A description of any corrective actions planned as a result of 
the event, including the means employed to repair any defects, and 
actions taken to reduce the probability of similar events occurring in 
the future.
    (5) Reference to any previous similar events involving the same 
packaging that are known to the licensee or certificate holder.
    (6) The name and telephone number of a person within the licensee's 
organization who is knowledgeable about the event and can provide 
additional information.
    (7) The extent of exposure of individuals to radiation or to 
radioactive materials without identification of individuals by name.
    (d) Report legibility. The reports submitted by licensees and/or 
certificate holders under this section must be of sufficient quality to 
permit reproduction and micrographic processing.

[69 FR 3796, Jan. 26, 2004]

Sec.  71.97  Advance notification of shipment of irradiated reactor fuel 
          and 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 designee, of the shipment of licensed material, 
through, or across the boundary of the State, before the transport, or 
delivery to a carrier, for transport, of licensed material outside the 
confines of the licensee's plant or other place of use or storage.
    (b) Advance notification is required under this section for 
shipments of irradiated reactor fuel in quantities less than that 
subject to advance notification requirements of Sec.  73.37(f) of this 
chapter. Advance notification is also required under this section for 
shipment of licensed material, other than irradiated fuel, meeting the 
following three conditions:
    (1) The licensed material is required by this part to be in Type B 
packaging for transportation;
    (2) The licensed material is being transported to or across a State 
boundary 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 A<INF>1</INF> value of the radionuclides as 
specified in appendix A, Table A-1 for special form radioactive 
material;
    (ii) 3000 times the A<INF>2</INF> value of the radionuclides as 
specified in appendix A, Table A-1 for normal form radioactive material; 
or
    (iii) 1000 TBq (27,000 Ci).
    (c) Procedures for submitting advance notification. (1) The 
notification must be made in writing to the office of each appropriate 
governor or governor's designee and to the Director, Division of Nuclear 
Security, Office of Nuclear Security and Incident Response.
    (2) A notification delivered by mail must be postmarked at least 7 
days before the beginning of the 7-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 at least 4 days 
before the beginning of the 7-day period during which departure of the 
shipment is estimated to occur.
    (i) A list of the names and mailing addresses of the governors' 
designees receiving advance notification of transportation of nuclear 
waste was published in the Federal Register on June 30, 1995 (60 FR 
34306).
    (ii) The list will be published annually in the Federal Register on 
or about June 30 to reflect any changes in information.
    (iii) A list of the names and mailing addresses of the governors' 
designees is available on request from the Director, Office of State 
Programs, U.S. Nuclear

[[Page 356]]

Regulatory Commission, Washington, DC 20555-0001.
    (4) The licensee shall retain a copy of the notification as a record 
for 3 years.
    (d) Information to be furnished in advance notification of shipment. 
Each advance notification of shipment of irradiated reactor fuel or 
nuclear waste must contain the following information:
    (1) The name, address, and telephone number of the shipper, carrier, 
and receiver of the irradiated reactor fuel or nuclear waste shipment;
    (2) A description of the irradiated reactor fuel or nuclear waste 
contained in the shipment, as specified in the regulations of DOT in 49 
CFR 172.202 and 172.203(d);
    (3) The point of origin of the shipment and the 7-day period during 
which departure of the shipment is estimated to occur;
    (4) The 7-day period during which arrival of the shipment at State 
boundaries is estimated to occur;
    (5) The destination of the shipment, and the 7-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.
    (e) Revision notice. A licensee who finds that schedule information 
previously furnished to a governor or governor'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 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 3 years.
    (f) Cancellation notice. (1) Each licensee who cancels an irradiated 
reactor fuel or 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, and to the 
Director, Division of Nuclear Security, Office of Nuclear Security and 
Incident Response.
    (2) The licensee shall state in the notice that it is a cancellation 
and identify the advance notification that is being canceled. The 
licensee shall retain a copy of the notice as a record for 3 years.

[60 FR 50264, Sept. 28, 1995, as amended at 67 FR 3586, Jan. 25, 2002; 
68 FR 14529, Mar. 26, 2003; 68 FR 23575, May 5, 2003; 68 FR 58818, Oct. 
10, 2003]

Sec.  71.99  Violations.

    (a) The Commission may obtain an injunction or other court order to 
prevent a violation of the provisions of--
    (1) The Atomic Energy Act of 1954, as amended;
    (2) Title II of the Energy Reorganization Act of 1974, as amended; 
or (3) A regulation or order issued pursuant to those Acts.
    (b) The Commission may obtain a court order for the payment of a 
civil penalty imposed under section 234 of the Atomic Energy Act:
    (1) For violations of--
    (i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107, or 109 of 
the Atomic Energy Act of 1954, as amended;
    (ii) Section 206 of the Energy Reorganization Act;
    (iii) Any rule, regulation, or order issued pursuant to the sections 
specified in paragraph (b)(1)(i) of this section; or
    (iv) Any term , condition, or limitation of any license issued under 
the sections specified in paragraph (b)(1)(i) of this section.
    (2) For any violation for which a license may be revoked under 
section 186 of the Atomic Energy Act of 1954, as amended.

Sec.  71.100  Criminal penalties.

    (a) Section 223 of the Atomic Energy Act of 1954, as amended, 
provides for criminal sanctions for willful violation of, attempted 
violation of, or conspiracy to violate, any regulation issued under 
sections 161b, 161i, or 161o of the Act. For purposes of section 223, 
all the regulations in part 71 are issued under one or more of sections 
161b, 161i, or 161o, except for the sections listed in paragraph (b) of 
this section.
    (b) The regulations in part 71 that are not issued under sections 
161b, 161i, or 161o for the purposes of section 223 are as follows: 
Sec. Sec.  71.0, 71.2, 71.4, 71.6, 71.7, 71.10, 71.31, 71.33, 71.35, 
71.37, 71.38, 71.39, 71.40, 71.41, 71.43, 71.45, 71.47, 71.51,

[[Page 357]]

71.55, 71.59, 71.65, 71.71, 71.73, 71.74, 71.75, 71.77, 71.99, and 
71.100.

[60 FR 50264, Sept. 28, 1995, as amended at 69 FR 3796, Jan. 26, 2004]

                       Subpart H_Quality Assurance

    Source: 69 FR 3796, Jan. 26, 2004, unless otherwise noted.

Sec.  71.101  Quality assurance requirements.

    (a) Purpose. This subpart 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 subpart, ``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. The licensee, certificate holder, and 
applicant for a CoC are responsible for the quality assurance 
requirements as they apply to design, fabrication, testing, and 
modification of packaging. Each licensee is responsible for the quality 
assurance provision which applies to its use of a packaging for the 
shipment of licensed material subject to this subpart.
    (b) Establishment of program. Each licensee, certificate holder, and 
applicant for a CoC shall establish, maintain, and execute a quality 
assurance program satisfying each of the applicable criteria of 
Sec. Sec.  71.101 through 71.137 and satisfying any specific provisions 
that are applicable to the licensee's activities including procurement 
of packaging. The licensee, certificate holder, and applicant for a CoC 
shall execute the applicable criteria in a graded approach to an extent 
that is commensurate with the quality assurance requirement's importance 
to safety.
    (c) Approval of program. (1) Before the use of any package for the 
shipment of licensed material subject to this subpart, each licensee 
shall obtain Commission approval of its quality assurance program. Using 
an appropriate method listed in Sec.  71.1(a), 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: ATTN: Document Control 
Desk, Director, Spent Fuel Project Office, Office of Nuclear Material 
Safety and Safeguards.
    (2) Before the fabrication, testing, or modification of any package 
for the shipment of licensed material subject to this subpart, each 
licensee, certificate holder, or applicant for a CoC shall obtain 
Commission approval of its quality assurance program. Each certificate 
holder or applicant for a CoC shall, in accordance with Sec.  71.1, 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.
    (d) Existing package designs. The provisions of this paragraph deal 
with packages that have been approved for use in accordance with this 
part before January 1, 1979, and which have been designed in accordance 
with the provisions of this part in effect at the time of application 
for package approval. Those packages will be accepted as having been 
designed in accordance with a quality assurance program that satisfies 
the provisions of paragraph (b) of this section.
    (e) Existing packages. The provisions of this paragraph deal with 
packages that have been approved for use in accordance with this part 
before January 1, 1979, have been at least partially fabricated before 
that date, and for which the fabrication is in accordance with the 
provisions of this part in effect at the time of application for 
approval of package design. These packages will be accepted as having 
been fabricated and assembled in accordance with a quality assurance 
program that satisfies the provisions of paragraph (b) of this section.
    (f) Previously approved programs. A Commission-approved quality 
assurance program that satisfies the applicable criteria of subpart H of 
this part,

[[Page 358]]

Appendix B of part 50 of this chapter, or subpart G of part 72 of this 
chapter, and that is established, maintained, and executed regarding 
transport packages, will be accepted as satisfying the requirements of 
paragraph (b) of this section. Before first use, the licensee, 
certificate holder, and applicant for a CoC shall notify the NRC, in 
accordance with Sec.  71.1, of its intent to apply its previously 
approved subpart H, Appendix B, or subpart G quality assurance program 
to transportation activities. The licensee, certificate holder, and 
applicant for a CoC shall identify the program by date of submittal to 
the Commission, Docket Number, and date of Commission approval.
    (g) 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 Sec.  34.31(b) of this chapter or equivalent Agreement 
State requirement, is deemed to satisfy the requirements of Sec. Sec.  
71.17(b) and 71.101(b).

Sec.  71.103  Quality assurance organization.

    (a) The licensee,\2\ certificate holder, and applicant for a CoC 
shall be responsible for the establishment and execution of the quality 
assurance program. The licensee, certificate holder, and applicant for a 
CoC 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\ While the term ``licensee'' is used in these criteria, the 
requirements are applicable to whatever design, fabrication, assembly, 
and testing of the package is accomplished with respect to a package 
before the time a package approval is issued.
---------------------------------------------------------------------------

    (b) The quality assurance functions are--
    (1) Assuring that an appropriate quality assurance program is 
established and effectively executed; and
    (2) Verifying, by procedures such as checking, auditing, and 
inspection, that activities affecting the functions that are important 
to safety have been correctly performed.
    (c) The persons and organizations performing quality assurance 
functions must have sufficient authority and organizational freedom to--
    (1) Identify quality problems;
    (2) Initiate, recommend, or provide solutions; and
    (3) Verify implementation of solutions.
    (d) The persons and organizations performing quality assurance 
functions shall report to a management level that assures that the 
required authority and organizational freedom, including sufficient 
independence from cost and schedule, when opposed to safety 
considerations, are provided.
    (e) Because of the many variables involved, such as the number of 
personnel, the type of activity being performed, and the location or 
locations where activities are performed, the organizational structure 
for executing the quality assurance program may take various forms, 
provided that the persons and organizations assigned the quality 
assurance functions have the required authority and organizational 
freedom.
    (f) Irrespective of the organizational structure, the individual(s) 
assigned the responsibility for assuring effective execution of any 
portion of the quality assurance program, at any location where 
activities subject to this section are being performed, must have direct 
access to the levels of management necessary to perform this function.

Sec.  71.105  Quality assurance program.

    (a) The licensee, certificate holder, and applicant for a CoC shall 
establish, at the earliest practicable time consistent with the schedule 
for accomplishing the activities, a quality assurance program that 
complies with the requirements of Sec. Sec.  71.101 through 71.137. The 
licensee, certificate holder, and applicant for a CoC 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 the packaging is

[[Page 359]]

used. The licensee, certificate holder, and applicant for a CoC shall 
identify the material and components to be covered by the quality 
assurance program, the major organizations participating in the program, 
and the designated functions of these organizations.
    (b) The licensee, certificate holder, and applicant for a CoC, 
through its quality assurance program, shall provide control over 
activities affecting the quality of the identified materials and 
components to an extent consistent with their importance to safety, and 
as necessary to assure conformance to the approved design of each 
individual package used for the shipment of radioactive material. The 
licensee, certificate holder, and applicant for a CoC shall assure that 
activities affecting quality are accomplished under suitably controlled 
conditions. Controlled conditions include the use of appropriate 
equipment; suitable environmental conditions for accomplishing the 
activity, such as adequate cleanliness; and assurance that all 
prerequisites for the given activity have been satisfied. The licensee, 
certificate holder, and applicant for a CoC shall take into account the 
need for special controls, processes, test equipment, tools, and skills 
to attain the required quality, and the need for verification of quality 
by inspection and test.
    (c) The licensee, certificate holder, and applicant for a CoC shall 
base the requirements and procedures of its quality assurance program on 
the following considerations concerning the complexity and proposed use 
of the package and its components:
    (1) The impact of malfunction or failure of the item to safety;
    (2) The design and fabrication complexity or uniqueness of the item;
    (3) The need for special controls and surveillance over processes 
and equipment;
    (4) The degree to which functional compliance can be demonstrated by 
inspection or test; and
    (5) The quality history and degree of standardization of the item.
    (d) The licensee, certificate holder, and applicant for a CoC shall 
provide for indoctrination and training of personnel performing 
activities affecting quality, as necessary to assure that suitable 
proficiency is achieved and maintained. The licensee, certificate 
holder, and applicant for a CoC shall review the status and adequacy of 
the quality assurance program at established intervals. Management of 
other organizations participating in the quality assurance program shall 
review regularly the status and adequacy of that part of the quality 
assurance program they are executing.

Sec.  71.107  Package design control.

    (a) The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that applicable regulatory requirements and 
the package design, as specified in the license or CoC for those 
materials and components to which this section applies, are correctly 
translated into specifications, drawings, procedures, and instructions. 
These measures must include provisions to assure that appropriate 
quality standards are specified and included in design documents and 
that deviations from standards are controlled. Measures must be 
established for the selection and review for suitability of application 
of materials, parts, equipment, and processes that are essential to the 
functions of the materials, parts, and components of the packaging that 
are important to safety.
    (b) The licensee, certificate holder, and applicant for a CoC shall 
establish measures for the identification and control of design 
interfaces and for coordination among participating design 
organizations. These measures must include the establishment of written 
procedures, among participating design organizations, for the review, 
approval, release, distribution, and revision of documents involving 
design interfaces. The design control measures must provide for 
verifying or checking the adequacy of design, by methods such as design 
reviews, alternate or simplified calculational methods, or by a suitable 
testing program. For the verifying or checking process, the licensee 
shall designate individuals or groups other than those who were 
responsible for the original design, but who may be from the same 
organization. Where a test program is used to verify the adequacy of a 
specific design feature in

[[Page 360]]

lieu of other verifying or checking processes, the licensee, certificate 
holder, and applicant for a CoC shall include suitable qualification 
testing of a prototype or sample unit under the most adverse design 
conditions. The licensee, certificate holder, and applicant for a CoC 
shall apply design control measures to the following:
    (1) Criticality physics, radiation shielding, stress, thermal, 
hydraulic, and accident analyses;
    (2) Compatibility of materials;
    (3) Accessibility for inservice inspection, maintenance, and repair;
    (4) Features to facilitate decontamination; and
    (5) Delineation of acceptance criteria for inspections and tests.
    (c) The licensee, certificate holder, and applicant for a CoC shall 
subject design changes, including field changes, to design control 
measures commensurate with those applied to the original design. Changes 
in the conditions specified in the CoC require prior NRC approval.

Sec.  71.109  Procurement document control.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that adequate quality is required in the 
documents for procurement of material, equipment, and services, whether 
purchased by the licensee, certificate holder, and applicant for a CoC 
or by its contractors or subcontractors. To the extent necessary, the 
licensee, certificate holder, and applicant for a CoC shall require 
contractors or subcontractors to provide a quality assurance program 
consistent with the applicable provisions of this part.

Sec.  71.111  Instructions, procedures, and drawings.

    The licensee, certificate holder, and applicant for a CoC shall 
prescribe activities affecting quality by documented instructions, 
procedures, or drawings of a type appropriate to the circumstances and 
shall require that these instructions, procedures, and drawings be 
followed. The instructions, procedures, and drawings must include 
appropriate quantitative or qualitative acceptance criteria for 
determining that important activities have been satisfactorily 
accomplished.

Sec.  71.113  Document control.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to control the issuance of documents such as 
instructions, procedures, and drawings, including changes, that 
prescribe all activities affecting quality. These measures must assure 
that documents, including changes, are reviewed for adequacy, approved 
for release by authorized personnel, and distributed and used at the 
location where the prescribed activity is performed.

Sec.  71.115  Control of purchased material, equipment, and services.

    (a) The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that purchased material, equipment, and 
services, whether purchased directly or through contractors and 
subcontractors, conform to the procurement documents. These measures 
must include provisions, as appropriate, for source evaluation and 
selection, objective evidence of quality furnished by the contractor or 
subcontractor, inspection at the contractor or subcontractor source, and 
examination of products on delivery.
    (b) The licensee, certificate holder, and applicant for a CoC shall 
have available documentary evidence that material and equipment conform 
to the procurement specifications before installation or use of the 
material and equipment. The licensee, certificate holder, and applicant 
for a CoC shall retain, or have available, this documentary evidence for 
the life of the package to which it applies. The licensee, certificate 
holder, and applicant for a CoC shall assure that the evidence is 
sufficient to identify the specific requirements met by the purchased 
material and equipment.
    (c) The licensee, certificate holder, and applicant for a CoC shall 
assess the effectiveness of the control of quality by contractors and 
subcontractors at intervals consistent with the importance, complexity, 
and quantity of the product or services.

[[Page 361]]

Sec.  71.117  Identification and control of materials, parts, and 
          components.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures for the identification and control of materials, 
parts, and components. These measures must assure that identification of 
the item is maintained by heat number, part number, or other appropriate 
means, either on the item or on records traceable to the item, as 
required throughout fabrication, installation, and use of the item. 
These identification and control measures must be designed to prevent 
the use of incorrect or defective materials, parts, and components.

Sec.  71.119  Control of special processes.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that special processes, including welding, 
heat treating, and nondestructive testing are controlled and 
accomplished by qualified personnel using qualified procedures in 
accordance with applicable codes, standards, specifications, criteria, 
and other special requirements.

Sec.  71.121  Internal inspection.

    The licensee, certificate holder, and applicant for a CoC shall 
establish and execute a program for inspection of activities affecting 
quality by or for the organization performing the activity, to verify 
conformance with the documented instructions, procedures, and drawings 
for accomplishing the activity. The inspection must be performed by 
individuals other than those who performed the activity being inspected. 
Examination, measurements, or tests of material or products processed 
must be performed for each work operation where necessary to assure 
quality. If direct inspection of processed material or products is not 
carried out, indirect control by monitoring processing methods, 
equipment, and personnel must be provided. Both inspection and process 
monitoring must be provided when quality control is inadequate without 
both. If mandatory inspection hold points, which require witnessing or 
inspecting by the licensee's designated representative and beyond which 
work should not proceed without the consent of its designated 
representative, are required, the specific hold points must be indicated 
in appropriate documents.

Sec.  71.123  Test control.

    The licensee, certificate holder, and applicant for a CoC shall 
establish a test program to assure that all testing required to 
demonstrate that the packaging components will perform satisfactorily in 
service is identified and performed in accordance with written test 
procedures that incorporate the requirements of this part and the 
requirements and acceptance limits contained in the package approval. 
The test procedures must include provisions for assuring that all 
prerequisites for the given test are met, that adequate test 
instrumentation is available and used, and that the test is performed 
under suitable environmental conditions. The licensee, certificate 
holder, and applicant for a CoC shall document and evaluate the test 
results to assure that test requirements have been satisfied.

Sec.  71.125  Control of measuring and test equipment.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that tools, gauges, instruments, and other 
measuring and testing devices used in activities affecting quality are 
properly controlled, calibrated, and adjusted at specified times to 
maintain accuracy within necessary limits.

Sec.  71.127  Handling, storage, and shipping control.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to control, in accordance with instructions, the 
handling, storage, shipping, cleaning, and preservation of materials and 
equipment to be used in packaging to prevent damage or deterioration. 
When necessary for particular products, special protective environments, 
such as inert gas atmosphere, and specific moisture content and 
temperature levels must be specified and provided.

[[Page 362]]

Sec.  71.129  Inspection, test, and operating status.

    (a) The licensee, certificate holder, and applicant for a CoC shall 
establish measures to indicate, by the use of markings such as stamps, 
tags, labels, routing cards, or other suitable means, the status of 
inspections and tests performed upon individual items of the packaging. 
These measures must provide for the identification of items that have 
satisfactorily passed required inspections and tests, where necessary to 
preclude inadvertent bypassing of the inspections and tests.
    (b) The licensee shall establish measures to identify the operating 
status of components of the packaging, such as tagging valves and 
switches, to prevent inadvertent operation.

Sec.  71.131  Nonconforming materials, parts, or components.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to control materials, parts, or components that do 
not conform to the licensee's requirements to prevent their inadvertent 
use or installation. These measures must include, as appropriate, 
procedures for identification, documentation, segregation, disposition, 
and notification to affected organizations. Nonconforming items must be 
reviewed and accepted, rejected, repaired, or reworked in accordance 
with documented procedures.

Sec.  71.133  Corrective action.

    The licensee, certificate holder, and applicant for a CoC shall 
establish measures to assure that conditions adverse to quality, such as 
deficiencies, deviations, defective material and equipment, and 
nonconformances, are promptly identified and corrected. In the case of a 
significant condition adverse to quality, the measures must assure that 
the cause of the condition is determined and corrective action taken to 
preclude repetition. The identification of the significant condition 
adverse to quality, the cause of the condition, and the corrective 
action taken must be documented and reported to appropriate levels of 
management.

Sec.  71.135  Quality assurance records.

    The licensee, certificate holder, and applicant for a CoC shall 
maintain sufficient written records to describe the activities affecting 
quality. The records must include the instructions, procedures, and 
drawings required by Sec.  71.111 to prescribe quality assurance 
activities and must include closely related specifications such as 
required qualifications of personnel, procedures, and equipment. The 
records must include the instructions or procedures which establish a 
records retention program that is consistent with applicable regulations 
and designates factors such as duration, location, and assigned 
responsibility. The licensee, certificate holder, and applicant for a 
CoC shall retain these records for 3 years beyond the date when the 
licensee, certificate holder, and applicant for a CoC last engage in the 
activity for which the quality assurance program was developed. If any 
portion of the written procedures or instructions is superseded, the 
licensee, certificate holder, and applicant for a CoC shall retain the 
superseded material for 3 years after it is superseded.

Sec.  71.137  Audits.

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

 Appendix A to Part 71--Determination of A<INF>1</INF> and A<INF>2</INF>

    I. Values of A<INF>1</INF> and A<INF>2</INF> for individual 
radionuclides, which are the bases for many activity limits elsewhere in 
these regulations, are given in Table A-1. The curie (Ci) values 
specified are obtained by converting from the Terabecquerel (TBq) value. 
The Terabecquerel values are the regulatory

[[Page 363]]

standard. The curie values are for information only and are not intended 
to be the regulatory standard. Where values of A<INF>1</INF> and 
A<INF>2</INF> are unlimited, it is for radiation control purposes only. 
For nuclear criticality safety, some materials are subject to controls 
placed on fissile material.
    II. a. For individual radionuclides whose identities are known, but 
which are not listed in Table A-1, the A<INF>1</INF> and A<INF>2</INF> 
values contained in Table A-3 may be used. Otherwise, the licensee shall 
obtain prior Commission approval of the A<INF>1</INF> and A<INF>2</INF> 
values for radionuclides not listed in Table A-1, before shipping the 
material.
    b. For individual radionuclides whose identities are known, but 
which are not listed in Table A-2, the exempt material activity 
concentration and exempt consignment activity values contained in Table 
A-3 may be used. Otherwise, the licensee shall obtain prior Commission 
approval of the exempt material activity concentration and exempt 
consignment activity values for radionuclides not listed in Table A-2, 
before shipping the material.
    c. The licensee shall submit requests for prior approval, described 
under paragraphs II.a. and II.b. of this Appendix, to the Commission, in 
accordance with Sec.  71.1 of this part.
    III. In the calculations of A<INF>1</INF> and A<INF>2</INF> for a 
radionuclide not in Table A-1, a single radioactive decay chain, in 
which radionuclides are present in their naturally occurring 
proportions, and in which no daughter radionuclide has a half-life 
either longer than 10 days, or longer than that of the parent 
radionuclide, shall be considered as a single radionuclide, and the 
activity to be taken into account, and the A<INF>1</INF> and 
A<INF>2</INF> value to be applied, shall be those corresponding to the 
parent radionuclide of that chain. In the case of radioactive decay 
chains in which any daughter radionuclide has a half-life either longer 
than 10 days, or greater than that of the parent radionuclide, the 
parent and those daughter radionuclides shall be considered as mixtures 
of different radionuclides.
    IV. For mixtures of radionuclides whose identities and respective 
activities are known, the following conditions apply:
    a. For special form radioactive material, the maximum quantity 
transported in a Type A package is as follows:
[GRAPHIC] [TIFF OMITTED] TR26JA04.014

where B(i) is the activity of radionuclide I, and A<INF>1</INF>(i) is 
the A<INF>1</INF> value for radionuclide I.
    b. For normal form radioactive material, the maximum quantity 
transported in a Type A package is as follows:

[Sigma]B(i)/A<INF>2</INF> (i) <= 1

where B(i) is the activity of radionuclide i, and A<INF>2</INF>(i) is 
the A<INF>2</INF> value for radionuclide i.
    c. Alternatively, the A<INF>1</INF> value for mixtures of special 
form material may be determined as follows:
[GRAPHIC] [TIFF OMITTED] TR26JA04.016

where f(i) is the fraction of activity for radionuclide I in the 
mixture, and A<INF>1</INF>(i) is the appropriate A<INF>1</INF> value for 
radionuclide I.
    d. Alternatively, the A<INF>2</INF> value for mixtures of normal 
form material may be determined as follows:
[GRAPHIC] [TIFF OMITTED] TR26JA04.017

where f(i) is the fraction of activity for radionuclide I in the 
mixture, and A<INF>2</INF>(i) is the appropriate A<INF>2</INF> value for 
radionuclide I.
    e. The exempt activity concentration for mixtures of nuclides may be 
determined as follows:
[GRAPHIC] [TIFF OMITTED] TR26JA04.018

where f(i) is the fraction of activity concentration of radionuclide I 
in the mixture, and [A] 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:

[[Page 364]]

[GRAPHIC] [TIFF OMITTED] TR26JA04.019

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.
    V. 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<INF>1</INF> or 
A<INF>2</INF> value, as appropriate, for the radionuclides in each group 
may be used in applying the formulas in paragraph IV. Groups may be 
based on the total alpha activity and the total beta/gamma activity when 
these are known, using the lowest A<INF>1</INF> or A<INF>2</INF> values 
for the alpha emitters and beta/gamma emitters.

[[Page 365]]



                                                                          Table A-1--A1 and A2 Values For Radionuclides
------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------
                                                                                                                                                                  Specific activity
     Symbol of  radionuclide        Element and atomic          A1 (TBq)               A1 (Ci)b               A2 (TBq)               A2 (Ci)b       --------------------------------------------
                                          number                                                                                                            (TBq/g)                (Ci/g)
------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------
Ac-225 (a).......................  Actinium (89).......  8.0x10-1               2.2x10\1\              6.0x10-3               1.6x10-1               2.1x10\3\              5.8x10\4\
Ac-227 (a).......................  ....................  9.0x10-1               2.4x10\1\              9.0x10-5               2.4x10-3               2.7                    7.2x10\1\
Ac-228...........................  ....................  6.0x10-1               1.6x10\1\              5.0x10-1               1.4x10\1\              8.4x10\4\              2.2x10\6\
Ag-105...........................  Silver (47).........  2.0                    5.4x10\1\              2.0                    5.4x10\1\              1.1x10\3\              3.0x10\4\
Ag-108m (a)......................  ....................  7.0x10-1               1.9x10\1\              7.0x10-1               1.9x10\1\              9.7x10-1               2.6x10\1\
Ag-110m (a)......................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              1.8x10\2\              4.7x10\3\
Ag-111...........................  ....................  2.0                    5.4x10\1\              6.0x10-1               1.6x10\1\              5.8x10\3\              1.6x10\5\
Al-26............................  Aluminum (13).......  1.0x10-1               2.7                    1.0x10-1               2.7                    7.0x10-4               1.9x10-2
Am-241...........................  Americium (95)......  1.0x10\1\              2.7x10\2\              1.0x10-3               2.7x10-2               1.3x10-1               3.4
Am-242m (a)......................  ....................  1.0x10\1\              2.7x10\2\              1.0x10-3               2.7x10-2               3.6x10-1               1.0x10\1\
Am-243 (a).......................  ....................  5.0                    1.4x10\2\              1.0x10-3               2.7x10-2               7.4x10-3               2.0x10-1
Ar-37............................  Argon (18)..........  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              3.7x10\3\              9.9x10\4\
Ar-39............................  ....................  4.0x10\1\              1.1x10\3\              2.0x10\1\              5.4x10\2\              1.3                    3.4x10\1\
Ar-41............................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    1.5x10\6\              4.2x10\7\
As-72............................  Arsenic (33)........  3.0x10-1               8.1                    3.0x10-1               8.1                    6.2x10\4\              1.7x10\6\
As-73............................  ....................  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              8.2x10\2\              2.2x10\4\
As-74............................  ....................  1.0                    2.7x10\1\              9.0x10-1               2.4x10\1\              3.7x10\3\              9.9x10\4\
As-76............................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    5.8x10\4\              1.6x10\6\
As-77............................  ....................  2.0x10\1\              5.4x10\2\              7.0x10-1               1.9x10\1\              3.9x10\4\              1.0x10\6\
At-211 (a).......................  Astatine (85).......  2.0x10\1\              5.4x10\2\              5.0x10-1               1.4x10\1\              7.6x10\4\              2.1x10\6\
Au-193...........................  Gold (79)...........  7.0                    1.9x10\2\              2.0                    5.4x10\1\              3.4x10\4\              9.2x10\5\
Au-194...........................  ....................  1.0                    2.7x10\1\              1.0                    2.7x10\1\              1.5x10\4\              4.1x10\5\
Au-195...........................  ....................  1.0x10\1\              2.7x10\2\              6.0                    1.6x10\2\              1.4x10\2\              3.7x10\3\
Au-198...........................  ....................  1.0                    2.7x10\1\              6.0x10-1               1.6x10\1\              9.0x10\3\              2.4x10\5\
Au-199...........................  ....................  1.0x10\1\              2.7x10\2\              6.0x10-1               1.6x10\1\              7.7x10\3\              2.1x10\5\
Ba-131 (a).......................  Barium (56).........  2.0                    5.4x10\1\              2.0                    5.4x10\1\              3.1x10\3\              8.4x10\4\
Ba-133...........................  ....................  3.0                    8.1x10\1\              3.0                    8.1x10\1\              9.4                    2.6x10\2\
Ba-133m..........................  ....................  2.0x10\1\              5.4x10\2\              6.0x10-1               1.6x10\1\              2.2x10\4\              6.1x10\5\
Ba-140 (a).......................  ....................  5.0x10-1               1.4x10\1\              3.0x10-1               8.1                    2.7x10\3\              7.3x10\4\
Be-7.............................  Beryllium (4).......  2.0x10\1\              5.4x10\2\              2.0x10\1\              5.4x10\2\              1.3x10\4\              3.5x10\5\
Be-10............................  ....................  4.0x10\1\              1.1x10\3\              6.0x10-1               1.6x10\1\              8.3x10-4               2.2x10-2
Bi-205...........................  Bismuth (83)........  7.0x10-1               1.9x10\1\              7.0x10-1               1.9x10\1\              1.5x10-3               4.2x10\4\
Bi-206...........................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    3.8x10\3\              1.0x10\5\
Bi-207...........................  ....................  7.0x10-1               1.9x10\1\              7.0x10-1               1.9x10\1\              1.9                    5.2x10\1\
Bi-210...........................  ....................  1.0                    2.7x10\1\              6.0x10-1               1.6x10\1\              4.6x10\3\              1.2x10\5\
Bi-210m (a)......................  ....................  6.0x10-1               1.6x10\1\              2.0x10-2               5.4x10-1               2.1x10-5               5.7x10-4
Bi-212 (a).......................  ....................  7.0x10-1               1.9x10\1\              6.0x10-1               1.6x10\1\              5.4x10\5\              1.5x10\7\
Bk-247...........................  Berkelium (97)......  8.0                    2.2x10\2\              8.0x10-4               2.2x10-2               3.8x10-2               1.0
Bk-249 (a).......................  ....................  4.0x10\1\              1.1x10\3\              3.0x10-1               8.1                    6.1x10\1\              1.6x10\3\
Br-76............................  Bromine (35)........  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              9.4x10\4\              2.5x10\6\
Br-77............................  ....................  3.0                    8.1x10\1\              3.0                    8.1x10\1\              2.6x10\4\              7.1x10\5\
Br-82............................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              4.0x10\4\              1.1x10\6\
C-11.............................  Carbon (6)..........  1.0                    2.7x10\1\              6.0x10-1               1.6x10\1\              3.1x10\7\              8.4x10\8\
C-14.............................  ....................  4.0x10\1\              1.1x10\3\              3.0                    8.1x10\1\              1.6x10-1               4.5

[[Page 366]]

 
Ca-41............................  Calcium (20)........  Unlimited              Unlimited              Unlimited              Unlimited              3.1x10-3               8.5x10-2
Ca-45............................  ....................  4.0x10\1\              1.1x10\3\              1.0                    2.7x10\1\              6.6x10\2\              1.8x10\4\
Ca-47 (a)........................  ....................  3.0                    8.1x10\1\              3.0x10-1               8.1                    2.3x10\4\              6.1x10\5\
Cd-109...........................  Cadmium (48)........  3.0x10\1\              8.1x10\2\              2.0                    5.4x10\1\              9.6x10\1\              2.6x10\3\
Cd-113m..........................  ....................  4.0x10\1\              1.1x10\3\              5.0x10-1               1.4x10\1\              8.3                    2.2x10\2\
Cd-115 (a).......................  ....................  3.0                    8.1x10\1\              4.0x10-1               1.1x10\1\              1.9x10\4\              5.1x10\5\
Cd-115m..........................  ....................  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              9.4x10\2\              2.5x10\4\
Ce-139...........................  Cerium (58).........  7.0                    1.9x10\2\              2.0                    5.4x10\1\              2.5x10\2\              6.8x10\3\
Ce-141...........................  ....................  2.0x10\1\              5.4x10\2\              6.0x10-1               1.6x10\1\              1.1x10\3\              2.8x10\4\
Ce-143...........................  ....................  9.0x10-1               2.4x10\1\              6.0x10-1               1.6x10\1\              2.5x10\4\              6.6x10\5\
Ce-144 (a).......................  ....................  2.0x10-1               5.4                    2.0x10-1               5.4                    1.2x10\2\              3.2x10\3\
Cf-248...........................  Californium (98)....  4.0x10\1\              1.1x10\3\              6.0x10-3               1.6x10-1               5.8x10\1\              1.6x10\3\
Cf-249...........................  ....................  3.0                    8.1x10\1\              8.0x10-4               2.2x10-2               1.5x10-1               4.1
Cf-250...........................  ....................  2.0x10\1\              5.4x10\2\              2.0x10-3               5.4x10-2               4.0                    1.1x10\2\
Cf-251...........................  ....................  7.0                    1.9x10\2\              7.0x10-4               1.9x10-2               5.9x10-2               1.6
Cf-252 (h).......................  ....................  5.0x10-2               1.4                    3.0x10-3               8.1x10-2               2.0x10\1\              5.4x10\2\
Cf-253 (a).......................  ....................  4.0x10\1\              1.1x10\3\              4.0x10-2               1.1                    1.1x10\3\              2.9x10\4\
Cf-254...........................  ....................  1.0x10-3               2.7x10-2               1.0x10-3               2.7x10-2               3.1x10\2\              8.5x10\3\
Cl-36............................  Chlorine (17).......  1.0x10\1\              2.7x10\2\              6.0x10-1               1.6x10\1\              1.2x10-3               3.3x10-2
Cl-38............................  ....................  2.0x10-1               5.4                    2.0x10-1               5.4                    4.9x10\6\              1.3x10\8\
Cm-240...........................  Curium (96).........  4.0x10\1\              1.1x10\3\              2.0x10-2               5.4x10-1               7.5x10\2\              2.0x10\4\
Cm-241...........................  ....................  2.0                    5.4x10\1\              1.0                    2.7x10\1\              6.1x10\2\              1.7x10\4\
Cm-242...........................  ....................  4.0x10\1\              1.1x10\3\              1.0x10-2               2.7x10-1               1.2x10\2\              3.3x10\3\
Cm-243...........................  ....................  9.0                    2.4x10\2\              1.0x10-3               2.7x10-2               1.9x10-3               5.2x10\1\
Cm-244...........................  ....................  2.0x10\1\              5.4x10\2\              2.0x10-3               5.4x10-2               3.0                    8.1x10\1\
Cm-245...........................  ....................  9.0                    2.4x10\2\              9.0x10-4               2.4x10-2               6.4x10-3               1.7x10-1
Cm-246...........................  ....................  9.0                    2.4x10\2\              9.0x10-4               2.4x10-2               1.1x10-2               3.1x10-1
Cm-247 (a).......................  ....................  3.0                    8.1x10\1\              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               1.6x10-5               4.2x10-3
Co-55............................  Cobalt (27).........  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              1.1x10\5\              3.1x10\6\
Co-56............................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    1.1x10\3\              3.0x10\4\
Co-57............................  ....................  1.0x10\1\              2.7x10\2\              1.0x10\1\              2.7x10\2\              3.1x10\2\              8.4x10\3\
Co-58............................  ....................  1.0                    2.7x10\1\              1.0                    2.7x10\1\              1.2x10\3\              3.2x10\4\
Co-58m...........................  ....................  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              2.2x10\5\              5.9x10\6\
Co-60............................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              4.2x10\1\              1.1x10\3\
Cr-51............................  Chromium (24).......  3.0x10\1\              8.1x10\2\              3.0x10\1\              8.1x10\2\              3.4x10\3\              9.2x10\4\
Cs-129...........................  Cesium (55).........  4.0                    1.1x10\2\              4.0                    1.1x10\2\              2.8x10\4\              7.6x10\5\
Cs-131...........................  ....................  3.0x10\1\              8.1x10\2\              3.0x10\1\              8.1x10\2\              3.8x10\3\              1.0x10\5\
Cs-132...........................  ....................  1.0                    2.7x10\1\              1.0                    2.7x10\1\              5.7x10\3\              1.5x10\5\
Cs-134...........................  ....................  7.0x10-1               1.9x10\1\              7.0x10-1               1.9x10\1\              4.8x10\1\              1.3x10\3\
Cs-134m..........................  ....................  4.0x10\1\              1.1x10\3\              6.0x10-1               1.6x10\1\              3.0x10\5\              8.0x10\6\
Cs-135...........................  ....................  4.0x10\1\              1.1x10\3\              1.0                    2.7x10\1\              4.3x10-5               1.2x10-3
Cs-136...........................  ....................  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              2.7x10\3\              7.3x10\4\
Cs-137 (a).......................  ....................  2.0                    5.4x10\1\              6.0x10-1               1.6x10\1\              3.2                    8.7x10\1\

[[Page 367]]

 
Cu-64............................  Copper (29).........  6.0                    1.6x10\2\              1.0                    2.7x10\1\              1.4x10\5\              3.9x10\6\
Cu-67............................  ....................  1.0x10\1\              2.7x10\2\              7.0x10-1               1.9x10\1\              2.8x10\4\              7.6x10\5\
Dy-159...........................  Dysprosium (66).....  2.0x10\1\              5.4x10\2\              2.0x10\1\              5.4x10\2\              2.1x10\2\              5.7x10\3\
Dy-165...........................  ....................  9.0x10-1               2.4x10\1\              6.0x10-1               1.6x10\1\              3.0x10\5\              8.2x10\6\
Dy-166 (a).......................  ....................  9.0x10-1               2.4x10\1\              3.0x10-1               8.1                    8.6x10\3\              2.3x10\5\
Er-169...........................  Erbium (68).........  4.0x10\1\              1.1x10\3\              1.0                    2.7x10\1\              3.1x10\3\              8.3x10\4\
Er-171...........................  ....................  8.0x10-1               2.2x10\1\              5.0x10-1               1.4x10\1\              9.0x10\4\              2.4x10\6\
Eu-147...........................  Europium (63).......  2.0                    5.4x10\1\              2.0                    5.4x10\1\              1.4x10\3\              3.7x10\4\
Eu-148...........................  ....................  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              6.0x10\2\              1.6x10\4\
Eu-149...........................  ....................  2.0x10\1\              5.4x10\2\              2.0x10\1\              5.4x10\2\              3.5x10\2\              9.4x10\3\
Eu-150 (short lived).............  ....................  2.0                    5.4x10\1\              7.0x10-1               1.9x10\1\              6.1x10\4\              1.6x10\6\
Eu-150 (long lived)..............  ....................  7x10-1                 1.9x10\1\              7.0x10-1               1.9x10\1\              6.1x10\4\              1.6x10\6\
Eu-152...........................  ....................  1.0                    2.7x10\1\              1.0                    2.7x10\1\              6.5                    1.8x10\2\
Eu-152m..........................  ....................  8.0x10-1               2.2x10\1\              8.0x10-1               2.2x10\1\              8.2x10\4\              2.2x10\6\
Eu-154...........................  ....................  9.0x10-1               2.4x10\1\              6.0x10-1               1.6x10\1\              9.8                    2.6x10\2\
Eu-155...........................  ....................  2.0x10\1\              5.4x10\2\              3.0                    8.1x10\1\              1.8x10\1\              4.9x10\2\
Eu-156...........................  ....................  7.0x10-1               1.9x10\1\              7.0x10-1               1.9x10\1\              2.0x10\3\              5.5x10\4\
F-18.............................  Fluorine (9)........  1.0                    2.7x10\1\              6.0x10-1               1.6x10\1\              3.5x10\6\              9.5x10\7\
Fe-52 (a)........................  Iron (26)...........  3.0x10-1               8.1                    3.0x10-1               8.1                    2.7x10\5\              7.3x10\6\
Fe-55............................  ....................  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              8.8x10\1\              2.4x10\3\
Fe-59............................  ....................  9.0x10-1               2.4x10\1\              9.0x10-1               2.4x10\1\              1.8x10\3\              5.0x10\4\
Fe-60 (a)........................  ....................  4.0x10\1\              1.1x10\3\              2.0x10-1               5.4                    7.4x10-4               2.0x10-2
Ga-67............................  Gallium (31)........  7.0                    1.9x10\2\              3.0                    8.1x10\1\              2.2x10\4\              6.0x10\5\
Ga-68............................  ....................  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              1.5x10\6\              4.1x10\7\
Ga-72............................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              1.1x10\5\              3.1x10\6\
Gd-146 (a).......................  Gadolinium (64).....  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              6.9x10\2\              1.9x10\4\
Gd-148...........................  ....................  2.0x10\1\              5.4x10\2\              2.0x10-3               5.4x10-2               1.2                    3.2x10\1\
Gd-153...........................  ....................  1.0x10\1\              2.7x10\2\              9.0                    2.4x10\2\              1.3x10\2\              3.5x10\3\
Gd-159...........................  ....................  3.0                    8.1x10\1\              6.0x10-1               1.6x10\1\              3.9x10\4\              1.1x10\6\
Ge-68 (a)........................  Germanium (32)......  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              2.6x10\2\              7.1x10\3\
Ge-71............................  ....................  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              5.8x10\3\              1.6x10\5\
Ge-77............................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    1.3x10\5\              3.6x10\6\
Hf-172 (a).......................  Hafnium (72)........  6.0x10-1               1.6x10\1\              6.0x10-1               1.6x10\1\              4.1x10\1\              1.1x10\3\
Hf-175...........................  ....................  3.0                    8.1x10\1\              3.0                    8.1x10\1\              3.9x10\2\              1.1x10\4\
Hf-181...........................  ....................  2.0                    5.4x10\1\              5.0x10-1               1.4x10\1\              6.3x10\2\              1.7x10\4\
Hf-182...........................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              8.1x10-6               2.2x10-4
Hg-194 (a).......................  Mercury (80)........  1.0                    2.7x10\1\              1.0                    2.7x10\1\              1.3x10-1               3.5
Hg-195m (a)......................  ....................  3.0                    8.1x10\1\              7.0x10-1               1.9x10\1\              1.5x10\4\              4.0x10\5\
Hg-197...........................  ....................  2.0x10\1\              5.4x10\2\              1.0x10\1\              2.7x10\2\              9.2x10\3\              2.5x10\5\
Hg-197m..........................  ....................  1.0x10\1\              2.7x10\2\              4.0x10-1               1.1x10\1\              2.5x10\4\              6.7x10\5\
Hg-203...........................  ....................  5.0                    1.4x10\2\              1.0                    2.7x10\1\              5.1x10\2\              1.4x10\4\
Ho-166...........................  Holmium (67)........  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              2.6x10\4\              7.0x10\5\
Ho-166m..........................  ....................  6.0x10-1               1.6x10\1\              5.0x10-1               1.4x10\1\              6.6x10-2               1.8
I-123............................  Iodine (53).........  6.0                    1.6x10\2\              3.0                    8.1x10\1\              7.1x10\4\              1.9x10\6\
I-124............................  ....................  1.0                    2.7x10\1\              1.0                    2.7x10\1\              9.3x10\3\              2.5x10\5\
I-125............................  ....................  2.0x10\1\              5.4x10\2\              3.0                    8.1x10\1\              6.4x10\2\              1.7x10\4\
I-126............................  ....................  2.0                    5.4x10\1\              1.0                    2.7x10\1\              2.9x10\3\              8.0x10\4\
I-129............................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              6.5x10-6               1.8x10-4
I-131............................  ....................  3.0                    8.1x10\1\              7.0x10-1               1.9x10\1\              4.6x10\3\              1.2x10\5\
I-132............................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              3.8x10\5\              1.0x10\7\

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I-133............................  ....................  7.0x10-1               1.9x10\1\              6.0x10-1               1.6x10\1\              4.2x10\4\              1.1x10\6\
I-134............................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    9.9x10\5\              2.7x10\7\
I-135 (a)........................  ....................  6.0x10-1               1.6x10\1\              6.0x10-1               1.6x10\1\              1.3x10\5\              3.5x10\6\
In-111...........................  Indium (49).........  3.0                    8.1x10\1\              3.0                    8.1x10\1\              1.5x10\4\              4.2x10\5\
In-113m..........................  ....................  4.0                    1.1x10\2\              2.0                    5.4x10\1\              6.2x10\5\              1.7x10\7\
In-114m (a)......................  ....................  1.0x10\1\              2.7x10\2\              5.0x10-1               1.4x10\1\              8.6x10\2\              2.3x10\4\
In-115m..........................  ....................  7.0                    1.9x10\2\              1.0                    2.7x10\1\              2.2x10\5\              6.1x10\6\
Ir-189 (a).......................  Iridium (77)........  1.0x10\1\              2.7x10\2\              1.0x10\1\              2.7x10\2\              1.9x10\3\              5.2x10\4\
Ir-190...........................  ....................  7.0x10-1               1.9x10\1\              7.0x10-1               1.9x10\1\              2.3x10\3\              6.2x10\4\
Ir-192 (c).......................  ....................  1.0                    2.7x10\1\              6.0x10-1               1.6x10\1\              3.4x10\2\              9.2x10\3\
Ir-194...........................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    3.1x10\4\              8.4x10\5\
K-40.............................  Potassium (19)......  9.0x10-1               2.4x10\1\              9.0x10-1               2.4x10\1\              2.4x10-7               6.4x10-6
K-42.............................  ....................  2.0x10-1               5.4                    2.0x10-1               5.4                    2.2x10\5\              6.0x10\6\
K-43.............................  ....................  7.0x10-1               1.9x10\1\              6.0x10-1               1.6x10\1\              1.2x10\5\              3.3x10\6\
Kr-81............................  Krypton (36)........  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              7.8x10-4               2.1x10-2
Kr-85............................  ....................  1.0x10\1\              2.7x10\2\              1.0x10\1\              2.7x10\2\              1.5x10\1\              3.9x10\2\
Kr-85m...........................  ....................  8.0                    2.2x10\2\              3.0                    8.1x10\1\              3.0x10\5\              8.2x10\6\
Kr-87............................  ....................  2.0x10-1               5.4                    2.0x10-1               5.4                    1.0x10\6\              2.8x10\7\
La-137...........................  Lanthanum (57)......  3.0x10\1\              8.1x10\2\              6.0                    1.6x10\2\              1.6x10-3               4.4x10-2
La-140...........................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              2.1x10\4\              5.6x10\5\
Lu-172...........................  Lutetium (71).......  6.0x10-1               1.6x10\1\              6.0x10-1               1.6x10\1\              4.2x10\3\              1.1x10\5\
Lu-173...........................  ....................  8.0                    2.2x10\2\              8.0                    2.2x10\2\              5.6x10\1\              1.5x10\3\
Lu-174...........................  ....................  9.0                    2.4x10\2\              9.0                    2.4x10\2\              2.3x10\1\              6.2x10\2\
Lu-174m..........................  ....................  2.0x10\1\              5.4x10\2\              1.0x10\1\              2.7x10\2\              2.0x10\2\              5.3x10\3\
Lu-177...........................  ....................  3.0x10\1\              8.1x10\2\              7.0x10-1               1.9x10\1\              4.1x10\3\              1.1x10\5\
Mg-28 (a)........................  Magnesium (12)......  3.0x10-1               8.1                    3.0x10-1               8.1                    2.0x10\5\              5.4x10\6\
Mn-52............................  Manganese (25)......  3.0x10-1               8.1                    3.0x10-1               8.1                    1.6x10\4\              4.4x10\5\
Mn-53............................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              6.8x10-5               1.8x10-3
Mn-54............................  ....................  1.0                    2.7x10\1\              1.0                    2.7x10\1\              2.9x10\2\              7.7x10\3\
Mn-56............................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    8.0x10\5\              2.2x10\7\
Mo-93............................  Molybdenum (42).....  4.0x10\1\              1.1x10\3\              2.0x10\1\              5.4x10\2\              4.1x10-2               1.1
Mo-99 (a) (i)....................  ....................  1.0                    2.7x10\1\              6.0x10-1               1.6x10\1\              1.8x10\4\              4.8x10\5\
N-13.............................  Nitrogen (7)........  9.0x10-1               2.4x10\1\              6.0x10-1               1.6x10\1\              5.4x10\7\              1.5x10\9\
Na-22............................  Sodium (11).........  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              2.3x10\2\              6.3x10\3\
Na-24............................  ....................  2.0x10-1               5.4                    2.0x10-1               5.4                    3.2x10\5\              8.7x10\6\
Nb-93m...........................  Niobium (41)........  4.0x10\1\              1.1x10\3\              3.0x10\1\              8.1x10\2\              8.8                    2.4x10\2\
Nb-94............................  ....................  7.0x10-1               1.9x10\1\              7.0x10-1               1.9x10\1\              6.9x10-3               1.9x10-1
Nb-95............................  ....................  1.0                    2.7x10\1\              1.0                    2.7x10\1\              1.5x10\3\              3.9x10\4\
Nb-97............................  ....................  9.0x10-1               2.4x10\1\              6.0x10-1               1.6x10\1\              9.9x10\5\              2.7x10\7\
Nd-147...........................  Neodymium (60)......  6.0                    1.6x10\2\              6.0x10-1               1.6x10\1\              3.0x10\3\              8.1x10\4\
Nd-149...........................  ....................  6.0x10-1               1.6x10\1\              5.0x10-1               1.4x10\1\              4.5x10\5\              1.2x10\7\
Ni-59............................  Nickel (28).........  Unlimited              Unlimited              Unlimited              Unlimited              3.0x10-3               8.0x10-2
Ni-63............................  ....................  4.0x10\1\              1.1x10\3\              3.0x10\1\              8.1x10\2\              2.1                    5.7x10\1\
Ni-65............................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              7.1x10\5\              1.9x10\7\

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Np-235...........................  Neptunium (93)......  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              5.2x10\1\              1.4x10\3\
Np-236 (short-lived).............  ....................  2.0x10\1\              5.4x10\2\              2.0                    5.4x10\1\              4.7x10-4               1.3x10-2
Np-236 (long-lived)..............  ....................  9.0x10\0\              2.4x10\2\              2.0x10-2               5.4x10-1               4.7x10-4               1.3x10-2
Np-237...........................  ....................  2.0x10\1\              5.4x10\2\              2.0x10-3               5.4x10-2               2.6x10-5               7.1x10-4
Np-239...........................  ....................  7.0                    1.9x10\2\              4.0x10-1               1.1x10\1\              8.6x10\3\              2.3x10\5\
Os-185...........................  Osmium (76).........  1.0                    2.7x10\1\              1.0                    2.7x10\1\              2.8x10\2\              7.5x10\3\
Os-191...........................  ....................  1.0x10\1\              2.7x10\2\              2.0                    5.4x10\1\              1.6x10\3\              4.4x10\4\
Os-191m..........................  ....................  4.0x10\1\              1.1x10\3\              3.0x10\1\              8.1x10\2\              4.6x10\4\              1.3x10\6\
Os-193...........................  ....................  2.0                    5.4x10\1\              6.0x10-1               1.6x10\1\              2.0x10\4\              5.3x10\5\
Os-194 (a).......................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    1.1x10\1\              3.1x10\2\
P-32.............................  Phosphorus (15).....  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              1.1x10\4\              2.9x10\5\
P-33.............................  ....................  4.0x10\1\              1.1x10\3\              1.0                    2.7x10\1\              5.8x10\3\              1.6x10\5\
Pa-230 (a).......................  Protactinium (91)...  2.0                    5.4x10\1\              7.0x10-2               1.9                    1.2x10\3\              3.3x10\4\
Pa-231...........................  ....................  4.0                    1.1x10\2\              4.0x10-4               1.1x10-2               1.7x10-3               4.7x10-2
Pa-233...........................  ....................  5.0                    1.4x10\2\              7.0x10-1               1.9x10\1\              7.7x10\2\              2.1x10\4\
Pb-201...........................  Lead (82)...........  1.0                    2.7x10\1\              1.0                    2.7x10\1\              6.2x10\4\              1.7x10\6\
Pb-202...........................  ....................  4.0x10\1\              1.1x10\3\              2.0x10\1\              5.4x10\2\              1.2x10-4               3.4x10-3
Pb-203...........................  ....................  4.0                    1.1x10\2\              3.0                    8.1x10\1\              1.1x10\4\              3.0x10\5\
Pb-205...........................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              4.5x10-6               1.2x10-4
Pb-210 (a).......................  ....................  1.0                    2.7x10\1\              5.0x10-2               1.4                    2.8                    7.6x10\1\
Pb-212 (a).......................  ....................  7.0x10-1               1.9x10\1\              2.0x10-1               5.4                    5.1x10\4\              1.4x10\6\
Pd-103 (a).......................  Palladium (46)......  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              2.8x10\3\              7.5x10\4\
Pd-107...........................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              1.9x10-5               5.1x10-4
Pd-109...........................  ....................  2.0                    5.4x10\1\              5.0x10-1               1.4x10\1\              7.9x10\4\              2.1x10\6\
Pm-143...........................  Promethium (61).....  3.0                    8.1x10\1\              3.0                    8.1x10\1\              1.3x10\2\              3.4x10\3\
Pm-144...........................  ....................  7.0x10-1               1.9x10\1\              7.0x10-1               1.9x10\1\              9.2x10\1\              2.5x10\3\
Pm-145...........................  ....................  3.0x10\1\              8.1x10\2\              1.0x10\1\              2.7x10\2\              5.2                    1.4x10\2\
Pm-147...........................  ....................  4.0x10\1\              1.1x10\3\              2.0                    5.4x10\1\              3.4x10\1\              9.3x10\2\
Pm-148m (a)......................  ....................  8.0x10-1               2.2x10\1\              7.0x10-1               1.9x10\1\              7.9x10\2\              2.1x10\4\
Pm-149...........................  ....................  2.0                    5.4x10\1\              6.0x10-1               1.6x10\1\              1.5x10\4\              4.0x10\5\
Pm-151...........................  ....................  2.0                    5.4x10\1\              6.0x10-1               1.6x10\1\              2.7x10\4\              7.3x10\5\
Po-210...........................  Polonium (84).......  4.0x10\1\              1.1x10\3\              2.0x10-2               5.4x10-1               1.7x10\2\              4.5x10\3\
Pr-142...........................  Praseodymium (59)...  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              4.3x10\4\              1.2x10\6\
Pr-143...........................  ....................  3.0                    8.1x10\1\              6.0x10-1               1.6x10\1\              2.5x10\3\              6.7x10\4\
Pt-188 (a).......................  Platinum (78).......  1.0                    2.7x10\1\              8.0x10-1               2.2x10\1\              2.5x10\3\              6.8x10\4\
Pt-191...........................  ....................  4.0                    1.1x10\2\              3.0                    8.1x10\1\              8.7x10\3\              2.4x10\5\
Pt-193...........................  ....................  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              1.4                    3.7x10\1\
Pt-193m..........................  ....................  4.0x10\1\              1.1x10\3\              5.0x10-1               1.4x10\1\              5.8x10\3\              1.6x10\5\
Pt-195m..........................  ....................  1.0x10\1\              2.7x10\2\              5.0x10-1               1.4x10\1\              6.2x10\3\              1.7x10\5\
Pt-197...........................  ....................  2.0x10\1\              5.4x10\2\              6.0x10-1               1.6x10\1\              3.2x10\4\              8.7x10\5\
Pt-197m..........................  ....................  1.0x10\1\              2.7x10\2\              6.0x10-1               1.6x10\1\              3.7x10\5\              1.0x10\7\
Pu-236...........................  Plutonium (94)......  3.0x10\1\              8.1x10\2\              3.0x10-3               8.1x10-2               2.0x10\1\              5.3x10\2\
Pu-237...........................  ....................  2.0x10\1\              5.4x10\2\              2.0x10\1\              5.4x10\2\              4.5x10\2\              1.2x10\4\
Pu-238...........................  ....................  1.0x10\1\              2.7x10\2\              1.0x10-3               2.7x10-2               6.3x10-1               1.7x10\1\
Pu-239...........................  ....................  1.0x10\1\              2.7x10\2\              1.0x10-3               2.7x10-2               2.3x10-3               6.2x10-2
Pu-240...........................  ....................  1.0x10\1\              2.7x10\2\              1.0x10-3               2.7x10-2               8.4x10-3               2.3x10-1
Pu-241 (a).......................  ....................  4.0x10\1\              1.1x10\3\              6.0x10-2               1.6                    3.8                    1.0x10\2\
Pu-242...........................  ....................  1.0x10\1\              2.7x10\2\              1.0x10-3               2.7x10-2               1.5x10-4               3.9x10-3
Pu-244 (a).......................  ....................  4.0x10-1               1.1x10\1\              1.0x10-3               2.7x10-2               6.7x10-7               1.8x10-5
Ra-223 (a).......................  Radium (88).........  4.0x10-1               1.1x10\1\              7.0x10-3               1.9x10-1               1.9x10\3\              5.1x10\4\

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Ra-224 (a).......................  ....................  4.0x10-1               1.1x10\1\              2.0x10-2               5.4x10-1               5.9x10\3\              1.6x10\5\
Ra-225 (a).......................  ....................  2.0x10-1               5.4                    4.0x10-3               1.1x10-1               1.5x10\3\              3.9x10\4\
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               1.6x10\1\              2.0x10-2               5.4x10-1               1.0x10\1\              2.7x10\2\
Rb-81............................  Rubidium (37).......  2.0                    5.4x10\1\              8.0x10-1               2.2x10\1\              3.1x10\5\              8.4x10\6\
Rb-83 (a)........................  ....................  2.0                    5.4x10\1\              2.0                    5.4x10\1\              6.8x10\2\              1.8x10\4\
Rb-84............................  ....................  1.0                    2.7x10\1\              1.0                    2.7x10\1\              1.8x10\3\              4.7x10\4\
Rb-86............................  ....................  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              3.0x10\3\              8.1x10\4\
Rb-87............................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              3.2x10-9               8.6x10-8
Rb(nat)..........................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              6.7x10\6\              1.8x10\8\
Re-184...........................  Rhenium (75)........  1.0                    2.7x10\1\              1.0                    2.7x10\1\              6.9x10\2\              1.9x10\4\
Re-184m..........................  ....................  3.0                    8.1x10\1\              1.0                    2.7x10\1\              1.6x10\2\              4.3x10\3\
Re-186...........................  ....................  2.0                    5.4x10\1\              6.0x10-1               1.6x10\1\              6.9x10\3\              1.9x10\5\
Re-187...........................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              1.4x10-9               3.8x10-8
Re-188...........................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              3.6x10\4\              9.8x10\5\
Re-189 (a).......................  ....................  3.0                    8.1x10\1\              6.0x10-1               1.6x10\1\              2.5x10\4\              6.8x10\5\
Re(nat)..........................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              0.0                    2.4x10-8
Rh-99............................  Rhodium (45)........  2.0                    5.4x10\1\              2.0                    5.4x10\1\              3.0x10\3\              8.2x10\4\
Rh-101...........................  ....................  4.0                    1.1x10\2\              3.0                    8.1x10\1\              4.1x10\1\              1.1x10\3\
Rh-102...........................  ....................  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              4.5x10\1\              1.2x10\3\
Rh-102m..........................  ....................  2.0                    5.4x10\1\              2.0                    5.4x10\1\              2.3x10\2\              6.2x10\3\
Rh-103m..........................  ....................  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              1.2x10\6\              3.3x10\7\
Rh-105...........................  ....................  1.0x10\1\              2.7x10\2\              8.0x10-1               2.2x10\1\              3.1x10\4\              8.4x10\5\
Rn-222 (a).......................  Radon (86)..........  3.0x10-1               8.1                    4.0x10-3               1.1x10-1               5.7x10\3\              1.5x10\5\
Ru-97............................  Ruthenium (44)......  5.0                    1.4x10\2\              5.0                    1.4x10\2\              1.7x10\4\              4.6x10\5\
Ru-103 (a).......................  ....................  2.0                    5.4x10\1\              2.0                    5.4x10\1\              1.2x10\3\              3.2x10\4\
Ru-105...........................  ....................  1.0                    2.7x10\1\              6.0x10-1               1.6x10\1\              2.5x10\5\              6.7x10\6\
Ru-106 (a).......................  ....................  2.0x10-1               5.4                    2.0x10-1               5.4                    1.2x10\2\              3.3x10\3\
S-35.............................  Sulphur (16)........  4.0x10\1\              1.1x10\3\              3.0                    8.1x10\1\              1.6x10\3\              4.3x10\4\
Sb-122...........................  Antimony (51).......  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              1.5x10\4\              4.0x10\5\
Sb-124...........................  ....................  6.0x10-1               1.6x10\1\              6.0x10-1               1.6x10\1\              6.5x10\2\              1.7x10\4\
Sb-125...........................  ....................  2.0                    5.4x10\1\              1.0                    2.7x10\1\              3.9x10\1\              1.0x10\3\
Sb-126...........................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              3.1x10\3\              8.4x10\4\
Sc-44............................  Scandium (21).......  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              6.7x10\5\              1.8x10\7\
Sc-46............................  ....................  5.0x10-1               1.4x10\1\              5.0x10-1               1.4x10\1\              1.3x10\3\              3.4x10\4\
Sc-47............................  ....................  1.0x10\1\              2.7x10\2\              7.0x10-1               1.9x10\1\              3.1x10\4\              8.3x10\5\
Sc-48............................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    5.5x10\4\              1.5x10\6\
Se-75............................  Selenium (34).......  3.0                    8.1x10\1\              3.0                    8.1x10\1\              5.4x10\2\              1.5x10\4\
Se-79............................  ....................  4.0x10\1\              1.1x10\3\              2.0                    5.4x10\1\              2.6x10-3               7.0x10-2
Si-31............................  Silicon (14)........  6.0x10-1               1.6x10\1\              6.0x10-1               1.6x10\1\              1.4x10\6\              3.9x10\7\
Si-32............................  ....................  4.0x10\1\              1.1x10\3\              5.0x10-1               1.4x10\1\              3.9                    1.1x10\2\
Sm-145...........................  Samarium (62).......  1.0x10\1\              2.7x10\2\              1.0x10\1\              2.7x10\2\              9.8x10\1\              2.6x10\3\
Sm-147...........................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              8.5x10-1               2.3x10-8
Sm-151...........................  ....................  4.0x10\1\              1.1x10\3\              1.0x10\1\              2.7x10\2\              9.7x10-1               2.6x10\1\

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Sm-153...........................  ....................  9.0                    2.4x10\2\              6.0x10-1               1.6x10\1\              1.6x10\4\              4.4x10\5\
Sn-113 (a).......................  Tin (50)............  4.0                    1.1x10\2\              2.0                    5.4x10\1\              3.7x10\2\              1.0x10\4\
Sn-117m..........................  ....................  7.0                    1.9x10\2\              4.0x10-1               1.1x10\1\              3.0x10\3\              8.2x10\4\
Sn-119m..........................  ....................  4.0x10\1\              1.1x10\3\              3.0x10\1\              8.1x10\2\              1.4x10\2\              3.7x10\3\
Sn-121m (a)......................  ....................  4.0x10\1\              1.1x10\3\              9.0x10-1               2.4x10\1\              2.0                    5.4x10\1\
Sn-123...........................  ....................  8.0x10-1               2.2x10\1\              6.0x10-1               1.6x10\1\              3.0x10\2\              8.2x10\3\
Sn-125...........................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              4.0x10\3\              1.1x10\5\
Sn-126 (a).......................  ....................  6.0x10-1               1.6x10\1\              4.0x10-1               1.1x10\1\              1.0x10-3               2.8x10-2
Sr-82 (a)........................  Strontium (38)......  2.0x10-1               5.4                    2.0x10-1               5.4                    2.3x10\3\              6.2x10\4\
Sr-85............................  ....................  2.0                    5.4x10\1\              2.0                    5.4x10\1\              8.8x10\2\              2.4x10\4\
Sr-85m...........................  ....................  5.0                    1.4x10\2\              5.0                    1.4x10\2\              1.2x10\6\              3.3x10\7\
Sr-87m...........................  ....................  3.0                    8.1x10\1\              3.0                    8.1x10\1\              4.8x10\5\              1.3x10\7\
Sr-89............................  ....................  6.0x10-1               1.6x10\1\              6.0x10-1               1.6x10\1\              1.1x10\3\              2.9x10\4\
Sr-90 (a)........................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    5.1                    1.4x10\2\
Sr-91 (a)........................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    1.3x10\5\              3.6x10\6\
Sr-92 (a)........................  ....................  1.0                    2.7x10\1\              3.0x10-1               8.1                    4.7x10\5\              1.3x10\7\
T(H-3)...........................  Tritium (1).........  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              3.6x10\2\              9.7x10\3\
Ta-178 (long-lived)..............  Tantalum (73).......  1.0                    2.7x10\1\              8.0x10-1               2.2x10\1\              4.2x10\6\              1.1x10\8\
Ta-179...........................  ....................  3.0x10\1\              8.1x10\2\              3.0x10\1\              8.1x10\2\              4.1x10\1\              1.1x10\3\
Ta-182...........................  ....................  9.0x10-1               2.4x10\1\              5.0x10-1               1.4x10\1\              2.3x10\2\              6.2x10\3\
Tb-157...........................  Terbium (65)........  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              5.6x10-1               1.5x10\1\
Tb-158...........................  ....................  1.0                    2.7x10\1\              1.0                    2.7x10\1\              5.6x10-1               1.5x10\1\
Tb-160...........................  ....................  1.0                    2.7x10\1\              6.0x10-1               1.6x10\1\              4.2x10\2\              1.1x10\4\
Tc-95m (a).......................  Technetium (43).....  2.0                    5.4x10\1\              2.0                    5.4x10\1\              8.3x10\2\              2.2x10\4\
Tc-96............................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              1.2x10\4\              3.2x10\5\
Tc-96m (a).......................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              1.4x10\6\              3.8x10\7\
Tc-97............................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              5.2x10-5               1.4x10-3
Tc-97m...........................  ....................  4.0x10\1\              1.1x10\3\              1.0                    2.7x10\1\              5.6x10\2\              1.5x10\4\
Tc-98............................  ....................  8.0x10-1               2.2x10\1\              7.0x10-1               1.9x10\1\              3.2x10-5               8.7x10-4
Tc-99............................  ....................  4.0x10\1\              1.1x10\3\              9.0x10-1               2.4x10\1\              6.3x10-4               1.7x10-2
Tc-99m...........................  ....................  1.0x10\1\              2.7x10\2\              4.0                    1.1x10\2\              1.9x10\5\              5.3x10\6\
Te-121...........................  Tellurium (52)......  2.0                    5.4x10\1\              2.0                    5.4x10\1\              2.4x10\3\              6.4x10\4\
Te-121m..........................  ....................  5.0                    1.4x10\2\              3.0                    8.1x10\1\              2.6x10\2\              7.0x10\3\
Te-123m..........................  ....................  8.0                    2.2x10\2\              1.0                    2.7x10\1\              3.3x10\2\              8.9x10\3\
Te-125m..........................  ....................  2.0x10\1\              5.4x10\2\              9.0x10-1               2.4x10\1\              6.7x10\2\              1.8x10\4\
Te-127...........................  ....................  2.0x10\1\              5.4x10\2\              7.0x10-1               1.9x10\1\              9.8x10\4\              2.6x10\6\
Te-127m (a)......................  ....................  2.0x10\1\              5.4x10\2\              5.0x10-1               1.4x10\1\              3.5x10\2\              9.4x10\3\
Te-129...........................  ....................  7.0x10-1               1.9x10\1\              6.0x10-1               1.6x10\1\              7.7x10\5\              2.1x10\7\
Te-129m (a)......................  ....................  8.0x10-1               2.2x10\1\              4.0x10-1               1.1x10\1\              1.1x10\3\              3.0x10\4\
Te-131m (a)......................  ....................  7.0x10-1               1.9x10\1\              5.0x10-1               1.4x10\1\              3.0x10\4\              8.0x10\5\
Te-132 (a).......................  ....................  5.0x10-1               1.4x10\1\              4.0x10-1               1.1x10\1\              1.1x10\4\              8.0x10\5\
Th-227...........................  Thorium (90)........  1.0x10\1\              2.7x10\2\              5.0x10-3               1.4x10-1               1.1x10\3\              3.1x10\4\
Th-228 (a).......................  ....................  5.0x10-1               1.4x10\1\              1.0x10-3               2.7x10-2               3.0x10\1\              8.2x10\2\
Th-229...........................  ....................  5.0                    1.4x10\2\              5.0x10-4               1.4x10-2               7.9x10-3               2.1x10-1
Th-230...........................  ....................  1.0x10\1\              2.7x10\2\              1.0x10-3               2.7x10-2               7.6x10-4               2.1x10-2
Th-231...........................  ....................  4.0x10\1\              1.1x10\3\              2.0x10-2               5.4x10-1               2.0x10\4\              5.3x10\5\
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                    8.6x10\2\              2.3x10\4\
Th(nat)..........................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              8.1x10-9               2.2x10-7
Ti-44 (a)........................  Titanium (22).......  5.0x10-1               1.4x10\1\              4.0x10-1               1.1x10\1\              6.4                    1.7x10\2\

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Tl-200...........................  Thallium (81).......  9.0x10-1               2.4x10\1\              9.0x10-1               2.4x10\1\              2.2x10\4\              6.0x10\5\
Tl-201...........................  ....................  1.0x10\1\              2.7x10\2\              4.0                    1.1x10\2\              7.9x10\3\              2.1x10\5\
Tl-202...........................  ....................  2.0                    5.4x10\1\              2.0                    5.4x10\1\              2.0x10\3\              5.3x10\4\
Tl-204...........................  ....................  1.0x10\1\              2.7x10\2\              7.0x10-1               1.9x10\1\              1.7x10\1\              4.6x10\2\
Tm-167...........................  Thulium (69)........  7.0                    1.9x10\2\              8.0x10-1               2.2x10\1\              3.1x10\3\              8.5x10\4\
Tm-170...........................  ....................  3.0                    8.1x10\1\              6.0x10-1               1.6x10\1\              2.2x10\2\              6.0x10\3\
Tm-171...........................  ....................  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\
U-230 (fast lung absorption)       Uranium (92)........  4.0x10\1\              1.1x10\3\              1.0x10-1               2.7                    1.0x10\3\              2.7x10\4\
 (a)(d).
U-230 (medium lung absorption)     ....................  4.0x10\1\              1.1x10\3\              4.0x10-3               1.1x10-1               1.0x10\3\              2.7x10\4\
 (a)(e).
U-230 (slow lung absorption)       ....................  3.0x10\1\              8.1x10\2\              3.0x10-3               8.1x10-2               1.0x10\3\              2.7x10\4\
 (a)(f).
U-232 (fast lung absorption) (d).  ....................  4.0x10\1\              1.1x10\3\              1.0x10-2               2.7x10-1               8.3x10-1               2.2x10\1\
U-232 (medium lung absorption)     ....................  4.0x10\1\              1.1x10\3\              7.0x10-3               1.9x10-1               8.3x10-1               2.2x10\1\
 (e).
U-232 (slow lung absorption) (f).  ....................  1.0x10\1\              2.7x10\2\              1.0x10-3               2.7x10-2               8.3x10-1               2.2x10\1\
U-233 (fast lung absorption) (d).  ....................  4.0x10\1\              1.1x10\3\              9.0x10-2               2.4                    3.6x10-4               9.7x10-3
U-233 (medium lung absorption)     ....................  4.0x10\1\              1.1x10\3\              2.0x10-2               5.4x10-1               3.6x10-4               9.7x10-3
 (e).
U-233 (slow lung absorption) (f).  ....................  4.0x10\1\              1.1x10\3\              6.0x10-3               1.6x10-1               3.6x10-4               9.7x10-3
U-234 (fast lung absorption) (d).  ....................  4.0x10\1\              1.1x10\3\              9.0x10-2               2.4                    2.3x10-4               6.2x10-3
U-234 (medium lung absorption)     ....................  4.0x10\1\              1.1x10\3\              2.0x10-2               5.4x10-1               2.3x10-4               6.2x10-3
 (e).
U-234 (slow lung absorption) (f).  ....................  4.0x10\1\              1.1x10\3\              6.0x10-3               1.6x10-1               2.3x10-4               6.2x10-3
U-235 (all lung absorption types)  ....................  Unlimited              Unlimited              Unlimited              Unlimited              8.0x10-8               2.2x10-6
 (a),(d),(e),(f).
U-236 (fast lung absorption) (d).  ....................  Unlimited              Unlimited              Unlimited              Unlimited              2.4x10-6               6.5x10-5
U-236 (medium lung absorption)     ....................  4.0x10\1\              1.1x10\3\              2.0x10-2               5.4x10-1               2.4x10-6               6.5x10-5
 (e).
U-236 (slow lung absorption) (f).  ....................  4.0x10\1\              1.1x10\3\              6.0x10-3               1.6x10-1               2.4x10-6               6.5x10-5
U-238 (all lung absorption types)  ....................  Unlimited              Unlimited              Unlimited              Unlimited              1.2x10-8               3.4x10-7
 (d),(e),(f).
U (nat)..........................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              2.6x10-8               7.1x10-7

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U (enriched to 20% or less)(g)...  ....................  Unlimited              Unlimited              Unlimited              Unlimited              See Table A-4          See Table A-4
U (dep)..........................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              See Table A-4          See Table A-4
V-48.............................  Vanadium (23).......  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              6.3x10\3\              1.7x10\5\
V-49.............................  ....................  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              3.0x10\2\              8.1x10\3\
W-178 (a)........................  Tungsten (74).......  9.0                    2.4x10\2\              5.0                    1.4x10\2\              1.3x10\3\              3.4x10\4\
W-181............................  ....................  3.0x10\1\              8.1x10\2\              3.0x10\1\              8.1x10\2\              2.2x10\2\              6.0x10\3\
W-185............................  ....................  4.0x10\1\              1.1x10\3\              8.0x10-1               2.2x10\1\              3.5x10\2\              9.4x10\3\
W-187............................  ....................  2.0                    5.4x10\1\              6.0x10-1               1.6x10\1\              2.6x10\4\              7.0x10\5\
W-188 (a)........................  ....................  4.0x10-1               1.1x10\1\              3.0x10-1               8.1                    3.7x10\2\              1.0x10\4\
Xe-122 (a).......................  Xenon (54)..........  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              4.8x10\4\              1.3x10\6\
Xe-123...........................  ....................  2.0                    5.4x10\1\              7.0x10-1               1.9x10\1\              4.4x10\5\              1.2x10\7\
Xe-127...........................  ....................  4.0                    1.1x10\2\              2.0                    5.4x10\1\              1.0x10\3\              2.8x10\4\
Xe-131m..........................  ....................  4.0x10\1\              1.1x10\3\              4.0x10\1\              1.1x10\3\              3.1x10\3\              8.4x10\4\
Xe-133...........................  ....................  2.0x10\1\              5.4x10\2\              1.0x10\1\              2.7x10\2\              6.9x10\3\              1.9x10\5\
Xe-135...........................  ....................  3.0                    8.1x10\1\              2.0                    5.4x10\1\              9.5x10\4\              2.6x10\6\
Y-87 (a).........................  Yttrium (39)........  1.0                    2.7x10\1\              1.0                    2.7x10\1\              1.7x10\4\              4.5x10\5\
Y-88.............................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              5.2x10\2\              1.4x10\4\
Y-90.............................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    2.0x10\4\              5.4x10\5\
Y-91.............................  ....................  6.0x10-1               1.6x10\1\              6.0x10-1               1.6x10\1\              9.1x10\2\              2.5x10\4\
Y-91m............................  ....................  2.0                    5.4x10\1\              2.0                    5.4x10\1\              1.5x10\6\              4.2x10\7\
Y-92.............................  ....................  2.0x10-1               5.4                    2.0x10-1               5.4                    3.6x10\5\              9.6x10\6\
Y-93.............................  ....................  3.0x10-1               8.1                    3.0x10-1               8.1                    1.2x10\5\              3.3x10\6\
Yb-169...........................  Ytterbium (70)......  4.0                    1.1x10\2\              1.0                    2.7x10\1\              8.9x10\2\              2.4x10\4\
Yb-175...........................  ....................  3.0x10\1\              8.1x10\2\              9.0x10-1               2.4x10\1\              6.6x10\3\              1.8x10\5\
Zn-65............................  Zinc (30)...........  2.0                    5.4x10\1\              2.0                    5.4x10\1\              3.0x10\2\              8.2x10\3\
Zn-69............................  ....................  3.0                    8.1x10\1\              6.0x10-1               1.6x10\1\              1.8x10\6\              4.9x10\7\
Zn-69m (a).......................  ....................  3.0                    8.1x10\1\              6.0x10-1               1.6x10\1\              1.2x10\5\              3.3x10\6\
Zr-88............................  Zirconium (40)......  3.0                    8.1x10\1\              3.0                    8.1x10\1\              6.6x10\2\              1.8x10\4\
Zr-93............................  ....................  Unlimited              Unlimited              Unlimited              Unlimited              9.3x10-5               2.5x10-3
Zr-95 (a)........................  ....................  2.0                    5.4x10\1\              8.0x10-1               2.2x10\1\              7.9x10\2\              2.1x10\4\
Zr-97 (a)........................  ....................  4.0x10-1               1.1x10\1\              4.0x10-1               1.1x10\1\              7.1x10\4\              1.9x10\6\
------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------
a A1 and/or A2 values include contributions from daughter nuclides with half-lives less than 10 days.
b The values of A1 and A2 in Curies (Ci) are approximate and for information only; the regulatory standard units are Terabecquerels (TBq), (see Appendix A to part 71--Determination of A1 and
  A2, Section I.). For radionuclide Bi-205, the specific activity is corrected to 1.5 x 10\3\ TBq/g. For radionuclide Cm-248, the specific activity is corrected to 1.6 x 10-\4\ TBq/g. For
  radionuclide Eu-150 (long lived), the A1 value is corrected to 7.0 x 10-\1\ TBq. For radionuclide Te-132(a), the specific activity is corrected to 3.0 x 10\5\ Ci/g.
c The quantity 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 A1 = 0.1 TBq (2.7 Ci) and A2 = 0.001 TBq (0.027 Ci) for Cf-252 for domestic use.
i A2 = 0.74 TBq (20 Ci) for Mo-99 for domestic use.


[[Page 374]]


                       Table A-2--Exempt Material Activity Concentrations and Exempt Consignment Activity Limits for Radionuclides
--------------------------------------------------------------------------------------------------------------------------------------------------------
                                                           Activity concentration  Activity concentration    Activity limit for      Activity limit for
      Symbol of  radionuclide         Element and atomic     for exempt material     for exempt material     exempt consignment      exempt consignment
                                            number                 (Bq/g)                  (Ci/g)                   (Bq)                    (Ci)
--------------------------------------------------------------------------------------------------------------------------------------------------------
Ac-225............................  Actinium (89)........  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Ac-227............................  .....................  1.0x10-1                2.7x10-12               1.0x10\3\               2.7x10-8
Ac-228............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Ag-105............................  Silver (47)..........  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ag-108m (b).......................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Ag-110m...........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Ag-111............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Al-26.............................  Aluminum (13)........  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Am-241............................  Americium (95).......  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7
Am-242m (b).......................  .....................  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7
Am-243 (b)........................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Ar-37.............................  Argon (18)...........  1.0x10\6\               2.7x10-5                1.0x10\8\               2.7x10-3
Ar-39.............................  .....................  1.0x10\7\               2.7x10-4                1.0x10\4\               2.7x10-7
Ar-41.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\9\               2.7x10-2
As-72.............................  Arsenic (33).........  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
As-73.............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
As-74.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
As-76.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
As-77.............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
At-211............................  Astatine (85)........  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Au-193............................  Gold (79)............  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Au-194............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Au-195............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Au-198............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Au-199............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ba-131............................  Barium (56)..........  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ba-133............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ba-133m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ba-140 (b)........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Be-7..............................  Beryllium (4)........  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Be-10.............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\6\               2.7x10-5
Bi-205............................  Bismuth (83).........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Bi-206............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Bi-207............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Bi-210............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Bi-210m...........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Bi-212 (b)........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Bk-247............................  Berkelium (97).......  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7
Bk-249............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Br-76.............................  Bromine (35).........  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Br-77.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Br-82.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
C-11..............................  Carbon (6)...........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
C-14..............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Ca-41.............................  Calcium (20).........  1.0x10\5\               2.7x10-6                1.0x10\7\               2.7x10-4
Ca-45.............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Ca-47.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Cd-109............................  Cadmium (48).........  1.0x10\4\               2.7x10-7                1.0x10\6\               2.7x10-5
Cd-113m...........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Cd-115............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Cd-115m...........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Ce-139............................  Cerium (58)..........  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ce-141............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Ce-143............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ce-144 (b)........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Cf-248............................  Californium (98).....  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Cf-249............................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Cf-250............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Cf-251............................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Cf-252............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Cf-253............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Cf-254............................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Cl-36.............................  Chlorine (17)........  1.0x10\4\               2.7x10-7                1.0x10\6\               2.7x10-5
Cl-38.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Cm-240............................  Curium (96)..........  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Cm-241............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Cm-242............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Cm-243............................  .....................  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7

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Cm-244............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Cm-245............................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Cm-246............................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Cm-247............................  .....................  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7
Cm-248............................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Co-55.............................  Cobalt (27)..........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Co-56.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Co-57.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Co-58.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Co-58m............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Co-60.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Cr-51.............................  Chromium (24)........  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Cs-129............................  Cesium (55)..........  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Cs-131............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Cs-132............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Cs-134............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Cs-134m...........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\5\               2.7x10-6
Cs-135............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Cs-136............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Cs-137 (b)........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Cu-64.............................  Copper (29)..........  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Cu-67.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Dy-159............................  Dysprosium (66)......  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Dy-165............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Dy-166............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Er-169............................  Erbium (68)..........  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Er-171............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Eu-147............................  Europium (63)........  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Eu-148............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Eu-149............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Eu-150 (short lived)..............  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Eu-150 (long lived)...............  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Eu-152............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Eu-152m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Eu-154............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Eu-155............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Eu-156............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
F-18..............................  Fluorine (9).........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Fe-52.............................  Iron (26)............  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Fe-55.............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\6\               2.7x10-5
Fe-59.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Fe-60.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Ga-67.............................  Gallium (31).........  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ga-68.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Ga-72.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Gd-146............................  Gadolinium (64)......  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Gd-148............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Gd-153............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Gd-159............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Ge-68.............................  Germanium (32).......  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Ge-71.............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\8\               2.7x10-3
Ge-77.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Hf-172............................  Hafnium (72).........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Hf-175............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Hf-181............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Hf-182............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Hg-194............................  Mercury (80).........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Hg-195m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Hg-197............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Hg-197m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Hg-203............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Ho-166............................  Holmium (67).........  1.0x10\3\               2.7x10-8                1.0x10\5\               2.7x10-6
Ho-166m...........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
I-123.............................  Iodine (53)..........  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
I-124.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
I-125.............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5

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I-126.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
I-129.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
I-131.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
I-132.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
I-133.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
I-134.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
I-135.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
In-111............................  Indium (49)..........  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
In-113m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
In-114m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
In-115m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ir-189............................  Iridium (77).........  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Ir-190............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Ir-192............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Ir-194............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
K-40..............................  Potassium (19).......  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
K-42..............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
K-43..............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Kr-81.............................  Krypton (36).........  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Kr-85.............................  .....................  1.0x10\5\               2.7x10-6                1.0x10\4\               2.7x10-7
Kr-85m............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\10\              2.7x10-1
Kr-87.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\9\               2.7x10-2
La-137............................  Lanthanum (57).......  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
La-140............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Lu-172............................  Lutetium (71)........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Lu-173............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Lu-174............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Lu-174m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Lu-177............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Mg-28.............................  Magnesium (12).......  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Mn-52.............................  Manganese (25).......  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Mn-53.............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\9\               2.7x10-2
Mn-54.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Mn-56.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Mo-93.............................  Molybdenum (42)......  1.0x10\3\               2.7x10-8                1.0x10\8\               2.7x10-3
Mo-99.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
N-13..............................  Nitrogen (7).........  1.0x10\2\               2.7x10-9                1.0x10\9\               2.7x10-2
Na-22.............................  Sodium (11)..........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Na-24.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Nb-93m............................  Niobium (41).........  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Nb-94.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Nb-95.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Nb-97.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Nd-147............................  Neodymium (60).......  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Nd-149............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ni-59.............................  Nickel (28)..........  1.0x10\4\               2.7x10-7                1.0x10\8\               2.7x10-3
Ni-63.............................  .....................  1.0x10\5\               2.7x10-6                1.0x10\8\               2.7x10-3
Ni-65.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Np-235............................  Neptunium (93).......  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Np-236 (short-lived)..............  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Np-236 (long-lived)...............  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Np-237 (b)........................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Np-239............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Os-185............................  Osmium (76)..........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Os-191............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Os-191m...........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Os-193............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Os-194............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
P-32..............................  Phosphorus (15)......  1.0x10\3\               2.7x10-8                1.0x10\5\               2.7x10-6
P-33..............................  .....................  1.0x10\5\               2.7x10-6                1.0x10\8\               2.7x10-3
Pa-230............................  Protactinium (91)....  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Pa-231............................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Pa-233............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Pb-201............................  Lead (82)............  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Pb-202............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Pb-203............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5

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Pb-205............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Pb-210 (b)........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Pb-212 (b)........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Pd-103............................  Palladium (46).......  1.0x10\3\               2.7x10-8                1.0x10\8\               2.7x10-3
Pd-107............................  .....................  1.0x10\5\               2.7x10-6                1.0x10\8\               2.7x10-3
Pd-109............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Pm-143............................  Promethium (61)......  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Pm-144............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Pm-145............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Pm-147............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Pm-148m...........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Pm-149............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Pm-151............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Po-210............................  Polonium (84)........  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Pr-142............................  Praseodymium (59)....  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Pr-143............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\6\               2.7x10-5
Pt-188............................  Platinum (78)........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Pt-191............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Pt-193............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Pt-193m...........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Pt-195m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Pt-197............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Pt-197m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Pu-236............................  Plutonium (94).......  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Pu-237............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Pu-238............................  .....................  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7
Pu-239............................  .....................  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7
Pu-240............................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Pu-241............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Pu-242............................  .....................  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7
Pu-244............................  .....................  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7
Ra-223 (b)........................  Radium (88)..........  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Ra-224 (b)........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Ra-225............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Ra-226 (b)........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Ra-228 (b)........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Rb-81.............................  Rubidium (37)........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Rb-83.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Rb-84.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Rb-86.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Rb-87.............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Rb(nat)...........................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Re-184............................  Rhenium (75).........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Re-184m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Re-186............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Re-187............................  .....................  1.0x10\6\               2.7x10-5                1.0x10\9\               2.7x10-2
Re-188............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Re-189............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Re(nat)...........................  .....................  1.0x10\6\               2.7x10-5                1.0x10\9\               2.7x10-2
Rh-99.............................  Rhodium (45).........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Rh-101............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Rh-102............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Rh-102m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Rh-103m...........................  .....................  1.0x10\4\               2.7x10-7                1.0x10\8\               2.7x10-3
Rh-105............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Rn-222 (b)........................  Radon (86)...........  1.0x10\1\               2.7x10-10               1.0x10\8\               2.7x10-3
Ru-97.............................  Ruthenium (44).......  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Ru-103............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Ru-105............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Ru-106 (b)........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
S-35..............................  Sulphur (16).........  1.0x10\5\               2.7x10-6                1.0x10\8\               2.7x10-3
Sb-122............................  Antimony (51)........  1.0x10\2\               2.7x10-9                1.0x10\4\               2.7x10-7
Sb-124............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Sb-125............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Sb-126............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Sc-44.............................  Scandium (21)........  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Sc-46.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Sc-47.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5

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Sc-48.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Se-75.............................  Selenium (34)........  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Se-79.............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Si-31.............................  Silicon (14).........  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Si-32.............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Sm-145............................  Samarium (62)........  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Sm-147............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Sm-151............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\8\               2.7x10-3
Sm-153............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Sn-113............................  Tin (50).............  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Sn-117m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Sn-119m...........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Sn-121m...........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Sn-123............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Sn-125............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Sn-126............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Sr-82.............................  Strontium (38).......  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Sr-85.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Sr-85m............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Sr-87m............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Sr-89.............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Sr-90 (b).........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\4\               2.7x10-7
Sr-91.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Sr-92.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
T(H-3)............................  Tritium (1)..........  1.0x10\6\               2.7x10-5                1.0x10\9\               2.7x10-2
Ta-178 (long-lived)...............  Tantalum (73)........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Ta-179............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Ta-182............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Tb-157............................  Terbium (65).........  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Tb-158............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Tb-160............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Tc-95m............................  Technetium (43)......  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Tc-96.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Tc-96m............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Tc-97.............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\8\               2.7x10-3
Tc-97m............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Tc-98.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Tc-99.............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
Tc-99m............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Te-121............................  Tellurium (52).......  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Te-121m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Te-123m...........................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Te-125m...........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Te-127............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Te-127m...........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Te-129............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Te-129m...........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Te-131m...........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Te-132............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Th-227............................  Thorium (90).........  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Th-228 (b)........................  .....................  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7
Th-229 (b)........................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Th-230............................  .....................  1.0                     2.7x10-11               1.0x10\4\               2.7x10-7
Th-231............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Th-232............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
Th-234 (b)........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\5\               2.7x10-6
Th (nat) (b)......................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
Ti-44.............................  Titanium (22)........  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
Tl-200............................  Thallium (81)........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Tl-201............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Tl-202............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Tl-204............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\4\               2.7x10-7
Tm-167............................  Thulium (69).........  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Tm-170............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Tm-171............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\8\               2.7x10-3
U-230 (fast lung absorption)        Uranium (92).........  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
 (b),(d).

[[Page 379]]

 
U-230 (medium lung absorption) (e)  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
U-230 (slow lung absorption) (f)..  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
U-232 (fast lung absorption)        .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
 (b),(d).
U-232 (medium lung absorption) (e)  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
U-232 (slow lung absorption) (f)..  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
U-233 (fast lung absorption) (d)..  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
U-233 (medium lung absorption) (e)  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
U-233 (slow lung absorption) (f)..  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
U-234 (fast lung absorption) (d)..  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
U-234 (medium lung absorption) (e)  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
U-234 (slow lung absorption) (f)..  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
U-235 (all lung absorption types)   .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
 (b),(d),(e),(f).
U-236 (fast lung absorption) (d)..  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
U-236 (medium lung absorption) (e)  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
U-236 (slow lung absorption) (f)..  .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
U-238 (all lung absorption types)   .....................  1.0x10\1\               2.7x10-10               1.0x10\4\               2.7x10-7
 (b),(d),(e),(f).
U (nat) (b).......................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
U (enriched to 20% or less)(g)....  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
U (dep)...........................  .....................  1.0                     2.7x10-11               1.0x10\3\               2.7x10-8
V-48..............................  Vanadium (23)........  1.0x10\1\               2.7x10-10               1.0x10\5\               2.7x10-6
V-49..............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
W-178.............................  Tungsten (74)........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
W-181.............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
W-185.............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\7\               2.7x10-4
W-187.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
W-188.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Xe-122............................  Xenon (54)...........  1.0x10\2\               2.7x10-9                1.0x10\9\               2.7x10-2
Xe-123............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\9\               2.7x10-2
Xe-127............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\5\               2.7x10-6
Xe-131m...........................  .....................  1.0x10\4\               2.7x10-7                1.0x10\4\               2.7x10-7
Xe-133............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\4\               2.7x10-7
Xe-135............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\10\              2.7x10-1

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Y-87..............................  Yttrium (39).........  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Y-88..............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Y-90..............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\5\               2.7x10-6
Y-91..............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\6\               2.7x10-5
Y-91m.............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Y-92..............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Y-93..............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\5\               2.7x10-6
Yb-169............................  Ytterbium (70).......  1.0x10\2\               2.7x10-9                1.0x10\7\               2.7x10-4
Yb-175............................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Zn-65.............................  Zinc (30)............  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Zn-69.............................  .....................  1.0x10\4\               2.7x10-7                1.0x10\6\               2.7x10-5
Zn-69m............................  .....................  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Zr-88.............................  Zirconium (40).......  1.0x10\2\               2.7x10-9                1.0x10\6\               2.7x10-5
Zr-93 (b).........................  .....................  1.0x10\3\               2.7x10-8                1.0x10\7\               2.7x10-4
Zr-95.............................  .....................  1.0x10\1\               2.7x10-10               1.0x10\6\               2.7x10-5
Zr-97 (b).........................  .....................  1.0x10\1\               2.7x10-10               1.0x10\5\               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-134 La-134
 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-220 Po-216
 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-226 Ra-222, Rn-218, Po-214
 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
 U-240 Np-240m
 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.


[[Page 381]]


                                                         Table A-3--General Values for A1 and A2
--------------------------------------------------------------------------------------------------------------------------------------------------------
                                             A1                             A2                  Activity       Activity        Activity       Activity
                              -------------------------------------------------------------- concentration   concentration    limits for     limits for
           Contents                                                                            for exempt     for exempt        exempt         exempt
                                    (TBq)           (Ci)           (TBq)           (Ci)      material  (Bq/ material  (Ci/   consignments   consignments
                                                                                                   g)             g)             (Bq)           (Ci)
--------------------------------------------------------------------------------------------------------------------------------------------------------
Only beta or gamma emitting    1 x 10-1        2.7 x 10\0\     2 x 10-2       5.4 x 10-1     1 x 10\1\      2.7 x 10-10     1 x 10\4\      2.7 x 10-7
 radionuclides are known to
 be present.
Only alpha emitting            2 x 10-1        5.4 x 10\0\     9 x 10-5       2.4 x 10-3     1 x 10-1       2.7 x 10-12     1 x 10\3\      2.7 x 10-8
 radionuclides are known to
 be present.
No relevant data are           1 x 10-3        2.7 x 10-2      9 x 10-5       2.4 x 10-3     1 x 10-1       2.7 x 10-12     1 x 10\3\      2.7 x 10-8
 available.
--------------------------------------------------------------------------------------------------------------------------------------------------------


[[Page 382]]


           Table A-4--Activity-mass Relationships for Uranium
------------------------------------------------------------------------
                                             Specific Activity
Uranium Enrichment \1\ wt % U-235 --------------------------------------
             present                      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.


[69 FR 3800, Jan. 26, 2004; 69 FR 58039, Sept. 29, 2004]