[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.
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(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.
[[Page 330]]
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
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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\
[[Page 368]]
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\
[[Page 369]]
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\
[[Page 370]]
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\
[[Page 371]]
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\
[[Page 372]]
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
[[Page 373]]
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
[[Page 375]]
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
[[Page 376]]
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
[[Page 380]]
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]