TITLE 32: ENERGY
CHAPTER II: DEPARTMENT OF NUCLEAR SAFETY
SUBCHAPTER b: RADIATION PROTECTION
PART 341
TRANSPORTATION OF RADIOACTIVE MATERIAL
Section
341.10 Purpose and Scope
341.20 Definitions
341.30 Requirement for License
341.40 Exemptions
341.50 Transportation of Licensed Material
341.60 General Licenses for Carriers
341.70 General License: Approved Packages
341.80 Previously Approved Type B Packages
341.90 General License: DOT Specification Container
341.100 General License: Use of Foreign Approved Package
341.110 General License: Type A, Fissile Class II Packages
341.120 General License: Restricted, Fissile Class II Package
341.130 Fissile Material: Assumptions as to Unknown Properties
341.140 Preliminary Determinations
341.150 Routine Determinations
341.160 Air Transport of Plutonium
341.170 Records
341.180 Reports
341.190 Advance Notification of Transport of Nuclear Waste
341.200 Quality Assurance Requirements
APPENDIX A DETERMINATION OF A1 AND A2
TABLE A A1 and A2 VALUES FOR RADIONUCLIDES
TABLE B RELATIONSHIP BETWEEN A1 AND E max FOR BETA EMITTERS
TABLE C RELATIONSHIP BETWEEN A3 AND THE ATOMIC NUMBER OF THE
RADIONUCLIDE
TABLE D ACTIVITY-MASS RELATIONSHIPS FOR URANIUM/THORIUM
AUTHORITY: Implementing and authorized by the Radiation Protection Act (Ill.
Rev. Stat. 1986 Supp., ch. 111�, pars. 211 et seq.), and Section 9 of the
Illinois Low-Level Radioactive Waste Management Act (Ill. Rev. Stat. 1986
Supp., ch. 111�, par. 241-9), and by Section 71 of The Civil Administrative
Code of Illinois (Ill. Rev. Stat. 1986 Supp., ch. 127, par. 63b17G).
SOURCE: Adopted at 10 Ill. Reg. 17616, effective September 25, 1986; amended
at 11 Ill. Reg. 5219, effective March 13, 1987; amended at 12 Ill. Reg. 2434,
effective January 15, 1988.
Section 341.10 Purpose and Scope
The regulations in this Part establish requirements for packaging, preparation
for shipment, and transportation of radioactive material and apply to any
person who transports radioactive material or delivers radioactive material to
a carrier for transport.
Section 341.20 Definitions
As used in this Part, the following definitions apply:
"A(1)" means the maximum activity of special form radioactive
material permitted in a Type A package.
"A(2)" means the maximum activity of radioactive material, other
than special form radioactive material, permitted in a Type A
package.
AGENCY NOTE: These values are either listed in Appendix A, Table
A, or may be derived in accordance with the procedure 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.
"Exclusive use" (also referred to in regulations of the U.S.
Department of Transportation as "sole use" or "full load") means
the sole use of a conveyance by a single consignor and for which
all initial, intermediate, and final loading and unloading are
carried out in accordance with the direction of the consignor or
consignee.
"Fissile material" means any special nuclear material* consisting
of or containing one or more fissile radionuclides. Fissile
radionuclides are plutonium-238, plutonium-239, plutonium-241,
uranium-233, and uranium-235. Neither natural nor depleted
uranium is fissile material.
*AGENCY NOTE: Department of Nuclear Safety (Department)
jurisdiction extends to special nuclear material only if
quantities are not sufficient to form a critical mass as defined
in 32 Ill. Adm. Code 310.
Fissile Class I: A package which may be transported in
unlimited numbers and in any arrangement, and which requires
no nuclear criticality safety controls during
transportation.
Fissile Class II: A package which may be transported
together with other packages in any arrangement but, for
criticality control, in numbers which do not exceed an
aggregate transport index* of 50. These shipments require
no other nuclear criticality safety control during
transportation. Individual packages may have a transport
index not less than 0.1 and not more than 10.
*AGENCY NOTE: A transport index is not assigned for
purposes of nuclear criticality safety but may be required
because of external radiation levels.
"Low specific activity material" means any of the following:
Uranium or thorium ores and physical or chemical
concentrates of those ores;
Unirradiated natural or depleted uranium or unirradiated
natural thorium;
Tritium oxide in aqueous solutions provided the
concentration does not exceed 5.0 millicuries (185 MBq) per
milliliter;
Material in which the radioactivity is essentially uniformly
distributed and in which the estimated average concentration
per gram of contents does not exceed:
0.0001 millicurie (3.7 kBq) of radionuclides for which
the A2 quantity in Appendix A of this Part is not more
than 0.05 curie (1.85 GBq);
0.005 millicurie (185 kBq) of radionuclides for which
the A2 quantity in Appendix A of this Part is more
than 0.05 curie (1.85 GBq), but not more than 1 curie
(37 GBq); or
0.3 millicurie (11.1 MBq) of radionuclides for which
the A2 quantity in Appendix A of this Part is more
than 1 curie (37 GBq).
Objects of non-radioactive material externally contaminated
with radioactive material, provided that the radioactive
material is not readily dispersible and the surface
contamination, when averaged over an area of 1 square meter,
does not exceed 0.0001 millicurie (220,000 transformations
per minute) (3.7 kBq) per square centimeter of radionuclides
for which the A2 quantity in Appendix A of this Part is not
more than 0.05 curie (1.85 GBq), or 0.001 millicurie
(2,200,000 disintegrations per minute) (37 kBq) per square
centimeter for other radionuclides.
"Normal form radioactive material" means radioactive material
which has not been demonstrated to qualify as "special form
radioactive material."
"Package" means the packaging together with its radioactive
contents as presented for transport.
"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.
"Regulations of the U.S. Department of Transportation (U.S. DOT)"
means the regulations in 49 CFR 100-189, revised as of October 1,
1986, exclusive of subsequent amendments or editions. A copy of
49 CFR 100-189 is available for public inspection at the
Department of Nuclear Safety.
"Special form radioactive material" means radioactive material
which satisfies the following conditions:
It is either a single solid piece or is contained in a
sealed capsule that can be opened only by destroying the
capsule;
The piece or capsule has at least one dimension not less
than 5 millimeters (0.197 inch); and
All special form radioactive material must meet the
requirements of the U.S. Nuclear Regulatory Commission (NRC)
regulations 10 CFR 71.75 and 71.77, revised as of January 1,
1987, exclusive of subsequent amendments or editions, except
that special form radioactive material designed or
constructed prior to July 1, 1985 need only meet the
requirements of 10 CFR 71.75 and 71.77 in effect on June 30,
1983. A copy of 10 CFR 71 is available for public
inspection at the Department of Nuclear Safety.
"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.
"Transport index" means the dimensionless number (rounded up to
the decimal place) 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 expressing the
maximum radiation level in millirem per hour at 1 meter from the
external surface of the package.
"Type A quantity" means a quantity of radioactive material, the
aggregate radioactivity of which does not exceed A1 for special
form radioactive material or A2 for normal form radioactive
material, where A1 and A2 are given in Appendix A of this Part or
may be determined by procedures described in Appendix A of this
Part.
"Type B package" means a Type B packaging together with its radio-
active contents. A Type B package design is designated as B(U) or
B(M). B(U) refers to the need for unilateral approval of interna-
tional shipments; B(M) refers to the need for multilateral
approval. 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 173. A Type B package approved prior to
September 6, 1983, was designated only as Type B. Limitations on
its use are specified in Section 341.80.
"Type B packaging" means a packaging designed to retain the
integrity of containment and shielding required by U.S. NRC
regulations when subjected to the normal conditions of transport
and hypothetical accident test conditions set forth in 10 CFR 71,
revised as of January 1, 1987, exclusive of subsequent amendments
or editions. A copy of 10 CFR 71 is available for public
inspection at the Department of Nuclear Safety.
"Type B quantity" means a quantity of radioactive material greater
than a Type A quantity.
(Source: Amended at 12 Ill. Reg. 2434, effective January 15, 1988)
Section 341.30 Requirement for License
No person shall transport radioactive material or deliver radioactive material
to a carrier for transport except as authorized in a general or specific
license issued by the Department or as exempted in Section 341.40.
Section 341.40 Exemptions
a) Common and contract carriers, freight forwarders, and warehousemen
who are subject to the requirements of the U.S. DOT in 49 CFR 170
through 189 or the U.S. Postal Service in the Postal Service Manual
(Domestic Mail Manual), Section 124.3 incorporated by reference, 39
CFR 111.1 (1984), are exempt from 32 Ill. Adm. Code 310, 320, 330,
340, 350, 400 and this Part to the extent that they transport or
store radioactive material in the regular course of their carriage
for another or storage incident thereto. Common and contract
carriers who are not subject to the requirements of the U.S. DOT or
U.S. Postal Service are subject to Section 341.30 and other
applicable sections of this Part.
b) Any licensee is exempt from the requirements of this Part to the
extent that the licensee delivers to a carrier for transport a
package containing radioactive material having a specific activity
not greater than 0.002 microcurie (74 Bq) per gram.
c) A licensee is exempt from all requirements of this Part, other than
Sections 341.50 and 341.160 with respect to shipment or carriage of
the following:
1) Packages containing no more than Type A quantities of
radioactive material if the package contains no fissile
material; or
2) Packages, transported between locations within the United
States, which contain only americium or plutonium in special
form with an aggregate radioactivity not to exceed 20 curies.
Section 341.50 Transportation of Licensed Material
a) No licensee may transport licensed material outside the confines of
his plant or other place of use or deliver licensed material to a
carrier for transport unless:
1) such transport and delivery is in compliance with the
regulations of the U.S. DOT, 49 CFR revised as of October 1,
1986, exclusive of subsequent amendments or editions, and;
2) any special instructions needed to safely open the package
have been made available to the consignee.
b) If, for any reason, the regulations of the U.S. DOT are not
applicable to a shipment of licensed material, the licensee shall
conform to the standards and requirements of those regulations to
the same extent as if the shipment were subject to the regulations.
(Source: Amended at 12 Ill. Reg. 2434, effective January 15, 1988)
Section 341.60 General Licenses for Carriers
a) A general license is hereby issued to any common or contract
carrier not exempt under Section 341.40 to receive, possess,
transport, and store radioactive material in the regular course of
its carriage for another or storage incident thereto, provided the
transportation and storage is in accordance with U.S. DOT
regulations (49 CFR 171 through 178, revised as of November 1,
1984, exclusive of subsequent amendments or editions), insofar as
such requirements relate to the loading and storage of packages,
placarding of the transporting vehicle, and incident reporting.*
Copies of 49 CFR 171 through 178 are available for inspection at
the Department of Nuclear Safety.
b) A general license is hereby issued to any private carrier to
transport radioactive material, provided the transportation is in
accordance with U.S. DOT regulations (49 CFR 171 through 178,
revised as of November 1, 1984, exclusive of subsequent amendments
or editions), insofar as such requirements relate to the loading
and storage of packages, placarding of the transporting vehicle,
and incident reporting.* Copies of 49 CFR 171 through 178 are
available for inspection at the Department of Nuclear Safety,
*AGENCY NOTE: Any notification of incidents referred to in those
U.S. DOT requirements shall be filed with, or made to, the
Department.
c) Persons who transport radioactive material pursuant to the general
licenses in Section 341.60(a) or 341.60(b) are exempt from the
requirements of 32 Ill. Adm. Code 340 and 400 to the extent that
they transport radioactive material.
Section 341.70 General License: Approved Packages
a) A general license is hereby issued to any licensee of the
Department to transport, or to deliver to a carrier for transport,
licensed material in a package for which a license, certificate of
compliance, or other approval has been issued by the U.S. Nuclear
Regulatory Commission.
b) This general license applies only to a licensee who:
1) Has a copy of the specific license, certificate of compliance,
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 prior to shipment;
2) Complies with the terms and conditions of the license,
certificate, or other approval, as applicable, and the
applicable requirements of Subsections 341.70(a), (b)(1),
(b)(3), (b)(4), (c), (d) and Sections 341.50, 341.140,
341.150, 341.170, 341.180, 341.190 and 341.200;
3) Prior to the licensee's first use of the package, has
registered with the U.S. Nuclear Regulatory Commission; and
4) Has a quality assurance program as required by Section 341.200
approved by the Department.
c) The general license in Subparagraph (a) applies only when the
package approval authorizes use of the package under this general
license.
d) For previously approved Type B packages which are not designated as
either B(U) or B(M) in the NRC Certificate of Compliance, this
general license is subject to additional restrictions of Section
341.80.
Section 341.80 Previously Approved Type B Packages
A Type B package previously approved by the NRC, but not designated as B(U) or
B(M) in the NRC Certificate of Compliance, may be used under the general
license of Section 341.70 with the following additional limitations:
a) Fabrication of the packaging was satisfactorily completed before
August 31, 1986, as demonstrated by application of its model number
in accordance with U.S. NRC regulations 10 CFR 71, Subparts E, F,
G, and H, revised as of January 1, 1985, exclusive of subsequent
amendments or editions. A copy of 10 CFR 71 is available for
public inspection at the Department of Nuclear Safety; and
b) The package may not be used for a shipment to a location outside
the United States after August 31, 1986, except under special
arrangement approved by the U.S. DOT in accordance with 49 CFR
173.471, revised as of November 1, 1984, exclusive of subsequent
amendments or editions. A copy of 49 CFR 173 is available for
public inspection at the Department of Nuclear Safety.
Section 341.90 General License: DOT Specification Container
a) A general license is issued to any licensee of the Department to
transport or to deliver to a carrier for transport licensed
material in a specification container for a Type B quantity of
radioactive material as specified in the regulations of the U.S.
DOT in 49 CFR 173 and 178, revised as of November 1, 1984,
exclusive of subsequent amendments or editions. Copies of 49 CFR
173 and 178 are available for public inspection at the Department
of Nuclear Safety.
b) This general license applies only to a licensee who has a quality
assurance program approved by the Department as satisfying the
provisions of Section 341.200.
c) This general license applies only to a licensee who:
1) Has a copy of the specifications in accordance with 49 CFR
178; and
2) Complies with the terms and conditions of the specifications
in accordance with 49 CFR 178 and the requirements of this
Part.
d) The general license in subsection (a) is subject to the limitation
that the specification container may not be used for a shipment to
a location outside the United States after August 31, 1986, except
under special arrangements approved by U.S. DOT in accordance with
49 CFR 173.472, revised as of November 1, 1984, exclusive of
subsequent amendments or editions. A copy of 49 CFR 173 is
available for public inspection at the Department of Nuclear
Safety.
Section 341.100 General License: Use of Foreign Approved Package
a) A general license is issued to any licensee of the Department to
transport or to deliver to a carrier for transport licensed
material in a package the design of which has been approved in a
foreign national competent authority certificate which has been
revalidated by the U.S. DOT as meeting the applicable requirements
of 49 CFR 171.12, revised as of November 1, 1984, exclusive of
subsequent amendments or editions.
b) This general license applies only to shipments made to or from
locations outside the United States.
c) This general license applies only to a licensee who:
1) Has a copy of the certificate, the revalidation, and the
drawings and other documents referenced in the certificate
relating to the use and maintenance of the packaging and to
the actions to be taken prior to shipment; and
2) Complies with the terms and conditions of the certificate and
revalidation and with the requirements of this Part.
Section 341.110 General License: Type A, Fissile Class II Packages
a) A general license is hereby issued to any licensee to transport
fissile material, or to deliver fissile material to a carrier for
transport, if the material is shipped as a Fissile Class II
package.
b) This general license applies only when a package contains no more
than a Type A quantity of radioactive material, including only one
of the following:
1) Up to 40 grams of uranium-235; or
2) Up to 30 grams of uranium-233; or
3) Up to 25 grams of the fissile radionuclides of plutonium,
except that for encapsulated plutonium-beryllium neutron
sources in special form, an A1 quantity of plutonium may be
present; or
4) A combination of fissile radionuclides in which the sum of the
ratios of the amount of each radionuclide to the corresponding
maximum amounts in Section 341.110(b)(1), (2), and (3) does
not exceed unity.
c) This general license applies only when:
1) A package containing more than 15 grams of fissile
radionuclides is labeled with a transport index not less than
the number given by the following equation, where the package
contains x grams of uranium-235, y grams of uranium-233, and z
grams of the fissile radionuclides of plutonium:
minimum transport index =
(0.4x + 0.67y + z)(1- 15 )
x+y+z
The transport index must be rounded up to one decimal place,
and may not exceed 10.0; or
2) For a package in which the only fissile material is in the
form of encapsulated plutonium-beryllium neutron sources in
special form, the transport index based on criticality
considerations shall be taken as 0.026 times the number of
grams of the fissile radionuclides of plutonium in excess of
15 grams. The transport index must be rounded up to one
decimal place, and shall not exceed 10.0.
Section 341.120 General License: Restricted, Fissile Class II Package
a) A general license is hereby issued to any licensee to transport
fissile material, or to deliver fissile material to a carrier for
transport, if the material is shipped as a Fissile Class II
package.
b) This general license applies only when:
1) The package contains no more than a Type A quantity of
radioactive material; and
2) Neither beryllium nor hydrogenous material enriched in
deuterium is present; and
3) The total mass of graphite present does not exceed 150 times
the total mass of uranium-235 plus plutonium; and
4) Substances having a higher hydrogen density than water, e.g.
certain hydrocarbon oils, are not present, except that
polyethylene may be used for packing or wrapping; and
5) Uranium-233 is not present, and the amount of plutonium does
not exceed 1% of the amount of uranium-235; and
6) The amount of uranium-235 is limited as follows:
A) If the fissile radionuclides are not uniformly
distributed, the maximum amount of uranium-235 per
package may not exceed the value given as follows:
Uranium enrichment in Permissible maximum
weight percent of grams of uranium-235
uranium-235 per package
not exceeding
*AGENCY NOTE: Pursuant to its agreement with the U.S. Nuclear
Regulatory Commission, Department jurisdiction extends only to
350 grams of uranium-235.
B) If the fissile radionuclides are distributed uniformly (i.e.,
cannot form a lattice arrangement within the packaging) the
maximum amount of uranium-235 per package may not exceed the
value given as follows:
Uranium enrichment Permissible maximum
in weight percent of grams of uranium-235
uranium-235 not per package
exceeding
*AGENCY NOTE: Pursuant to its agreement with the U.S.
Nuclear Regulatory Commission, Department jurisdiction
extends only to 350 grams of uranium-235.
7) The transport index of each package based on criticality
considerations is taken as ten (10) times the number of
grams of uranium-235 in the package divided by the maximum
allowable number of grams per package in accordance with
Subsection (b)(6)(A) or (b)(6)(B) above as applicable.
Section 341.130 Fissile Material: 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
nuclear reactivity.
Section 341.140 Preliminary Determinations
Prior to the first use of any packaging for the shipment of radioactive
material:
a) The licensee shall ascertain that there are no defects in the
packaging which could impact on compliance with the standards
specified in 10 CFR 71, Subparts (E) and (F), revised as of January
1985, exclusive of subsequent amendments or editions;
b) Where the maximum normal operating pressure will exceed 34.3
kilopascal (5 psi) gauge, the licensee shall test the containment
system at an internal pressure at least 50% higher than the maximum
normal operating pressure to verify the capability of that system
to maintain its structural integrity at that pressure.
c) The licensee shall conspicuously and durably mark the packaging
with its model number, gross weight, and a package identification
number assigned by the U.S. Nuclear Regulatory Commission. Prior
to applying the model number, the licensee shall determine that the
packaging has been fabricated in accordance with the design
approved in the certificate of compliance issued by the U.S.
Nuclear Regulatory Commission.
Section 341.150 Routine Determinations
Prior to each shipment of licensed material, the licensee shall ensure that
the package with its contents satisfies the requirements of this Part and of
the license. The licensee shall determine that:
a) The package is proper for the contents to be shipped in accordance
with 49 CFR 173.401 through 173.435;
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 sealed and has space or other
specified provision for expansion of the liquid in accordance with
10 CFR 71, Subpart F, revised as of January 1985, exclusive of
subsequent amendments or editions;
e) Any pressure relief device is operable and set in accordance with
the certificate of compliance;
f) The package has been loaded and closed in accordance with written
procedures;
g) Any structural part of the package which could be used to lift or
tie down the package during transport is rendered inoperable for
that purpose unless it satisfies design requirements specified in
accordance with 10 CFR 71.45, revised as of January 1985, exclusive
of subsequent amendments or editions;
h) The package meets the following requirements for removable
contamination:
1) The level of non-fixed (removable) radioactive contamination
on the external surfaces of each package offered for shipment
is as low as reasonably achievable. The level of non-fixed
radioactive contamination may be determined by wiping an area
of 300 square centimeters of the surface concerned with an
absorbent material, using moderate pressure, and measuring the
activity on the wiping material. Sufficient measurements must
be taken in the most appropriate locations to yield a
representative assessment of the non-fixed contamination
levels.* Except as provided under Section 341.150(h) (2), the
amount of radioactivity measured on any single wiping material
when averaged over the surface wiped, must not exceed the
limits given in Subsection (h)(1) of this Part at any time
during transport. Other methods of assessment of equal or
greater efficiency may be used. When other methods are used,
the detection efficiency of the method used must be taken into
account and in no case may the non-fixed contamination on the
external surfaces of the package exceed ten (10) times the
limits listed as follows:
Beta-gamma emitting
radionuclides; all radio-
nuclides with half-lives
less than ten (10) days;
natural uranium; natural
thorium; uranium-235;
uranium-238; thorium-232;
thorium-228; and thorium-230
when contained in ores or
physical concentrates......... 10-5 22
All other alpha emitting
radionuclides............ 10-6 2.2
2) In the case of packages transported as exclusive use
shipments by rail or highway only, the non-fixed radioactive
contamination at any time during transport must not exceed
ten (10) times the levels prescribed in Section 341.150(h)
(1). The levels at the beginning of transport must not
exceed the levels prescribed in Section 341.150(h)(1);
*AGENCY NOTE: One generally acceptable technique is to
perform one wipe test per square meter of surface area of
the package. Appropriate locations for wipes include the
areas where the package might leak through sealing gaskets
or a location where water might stand on the container.
i) External radiation levels around the package and around the
vehicle, if applicable, will not exceed 200 millirem per hour at
any point on the external surface of the package at any time
during transportation. The transport index shall not exceed ten
(10).
j) For a package transported as exclusive use by rail, highway, or
water, radiation levels external to the package may exceed the
limits specified in Subparagraph (i) but must not exceed any of
the following:
1) 200 millirem/hour on the accessible external surface of the
package unless the following conditions are met, in which
case the limit is 1000 millirem per hour.
A) The shipment is made in a closed transport vehicle;
B) Provisions are made to secure the package so that its
position within the vehicle remains fixed during
transportation; and
C) There are no loading or unloading operations between
the beginning and end of the transportation;
2) 200 millirem/hour at any point on the outer surface of the
vehicle, including the upper and lower surfaces, or, in the
case of an open vehicle, at any point on the vertical planes
projected from the outer edges of the vehicle, on the upper
surface of the load, and on the lower external surface of
the vehicle;
3) 10 millirem/hour at any point two meters from the vertical
planes represented by the outer lateral surfaces of the
vehicle, or, in the case of an open vehicle, at any point
two meters from the vertical planes projected from the outer
edges of the vehicle; and
4) 2 millirem/hour in any normally occupied position of the
vehicle, except that this provision does not apply to
private motor carriers when persons occupying these
positions are provided with special health supervision,
personnel radiation exposure monitoring devices, and
training in accordance with 32 Ill. Adm. Code 400.
k) A package must be prepared for transport so that in still air at
lOO�F (38�C) and in the shade, no accessible surface of a package
would have a temperature exceeding 122�F (50�C) in a nonexclusive
use shipment or 180�F (82�C) in an exclusive use shipment.
Accessible package surface temperatures shall not exceed these
limits at any time during transportation.
Section 341.160 Air Transport of Plutonium
Notwithstanding the provisions of any general licenses and notwithstanding any
exemptions stated directly in this part or included indirectly by citation of
U.S. DOT regulations, as may be applicable, the licensee shall assure that
plutonium in any form is not transported by air or delivered to a carrier for
air transport unless:
a) The plutonium is contained in a medical device designed for
individual human application; or
b) The plutonium is contained in a material in which the specific
activity is not greater than 0.002 microcuries (74 Bq) per gram of
material and in which the radioactivity is essentially uniformly
distributed; or
c) The plutonium is shipped in a single package containing no more
than an A2 quantity of plutonium in any isotope or form and is
shipped in accordance with Section 341.50; or
d) The plutonium is shipped in a package specifically authorized for
the shipment of plutonium by air in the Certificate of Compliance
for that package issued by the U.S. Nuclear Regulatory Commission.
Section 341.170 Records
a) Each licensee shall maintain for a period of two (2) years after
shipment a record of each shipment of licensed material not exempt
under Section 341.40, showing, where applicable:
1) Identification of the packaging by model number;
2) Verification that there are no defects in the packaging, as
shipped which would prevent the package from meeting the
standards of 10 CFR 71, Subparts E and F, revised as of
January 1985, exclusive of subsequent amendments or editions;
3) Volume and identification of coolant;
4) Type and quantity of licensed material in each package, and
the total quantity of each shipment;
5) Date of the shipment;
6) Name and address of the transferee;
7) Address to which the shipment was made; and
8) Results of the determinations required by Section 341.130.
b) The licensee shall make available to the Department for inspection,
at any time during shipment or upon three days notice after
shipment, all records required by this Part.
Section 341.180 Reports
The licensee shall report to the Department within 30 days:
a) Any instance in which a reduction in the effectiveness of any
authorized packaging impacts upon compliance with 10 CFR 71,
Subparts E and F, revised as of January 1985, exclusive of
subsequent amendments or editions; and
b) Details of any defects in the packaging after first use impacting
upon compliance with 10 CFR 71, Subparts E and F, with the means
employed to repair the defects and prevent their recurrence.
Section 341.190 Advance Notification of Transport of Nuclear Waste
a) Licensees who transport radioactive waste or deliver radioactive
waste to a carrier for transport outside of the confines of the
licensee's facility or other place of use or storage, must provide
advance notification of such transport to the governor, or
governor's designee* in accordance with subsection (b). Such
notification shall include the governors or governors' designees of
all states through which the radioactive waste is to be
transported.
*AGENCY NOTE: A list of the mailing addresses of the governors and
governors' designees is available upon request from the Director,
Office of State Programs, U.S. Nuclear Regulatory Commission,
Washington, D.C. 20555.
b) Advance notification is required only when:
1) The nuclear waste is required to be in Type B packaging for
transportation;
2) The nuclear waste is being transported to, through, or across
state boundaries to a disposal site or to a collection point
for transport to a disposal site;
3) The quantity of licensed material in a single package exceeds:
A) 5,000 curies (185 TBq) of special form radionuclides;
B) 5,000 curies (185 TBq) of uncompressed gases of argon-41,
krypton-85m, krypton-87, xenon-131m, or xenon-135;
C) 50,000 curies (1.85 PBq) of argon-37, or of uncompressed
gases of krypton-85 or xenon-133, or of hydrogen-3 as a
gas, as luminous paint, or adsorbed on solid material;
D) 20 curies (740 GBq) of other non-special form
radionuclides for which A2 is less than or equal to four
(4) curies (148 GBq); or
E) 200 curies (7.4 TBq) of other non-special form radionu-
clides for which A2 is greater than four (4) curies (148
GBq).
c) Each advance notification required by Section 341.190(a) shall
contain the following information:
1) The name, address, and telephone number of the shipper,
carrier, and receiver of the shipment;
2) A description of the nuclear waste contained in the shipment
as required by the regulations of the U.S. DOT, 49 CFR 172.202
and 172.203(d), revised as of November 1, 1984*;
*AGENCY NOTE: Requirements contained in subsequent amendments
or editions of 49 CFR 172 are not incorporated into this rule.
A copy of 49 CFR 172 is available for public inspection at the
Department of Nuclear Safety.
3) The point of origin of the shipment and the seven-day period
during which departure of the shipment is estimated to occur;
4) The seven-day period during which arrival of the shipment at
state boundaries is estimated to occur;
5) The destination of the shipment, and the seven-day period
during which arrival of the shipment is estimated to occur;
and
6) A point of contact, with a telephone number, for current
shipment information.
d) The notification required by Section 341.190(a) shall be made in
writing to the office of the Governor or Governor's designee and to
the Department. A notification delivered by mail must be
postmarked at least seven days before the beginning of the seven-
day period during which departure of the shipment is estimated to
occur. A notification delivered by messenger must reach the office
of the governor, or governor's designee, at least four (4) days
before the beginning of the seven-day period during which departure
of the shipment is estimated to occur. A copy of the notification
shall be retained by the licensee for one (1) year.
e) The licensee shall notify the Governor, or Governor's designee, and
the Department of any changes to schedule information provided
pursuant to Section 341.190(a). Such notification shall be by
telephone to a responsible individual in the Office of the
Governor, or Governor's designee, and in the Department. The
licensee shall maintain for one (1) year a record of the name of
the individual contacted.
f) Each licensee who cancels a nuclear waste shipment, for which
advance notification has been sent, shall send a cancellation
notice to the Governor, or Governor's designee, and to the
Department. A copy of the notice shall be retained by the licensee
for one (1) year.
Section 341.200 Quality Assurance Requirements
a) Each person licensed pursuant to this Part shall establish,
maintain, and execute a quality assurance program to verify, by
procedures such as checking, auditing, and inspection, that
deficiencies, deviations, and defective material and equipment
relating to the shipment of packages containing radioactive
materials are promptly identified and corrected. Prior to the use
of any package for the shipment of radioactive material, each
licensee shall obtain Department approval of its quality assurance
program. Such approval shall be in accordance with the U.S.
Nuclear Regulatory Commission standards contained in their
Regulatory Guide on Quality Assurance, Reg. Guide #7.10,
Establishing Quality Assurance Programs for Packaging used in the
Transport of Radioactive Material, published January, 1983,
exclusive of subsequent amendments or editions. A copy of the
Regulatory Guide is available for public inspection at the
Department of Nuclear Safety.
b) Each person licensed pursuant to this Part shall document the
quality assurance program by written procedures or instructions and
shall carry out the program in accordance with those procedures
throughout the period during which packaging is used. The licensee
shall identify the material and components to be covered by the
quality assurance program.
c) A person licensed pursuant to this Part shall maintain sufficient
written records to demonstrate compliance with the quality
assurance program. Records pertaining to the use of a package for
shipment of radioactive material must be retained for a period of
two (2) years after shipment.
(Source: Amended at 11 Ill. Reg. 5219, effective March 13, 1987)
SECTION 341. APPENDIX A DETERMINATION OF A1 and A2
a) Single radionuclides.
1) For a single radionuclide of known identity, the values of
A1 and A2 are taken from Table A-1 if listed there. The
values of A1 and A2 in Table A-1 are also applicable for
radionuclides contained in alpha neutron or gamma neutron
sources.
2) For any single radionuclide whose identity is known but
which is not listed in Table A-1, the values of A1 and A2
are determined according to the following procedure:
A) If the radionuclide emits only one type of radiation,
A1 is determined according to the rules in paragraphs
(i), (ii), (iii), and (iv) of this paragraph. For
radionuclides emitting different kinds of radiation,
A1 is the most restrictive value of those determined
for each kind of radiation. However, in both cases, A1
is restricted to a maximum of 1000 Ci (37 TBq). If a
parent nuclide decays into a shorter-lived daughter
with a half-life not greater than ten (10) days, A1 is
calculated for both the parent and the daughter, and
the more limiting of the two (2) values is assigned to
the parent nuclide.
i) For gamma emitters, A1 is determined by the
expression:
A1 = 9 curies
K
where K is the gamma-ray constant, corresponding
to the dose in R/h at 1 m per Ci; the number 9
results from the choice of 1 rem/h at a distance
of 3 m as the reference dose-equivalent rate.
ii) For X-ray emitters, A1 is determined by the
atomic number of the nuclide;
for Z less than or equal to 55, A1=1000 Ci (37
TBq)
for Z greater than 55, A1=200 Ci (7.4 TBq)
where Z is the atomic number of the nuclide.
iii) For beta emitters, A1 is determined by the
maximum beta energy (Emax) according to Table A-
2;
iv) For alpha emitters, A1 is determined by the
expression:
A1 = 1000 A3
where A3 is the value listed in Table A-3;
B) A2 is the more restrictive of the following two (2)
values:
i) The corresponding A1; and
ii) The value A3 obtained from Table A-3.
3) For any single radionuclide whose identity is unknown, the
value of A1 is taken to be 2 Ci (74 GBq) and the value of A2
is taken to be 0.002 Ci (74 MBq). However, if the atomic
number of the radionuclide is known to be less than 82, the
value of A1 is taken to be 10 Ci (370 GBq) and the value of
A2 is taken to be 0.4 Ci (14.8 GBq).
b) Mixtures of radionuclides, including radioactive decay chains.
1) For mixed fission products the following activity limits may
be assumed if a detailed analysis of the mixture is not
carried out:
A1 = 10 Ci (370 GBq)
A2 = 0.4 Ci (14.8 GBq)
2) A single radioactive decay chain is considered to be a
single radionuclide when the radionuclides are present in
their naturally occurring proportions and no daughter
nuclide has a half-life either longer than ten (10) days or
longer than that of the parent nuclide. The activity to be
taken into account and the A1 or A2 value from Table A-1 to
be applied are those corresponding to the parent nuclide of
that chain. When calculating A1 or A2 values, radiation
emitted by daughters must be considered. However, in the
case of radioactive decay chains in which any daughter
nuclide has a half-life either longer than ten (10) days or
greater than that of the parent nuclide, the parent and
daughter nuclides are considered to be mixtures of different
nuclides.
3) In the case of a mixture of different radionuclides, where
the identity and activity of each radionuclide are known,
the permissible activity of each radionuclide R1, R2...Rn is
such that F1 + F2 +...Fn is greater than unity, where
F1 = Total activity of R1
Ai(R1)
F2 = Total activity of R2
Ai(R2)
Fn = Total Activity of Rn
Ai(Rn)
Ai(R1, R2...Rn) is the value of A1 or A2 as appropriate for
the nuclide R1, R2...Rn.
4) When the identity of each radionuclide is known but the
individual activities of some of the radionuclides are not
known, the formula given in subparagraph (3) is applied to
establish the values of A1 or A2 as appropriate. All the
radionuclides whose individual activities are not known
(their total activity will, however, be known) are classed
in a single group and the most restrictive value of A1 or A2
applicable to any one of them is used as the value of A1 or
A2 in the denominator of the fraction.
5) Where the identity of each radionuclide is known but the
individual activity of none of the radionuclides is known,
the most restrictive value of A1 or A2 applicable to any one
of the radionuclides present is adopted as the applicable
value.
6) When the identity of none of the nuclides is known, the
value of A1 is taken to be 2 Ci (74 GBq) and the value of A2
is taken to be 0.002 Ci (74 MBq). However, if alpha
emitters are known to be absent, the value of A2 is taken to
be 0.4 Ci (14.8 GBq).
(Source: Amended at 12 Ill. Reg. 2434, effective January 15, 1988)
SECTION 341. TABLE A
A1 and A2 VALUES FOR RADIONUCLIDES
(See Agency Notes At End Of Table)
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
227Ac Actinium (89) 1000 0.003 7.2 x 10
228Ac 10 4 2.2 x 106
105Ag Silver (47) 40 40 3.1 x 104
110mAg 7 7 4.7 x 103
111Ag 100 20 1.6 x 105
241Am Americium (95) 8 0.008 3.2
243Am 8 0.008 1.9 x 10-1
37Ar (compressed or Argon (18) 1000 1000 1.0 x 105
uncompressed)*
41Ar (uncompressed)* 20 20 4.3 x 107
41Ar (compressed)* 1 1 4.3 x 107
73As Arsenic (33) 1000 400 2.4 x 104
74As 20 20 1.0 x 105
76As 10 10 1.6 x 106
77As 300 20 1.1 x 106
211At Astatine (85) 200 7 2.1 x 106
193Au Gold (79) 200 200 9.3 x 105
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
196Au 30 30 1.2 x 105
198Au 40 20 2.5 x 105
199Au 200 25 2.1 x 105
131Ba Barium (56) 40 40 8.7 x 104
133Ba 40 10 4.0 x 102
140Ba 20 20 7.3 x 104
7Be Beryllium (4) 300 300 3.5 x 105
206Bi Bismuth (83) 5 5 9.9 x 104
207Bi 10 10 2.2 x 102
210Bi (RaE) 100 4 1.2 x 105
212Bi 6 6 1.5 x 107
249Bk Berkelium (97) 1000 1 1.8 x 103
77Br Bromine (35) 70 25 7.1 x 105
82Br 6 6 1.1 x 106
11C Carbon (6) 20 20 8.4 x 108
14C 1000 60 4.6
45Ca Calcium (20) 1000 25 1.9 x 104
47Ca 20 20 5.9 x 105
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
109Cd Cadmium (48) 1000 70 2.6 x 103
115mCd 30 30 2.6 x 104
115Cd 80 20 5.1 x 105
139Ce Cerium (58) 100 100 6.5 x 103
141Ce 300 25 2.8 x 104
143Ce 60 20 6.6 x 105
144Ce 10 7 3.2 x 103
249Cf Californium (98) 2 0.002 3.1
250Cf 7 0.007 1.3 x 102
252Cf 2 0.009 6.5 x 102
36Cl Chlorine (17) 300 10 3.2 x 10-2
38Cl 10 10 1.3 x 108
242Cm Curium (96) 200 0.2 3.3 x 103
243Cm 9 0.009 4.2 x 10
244Cm 10 0.01 8.2 x 10
245Cm 6 0.006 1.0 x 10-1
246Cm 6 0.006 3.6 x 10-1
56Co Cobalt (27) 5 5 3.0 x 104
57Co 90 90 8.5 x 103
58mCo 1000 1000 5.9 x 106
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
58Co 20 20 3.1 x 104
60Co 7 7 1.1 x 103
51Cr Chromium (24) 600 600 9.2 x 104
129Cs Cesium (55) 40 40 7.6 x 105
131Cs 1000 1000 1.0 x 105
134mCs 1000 10 7.4 x 106
134Cs 10 10 1.2 x 103
135Cs 1000 25 8.8 x 10-4
136Cs 7 7 7.4 x 104
137Cs 30 10 9.8 x 10
64Cu Copper (29) 80 25 3.8 x 106
67Cu 200 25 7.9 x 105
165Dy Dysprosium (66) 100 20 8.2 x 106
166Dy 1000 200 2.3 x 105
169Er Erbium (68) 1000 25 8.2 x 104
171Er 50 20 2.4 x 106
152mEu Europium (63) 30 30 2.2 x 106
152Eu 20 10 1.9 x 102
154Eu 10 5 1.5 x 102
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
155Eu 400 60 1.4 x 103
18F Fluorine (9) 20 20 9.3 x 107
52Fe Iron (26) 5 5 7.3 x 106
55Fe 1000 1000 2.2 x 103
59Fe 10 10 4.9 x 104
67Ga Gallium (31) 100 100 6.0 x 105
68Ga 20 20 4.0 x 107
72Ga 7 7 3.1 x 106
153Gd Gadolinium (64) 200 100 3.6 x 103
159Gd 300 20 1.1 x 106
68Ge Germanium (32) 20 10 7.0 x 103
71Ge 1000 1000 1.6 x 105
3H Hydrogen (1) see T-Tritium
181Hf Hafnium (72) 30 25 1.6 x 104
197mHg Mercury (80) 200 200 6.6 x 105
197Hg 200 200 2.5 x 105
203Hg 80 25 1.4 x 104
166Ho Holmium (67) 30 30 6.9 x 105
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
123I Iodine (53) 50 50 1.9 x 106
125I 1000 70 1.7 x 104
126I 40 10 7.8 x 104
129I 1000 2 1.6 x 10-4
131I 40 10 1.2 x 105
132I 7 7 1.1 x 107
133I 30 30 1.1 x 106
134I 8 8 2.7 x 107
135I 10 10 3.5 x 106
111In Indium (49) 30 25 4.2 x 105
113mIn 60 60 1.6 x 107
114mIn 30 20 2.3 x 104
115mIn 100 20 6.1 x 106
190Ir Iridium (77) 10 10 6.2 x 104
192Ir 20 10 9.1 x 103
194Ir 10 10 8.5 x 105
42K Potassium (19) 10 10 6.0 x 106
43K 20 10 3.3 x 106
85mKr (uncompressed)* Krypton (36) 100 100 8.4 x 106
85mKr (compressed)* 3 3 8.4 x 106
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
85Kr (uncompressed)* 1000 1000 4.0 x 102
85Kr (compressed)* 5 5 4.0 x 102
87Kr (uncompressed)* 20 20 2.8 x 107
87Kr (compressed)* 0.6 0.6 2.8 x 107
140La Lanthanum (57) 30 30 5.6 x 105
177Lu Lutetium (71) 300 25 1.1 x 105
MFP Mixed Fission 10 0.4 --
Products
28Mg Magnesium (12) 6 6 5.2 x 106
52Mn Manganese (25) 5 5 4.4 x 105
54Mn 20 20 8.3 x 103
56Mn 5 5 2.2 x 107
99Mo Molybdenum (42) 100 20 4.7 x 105
13N Nitrogen (7) 20 10 1.5 x 109
22Na Sodium (11) 8 8 6.3 x 103
24Na 5 5 8.7 x 106
93mNb Niobium (41) 1000 200 1.1 x 103
95Nb 20 20 3.9 x 104
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
97Nb 20 20 2.6 x 107
147Nd Neodymium (60) 100 20 8.0 x 104
149Nd 30 20 1.1 x 107
59Ni Nickel (28) 1000 900 8.1 x 10-2
63Ni 1000 100 4.6 x 10
65Ni 10 10 1.9 x 107
237Np Neptunium (93) 5 0.005 6.9 x 10-4
239Np 200 25 2.3 x 105
1850s Osmium (76) 20 20 7.3 x 103
1910s 600 200 4.6 x 104
191mOs 200 200 1.2 x 106
1930s 100 20 5.3 x 105
32P Phosphorus (15) 30 30 2.9 x 105
230Pa Protactinium (91) 20 0.8 3.2 x 104
231Pa 2 0.002 4.5 x 10-2
233Pa 100 100 2.1 x 104
201Pb Lead (82) 20 20 1.7 x 106
210Pb 100 0.2 8.8 x 10
212Pb 6 5 1.4 x 106
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
103Pd Palladium (46) 1000 700 7.5 x 104
109Pd 100 20 2.1 x 106
147Pm Promethium (61) 1000 25 9.4 x 102
149Pm 100 20 4.2 x 105
210Po Polonium (84) 200 0.2 4.5 x 103
142Pr Praseodymium (59) 10 10 1.2 x 104
143Pr 300 20 6.6 x 104
191Pt Platinum (78) 100 100 2.3 x 105
193mPt 200 200 2.0 x 105
197mPt 300 20 1.2 x 107
197Pt 300 20 8.8 x 105
238Pu Plutonium (94) 3 0.003 1.7 x 10
239Pu 2 0.002 6.2 x 10-2
240Pu 2 0.002 2.3 x 10-1
241Pu 1000 0.1 1.1 x 102
242Pu 3 0.003 3.9 x 10-3
223Ra Radium (88) 50 0.2 5.0 x 104
224Ra 6 0.5 1.6 x 105
226Ra 10 0.05 1.0
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
228Ra 10 0.05 2.3 x 102
81Rb Rubidium (37) 30 25 8.2 x 106
86Rb 30 30 8.1 x 104
87Rb Unlimited Unlimited 6.6 x 10-8
Rb (natural) Unlimited Unlimited 1.8 x 10-8
186Re Rhenium (75) 100 20 1.9 x 105
187Re Unlimited Unlimited 3.8 x 10-8
188Re 10 10 1.0 x 106
Re (natural) Unlimited Unlimited 2.4 x 10-8
103mRh Rhodium (45) 1000 1000 3.2 x 107
105Rh 200 25 8.2 x 105
222Rn Radon (86) 10 2 1.5 x 105
97Ru Ruthenium (44) 80 80 5.5 x 105
103Ru 30 25 3.2 x 104
105Ru 20 20 6.6 x 106
106Ru 10 7 3.4 x 103
35S Sulfur (16) 1000 60 4.3 x 104
122Sb Antimony (51) 30 30 3.9 x 105
124Sb 5 5 1.8 x 104
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
125Sb 40 25 1.4 x 103
46Sc Scandium (21) 8 8 3.4 x 104
47Sc 200 20 8.2 x 105
48Sc 5 5 1.5 x 106
75Se Selenium (34) 40 40 1.4 x 104
31Si Silicon (14) 100 20 3.9 x 107
147Sm Samarium (62) Unlimited Unlimited 2.0 x 10-8
151Sm 1000 90 2.6 x 10
153Sm 300 20 4.4 x 105
113Sn Tin (50) 60 60 1.0 x 104
119mSn 100 100 4.4 x 103
125Sn 10 10 1.1 x 105
85mSr Strontium (38) 80 80 3.2 x 107
85Sr 30 30 2.4 x 104
87mSr 50 50 1.2 x 107
89Sr 100 10 2.9 x 104
90Sr 10 0.4 1.5 x 102
91Sr 10 10 3.6 x 106
92Sr 10 10 1.3 x 107
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
T (uncompressed)* Tritium (1) 1000 1000 9.7 x 103
T (compressed)* 1000 1000 9.7 x 103
T (activated 1000 1000 9.7 x 103
luminous paint)
T (adsorbed on 1000 1000 9.7 x 103
solid carrier)
T (tritiated water) 1000 1000 9.7 x 103
T (other forms) 20 20 9.7 x 103
182Ta Tantalum (73) 20 20 6.2 x
103
160Tb Terbium (65) 20 10 1.1 x 104
96mTc Technetium (43) 1000 1000 3.8 x 107
96Tc 6 6 3.2 x 105
97mTc 1000 200 1.5 x 104
97Tc 1000 400 1.4 x 10-3
99mTc 100 100 5.2 x 106
99Tc 1000 25 1.7 x 10-2
125mTe Tellurium (52) 1000 100 1.8 x 104
127mTe 300 20 4.0 x 104
127Te 300 20 2.6 x 106
129mTe 30 10 2.5 x 104
129Te 100 20 2.0 x 107
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
131mTe 10 10 8.0 x 105
132Te 7 7 3.1 x 105
227Th Thorium (90) 200 0.2 3.2 x 104
228Th 6 0.008 8.3 x 102
230Th 3 0.003 1.9 x 10-2
231Th 1000 25 5.3 x 105
232Th Unlimited Unlimited 1.1 x 10-7
234Th 10 10 2.3 x 104
Th (natural) Unlimited Unlimited 2.2 x 10-7
Th (irradiated)** ----- ------ ------
200Tl Thallium (81) 20 20 5.8 x 105
201Tl 200 200 2.2 x 105
202Tl 40 40 5.4 x 104
204Tl 300 10 4.3 x 102
170Tm Thulium (69) 300 10 6.0 x 103
171Tm 1000 100 1.1 x 103
230U Uranium (92) 100 0.1 2.7 x 104
232U 30 0.03 2.1 x 10
233U 100 0.1 9.5 x 10-3
234U 100 0.1 6.2 x 10-3
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
235U 100 0.2 2.1 x 10-6
236U 200 0.2 6.3 x 10-5
238U Unlimited Unlimited 3.3 x 10-7
U (natural) Unlimited Unlimited (See Table
A-4)
U (enriched) < 20% Unlimited Unlimited (See Table
A-4)
U (enriched) 100 0.1 (See Table
20% or greater A-4)
U (depleted) Unlimited Unlimited (See Table
A-4)
U (irradiated)*** ----- ----- -----
48V Vanadium (23) 6 6 1.7 x 105
181W Tungsten (74) 200 100 5.0 x 103
185W 1000 25 9.7 x 10-3
187W 40 20 7.0 x 105
127Xe (uncompressed)* Xenon (54) 70 70 2.8 x 104
127Xe (compressed)* 5 5 2.8 x 104
131mXe (compressed)* 10 10 1.0 x 105
131mXe (uncompressed)* 100 100 1.0 x 105
133Xe (uncompressed)* 1000 1000 1.9 x 105
133Xe (compressed)* 5 5 1.9 x 105
135Xe (uncompressed)* 70 70 2.5 x 105
Symbol of Element and A1(Ci) A2(Ci) Specific
Radionuclide Atomic Number Activity
(Ci/g)
135Xe (compressed)* 2 2 2.5 x 105
87Y Yttrium (39) 20 20 4.5 x 10
90Y 10 10 2.5 x 105
91mY 30 30 4.1 x 107
91Y 30 30 2.5 x 104
92Y 10 10 9.5 x 106
93Y 10 10 3.2 x 106
169Yb Ytterbium (70) 80 80 2.3 x 105
175Yb 400 25 1.8 x 105
65Zn Zinc (30) 30 30 8.0 x 103
69mZn 40 20 3.3 x 106
69Zn 300 20 5.3 x 107
93Zr Zirconium (40) 1000 200 3.5 x 10-3
95Zr 20 20 2.1 x 104
97Zr 20 20 2.0 x 106
*AGENCY NOTE: For the purpose of Table A, compressed gas means a gas at a
pressure which exceeds the ambient atmospheric pressure at the location where
the containment system was closed.
**AGENCY NOTE: The values of A1 and A2 must be calculated in accordance with
the procedure specified in Appendix A, paragraph b(3), taking into account the
activity of the fission products and of the uranium-233 in addition to that of
the thorium.
***AGENCY NOTE: The values of A1 and A2 must be calculated in accordance with
the procedure specified in Appendix A, paragraph b(3), taking into account the
activity of the fission products and plutonium isotopes in addition to that of
the uranium.
SECTION 341. TABLE B
RELATIONSHIP BETWEEN A1 AND Emax FOR BETA EMITTERS
Emax (MeV) A1 (Ci)
less than 0.5 1000
0.5 - less than 1.0 300
1.0 - less than 1.5 100
1.5 - less than 2.0 30
greater than or
equal to 2.0 10
SECTION 341. TABLE C
RELATIONSHIP BETWEEN A3 AND THE ATOMIC NUMBER
OF THE RADIONUCLIDE
A3
Atomic Half-life less Half-life 1000 days Half-life greater
Number than 1000 days to 106 years than 106 years
1 to 81 3 Ci .05 Ci 3 Ci
82 and above .002 Ci .002 Ci 3 Ci
SECTION 341. TABLE D
ACTIVITY-MASS RELATIONSHIPS FOR URANIUM/THORIUM
Thorium and Specific Activity
Uranium Enrichment*
wt % 235U present Ci/g g/Ci
0.45 5.0 x 10-7 2.0 x 106
0.72 (natural) 7.06 x 10-7 1.42 x 106
1.0 7.6 x 10-7 1.3 x 106
1.5 1.0 x 10-6 1.0 x 106
5.0 2.7 x 10-6 3.7 x 105
10.0 4.8 x 10-6 2.1 x 105
20.0 1.0 x 10-5 1.0 x 105
35.0 2.0 x 10-5 5.0 x 104
50.0 2.5 x 10-5 4.0 x 104
90.0 5.8 x 10-5 1.7 x 104
93.0 7.0 x 10-5 1.4 x 104
95.0 9.1 x 10-5 1.1 x 104
Natural Thorium 2.2 x 10-7 4.6 x 106
*The figures for uranium include representative values for the activity of the
uranium-234 which is concentrated during the enrichment process. The activity
for thorium includes the equilibrium concentration of thorium-228.
