| (A) A general license is issued to any licensee of
the agency to transport, or to deliver to a carrier for transport,
radioactive 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 NRC as satisfying
the provisions of Title 10, CFR, Part 71, Subpart H.
(C) This general license applies only to a licensee
who meets the following requirements:
(i) has a copy of the CoC or other approval by the
NRC of the package, and has the drawings and other documents referenced
in the approval relating to the use and maintenance of the packaging
and to the actions to be taken before shipment; and
(ii) complies with the terms and conditions of the
specific license, certificate, or other approval by the NRC, as applicable,
and the applicable requirements of Title 10, CFR, Part 71, Subparts
A, G, and H; and
(iii) before the licensee's first use of the package,
submits in writing to: ATTN: Document Control Desk, Director, Division
of Spent Fuel Storage and Transportation, Office of Nuclear Material
Safety and Safeguards, using an appropriate method listed in Title
10, CFR, Part 71, 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 in accordance with 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 paragraph (2) of this
subsection.
(F) For 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 §289.255(m)(2)(B) of this title (relating
to Radiation Safety Requirements and Licensing and Registration Procedures
for Industrial Radiography), is deemed to satisfy the requirements
of subparagraph (B) of this paragraph.
(2) Previously approved package.
(A) A Type B package previously approved by the NRC,
but not designated as B(U), B(M), B(U)F or B(M)F in the identification
number of the NRC certificate of compliance, or Type AF packages approved
by the NRC prior to September 6, 1983, may be used in accordance with
the general license of paragraph (1) of this subsection with the following
additional conditions:
(i) fabrication of the packaging was satisfactorily
completed before August 31, 1986, as demonstrated by application of
its model number in accordance with subsection (k)(3) of this section;
(ii) 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
(iii) subparagraph (A) of this paragraph 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 in accordance with the general license of paragraph (1)
of this subsection with the following additional conditions:
(i) fabrication of the package is satisfactorily completed
by April 1, 1999, as demonstrated by application of its model number
in accordance with subsection (k)(3) of this section;
(ii) a package used for a shipment to a location outside
the United States is subject to multilateral approval as defined in
DOT regulations Title 49, CFR §173.403; and
(iii) 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 in accordance with the general license of paragraph (1) of
this subsection with the following additional conditions:
(i) fabrication of the package shall be satisfactorily
completed by December 31, 2006, as demonstrated by application of
its model number in accordance with subsection (k)(3) of this section.
(ii) 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 Title 49, CFR, §173.403.
(3) DOT specification container.
(A) A general license is issued to any licensee 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 Title 49, CFR, Parts
173 and 178.
(B) This general license applies only to a licensee
who:
(i) has a quality assurance program required by subsections
(s), (t), and (u) of this section and Title 10, CFR, Part 71, Subpart
H;
(ii) has a copy of the specification; and
(iii) complies with the terms and conditions of the
specification and the applicable requirements of this section.
(C) The general license in subparagraph (A) of this
paragraph 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 Title 49, CFR, §173.403.
(4) Use of foreign approved package.
(A) A general license is issued to any licensee 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 the DOT
as meeting the applicable requirements of Title 49, CFR, §171.23.
(B) Except as otherwise provided by this section, the
general license applies only to a licensee who has a quality assurance
program approved by the NRC as satisfying the applicable provisions
of Title 10, CFR, Part 71.
(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:
(i) has a copy of the applicable certificate, the revalidation,
and the drawings and other documents referenced in the certificate
relating to the use and maintenance of the packaging and to the actions
to be taken prior to shipment; and
(ii) complies with the terms and conditions of the
certificate and revalidation, and with the applicable requirements
of Title 10, CFR, Part 71, Subparts A, G, and H.
(5) Fissile material.
(A) A general license is issued to any licensee to
transport fissile material, or to deliver fissile material to a carrier
for transport, if the material is shipped in accordance with this
section. The fissile material need not be contained in a package that
meets the standards of this section; however, the material shall be
contained in a Type A package. The Type A package shall also meet
the DOT requirements of Title 49, CFR, §173.417(a).
(B) The general license applies only to a licensee
who has a quality assurance program approved by the NRC as satisfying
the provisions of Title 10, CFR, Part 71.
(C) The general license applies only when a package's
contents:
(i) contain no more than a Type A quantity of radioactive
material; and
(ii) contain less than 500 total grams of beryllium,
graphite, or hydrogeneous material enriched in deuterium.
(D) The general license applies only to packages containing
fissile material that are labeled with a CSI that:
(i) has been determined in accordance with paragraph
(E) of this subsection;
(ii) has a value less than or equal to 10.0; and
(iii) for a shipment of multiple packages containing
fissile material, the sum of the CSIs shall be less than or equal
to 50.0 (for shipment on a nonexclusive use conveyance) and less than
or equal to 100.0 (for shipment on an exclusive use conveyance).
(E) The CSI shall be as follows:
(i) the value for the CSI shall be greater than or
equal to the number calculated by the following equation:
Attached Graphic
(ii) the calculated CSI shall be rounded up to the
first decimal place;
(iii) the values of X, Y, and Z used in the CSI equation
shall be taken from Tables 257-1 or 257-2 of this clause, as appropriate;
Attached Graphic
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