| (iv) if Table 257-2 of clause (iii) of this subparagraph
is used to obtain the value of X, then the values for the terms in
the equation for uranium-233 and plutonium shall be assumed to be
zero; and
(v) Table 257-1 values of clause (iii) of this subparagraph
for X, Y, and Z shall be used to determine the CSI if:
(I) uranium-233 is present in the package;
(II) the mass of plutonium exceeds 1% 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 H2 O)
(e.g. certain hydrocarbon oils or plastics) are present in any form,
except as polyethylene used for packing or wrapping.
(6) Plutonium-beryllium special form material.
(A) A general license is issued to any licensee to
transport fissile material in the form of plutonium-beryllium (Pu-Be)
special form sealed sources, or to deliver Pu-Be sealed sources to
a carrier for transport, if the material is shipped in accordance
with this section. This material need not be contained in a package
that meets the standards of Title 10, CFR, Part 71, 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 material;
and
(ii) contain less than 1000g of plutonium, provided
that plutonium-239, plutonium-241, or any combination of these radionuclides,
constitutes less than 240 g of the total quantity of plutonium in
the package.
(D) The general license applies only to packages labeled
with a CSI that:
(i) has been determined in accordance with subparagraph
(E) of this paragraph;
(ii) has a value less than or equal to 100.0; and
(iii) for a shipment of multiple packages containing
Pu-Be sealed sources, 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 or exclusive use conveyance).
(E) The value for the CSI shall be as follows:
(i) 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.
(j) 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.
(k) Preliminary determinations. Before the first use
of any packaging for the shipment of licensed material the licensee
shall:
(1) ascertain that there are no cracks, pinholes, uncontrolled
voids, or other defects that could significantly reduce the effectiveness
of the packaging;
(2) where the maximum normal operating pressure will
exceed 35 kPa (5 lbf/in2) gauge, 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;
(3) 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 NRC; and
(4) ascertain that the determinations in subsections
(a) through (c) of this section have been made in accordance with
Title 10, CFR, §71.85.
(l) Routine determinations. Before each shipment of
radioactive material, the licensee shall ensure that the package with
its contents satisfies the applicable requirements of this section
and of the license. The licensee shall determine that:
(1) the package is proper for the contents to be shipped;
(2) the package is in unimpaired physical condition
except for superficial defects such as marks or dents;
(3) each closure device of the packaging, including
any required gasket, is properly installed, secured, and free of defects;
(4) any system for containing liquid is adequately
sealed and has adequate space or other specified provision for expansion
of the liquid;
(5) any pressure relief device is operable and set
in accordance with written procedures;
(6) the package has been loaded and closed in accordance
with written procedures;
(7) for fissile material, any moderator or neutron
absorber, if required, is present and in proper condition;
(8) 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 Title 10, CFR, §71.45;
(9) the level of non-fixed (removable) radioactive
contamination on the external surfaces of each package offered for
shipment is as low as reasonably achievable (ALARA), and within the
limits specified in DOT regulations in Title 49, CFR, §173.443;
(10) external radiation levels around the package and
around the vehicle, if applicable, will not exceed the following limits
at any time during transportation:
(A) Except as provided in subparagraph (B) of this
paragraph, each package of radioactive materials offered for transportation
shall be designed and prepared for shipment so that under conditions
normally incident to transportation the radiation level does not exceed
2 mSv/hr (200 mrem/hr) at any point on the external surface of the
package, and the transport index does not exceed 10.
(B) A package that exceeds the radiation level limits
specified in subparagraph (A) of this paragraph shall be transported
by exclusive use shipment only, and the radiation levels for such
shipment shall not exceed the following during transportation:
(i) 2 mSv/hr (200 mrem/hr) on the external surface
of the package, unless the following conditions are met, in which
case the limit is 10 mSv/hr (1,000 mrem/hr):
(I) the shipment is made in a closed transport vehicle;
(II) the package is secured within the vehicle so that
its position remains fixed during transportation; and
(III) there are no loading or unloading operations
between the beginning and end of the transportation;
(ii) 2 mSv/hr (200 mrem/hr) at any point on the outer
surface of the vehicle, including the top and underside of the vehicle;
or in the case of a flat-bed style vehicle, at any point on the vertical
planes projected from the outer edges of the vehicle, on the upper
surface of the load or enclosure, if used, and on the lower external
surface of the vehicle; and
(iii) 0.1 mSv/hr (10 mrem/hr) at any point 2 meters
(m) (6.6 feet (ft)) 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 m (6.6 ft) from the vertical
planes projected by the outer edges of the vehicle (excluding the
top and underside of the vehicle); and
(iv) 0.02 mSv/hr (2 mrem/hr) in any normally occupied
space, except that this provision does not apply to private carriers,
if exposed personnel under their control wear radiation dosimetry
devices in conformance with §289.202(q) of this title;
(C) For shipments made in accordance with the provisions
of subparagraph (B) of this paragraph, the shipper shall provide specific
written instructions to the carrier for maintenance of the exclusive
use shipment controls. The instructions shall be included with the
shipping paper information.
(D) The written instructions required for exclusive
use shipments shall 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.
Cont'd... |
