| (ii) Natural uranium, depleted uranium, natural thorium
or their compounds or mixtures, provided they are unirradiated and
in solid or liquid form; or
(iii) Radioactive material other than fissile material
for which the A2 value is unlimited;
or
(iv) Other radioactive material (e.g.: mill tailings,
contaminated earth, concrete, rubble, other debris, and activated
material) in which the radioactivity 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 subsection (ee) of this section.
(B) LSA-II.
(i) Water with tritium concentration up to 0.8 terabecquerel
per liter (TBq/l) (20.0 curies per liter (Ci/l)); or
(ii) Other material in which the radioactivity is distributed
throughout, and the average specific activity does not exceed 10-4
A2/g for solids and gases, and 10-5 A2/g for liquids.
(C) LSA-III. Solids (e.g., consolidated wastes, activated
materials), excluding powders, that satisfy the requirements of Title
10, CFR, §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.); and
(ii) the radioactive material is relatively insoluble,
or it is intrinsically contained in a relatively insoluble material,
so that, even with a loss of packaging, the loss of radioactive material
per package by leaching, when placed in water for 7 days, will not
exceed 0.1 A2; and
(iii) the estimated average specific activity of the
solid, excluding any shielding material, does not exceed 2 x 10-3
A2/g.
(28) Low toxicity alpha emitters--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.
(29) Maximum normal operating pressure--The maximum
gauge pressure that would develop in the containment system in a period
of 1 year under the heat condition specified in Title 10, CFR, §71.71(c)(1),
in the absence of venting, external cooling by an ancillary system,
or operational controls during transport.
(30) Natural thorium--Thorium with the naturally occurring
distribution of thorium isotopes (essentially 100 weight percent thorium-232).
(31) Normal form radioactive material--Radioactive
material that has not been demonstrated to qualify as special form
radioactive material.
(32) NRC Forms 540, 540A, 541, 541A, 542, and 542A--Official
NRC forms referenced in subsection (ff) of this section which includes
the information required by DOT in Title 49, CFR, Part 172. Licensees
need not use originals of these forms as long as any substitute forms
contain the equivalent information. Licensees may include additional
information deemed relevant to the licensee's shipment of low-level
radioactive waste. Upon agreement between the shipper and consignee,
NRC Forms 541 (and 541A) and NRC Forms 542 (and 542A) or equivalent
documents may be completed, transmitted, and stored in electronic
media. The electronic media shall have the capability for producing
legible, accurate, and complete records in the format of the uniform
manifest.
(33) Package--The packaging together with its radioactive
contents as presented for transport.
(A) Fissile material package, Type AF package, Type
BF package, Type B(U)F package, or Type B(M)F package--A fissile material
packaging together with its fissile material contents.
(B) Type A package--A Type A packaging together with
its radioactive contents. A Type A package is defined and shall comply
with the DOT regulations in Title 49, CFR, Part 173.
(C) Type B package--A Type B packaging together with
its radioactive contents. On approval by the NRC, 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 kilopascals (kPa) (100
pounds per square inch (lb/in2)) gauge or a pressure relief device
that would allow the release of radioactive material to the environment
under the tests specified in Title 10, CFR, §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 Title 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 Title 10, CFR, §71.19.
(34) Packaging--The assembly of components necessary
to ensure compliance with the packaging requirements of this section.
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.
(35) Physical description--The items called for on
NRC Form 541 to describe a LLRW.
(36) Registered freight forwarder--A freight forwarder
that has an emergency plan approved in accordance with subsection
(r) of this section and has been issued a registration letter.
(37) Registered shipper--A shipper that has an emergency
plan approved in accordance with subsection (r) of this section, and
shipping containers approved in accordance with subsection(cc)(8)
of this section and been issued a registration letter.
(38) Registered transporter--A transporter that has
an emergency plan approved in accordance with subsection (r) of this
section, and proof of financial responsibility submitted and approved
in accordance with subsection(e)(4) of this section and has been issued
a registration letter.
(39) Residual waste--LLRW resulting from processing
or decontamination activities that cannot be easily separated into
distinct batches attributable to specific waste generators. This waste
is attributable to the processor or decontamination facility, as applicable.
(40) Shipper--The licensed entity (i.e., the waste
generator, waste collector, or waste processor) who offers LLRW for
transportation, typically consigning this type of waste to a licensed
waste collector, waste processor, or land disposal facility operator.
This definition applies only to shipments of LLRW shipped to a Texas
LLRW disposal facility.
(41) Site of usage--The licensee's facility, including
all buildings and structures between which radioactive material is
transported and all roadways that are not within the public domain
on which radioactive material can be transported.
(42) Special form radioactive material--Radioactive
material that satisfies the following conditions:
(A) it is either a single solid piece or is contained
in a sealed capsule that can be opened only by destroying the capsule;
(B) the piece or capsule has at least one dimension
not less than 5 millimeters (0.2 in); and
(C) it satisfies the requirements of Title 10, CFR, §71.75.
A special form encapsulation designed in accordance with the requirements
of this subsection in effect on or after June 30, 1983 (see Title
10, CFR, Part 71, revised as of January 1, 1983), and constructed
before July 1, 1985; a special form encapsulation designed in accordance
with the requirements of this subsection in effect on or after March
31, 1996 (see Title 10, CFR, Part 71, revised as of January 1, 1996),
and constructed before April 1, 1998; and
(D) special form material that was successfully tested
before September 10, 2015, in accordance with the requirements of
Title 10, CFR, §71.75(d) in effect before September 10, 2015
may continue to be used. Any other special form encapsulation must
meet the specifications of this definition.
(43) Specific activity of a radionuclide--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.
(44) Spent nuclear fuel or spent fuel--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 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.
Cont'd... |
