Export Controls and Physical Security Standards, 39289-39300 [2014-15828]
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39289
Rules and Regulations
Federal Register
Vol. 79, No. 132
Thursday, July 10, 2014
This section of the FEDERAL REGISTER
contains regulatory documents having general
applicability and legal effect, most of which
are keyed to and codified in the Code of
Federal Regulations, which is published under
50 titles pursuant to 44 U.S.C. 1510.
The Code of Federal Regulations is sold by
the Superintendent of Documents. Prices of
new books are listed in the first FEDERAL
REGISTER issue of each week.
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 110
RIN 3150–AJ33
[NRC–2014–0007]
Export Controls and Physical Security
Standards
Nuclear Regulatory
Commission.
ACTION: Final rule.
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AGENCY:
SUMMARY: The U.S. Nuclear Regulatory
Commission (NRC) is amending its
regulations pertaining to the export and
import of nuclear materials and
equipment. This rulemaking is
necessary to conform the export controls
of the United States to the international
export control guidelines of the Nuclear
Suppliers Group (NSG), of which the
United States is a member, and to
incorporate by reference the current
version of the International Atomic
Energy Agency’s (IAEA) document,
‘‘Nuclear Security Recommendations on
Physical Protection of Nuclear Material
and Nuclear Facilities (INFCIRC/225/
Revision 5), January 2011.’’ Also, this
final rule makes certain editorial
revisions, and corrects typographical
errors.
DATES: The final rule is effective August
11, 2014, except that the changes to
§ 110.44(a) and (b)(1) and appendix M to
10 CFR part 110 are effective December
31, 2014. The incorporation by reference
of the material in this document is
approved as of December 31, 2014.
ADDRESSES: Please refer to Docket ID
NRC–2014–0007 when contacting the
NRC about the availability of
information for this final rule. You can
access publicly-available information
related to this final rule by any of the
following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
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for Docket ID NRC–2014–0007. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
final rule.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publicly
available documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. The
ADAMS accession number for each
document referenced in this document
(if that document is available in
ADAMS) is provided the first time that
a document is referenced.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT:
Brooke G. Smith, Office of International
Programs, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone: 301–415–2347, email:
Brooke.Smith@nrc.gov.
SUPPLEMENTARY INFORMATION:
Table of Contents
I. Background
II. Section-by-Section Analysis
III. Regulatory Flexibility Certification
IV. Regulatory Analysis
V. Backfitting and Issue Finality
VI. Plain Writing
VII. Environmental Impact Statement
VIII. Paperwork Reduction Act
IX. Congressional Review Act
X. Voluntary Consensus Standards
I. Background
The NSG is a group of like-minded
States that seeks to contribute to the
nonproliferation of nuclear weapons
through the implementation of
guidelines for nuclear exports and
nuclear-related exports. As a
participating government in the NSG,
the United States has committed to
controlling for export items on the NSG
control lists. Participating governments
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are charged with implementing the
changes adopted to the list as soon as
possible after approval.
This final rule conforms the NRC’s
export and import regulations in 10 CFR
part 110, ‘‘Export and Import of Nuclear
Equipment and Material,’’ and
appendices A, B, C, D, E, F, G, H, I, J,
K, N, and O, which contain illustrative
lists of items under the NRC’s export
licensing authority, to current nuclear
nonproliferation policies of the
Executive Branch. These revisions are
necessary to implement changes made
to the NSG Guidelines, ‘‘Guidelines for
Nuclear Transfers (INFCIRC/254/
Revision 12/Part 1), June 2013,’’ as
adopted by the governments
participating in the NSG at the June
2012 and 2013 Plenary Meetings. In
addition, this rule amends § 110.30,
‘‘Members of the Nuclear Suppliers
Group,’’ to add Mexico and Serbia as
member countries of the NSG that are
eligible to receive radioactive materials
under certain general licenses for
export. The NSG Guidelines can be
found at:
www.nuclearsuppliersgroup.org.
In January 2011, the IAEA published
the document titled, ‘‘Nuclear Security
Recommendations on Physical
Protection of Nuclear Material and
Nuclear Facilities (INFCIRC/225/
Revision 5).’’ This rule also amends
§ 110.44 and appendix M to 10 CFR part
110 to incorporate by reference the
update and recommendations contained
in Revision 5 of this IAEA document.
The NRC staff has determined that
these changes are consistent with
current U.S. policy, and will pose no
unreasonable risk to the public health
and safety or to the common defense
and security of the United States.
Because this rule involves a foreign
affairs function of the United States, the
notice and comment provisions of the
Administrative Procedure Act do not
apply (5 U.S.C. 553(a)(1)). In addition,
solicitation of public comments would
delay the U.S. conformance with its
international obligations, and would be
contrary to the public interest (5 U.S.C.
553(b)). The final rule is effective
August 11, 2014, except that the
changes to § 110.44(a) and (b)(1) and
appendix M to 10 CFR part 110 are
effective December 31, 2014.
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II. Section by Section Analysis
Section 110.2
Definitions
Paragraph (2)(ii) of the definition of
‘‘Utilization facility’’ is amended to
make conforming changes consistent
with the changes to appendix A to 10
CFR part 110.
Section 110.26 General License for the
Export of Nuclear Reactor Components
This rule amends § 110.26 to make
conforming changes to paragraph (a)
consistent with the changes to appendix
A to 10 CFR part 110.
Section 110.30 Members of the
Nuclear Suppliers Group
This rule amends § 110.30 to update
the list of NSG members by adding
Mexico and Serbia.
Section 110.42
Criteria
Export Licensing
This rule amends § 110.42 to make
conforming changes to Footnote 1
consistent with the changes to appendix
A to 10 CFR part 110.
Section 110.44
Standards
Physical Security
Paragraphs (a) and (b)(1) of § 110.44
are amended to incorporate by reference
the most recent revision to INFCIRC/
225/Revision 5, ‘‘The Physical
Protection of Nuclear Material and
Nuclear Facilities.’’ The effective date
for these changes is delayed until
December 31, 2014, to provide adequate
time for countries to meet the
recommendations in Revision 5. ‘‘The
Physical Protection of Nuclear Material
and Nuclear Facilities,’’ INFCIRC/225/
Revision 4 (corrected), July 1999, will
continue to be used as the physical
protection standard in recipient
countries until the effective date for
INFCIRC/225/Revision 5, as
incorporated by reference in 10 CFR
part 110.
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Appendices A, B, C, D, E, F, G, H, I, J,
K, N and O to Part 110
These appendices are amended to
reflect the updated guidelines of the
NSG consistent with the IAEA
document, ‘‘Guidelines for Nuclear
Transfers, (INFCIRC/254/Revision 12/
Part 1).’’ The appendices in 10 CFR part
110 are illustrative only and are not
meant to be inclusive lists of facilities
and equipment under the NRC’s export
licensing jurisdiction.
Appendix M to Part 110—
Categorization of Nuclear Material
Appendix M is amended to update
the Categorization of Nuclear Material
table to be consistent with IAEA
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publication, INFCIRC/225/Revision 5.
The changes to appendix M of 10 CFR
part 110 are effective December 31,
2014.
III. Regulatory Flexibility Certification
As required by the Regulatory
Flexibility Act of 1980 (5 U.S.C. 605(b)),
the Commission certifies that this final
rule will not have a significant
economic impact on a substantial
number of small entities. This rule
affects only companies exporting
nuclear equipment and material to and
from the United States and they do not
fall within the scope of the definition of
‘‘small entities’’ set forth in the
Regulatory Flexibility Act (5 U.S.C.
601(3)), or the Size Standards
established by the NRC (10 CFR 2.810).
IV. Regulatory Analysis
This rulemaking is necessary to reflect
the nuclear nonproliferation policy of
the Executive Branch including U.S.
Government commitments to
controlling export items on the NSG
control lists and the IAEA publication,
INFCIRC/225/Revision 5. This final rule
is expected to have no changes in the
information collection burden or cost to
the public.
V. Backfit Analysis and Issue Finality
The NRC has determined that a
backfit analysis is not required for this
rule because these amendments do not
include any provisions that would
impose backfits as defined in 10 CFR
Chapter I.
VI. Plain Writing
The Plain Writing Act of 2010 (Pub.
L. 111–274) requires Federal agencies to
write documents in a clear, concise, and
well-organized manner. The NRC has
written this document to be consistent
with the Plain Writing Act as well as the
Presidential Memorandum, ‘‘Plain
Language in Government Writing,’’
published June 10, 1998 (63 FR 31883).
VII. Environmental Impact: Categorical
Exclusion
The NRC has determined that this
final rule is the type of action described
in categorical exclusion 10 CFR
51.22(c)(1). Therefore, neither an
environmental impact statement nor an
environmental assessment has been
prepared for the rule.
VIII. Paperwork Reduction Act
Statement
This final rule does not contain new
or amended information collection
requirements subject to the Paperwork
Reduction Act of 1995 (44 U.S.C. 3501
et seq.). Existing requirements were
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approved by the Office of Management
and Budget (OMB) under approval
number 3150–0036.
Public Protection Notification
The NRC may not conduct or sponsor,
and a person is not required to respond
to, a request for information or an
information collection requirement
unless the requesting document
displays a currently valid OMB control
number.
IX. Congressional Review Act
Under the Congressional Review Act
of 1996, the NRC has determined that
this action is not a major rule and has
verified this determination with the
Office of Information and Regulatory
Affairs of OMB.
X. Voluntary Consensus Standards
The National Technology Transfer
and Advancement Act of 1995 (Pub. L.
104–113) requires that Federal Agencies
use technical standards that are
developed or adopted by voluntary
consensus standards bodies unless
using such a standard is inconsistent
with applicable law or otherwise
impractical. This final rule does not
constitute the establishment of a
standard for which the use of a
voluntary consensus standard would be
applicable.
List of Subjects in 10 CFR Part 110
Administrative practice and
procedure, Classified information,
Criminal penalties, Export, Import,
Incorporation by reference,
Intergovernmental relations, Nuclear
materials, Nuclear power plants and
reactors, Reporting and recordkeeping
requirements, Scientific equipment.
For the reasons set out in the
preamble and under the authority of the
Atomic Energy Act of 1954, as amended,
the Energy Reorganization Act of 1974,
as amended, and 5 U.S.C. 552 and 553,
the NRC is adopting the following
amendments to 10 CFR part 110.
PART 110—EXPORT AND IMPORT OF
NUCLEAR EQUIPMENT AND
MATERIAL
1. The authority citation for part 110
continues to read as follows:
■
Authority: Atomic Energy Act secs. 51, 53,
54, 57, 63, 64, 65, 81, 82, 103, 104, 109, 111,
126, 127, 128, 129, 161, 181, 182, 183, 187,
189, 223, 234 (42 U.S.C. 2071, 2073, 2074,
2077, 2092–2095, 2111, 2112, 2133, 2134,
2139, 2139a, 2141, 2154–2158, 2201, 2231–
2233, 2237, 2239, 2273, 2282); Energy
Reorganization Act sec. 201 (42 U.S.C. 5841;
Solar, Wind, Waste, and Geothermal Power
Act of 1990 sec. 5 (42 U.S.C.2243);
Government Paperwork Elimination Act sec.
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1704, 112 Stat. 2750 (44 U.S.C. 3504 note);
Energy Policy Act of 2005, 119 Stat. 594.
Sections 110.1(b)(2) and 110.1(b)(3) also
issued under 22 U.S.C. 2403. Section 110.11
also issued under Atomic Energy Act secs.
54(c), 57(d), 122 (42 U.S.C. 2074, 2152).
Section 110.50(b)(3) also issued under
Atomic Energy Act sec. 123 (42 U.S.C. 2153).
Section 110.51 also issued under Atomic
Energy Act sec. 184 (42 U.S.C. 2234). Section
110.52 also issued under Atomic Energy Act
sec. 186, (42 U.S.C. 2236). Sections 110.80–
110.113 also issued under 5 U.S.C. 552, 554.
Sections 110.130–110.135 also issued under
5 U.S.C. 553. Sections 110.2 and 110.42(a)(9)
also issued under Intelligence Authorization
Act sec. 903 (42 U.S.C. 2151 et seq.).
2. In § 110.2, revise paragraph (2)(ii) of
the definition of ‘‘Utilization facility’’ to
read as follows:
■
§ 110.2
Definitions.
*
*
*
*
*
Utilization facility means:
*
*
*
*
*
(2) * * *
(ii) Reactor primary coolant pump or
circulator;
*
*
*
*
*
■ 3. In § 110.26, revise the introductory
text of paragraph (a) to read as follows:
§ 110.26 General license for the export of
nuclear reactor components.
(a) A general license is issued to any
person to export to a destination listed
in paragraph (b) of this section any
nuclear reactor component of U.S.
origin described in paragraphs (5)
through (11) of appendix A to this part
if—
*
*
*
*
*
§ 110.30
[Amended]
4. Amend § 110.30 by adding the
words ‘‘Mexico’’ and ‘‘Serbia’’ in
alphabetical order.
■ 5. In § 110.42, revise footnote 1 to read
as follows:
■
§ 110.42
Export licensing criteria.
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*
*
*
*
*
1 Export of nuclear reactors, reactor
pressure vessels, reactor primary
coolant pumps and circulators, ‘‘online’’ reactor fuel charging and
discharging machines, and complete
reactor control rod systems, as specified
in paragraphs (1) through (4) of
appendix A to this part, are subject to
the export licensing criteria in
§ 110.42(a). Exports of nuclear reactor
components, as specified in paragraphs
(5) through (11) of appendix A to this
part, when exported separately from the
items described in paragraphs (1)
through (4) of appendix A to this part,
are subject to the export licensing
criteria in § 110.42(b).
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6. In § 110.44, revise paragraphs (a)
and (b)(1) to read as follows:
■
§ 110.44
Physical security standards.
(a) Physical security measures in
recipient countries must provide
protection at least comparable to the
recommendations in the current version
of IAEA publication, ‘‘Nuclear Security
Recommendations on Physical
Protection of Nuclear Material and
Nuclear Facilities’’ (INFCIRC/225/
Revision 5), January 2011, which is
incorporated by reference in this part.
This incorporation by reference was
approved by the Director of the Office
of the Federal Register in accordance
with 5 U.S.C. 552(a) and 1 CFR part 51.
Notice of any changes made to the
material incorporated by reference will
be published in the Federal Register.
Copies of INFCIRC/225/Revision 5 may
be obtained from the Marketing and
Sales Unit, Publishing Section, IAEA,
Vienna International Centre, P.O. Box
100, 1400 Vienna Austria; Fax: 43 1
2600 29302; telephone: 43 1 2600
22417; email: sales.publications
@iaea.org; Web site: https://
www.iaea.org/books. You may inspect a
copy at the NRC Library, 11545
Rockville Pike, Rockville, Maryland
20852–2738, telephone: 301–415–4737
or 1–800–397–4209, between 8:30 a.m.
and 4:15 p.m.; or at the National
Archives and Records Administration
(NARA). For information on the
availability of this material at NARA,
call 202–741–6030, or go to: https://
www.archives.gov/federal-register/cfr/
ibr-locations.html.
(b) * * *
(1) Receipt by the appropriate U.S.
Executive Branch Agency of written
assurances from the relevant recipient
country government that physical
security measures providing protection
at least comparable to the
recommendations set forth in INFCIRC/
225/Revision 5.
*
*
*
*
*
■ 7. Revise appendix A to part 110 to
read as follows:
Appendix A to Part 110—Illustrative
List of Nuclear Reactor Equipment
Under NRC Export Licensing Authority
Note: A nuclear reactor basically includes
the items within or attached directly to the
reactor vessel, the equipment which controls
the level of power in the core, and the
components which normally contain or come
in direct contact with or control the primary
coolant of the reactor core.
(1) Reactor pressure vessels, i.e., metal
vessels, as complete units or major shopfabricated parts, especially designed or
prepared to contain the core of a nuclear
reactor and capable of withstanding the
operating pressure of the primary coolant.
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(2) On-line (e.g., CANDU) reactor fuel
charging and discharging machines, i.e.,
manipulative equipment especially designed
for inserting or removing fuel in an operating
nuclear reactor.
(3) Complete reactor control rod system,
i.e., rods especially designed or prepared for
the control of the reaction rate in a nuclear
reactor, including the neutron absorbing part
and the support or suspension structures
therefor.
(4) Reactor primary coolant pumps or
circulators, i.e., pumps or circulators
especially designed or prepared for
circulating the primary coolant in a nuclear
reactor.
(5) Reactor pressure tubes, i.e., tubes
especially designed or prepared to contain
both fuel elements and the primary coolant
in a nuclear reactor.
(6) Zirconium tubes, i.e., zirconium metal
and alloys in the form of tubes or assemblies
of tubes especially designed or prepared for
use as fuel cladding in a nuclear reactor.
(7) Reactor internals, e.g., core support
structures, control and rod guide tubes, fuel
channels, calandria tubes, thermal shields,
baffles, core grid plates, and diffuser plates
especially designed or prepared for use in a
nuclear reactor.
(8) Reactor control rod drive mechanisms,
including detection and measuring
equipment to determine neutron flux levels
within the core of a nuclear reactor.
(9) Heat exchangers, e.g., steam generators
especially designed or prepared for the
primary, or intermediate, coolant circuit of a
nuclear reactor or heat exchangers especially
designed or prepared for use in the primary
coolant circuit of a nuclear reactor.
(10) External thermal shields especially
designed or prepared for use in a nuclear
reactor for reduction of heat loss and also for
containment vessel protection.
(11) Any other components especially
designed or prepared for use in a nuclear
reactor or in any of the components
described in this appendix.
8. Revise appendix B to part 110 to
read as follows:
■
Appendix B to Part 110—Illustrative
List of Gas Centrifuge Enrichment Plant
Components Under NRC’s Export
Licensing Authority
1. Assemblies and components especially
designed or prepared for use in gas
centrifuges.
Note: The gas centrifuge normally consists
of a thin-walled cylinder(s) of between 75
mm and 650 mm diameter contained in a
vacuum environment and spun at high
peripheral speed (of the order of 300 m/per
second and more) with the central axis
vertical. In order to achieve high speed, the
materials of construction for the rotating
rotor assembly, and hence its individual
components, have to be manufactured to very
close tolerances in order to minimize the
unbalance. In contrast to other centrifuges,
the gas centrifuge for uranium enrichment is
characterized by having within the rotor
chamber a rotating disc-shaped baffle(s) and
a stationary tube arrangement for feeding and
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extracting uranium hexafluoride (UF6) gas
and featuring at least three separate channels
of which two are connected to scoops
extending from the rotor axis towards the
periphery of the rotor chamber. Also
contained within the vacuum environment
are a number of critical items which do not
rotate and which, although they are
especially designed, are not difficult to
fabricate nor are they fabricated out of unique
materials. A centrifuge facility, however,
requires a large number of these components
so that quantities can provide an important
indication of end use.
1.1 Rotating Components
(a) Complete Rotor Assemblies: Thinwalled cylinders, or a number of
interconnected thin-walled cylinders,
manufactured from one of the high strengthto-density ratio materials described in the
footnote to this section.
If interconnected, the cylinders are joined
together by flexible bellows or rings as
described in § 1.1(c) of this appendix. The
rotor is fitted with an internal baffle(s) and
end caps, as described in § 1.1(d) and (e) of
this appendix, if in final form. However, the
complete assembly may be delivered only
partly assembled.
(b) Rotor Tubes: Especially designed or
prepared thin-walled cylinders with
thickness of 12 mm or less, a diameter of
between 75 mm and 650 mm, and
manufactured from one of the high strengthto-density ratio materials described in the
footnote to this section.
(c) Rings or Bellows: Components
especially designed or prepared to give
localized support to the rotor tube or to join
together a number of rotor tubes. The bellows
in a short cylinder of wall thickness 3 mm
or less, a diameter of between 75 mm and 650
mm, having a convolute, and manufactured
from one of the high strength-to-density ratio
materials described in the footnote to this
section.
(d) Baffles: Disc shaped components of
between 75 mm and 650 mm diameter
especially designed or prepared to be
mounted inside the centrifuge rotor tube, in
order to isolate the take-off chamber from the
main separation chamber and, in some cases,
to assist the UF6 gas circulation within the
main separation chamber of the rotor tube,
and manufactured from one of the high
strength-to-density ratio materials described
in the footnote to this section.
(e) Top Caps/Bottom Caps: Disc shaped
components of between 75 mm and 650 mm
diameter especially designed or prepared to
fit to the ends of the rotor tube, and so
contain the UF6 within the rotor tube, and in
some cases to support, retain or contain as an
integrated part, an element of the upper
bearing (top cap) or to carry the rotating
elements of the motor and lower bearing
(bottom cap), and manufactured from one of
the high strength-to-density ratio materials
described in the footnote to this section.
Footnote
The materials used for centrifuge rotating
components include the following:
(a) Maraging steel capable of an ultimate
tensile strength of 1.95 GPa or more.
(b) Aluminum alloys capable of an ultimate
tensile strength of 0.46 GPa or more.
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(c) Filamentary materials suitable for use in
composite structures and having a specific
modulus of 3.18 × 106 m or greater and a
specific ultimate tensile strength of 7.62 ×
104 m or greater.
(‘‘Specific Modulus’’ is the Young’s modulus
in N/m2 divided by the specific weight in
N/m3 when measured at a temperature of 23
± 20 °C and a relative humidity of 50 ± 5
percent. ‘‘Specific tensile strength’’ is the
ultimate tensile strength in N/m2 divided by
the specific weight in N/m3 when measured
at a temperature of 23 ± 20 °C and a relative
humidity of 50 ± 5 percent.)
1.2 Static Components
(a) Magnetic Suspension Bearings: 1.
Especially designed or prepared bearing
assemblies consisting of an annular magnet
suspended within a housing containing a
damping medium. The housing will be
manufactured from a UF6 resistant material
(see footnote to § 2 of this appendix). The
magnet couples with a pole piece or a second
magnet fitted to the top cap described in
§ 1.1(e) of this appendix. The magnet may be
ring-shaped with a relation between outer
and inner diameter smaller or equal to 1.6:1.
The magnet may be in a form having an
initial permeability of 0.15 Henry/meter or
more, or a remanence of 98.5 percent or
more, or an energy product of greater than
80,000 joules/m3. In addition to the usual
material properties, it is a prerequisite that
the deviation of the magnetic axes from the
geometrical axes is limited to very small
tolerances (lower than 0.1 mm) or that
homogeneity of the material of the magnet is
specially called for.
2. Active magnetic bearings especially
designed or prepared for use with gas
centrifuges. These bearings usually have the
following characteristics:
(i) Designed to keep centred a rotor
spinning at 600 Hz or more; and
(ii) Associated to a reliable electrical power
supply and/or to an uninterruptible power
supply (UPS) unit in order to function for
more than 1 hour.
(b) Bearings/Dampers: Especially designed
or prepared bearings comprising a pivot/cup
assembly mounted on a damper. The pivot is
normally a hardened steel shaft polished into
a hemisphere at one end with a means of
attachment to the bottom cap described in
§ 1.1(e) of this appendix at the other. The
shaft may, however, have a hydrodynamic
bearing attached. The cup is pellet-shaped
with hemispherical indentation in one
surface. These components are often
supplied separately to the damper.
(c) Molecular Pumps: Especially designed
or prepared cylinders having internally
machined or extruded helical grooves and
internally machined bores. Typical
dimensions are as follows: 75 mm to 650 mm
internal diameter, 10 mm or more wall
thickness, with a length equal to or greater
than the diameter. The grooves are typically
rectangular in cross-section and 2 mm or
more in depth.
(d) Motor Stators: Especially designed or
prepared ring shaped stators for high speed
multi-phase alternating current (AC)
hysteresis (or reluctance) motors for
synchronous operation within a vacuum at a
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frequency of 600 Hz or greater and a power
of 40 volts amps or greater. The stators may
consist of multi-phase windings on a
laminated low loss iron core comprised of
thin layers typically 2.0 mm thick or less.
(e) Centrifuge housing/recipients:
Components especially designed or prepared
to contain the rotor tube assembly of a gas
centrifuge. The housing consists of a rigid
cylinder of wall thickness up to 30 mm with
precision machined ends to locate the
bearings and with one or more flanges for
mounting. The machined ends are parallel to
each other and perpendicular to the
cylinder’s longitudinal axis to within 0.05
degrees or less. The housing may also be a
honeycomb type structure to accommodate
several rotor tubes.
(f) Scoops: Especially designed or prepared
tubes for the extraction of UF6 gas from
within the rotor tube by a Pitot tube action
(that is, with an aperture facing into the
circumferential gas flow within the rotor
tube, for example by bending the end of a
radially disposed tube) and capable of being
fixed to the central gas extraction system.
2. Especially designed or prepared
auxiliary systems, equipment, and
components for gas centrifuge enrichment
plants.
Note: The auxiliary systems, equipment,
and components for a gas centrifuge
enrichment plant are the systems of the plant
needed to feed UF6 to the centrifuges to link
the individual centrifuges to each other to
form cascades (or stages) to allow for
progressively higher enrichments and to
extract the product and tails of UF6 from the
centrifuges, together with the equipment
required to drive the centrifuges or to control
the plant.
Normally UF6 is evaporated from the solid
using heated autoclaves and is distributed in
gaseous form to the centrifuges by way of
cascade header pipework. The ‘‘product’’ and
‘‘tails’’ of UF6 gaseous streams flowing from
the centrifuges are also passed by way of
cascade header pipework to cold traps
(operating at about 203 K (¥70 °C)) where
they are condensed prior to onward transfer
into suitable containers for transportation or
storage. Because an enrichment plant
consists of many thousands of centrifuges
arranged in cascades, there are many
kilometers of cascade header pipework
incorporating thousands of welds with a
substantial amount of repetition of layout.
The equipment, component and piping
systems are fabricated to very high vacuum
and cleanliness standards.
Some of the items listed below either come
into direct contact with the UF6 process gas
or directly control the centrifuges and the
passage of the gas from centrifuge to
centrifuge and cascade to cascade. Materials
resistant to corrosion by UF6 include copper,
copper alloys, stainless steel, aluminum,
aluminum oxide, aluminum alloys, nickel or
alloys containing 60 percent or more nickel,
and fluorinated hydrocarbon polymers.
(a) Feed Systems/Product and Tails
Withdrawal Systems: Especially designed or
prepared process systems or equipment for
enrichment plants made of or protected by
materials resistant to corrosion by UF6
including:
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1. Feed autoclaves, ovens, or systems used
for passing UF6 to the enrichment process.
2. Desublimers, cold traps, or pumps used
to remove UF6 from the enrichment process
for subsequent transfer upon heating.
3. Solidification or liquefaction stations
used to remove UF6 from the enrichment
process by compressing and converting UF6
to a liquid or solid form.
4. ‘‘Product’’ and ‘‘tails’’ stations used for
transferring UF6 into containers.
(b) Machine Header Piping Systems:
Especially designed or prepared piping
systems and header systems for handling UF6
within the centrifuge cascades.
This piping network is normally of the
‘‘triple’’ header system with each centrifuge
connected to each of the headers. There is
therefore a substantial amount of repetition
in its form. It is wholly made of or protected
by UF6 resistant materials (see Note to this
section) and is fabricated to very high
vacuum and cleanliness standards.
(c) Special shut-off and control valves:
1. Shut-off valves especially designed or
prepared to act on the feed, ‘‘product’’ or
‘‘tails’’ UF6 gaseous streams of an individual
gas centrifuge.
2. Bellows-sealed valves, manual or
automated, shut-off or control, made of or
protected by materials resistant to corrosion
by UF6, with an inside diameter of 10 to 160
mm, especially designed or prepared for use
in main or auxiliary systems of gas centrifuge
enrichment plants.
Typical especially designed or prepared
valves include bellow-sealed valves, fast
acting closure-types, fast acting valves, and
others.
(d) UF6 Mass Spectrometers/Ion Sources:
Especially designed or prepared mass
spectrometers capable of taking on-line
samples from UF6 gas streams and having all
of the following:
1. Capable of measuring ions of 320 atomic
mass units or greater and having a resolution
of better than 1 part in 320.
2. Ion sources constructed of or protected
by nickel, nickel-copper alloys with a nickel
content of 60 percent or more by weight, or
nickel-chrome alloys.
3. Electron bombardment ionization
sources.
4. Having a collector system suitable for
isotope analysis.
(e) Frequency Changers: Frequency
changers (also known as converters or
inverters) especially designed or prepared to
supply motor stators as defined under
§ 1.2(d) of this appendix, or parts,
components, and subassemblies of such
frequency changers having all of the
following characteristics:
1. A multiphase output of 600 Hz or
greater; and
2. High stability (with frequency control
better than 0.2 percent).
(f) Any other components especially
designed or prepared for use in a gas
centrifuge enrichment plant or in any of the
components described in this appendix.
9. Revise appendix C to part 110 to
read as follows:
■
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Appendix C to Part 110—Illustrative
List of Gaseous Diffusion Enrichment
Plant Assemblies and Components
Under NRC Export Licensing Authority
Note: In the gaseous diffusion method of
uranium isotope separation, the main
technological assembly is a special porous
gaseous diffusion barrier, heat exchanger for
cooling the gas (which is heated by the
process of compression), seal valves and
control valves, and pipelines. Inasmuch as
gaseous diffusion technology uses uranium
hexafluoride (UF6), all equipment, pipeline
and instrumentation surfaces (that come in
contact with the gas) must be made of
materials that remain stable in contact with
UF6. A gaseous diffusion facility requires a
number of these assemblies, so that
quantities can provide an important
indication of end use.
The auxiliary systems, equipment, and
components for gaseous diffusion enrichment
plants are the systems of plant needed to feed
UF6 to the gaseous diffusion assembly to link
the individual assemblies to each other to
form cascades (or stages) to allow for
progressively higher enrichments and to
extract the ‘‘product’’ and ‘‘tails’’ UF6 from
the diffusion cascades. Because of the high
inertial properties of diffusion cascades, any
interruption in their operation, and
especially their shut-down, leads to serious
consequences. Therefore, a strict and
constant maintenance of vacuum in all
technological systems, automatic protection
for accidents, and precise automated
regulation of the gas flow is of importance in
a gaseous diffusion plant. All this leads to a
need to equip the plant with a large number
of special measuring, regulating, and
controlling systems.
Normally UF6 is evaporated from cylinders
placed within autoclaves and is distributed
in gaseous form to the entry point by way of
cascade header pipework. The ‘‘product’’ and
‘‘tails’’ UF6 gaseous streams flowing from exit
points are passed by way of cascade header
pipework to either cold traps or to
compression stations where the UF6 gas is
liquified prior to onward transfer into
suitable containers for transportation or
storage. Because a gaseous diffusion
enrichment plant consists of a large number
of gaseous diffusion assemblies arranged in
cascades, there are many kilometers of
cascade header pipework, incorporating
thousands of welds with substantial amounts
of repetition of layout. The equipment,
components, and piping systems are
fabricated to very high vacuum and
cleanliness standards.
The items listed below either come into
direct contact with the UF6 process gas or
directly control the flow within the cascade.
All surfaces which come into contact with
the process gas are wholly made of, or lined
with, UF6-resistant materials. For the
purposes of this appendix, the materials
resistant to corrosion by UF6 include copper,
copper alloys, stainless steel, aluminum,
aluminum oxide, aluminum alloys, nickel or
alloys containing 60 percent or more nickel
and fluorinated hydrocarbon polymers.
1. Assemblies and components especially
designed or prepared for use in gaseous
diffusion enrichment.
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1.1 Gaseous Diffusion Barriers and Barrier
Materials
(a) Especially designed or prepared thin,
porous filters, with a pore size of 10–100 nm,
a thickness of 5 mm or less, and for tubular
forms, a diameter of 25 mm or less, made of
metallic, polymer or ceramic materials
resistant to corrosion by UF6 (See Note in § 2
of this appendix).
(b) Especially prepared compounds or
powders for the manufacture of such filters.
Such compounds and powders include
nickel or alloys containing 60 percent or
more nickel, aluminum oxide, or UF6resistant fully fluorinated hydrocarbon
polymers having a purity of 99.9 percent by
weight or more, a particle size less than 10
mm, and a high degree of particle size
uniformity, which are especially prepared for
the manufacture of gaseous diffusion barriers.
1.2 Diffuser Housings
Especially designed or prepared
hermetically sealed vessels for containing the
gaseous diffusion barrier, made of or
protected by UF6-resistant materials (See
Note in § 2 of this appendix).
1.3 Compressors and Gas Blowers
Especially designed or prepared
compressors or gas blowers with a suction
volume capacity of 1 m3 per minute or more
of UF6, and with a discharge pressure of up
to 500 kPa, designed for long-term operation
in the UF6 environment, as well as separate
assemblies of such compressors and gas
blowers. These compressors and gas blowers
have a pressure ratio of 10:1 or less and are
made of, or protected by, materials resistant
to UF6 (See Note in § 2 of this appendix).
1.4 Rotary Shaft Seals
Especially designed or prepared vacuum
seals, with seal feed and seal exhaust
connections, for sealing the shaft connecting
the compressor or the gas blower rotor with
the driver motor so as to ensure a reliable
seal against in-leaking of air into the inner
chamber of the compressor or gas blower
which is filled with UF6. Such seals are
normally designed for a buffer gas in-leakage
rate of less than 1000 cm3 per minute.
1.5 Heat Exchangers for Cooling UF6
Especially designed or prepared heat
exchangers made of or protected by UF6
resistant materials (see Note to § 2 of this
appendix) and intended for a leakage
pressure change rate of less than 10 Pa per
hour under a pressure difference of 100 kPa.
2. Auxiliary systems, equipment, and
components especially designed or prepared
for use in gaseous diffusion enrichment.
Note: The items listed below either come
into direct contact with the UF6 process gas
or directly control the flow within the
cascade. Materials resistant to corrosion by
UF6 include copper, copper alloys, stainless
steel, aluminum, aluminum oxide, aluminum
alloys, nickel or alloys containing 60 percent
or more nickel, and fluorinated hydrocarbon
polymers.
2.1 Feed Systems/Product and Tails
Withdrawal Systems
Especially designed or prepared process
systems or equipment for enrichment plants
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made of, or protected by, materials resistant
to corrosion by UF6, including:
(1) Feed autoclaves, ovens, or systems used
for passing UF6 to the enrichment process;
(2) Desublimers, cold traps, or pumps used
to remove UF6 from the enrichment process
for subsequent transfer upon heating;
(3) Solidification or liquefaction stations
used to remove UF6 from the enrichment
process by compressing and converting UF6
to a liquid or solid form;
(4) ‘‘Product’’ or ‘‘tails’’ stations used for
transferring UF6 into containers.
2.2 Header Piping Systems
Especially designed or prepared piping
systems and header systems for handling UF6
within the gaseous diffusion cascades. This
piping network is normally of the ‘‘double’’
header system with each cell connected to
each of the headers.
2.3 Vacuum Systems
(a) Especially designed or prepared
vacuum manifolds, vacuum headers and
vacuum pumps having a suction capacity of
5 m3 per minute or more.
(b) Vacuum pumps especially designed for
service in UF6-bearing atmospheres made of,
or protected by, materials resistant to
corrosion by UF6 (See Note to this section).
These pumps may be either rotary or positive
displacement, may have fluorocarbon seals,
and may have special working fluids present.
2.4 Special Shut-Off and Control Valves
Especially designed or prepared bellowssealed valves, manual or automated, shut-off
or control valves, made of, or protected by,
materials resistant to corrosion by UF6, for
installation in main and auxiliary systems of
gaseous diffusion enrichment plants.
2.5 UF6 Mass Spectrometers/Ion Sources
Especially designed or prepared mass
spectrometers capable of taking on-line
samples from UF6 gas streams and having all
of the following:
(a) Capable of measuring ions of 320
atomic mass units or greater and having a
resolution of better than 1 part in 320;
(b) ion sources constructed of or protected
by nickel, nickel-copper alloys with a nickel
content of 60 percent or more by weight, or
nickel-chrome alloys;
(c) electron bombardment ionization
sources; and
(d) having a collector system suitable for
isotopic analysis.
3. Any other components especially
designed or prepared for use in a gaseous
diffusion enrichment plant or in any of the
components described in this appendix.
10. Revise appendix D to part 110 to
read as follows:
tkelley on DSK3SPTVN1PROD with RULES
■
Appendix D to Part 110—Illustrative
List of Aerodynamic Enrichment Plant
Equipment and Components Under
NRC Export Licensing Authority
Note: In aerodynamic enrichment
processes, a mixture of gaseous UF6 and light
gas (hydrogen or helium) is compressed and
then passed through separating elements
wherein isotopic separation is accomplished
by the generation of high centrifugal forces
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over a curved-wall geometry. Two processes
of this type have been successfully
developed: The separation nozzle process
and the vortex tube process. For both
processes, the main components of a
separation stage included cylindrical vessels
housing the special separation elements
(nozzles or vortex tubes), gas compressors,
and heat exchangers to remove the heat of
compression. An aerodynamic plant requires
a number of these stages, so that quantities
can provide an important indication of end
use. Because aerodynamic processes use UF6,
all equipment, pipeline and instrumentation
surfaces (that come in contact with the gas)
must be made of, or protected by, materials
that remain stable in contact with UF6. All
surfaces which come into contact with the
process gas are made of, or protected by, UF6resistant materials; including copper, copper
alloys, stainless steel, aluminum, aluminum
oxide, aluminum alloys, nickel or alloys
containing 60 percent or more nickel by
weight, and fluorinated hydrocarbon
polymers.
The following items either come into direct
contact with the UF6 process gas or directly
control the flow within the cascade:
(1) Separation nozzles and assemblies.
Especially designed or prepared separation
nozzles and assemblies thereof. The
separation nozzles consist of slit-shaped,
curved channels having a radius of curvature
less than 1 mm, resistant to corrosion by UF6
and having a knife-edge within the nozzle
that separates the gas flowing through the
nozzle into two fractions.
(2) Vortex tubes and assemblies.
Especially designed or prepared vortex
tubes and assemblies thereof. The vortex
tubes are cylindrical or tapered, made of, or
protected by, materials resistant to corrosion
by UF6, and with one or more tangential
inlets. The tubes may be equipped with
nozzle-type appendages at either or both
ends.
The feed gas enters the vortex tube
tangentially at one end or through swirl
vanes or at numerous tangential positions
along the periphery of the tube.
(3) Compressors and gas blowers.
Especially designed or prepared
compressors or gas blowers made of, or
protected by, materials resistant to corrosion
by the UF6/carrier gas (hydrogen or helium)
mixture.
(4) Rotary shaft seals.
Especially designed or prepared rotary
shaft seals, with seal feed and seal exhaust
connections, for sealing the shaft connecting
the compressor rotor or the gas blower rotor
with the driver motor to ensure a reliable seal
against out-leakage of process gas or inleakage of air or seal gas into the inner
chamber of the compressor or gas blower
which is filled with a UF6/carrier gas
mixture.
(5) Heat exchangers for gas cooling.
Especially designed or prepared heat
exchangers, made of, or protected by,
materials resistant to corrosion by UF6.
(6) Separation element housings.
Especially designed or prepared separation
element housings, made of, or protected by,
materials resistant to corrosion by UF6, for
containing vortex tubes or separation
nozzles.
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(7) Feed systems/product and tails
withdrawal systems.
Especially designed or prepared process
systems or equipment for enrichment plants
made of, or protected by, materials resistant
to corrosion by UF6, including:
(i) Feed autoclaves, ovens, or systems used
for passing UF6 to the enrichment process;
(ii) Desublimers (or cold traps) used to
remove UF6 from the enrichment process for
subsequent transfer upon heating;
(iii) Solidification or liquefaction stations
used to remove UF6 from the enrichment
process by compressing and converting UF6
to a liquid or solid form; and
(iv) ‘‘Product’’ or ‘‘tails’’ stations used for
transferring UF6 into containers.
(8) Header piping systems.
Especially designed or prepared header
piping systems, made of or protected by
materials resistant to corrosion by UF6, for
handling UF6 within the aerodynamic
cascades. The piping network is normally of
the ‘‘double’’ header design with each stage
or group of stages connected to each of the
headers.
(9) Vacuum systems and pumps.
(i) Especially designed or prepared vacuum
systems consisting of vacuum manifolds,
vacuum headers and vacuum pumps, and
designed for service in UF6-bearing
atmospheres.
(ii) Especially designed or prepared
vacuum pumps for service in UF6-bearing
atmospheres and made of, or protected by,
materials resistant to corrosion by UF6. These
pumps may use fluorocarbon seals and
special working fluids.
(10) Special shut-off and control valves.
Especially designed or prepared bellowssealed valves, manual or automated, shut-off
or control valves made of, or protected by,
materials resistant to corrosion by UF6 with
a diameter of 40 mm or greater for
installation in main and auxiliary systems of
aerodynamic enrichment plants.
(11) UF6 mass spectrometers/ion sources.
Especially designed or prepared mass
spectrometers capable of taking on-line
samples from UF6 gas streams and having all
of the following:
(i) Capable of measuring ions of 320 atomic
mass units or greater and having a resolution
of better than 1 part in 320;
(ii) Ion sources constructed of or protected
by nickel, nickel-copper alloys with a nickel
content of 60 percent or more by weight, or
nickel-chrome alloys;
(iii) Electron bombardment ionization
sources; and
(iv) Collector system suitable for isotopic
analysis.
(12) UF6/carrier gas separation systems.
Especially designed or prepared process
systems for separating UF6 from carrier gas
(hydrogen or helium).
These systems are designed to reduce the
UF6 content in the carrier gas to 1 ppm or
less and may incorporate equipment such as:
(i) Cryogenic heat exchangers and
cryoseparators capable of temperatures of 153
K (–120 °C) or less;
(ii) Cryogenic refrigeration units capable of
temperatures of 153 K (–120 °C) or less;
(iii) Separation nozzle or vortex tube units
for the separation of UF6 from carrier gas; or
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(iv) UF6 cold traps capable of freezing out
UF6.
(13) Any other components especially
designed or prepared for use in an
aerodynamic enrichment plant or in any of
the components described in this appendix.
11. Revise appendix E to part 110 to
read as follows:
■
tkelley on DSK3SPTVN1PROD with RULES
Appendix E to Part 110—Illustrative
List of Chemical Exchange or Ion
Exchange Enrichment Plant Equipment
and Components Under NRC Export
Licensing Authority
Note: The slight difference in mass
between the isotopes of uranium causes
small changes in chemical reaction equilibria
that can be used as a basis for separation of
the isotopes. Two processes have been
successfully developed: Liquid-liquid
chemical exchange and solid-liquid ion
exchange.
A. In the liquid-liquid chemical exchange
process, immiscible liquid phases (aqueous
and organic) are countercurrently contacted
to give the cascading effect of thousands of
separation stages. The aqueous phase
consists of uranium chloride in hydrochloric
acid solution; the organic phase consists of
an extractant containing uranium chloride in
an organic solvent. The contactors employed
in the separation cascade can be liquid-liquid
exchange columns (such as pulsed columns
with sieve plates) or liquid centrifugal
contactors. Chemical conversions (oxidation
and reduction) are required at both ends of
the separation cascade in order to provide for
the reflux requirements at each end. A major
design concern is to avoid contamination of
the process streams with certain metal ions.
Plastic, plastic-lined (including use of
fluorocarbon polymers) and/or glass-lined
columns and piping are therefore used.
(1) Liquid-liquid exchange columns.
Countercurrent liquid-liquid exchange
columns having mechanical power input
especially designed or prepared for uranium
enrichment using the chemical exchange
process. For corrosion resistance to
concentrated hydrochloric acid solutions,
these columns and their internals are
normally made of, or protected by, suitable
plastic materials (such as fluorinated
hydrocarbon polymers) or glass. The stage
residence time of the columns is normally
designed to be 30 seconds or less.
(2) Liquid-liquid centrifugal contactors.
Especially designed or prepared for
uranium enrichment using the chemical
exchange process. These contactors use
rotation to achieve dispersion of the organic
and aqueous streams and then centrifugal
force to separate the phases. For corrosion
resistance to concentrated hydrochloric acid
solutions, the contactors are normally made
of, or protected by, suitable plastic materials
(such as fluorinated hydrocarbon polymers)
or glass. The stage residence time of the
centrifugal contactors is designed to be short
(30 seconds or less).
(3) Uranium reduction systems and
equipment.
(i) Especially designed or prepared
electrochemical reduction cells to reduce
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uranium from one valence state to another for
uranium enrichment using the chemical
exchange process. The cell materials in
contact with process solutions must be
corrosion resistant to concentrated
hydrochloric acid solutions.
The cell cathodic compartment must be
designed to prevent re-oxidation of uranium
to its higher valence state. To keep the
uranium in the cathodic compartment, the
cell may have an impervious diaphragm
membrane constructed of special cation
exchange material. The cathode consists of a
suitable solid conductor such as graphite.
These systems consist of solvent extraction
equipment for stripping the U∂4 from the
organic stream into an aqueous solution,
evaporation and/or other equipment to
accomplish solution pH adjustment and
control, and pumps or other transfer devices
for feeding to the electrochemical reduction
cells. A major design concern is to avoid
contamination of the aqueous stream with
certain metal ions. For those parts in contact
with the process stream, the system is
constructed of equipment made of, or
protected by, materials such as glass,
fluorocarbon polymers, polyphenyl sulfate,
polyether sulfone, and resin-impregnated
graphite.
(ii) Especially designed or prepared
systems at the product end of the cascade for
taking the U∂4 out of the organic stream,
adjusting the acid concentration, and feeding
to the electrochemical reduction cells.
These systems consist of solvent extraction
equipment for stripping the U∂4 from the
organic stream into an aqueous solution,
evaporation and/or other equipment to
accomplish solution pH adjustment and
control, and pumps or other transfer devices
for feeding to the electrochemical reduction
cells. A major design concern is to avoid
contamination of the aqueous stream with
certain metal ions. For those parts in contact
with the process stream, the system is
constructed of equipment made of, or
protected by, materials such as glass,
fluorocarbon polymers, polyphenyl sulfate,
polyether sulfone, and resin-impregnated
graphite.
(4) Feed preparation systems.
Especially designed or prepared systems
for producing high-purity uranium chloride
feed solutions for chemical exchange
uranium isotope separation plants.
These systems consist of dissolution,
solvent extraction and/or ion exchange
equipment for purification and electrolytic
cells for reducing the uranium U∂6 or U∂4
to U∂3. These systems produce uranium
chloride solutions having only a few parts
per million of metallic impurities such as
chromium, iron, vanadium, molybdenum,
and other bivalent or higher multi-valent
cations. Materials of construction for portions
of the system processing high-purity U∂3
include glass, fluorinated hydrocarbon
polymers, polyphenyl sulfate or polyether
sulfone plastic-lined and resin-impregnated
graphite.
(5) Uranium oxidation systems.
Especially designed or prepared systems
for oxidation of U∂3 to U∂4 for return to the
uranium isotope separation cascade in the
chemical exchange enrichment process.
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These systems may incorporate equipment
such as:
(i) Equipment for contacting chlorine and
oxygen with the aqueous effluent from the
isotope separation equipment and extracting
the resultant U∂4 into the stripped organic
stream returning from the product end of the
cascade; and
(ii) Equipment that separates water from
hydrochloric acid so that the water and the
concentrated hydrochloric acid may be
reintroduced to the process at the proper
locations.
B. In the solid-liquid ion-exchange process,
enrichment is accomplished by uranium
adsorption/desorption on a special, fastacting, ion-exchange resin or adsorbent. A
solution of uranium in hydrochloric acid and
other chemical agents is passed through
cylindrical enrichment columns containing
packed beds of the adsorbent. For a
continuous process, a reflux system is
necessary to release the uranium from the
adsorbent back in the liquid flow so that
‘‘product’’ and ‘‘tails’’ can be collected. This
is accomplished with the use of suitable
reduction/oxidation chemical agents that are
fully regenerated in separate external circuits
and that may be partially regenerated within
the isotopic separation columns themselves.
The presence of hot concentrated
hydrochloric acid solutions in the process
requires that the equipment be made of, or
protected by, special corrosion-resistant
materials.
(1) Fast reacting ion exchange resins/
adsorbents.
Especially designed or prepared for
uranium enrichment using the ion exchange
process, including porous macroreticular
resins, and/or pellicular structures in which
the active chemical exchange groups are
limited to a coating on the surface of an
inactive porous support structure, and other
composite structures in any suitable form
including particles or fibers. These ion
exchange resins/adsorbents have diameters of
0.2 mm or less and must be chemically
resistant to concentrated hydrochloric acid
solutions as well as physically strong enough
so as not to degrade in the exchange
columns. The resins/adsorbents are
especially designed to achieve very fast
uranium isotope exchange kinetics (exchange
rate half-time of less than 10 seconds) and are
capable of operating at a temperature in the
range of 373 K (100 °C) to 473 K (200 °C).
(2) Ion exchange columns.
Cylindrical columns greater than 1000 mm
in diameter for containing and supporting
packed beds of ion exchange resin/adsorbent,
especially designed or prepared for uranium
enrichment using the ion exchange process.
These columns are made of, or protected by,
materials (such as titanium or fluorocarbon
plastics) resistant to corrosion by
concentrated hydrochloric acid solutions and
are capable of operating at a temperature in
the range of 373 K (100 °C) to 473 K (200 °C)
and pressures above 0.7 MPa.
(3) Ion exchange reflux systems.
(i) Especially designed or prepared
chemical or electrochemical reduction
systems for regeneration of the chemical
reducing agent(s) used in ion exchange
uranium enrichment cascades.
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The ion exchange enrichment process may
use, for example, trivalent titanium (Ti∂3) as
a reducing cation in which case the reduction
system would regenerate Ti∂3 by reducing
Ti∂4.
(ii) Especially designed or prepared
chemical or electrochemical oxidation
systems for regeneration of the chemical
oxidizing agent(s) used in ion exchange
uranium enrichment cascades.
The ion exchange enrichment process may
use, for example, trivalent iron (Fe∂3) as an
oxidant in which case the oxidation system
would regenerate Fe∂3 by oxidizing Fe∂2.
C. Any other components especially
designed or prepared for use in a chemical
exchange or ion exchange enrichment plant
or in any of the components described in this
appendix.
12. Revise appendix F to part 110 to
read as follows:
■
tkelley on DSK3SPTVN1PROD with RULES
Appendix F to Part 110—Illustrative
List of Laser-Based Enrichment Plant
Equipment and Components Under
NRC Export Licensing Authority
Note: Present systems for enrichment
processes using lasers fall into two
categories: The process medium is atomic
uranium vapor and the process medium is
the vapor of a uranium compound,
sometimes mixed with another gas or gases.
Common nomenclature for these processes
include: First category-atomic vapor laser
isotope separation; and second categorymolecular laser isotope separation including
chemical reaction by isotope selective laser
activation. The systems, equipment, and
components for laser enrichment plants
include: (a) Devices to feed uranium-metal
vapor for selective photo-ionization or
devices to feed the vapor of a uranium
compound (for selective photo-dissociation
or selective excitation/activation); (b) devices
to collect enriched and depleted uranium
metal as ‘‘product’’ and ‘‘tails’’ in the first
category, and devices to collect enriched and
depleted uranium compounds as ‘‘product’’
and ‘‘tails’’ in the second category; (c)
process laser systems to selectively excite the
uranium-235 species; and (d) feed
preparation and product conversion
equipment. The complexity of the
spectroscopy of uranium atoms and
compounds may require incorporation of a
number of available laser and laser optics
technologies.
All surfaces that come into direct contact
with the uranium or UF6 are wholly made of,
or protected by, corrosion-resistant materials.
For laser-based enrichment items, the
materials resistant to corrosion by the vapor
or liquid of uranium metal or uranium alloys
include yttria-coated graphite and tantalum;
and the materials resistant to corrosion by
UF6 include copper, copper alloys, stainless
steel, aluminum, aluminum oxide, aluminum
alloys, nickel or alloys containing 60 percent
or more nickel by weight, and fluorinated
hydrocarbon polymers. Many of the
following items come into direct contact with
uranium metal vapor or liquid or with
process gas consisting of UF6 or a mixture of
UF6 and other gases:
(1) Uranium vaporization systems (atomic
vapor based methods).
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Especially designed or prepared uranium
metal vaporization systems for use in laser
enrichment.
These systems may contain electron beam
guns and are designed to achieve a delivered
power (1 kW or greater) on the target
sufficient to generate uranium metal vapour
at a rate required for the laser enrichment
function.
(2) Liquid or vapor uranium metal
handling systems and components (atomic
vapor based methods).
Especially designed or prepared systems
for handling molten uranium, molten
uranium alloys, or uranium metal vapor.
The liquid uranium metal handling
systems may consist of crucibles and cooling
equipment for the crucibles. The crucibles
and other system parts that come into contact
with molten uranium, molten uranium
alloys, or uranium metal vapor are made of,
or protected by, materials of suitable
corrosion and heat resistance, such as
tantalum, yttria-coated graphite, graphite
coated with other rare earth oxides, or
mixtures thereof.
(3) Uranium metal ‘‘product’’ and ‘‘tails’’
collector assemblies (atomic vapor based
methods).
Especially designed or prepared ‘‘product’’
and ‘‘tails’’ collector assemblies for uranium
metal in liquid or solid form.
Components for these assemblies are made
of or protected by materials resistant to the
heat and corrosion of uranium metal vapor or
liquid, such as yttria-coated graphite or
tantalum, and may include pipes, valves,
fittings, ‘‘gutters,’’ feed-throughs, heat
exchangers and collector plates for magnetic,
electrostatic, or other separation methods.
(4) Separator module housings (atomic
vapor based methods).
Especially designed or prepared cylindrical
or rectangular vessels for containing the
uranium metal vapor source, the electron
beam gun, and the ‘‘product’’ and ‘‘tails’’
collectors. These housings have multiplicity
of ports for electrical and water feedthroughs, laser beam windows, vacuum
pump connections, and instrumentation
diagnostics and monitoring with opening and
closure provisions to allow refurbishment of
internal components.
(5) Supersonic expansion nozzles
(molecular based methods).
Especially designed or prepared supersonic
expansion nozzles for cooling mixtures of
UF6 and carrier gas to 150 K (¥123 °C) or
less which are corrosion resistant to UF6.
(6) ‘‘Product’’ or ‘‘tails’’ collectors
(molecular based methods).
Especially designed or prepared
components or devices for collecting
uranium product material or uranium tails
material following illumination with laser
light.
In one example of molecular laser isotope
separation, the product collectors serve to
collect enriched uranium pentafluoride (UF5)
solid material. The product collectors may
consist of filter, impact, or cyclone-type
collectors, or combinations thereof, and must
be corrosion resistant to the UF5/UF6
environment.
(7) UF6/carrier gas compressors (molecular
based methods).
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Especially designed or prepared
compressors for UF6/carrier gas mixtures,
designed for long term operation in a UF6
environment. Components of these
compressors that come into contact with
process gas are made of, or protected by,
materials resistant to UF6 corrosion.
(8) Rotary shaft seals (molecular based
methods).
Especially designed or prepared rotary
shaft seals, with seal feed and seal exhaust
connections, for sealing the shaft connecting
the compressor rotor with the driver motor to
ensure a reliable seal against out-leakage of
process gas or in-leakage of air or seal gas
into the inner chamber of the compressor
which is filled with a UF6/carrier gas
mixture.
(9) Fluorination systems (molecular based
methods).
Especially designed or prepared systems
for fluorinating UF5 (solid) to UF6 (gas).
These systems are designed to fluorinate
the collected UF5 powder to UF6 for
subsequent collection in product containers
or for transfer as feed for additional
enrichment. In one approach, the
fluorination reaction may be accomplished
within the isotope separation system to react
and recover directly off the ‘‘product’’
collectors. In another approach, the UF5
powder may be removed/transferred from the
‘‘product’’ collectors into a suitable reaction
vessel (e.g., fluidized-bed reactor, screw
reactor or flame tower) for fluorination. In
both approaches, equipment is used for
storage and transfer of fluorine (or other
suitable fluorinating agents) and for
collection and transfer of UF6.
(10) UF6 mass spectrometers/ion sources
(molecular based methods).
Especially designed or prepared mass
spectrometers capable of taking on-line
samples from UF6 gas streams and having all
of the following characteristics:
(i) Capable of measuring ions of 320 atomic
mass units or greater and having a resolution
of better than 1 part in 320;
(ii) Ion sources constructed of or protected
by nickel, nickel-copper alloys with a nickel
content of 60 percent or more by weight, or
nickel-chrome alloys;
(iii) Electron bombardment ionization
sources; and
(iv) Collector system suitable for isotopic
analysis.
(11) Feed systems/product and tails
withdrawal systems (molecular based
methods).
Especially designed or prepared process
systems or equipment for enrichment plants
made of or protected by materials resistant to
corrosion by UF6, including:
(i) Feed autoclaves, ovens, or systems used
for passing UF6 to the enrichment process;
(ii) Desublimers (or cold traps) used to
remove UF6 from the enrichment process for
subsequent transfer upon heating;
(iii) Solidification or liquefaction stations
used to remove UF6 from the enrichment
process by compressing and converting UF6
to a liquid or solid; and
(iv) ‘‘Product’’ or ‘‘tails’’ stations used to
transfer UF6 into containers.
(12) UF6/carrier gas separation systems
(molecular based methods).
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Especially designed or prepared process
systems for separating UF6 from carrier gas.
These systems may incorporate equipment
such as:
(i) Cryogenic heat exchangers or
cryoseparators capable of temperatures of 153
K (¥120 °C) or less;
(ii) Cryogenic refrigeration units capable of
temperatures of 153 K (¥120 °C) or less; or
(iii) UF6 cold traps capable of freezing out
UF6.
(13) Lasers or Laser systems.
Especially designed or prepared for the
separation of uranium isotopes.
The laser system typically contains both
optical and electronic components for the
management of the laser beam (or beams) and
the transmission to the isotope separation
chamber. The laser system for atomic vapor
based methods usually consists of tunable
dye lasers pumped by another type of laser
(e.g., copper vapor lasers or certain solidstate lasers). The laser system for molecular
based methods may consist of CO2 lasers or
excimer lasers and a multi-pass optical cell.
Lasers or laser systems for both methods
require spectrum frequency stabilization for
operation over extended periods of time.
(14) Any other components especially
designed or prepared for use in a laser-based
enrichment plant or in any of the
components described in this appendix.
13. Revise appendix G to part 110 to
read as follows:
■
tkelley on DSK3SPTVN1PROD with RULES
Appendix G to Part 110—Illustrative
List of Plasma Separation Enrichment
Plant Equipment and Components
Under NRC Export Licensing Authority
Note: In the plasma separation process, a
plasma of uranium ions passes through an
electric field tuned to the 235U ion resonance
frequency so that they preferentially absorb
energy and increase the diameter of their
corkscrew-like orbits. Ions with a largediameter path are trapped to produce a
product enriched in 235U. The plasma, made
by ionizing uranium vapor, is contained in a
vacuum chamber with a high-strength
magnetic field produced by a
superconducting magnet. The main
technological systems of the process include
the uranium plasma generation system, the
separator module with superconducting
magnet, and metal removal systems for the
collection of ‘‘product’’ and ‘‘tails.’’
(1) Microwave power sources and
antennae.
Especially designed or prepared
microwave power sources and antennae for
producing or accelerating ions having the
following characteristics: Greater than 30
GHz frequency and greater than 50 kW mean
power output for ion production.
(2) Ion excitation coils.
Especially designed or prepared radio
frequency ion excitation coils for frequencies
of more than 100 kHz and capable of
handling more than 40 kW mean power.
(3) Uranium plasma generation systems.
Especially designed or prepared systems
for the generation of uranium plasma for use
in plasma separation plants.
(4) Uranium metal ‘‘product’’ and ‘‘tails’’
collector assemblies.
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Especially designed or prepared ‘‘product’’
and ‘‘tails’’ collector assemblies for uranium
metal in solid form. These collector
assemblies are made of, or protected by,
materials resistant to the heat and corrosion
of uranium metal vapor, such as yttria-coated
graphite or tantalum.
(5) Separator module housings.
Especially designed or prepared cylindrical
vessels for use in plasma separation
enrichment plants for containing the
uranium plasma source, radio-frequency
drive coil, and the ‘‘product’’ and ‘‘tails’’
collectors.
These housings have a multiplicity of ports
for electrical feed-throughs, diffusion pump
connections, and instrumentation diagnostics
and monitoring. They have provisions for
opening and closure to allow for
refurbishment of internal components and
are constructed of a suitable non-magnetic
material such as stainless steel.
(6) Any other components especially
designed or prepared for use in a plasma
separation enrichment plant or in any of the
components described in this appendix.
14. In appendix H to part 110, add a
new paragraph (4) to read as follows:
■
Appendix H to Part 110—Illustrative
List of Electromagnetic Enrichment
Plant Equipment and Components
Under NRC Export Licensing Authority
*
*
*
*
*
(4) Any other components especially
designed or prepared for use in an
electromagnetic enrichment plant or in any
of the components described in this
appendix.
15. Revise appendix I to part 110 to
read as follows:
■
Appendix I to Part 110—Illustrative
List of Reprocessing Plant Components
Under NRC Export Licensing Authority
Note: Reprocessing irradiated nuclear fuel
separates plutonium and uranium from
intensely radioactive fission products and
other transuranic elements. Different
technical processes can accomplish this
separation. However, over the years Purex
has become the most commonly used and
accepted process. Purex involves the
dissolution of irradiated nuclear fuel in nitric
acid, followed by separation of the uranium,
plutonium, and fission products by solvent
extraction using a mixture of tributyl
phosphate in an organic diluent.
Purex facilities have process functions
similar to each other, including: Irradiated
fuel element chopping, fuel dissolution,
solvent extraction, and process liquor
storage. There may also be equipment for
thermal denitration of uranium nitrate,
conversion of plutonium nitrate to oxide
metal, and treatment of fission product waste
liquor to a form suitable for long term storage
or disposal. However, the specific type and
configuration of the equipment performing
these functions may differ between Purex
facilities for several reasons, including the
type and quantity of irradiated nuclear fuel
to be reprocessed and the intended
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39297
disposition of the recovered materials, and
the safety and maintenance philosophy
incorporated into the design of the facility. A
plant for the reprocessing of irradiated fuel
elements includes the equipment and
components which normally come in direct
contact with and directly control the
irradiated fuel and the major nuclear material
and fission product processing streams.
(1) Irradiated fuel element chopping
machines.
Remotely operated equipment especially
designed or prepared for use in a
reprocessing plant and intended to cut, chop,
or shear irradiated nuclear fuel assemblies,
bundles, or rods. This equipment breaches
the cladding of the fuel to expose the
irradiated nuclear material to dissolution.
Especially designed metal cutting shears are
the most commonly employed, although
advanced equipment, such as lasers, may be
used.
(2) Dissolvers.
Critically safe tanks (e.g. small diameter,
annular, or slab tanks) especially designed or
prepared for use in a reprocessing plant,
intended for dissolution of irradiated nuclear
fuel and which are capable of withstanding
hot, highly corrosive liquid, and which can
be remotely loaded and maintained.
Dissolvers normally receive the choppedup spent fuel. In these critically safe vessels,
the irradiated nuclear material is dissolved in
nitric acid and the remaining hulls removed
from the process stream.
(3) Solvent extractors and solvent
extraction equipment.
Especially designed or prepared solvent
extractors such as packed or pulse columns,
mixer settlers, or centrifugal contactors for
use in a plant for the reprocessing of
irradiated fuel. Solvent extractors must be
resistant to the corrosive effect of nitric acid.
Solvent extractors are normally fabricated to
extremely high standards (including special
welding and inspection and quality
assurance and quality control techniques) out
of low carbon stainless steels, titanium,
zirconium, or other high quality materials.
Solvent extractors both receive the solution
of irradiated fuel from the dissolvers and the
organic solution which separates the
uranium, plutonium, and fission products.
Solvent extraction equipment is normally
designed to meet strict operating parameters,
such as long operating lifetimes with no
maintenance requirements or adaptability to
easy replacement, simplicity of operation and
control, and flexibility for variations in
process conditions.
(4) Chemical holding or storage vessels.
Especially designed or prepared holding or
storage vessels for use in a plant for the
reprocessing of irradiated fuel. The holding
or storage vessels must be resistant to the
corrosive effect of nitric acid. The holding or
storage vessels are normally fabricated of
materials such as low carbon stainless steels,
titanium or zirconium, or other high quality
materials. Holding or storage vessels may be
designed for remote operation and
maintenance and may have the following
features for control of nuclear criticality:
(i) Walls or internal structures with a boron
equivalent of at least 2 percent, or
(ii) A maximum diameter of 175 mm (7 in)
for cylindrical vessels, or
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(iii) A maximum width of 75 mm (3 in) for
either a slab or annular vessel.
(5) Neutron measurement systems for
process control.
Neutron measurement systems especially
designed or prepared for integration and use
with automated process control systems in a
plant for the reprocessing of irradiated fuel
elements. These systems involve the
capability of active and passive neutron
measurement and discrimination in order to
determine the fissile material quantity and
composition. The complete system is
composed of a neutron generator, a neutron
detector, amplifiers, and signal processing
electronics.
The scope of this entry does not include
neutron detection and measurement
instruments that are designed for nuclear
material accountancy and safeguarding or
any other application not related to
integration and use with automated process
control systems in a plant for the
reprocessing of irradiated fuel elements.
(6) Plutonium nitrate to plutonium oxide
conversion systems. Complete systems
especially designed or prepared for the
conversion of plutonium nitrate to plutonium
oxide, in particular adapted so as to avoid
criticality and radiation effects and to
minimize toxicity hazards.
(7) Plutonium metal production systems.
Complete systems especially designed or
prepared for the production of plutonium
metal, in particular adapted so as to avoid
criticality and radiation effects and to
minimize toxicity hazards.
(8) Process control instrumentation
specially designed or prepared for
monitoring or controlling the processing of
material in a reprocessing plant.
(9) Any other components especially
designed or prepared for use in a
reprocessing plant or in any of the
components described in this appendix.
16. In appendix J to part 110, add a
new paragraph (c) to read as follows:
■
Appendix J to Part 110—Illustrative
List of Uranium Conversion Plant
Equipment and Plutonium Conversion
Plant Equipment Under NRC Export
Licensing Authority
*
*
*
*
*
(c) Any other components especially
designed or prepared for use in a uranium
conversion plant or plutonium conversion
plant or in any of the components described
in this appendix.
17. Revise appendix K to part 110 to
read as follows:
tkelley on DSK3SPTVN1PROD with RULES
■
Appendix K to Part 110—Illustrative
List of Equipment and Components
Under NRC Export Licensing Authority
for Use in a Plant for the Production of
Heavy Water, Deuterium and
Deuterium Compounds
Note: Heavy water can be produced by a
variety of processes. However, two processes
have proven to be commercially viable: The
water-hydrogen sulphide exchange process
(GS process) and the ammonia-hydrogen
exchange process.
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A. The GS process is based upon the
exchange of hydrogen and deuterium
between water and hydrogen sulphide within
a series of towers which are operated with
the top section cold and the bottom section
hot. Water flows down the towers while the
hydrogen sulphide gas circulates from the
bottom to the top of the towers. A series of
perforated trays are used to promote mixing
between the gas and the water. Deuterium
migrates to the water at low temperatures and
to the hydrogen sulphide at high
temperatures. Gas or water, enriched in
deuterium, is removed from the first stage
towers at the junction of the hot and cold
sections and the process is repeated in
subsequent stage towers. The product of the
last stage, water enriched up to 30 percent in
deuterium, is sent to a distillation unit to
produce reactor grade heavy water; i.e., 99.75
percent deuterium oxide.
B. The ammonia-hydrogen exchange
process can extract deuterium from synthesis
gas through contact with liquid ammonia in
the presence of a catalyst. The synthesis gas
is fed into exchange towers and then to an
ammonia converter. Inside the towers the gas
flows from the bottom to the top while the
liquid ammonia flows from the top to the
bottom. The deuterium is stripped from the
hydrogen in the synthesis gas and
concentrated in the ammonia. The ammonia
then flows into an ammonia cracker at the
bottom of the tower while the gas flows into
an ammonia converter at the top. Further
enrichment takes place in subsequent stages
and reactor-grade heavy water is produced
through final distillation. The synthesis gas
feed can be provided by an ammonia plant
that can be constructed in association with a
heavy water ammonia-hydrogen exchange
plant. The ammonia-hydrogen exchange
process can also use ordinary water as a feed
source of deuterium.
C.1. Much of the key equipment for heavy
water production plants using either the GS
process or the ammonia-hydrogen exchange
process are common to several segments of
the chemical and petroleum industries;
particularly in small plants using the GS
process. However, few items are available
‘‘off-the-shelf.’’ Both processes require the
handling of large quantities of flammable,
corrosive, and toxic fluids at elevated
pressures. Therefore, in establishing the
design and operating standards for plants and
equipment using these processes, careful
attention to materials selection and
specifications is required to ensure long
service life with high safety and reliability
factors. The choice is primarily a function of
economics and need. Most equipment,
therefore, is prepared to customer
requirements.
In both processes, equipment which
individually is not especially designed or
prepared for heavy water production can be
assembled into especially designed or
prepared systems for producing heavy water.
Examples of such systems are the catalyst
production system used in the ammoniahydrogen exchange process and the water
distillation systems used for the final
concentration of heavy water to reactor-grade
in either process.
C.2. Equipment especially designed or
prepared for the production of heavy water
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utilizing either the water-hydrogen sulphide
exchange process or the ammonia-hydrogen
exchange process:
(i) Water-hydrogen Sulphide Exchange
Towers.
Exchange towers with diameters of 1.5 m
or greater and capable of operating at
pressures greater than or equal to 2 MPa (300
psi) especially designed or prepared for
heavy water production utilizing the waterhydrogen sulphide exchange process.
(ii) Blowers and Compressors.
Single stage, low head (i.e., 0.2 MPa or 30
psi) centrifugal blowers or compressors for
hydrogen-sulphide gas circulation (i.e., gas
containing more than 70 percent H2S). The
blowers or compressors have a throughput
capacity greater than or equal to 56 m3/
second (120,000 standard cubic feet per
minute) while operating at pressures greater
than or equal to 1.8 MPa (260 psi) suction
and have seals designed for wet H2S service.
(iii) Ammonia-Hydrogen Exchange Towers.
Ammonia-hydrogen exchange towers
greater than or equal to 35 m (114.3 ft) in
height with diameters of 1.5 m (4.9 ft) to 2.5
m (8.2 ft) capable of operating at pressures
greater than 15 MPa (2225 psi). The towers
have at least one flanged, axial opening of the
same diameter as the cylindrical part through
which the tower internals can be inserted or
withdrawn.
(iv) Tower Internals and Stage Pumps Used
in the Ammonia-hydrogen Exchange Process.
Tower internals include especially
designed stage contactors which promote
intimate gas/liquid contact. Stage pumps
include especially designed submersible
pumps for circulation of liquid ammonia
within a contacting stage internal to the stage
towers.
(v) Ammonia Crackers Utilizing the
Ammonia-hydrogen Exchange Process.
Ammonia crackers with operating
pressures greater than or equal to 3 MPa (450
psi) especially designed or prepared for
heavy water production utilizing the
ammonia-hydrogen exchange process.
(vi) Ammonia Synthesis Converters or
Synthesis Units.
Ammonia synthesis converters or synthesis
units especially designed or prepared for
heavy water production utilizing the
ammonia-hydrogen exchange process.
These converters or units take synthesis
gas (nitrogen and hydrogen) from an
ammonia/hydrogen high-pressure exchange
column (or columns), and the synthesized
ammonia is returned to the exchange column
(or columns).
(vii) Infrared Absorption Analyzers.
Infrared absorption analyzers capable of
‘‘on-line’’ hydrogen/deuterium ratio analysis
where deuterium concentrations are equal to
or greater than 90 percent.
(viii) Catalytic Burners Used in the
Ammonia-hydrogen Exchange Process.
Catalytic burners for the conversion of
enriched deuterium gas into heavy water
especially designed or prepared for heavy
water production utilizing the ammoniahydrogen exchange process.
(ix) Complete Heavy Water Upgrade
Systems or Columns.
Complete heavy water upgrade systems or
columns especially designed or prepared for
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the upgrade of heavy water to reactor-grade
deuterium concentration. These systems,
which usually employ water distillation to
separate heavy water from light water, are
especially designed or prepared to produce
reactor-grade heavy water (i.e., typically
99.75 percent deuterium oxide) from heavy
water feedstock of lesser concentration.
D. Any other components especially
designed or prepared for use in a plant for
the production of heavy water, deuterium,
and deuterium compounds or in any of the
components described in this appendix.
39299
18. Revise appendix M to part 110 to
read as follows:
■
Appendix M to Part 110—
Categorization of Nuclear Material
CATEGORIZATION OF NUCLEAR MATERIAL
[From IAEA INFCIRC/225/Revision 5]
Form
Category I
1. Plutonium1 ........
Unirradiated 2 ........................
2 kg or more ........................
Less than 2 kg but more
than 500 g.
500 g or less but more than
15 g.
2. Uranium-235
(235U).
Unirradiated 2:
—Uranium enriched to
20 percent 235U or
more.
—Uranium enriched to
10 percent 235U but
less than 20 percent
235U.
—Uranium enriched
above natural, but
less than 10 percent
235U.
Unirradiated 2 ........................
5 kg or more ........................
Less than 5 kg but more
than 1 kg.
1 kg or less but more than
15 g.
..............................................
10 kg or more ......................
Less than 10 kg but more
than 1 kg.
..............................................
..............................................
10 kg or more.
2 kg or more ........................
500 g or less but more than
15 g.
..............................................
..............................................
Less than 2 kg but more
than 500 g.
Depleted or natural uranium,
thorium or low enriched
fuel (less than 10 percent
fissile content) 4 5
3. Uranium-233
(233U).
4. Irradiated Fuel
(The categorization of irradiated
fuel in the table
is based on
international
transport considerations. The
State may assign
a different category for domestic use, storage
and transport
taking all relevant factors into
account).
Category II
Category III 3
Material
1 All
plutonium except that with isotopic concentration exceeding 80 percent in plutonium-238.
not irradiated in a reactor or material irradiated in a reactor but with a radiation level equal to or less than 1 Gy/h (100 rad/h) at 1 m
unshielded.
3 Quantities not falling in Category III and natural uranium, depleted uranium and thorium should be protected at least in accordance with prudent management practice.
4 Although this level of protection is recommended, it would be open to States, upon evaluation of the specific circumstances, to assign a different category of physical protection.
5 Other fuel which by virtue of its original fissile material content is classified as Category I or II before irradiation may be reduced one category
level while the radiation level from the fuel exceeds 1 Gy/h (100 rad/h) at one meter unshielded.
2 Material
19. In appendix N to part 110, add a
new paragraph c. to read as follows:
■
Appendix N to Part 110—Illustrative
List of Lithium Isotope Separation
Facilities, Plants and Equipment Under
NRC’s Export Licensing Authority
tkelley on DSK3SPTVN1PROD with RULES
*
*
*
*
*
c. Any other components especially
designed or prepared for use in a
reprocessing plant or in any of the
components described in this appendix.
20. Revise appendix O to part 110 to
read as follows:
■
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Appendix O to Part 110—Illustrative
List of Fuel Element Fabrication Plant
Equipment and Components Under
NRC’s Export Licensing Authority
Note: Nuclear fuel elements are
manufactured from source or special nuclear
material. For oxide fuels, the most common
type of fuel equipment for pressing pellets,
sintering, grinding and grading will be
present. Mixed oxide fuels are handled in
glove boxes (or equivalent containment) until
they are sealed in the cladding. In all cases,
the fuel is hermetically sealed inside a
suitable cladding which is designed to be the
primary envelope encasing the fuel so as to
provide suitable performance and safety
during reactor operation. Also, in all cases,
precise control of processes, procedures and
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equipment to extremely high standards is
necessary in order to ensure predictable and
safe fuel performance.
(a) Items that are considered especially
designed or prepared for the fabrication of
fuel elements include equipment that:
(1) Normally comes in direct contact with,
or directly processes or controls, the
production flow of nuclear material;
(2) Seals the nuclear material within the
cladding;
(3) Checks the integrity of the cladding or
the seal;
(4) Checks the finished treatment of the
sealed fuel; or
(5) Is used for assembling reactor fuel
elements.
(b) This equipment or systems of
equipment may include, for example:
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Federal Register / Vol. 79, No. 132 / Thursday, July 10, 2014 / Rules and Regulations
(1) Fully automatic pellet inspection
stations especially designed or prepared for
checking final dimensions and surface
defects of fuel pellets;
(2) Automatic welding machines especially
designed or prepared for welding end caps
onto the fuel pins (or rods);
(3) Automatic test and inspection stations
especially designed or prepared for checking
the integrity of completed fuel pins (or rods).
This item typically includes equipment for:
(i) X-ray examination of pin (or rod) end
cap welds;
(ii) Helium leak detection from pressurized
pins (or rods); and
(iii) Gamma-ray scanning of the pins (or
rods) to check for correct loading of the fuel
pellets inside.
(4) Systems especially designed or
prepared to manufacture nuclear fuel
cladding.
(c) Any other components especially
designed or prepared for use in a fuel
element fabrication plant or in any of the
components described in this appendix.
Dated at Rockville, Maryland, this 18th day
of June, 2014.
For the Nuclear Regulatory Commission.
Mark A. Satorius,
Executive Director for Operations.
[FR Doc. 2014–15828 Filed 7–9–14; 8:45 am]
BILLING CODE 7590–01–P
DEPARTMENT OF TRANSPORTATION
Federal Aviation Administration
14 CFR Part 39
[Docket No. FAA–2014–0341; Directorate
Identifier 2014–NM–102–AD; Amendment
39–17874; AD 2014–12–13]
RIN 2120–AA64
Airworthiness Directives; the Boeing
Company Airplanes
Federal Aviation
Administration (FAA), DOT.
ACTION: Final rule; request for
comments.
AGENCY:
tkelley on DSK3SPTVN1PROD with RULES
VerDate Mar<15>2010
16:13 Jul 09, 2014
Jkt 232001
This AD is effective July 25,
2014.
The Director of the Federal Register
approved the incorporation by reference
of a certain publication listed in this AD
as of April 9, 2014 (79 FR 12368, March
5, 2014).
We must receive any comments on
this AD by August 25, 2014.
ADDRESSES: You may send comments,
using the procedures found in 14 CFR
11.43 and 11.45, by any of the following
methods:
• Federal eRulemaking Portal: Go to
https://www.regulations.gov. Follow the
instructions for submitting comments.
• Fax: 202–493–2251.
• Mail: U.S. Department of
Transportation, Docket Operations, M–
30, West Building Ground Floor, Room
W12–140, 1200 New Jersey Avenue SE.,
Washington, DC 20590.
• Hand Delivery: U.S. Department of
Transportation, Docket Operations, M–
30, West Building Ground Floor, Room
W12–140, 1200 New Jersey Avenue SE.,
Washington, DC 20590, between 9 a.m.
and 5 p.m., Monday through Friday,
except Federal holidays.
For service information identified in
this AD, contact Boeing Commercial
Airplanes, Attention: Data & Services
Management, P.O. Box 3707, MC 2H–65,
Seattle, WA 98124–2207; telephone
206–544–5000, extension 1; fax 206–
766–5680; Internet https://
www.myboeingfleet.com. You may view
this referenced service information at
the FAA, Transport Airplane
Directorate, 1601 Lind Avenue SW.,
Renton, WA. For information on the
availability of this material at the FAA,
call 425–227–1221.
DATES:
Examining the AD Docket
We are superseding
Airworthiness Directive (AD) 2014–03–
06 for all the Boeing Company Model
737–100, –200, –200C, –300, –400, and
–500 series airplanes. AD 2014–03–06
required repetitive inspections for
cracking of the aft support fitting for the
main landing gear (MLG) beam, and the
rear spar upper chord and rear spar web
in the area of rear spar station (RSS)
224.14; and repair if necessary. This AD
clarifies two paragraph references. This
AD was prompted by a determination
that two paragraph references were in
error. We are issuing this AD to detect
and correct cracking of the aft support
fitting for the main landing gear (MLG)
beam, and the rear spar upper chord and
SUMMARY:
rear spar web in the area of rear spar
station (RSS) 224.14, which could grow
and result in a fuel leak and possible
fire.
You may examine the AD docket on
the Internet at https://
www.regulations.gov by searching for
and locating Docket No. FAA–2014–
0341; or in person at the Docket
Management Facility between 9 a.m.
and 5 p.m., Monday through Friday,
except Federal holidays. The AD docket
contains this AD, the regulatory
evaluation, any comments received, and
other information. The street address for
the Docket Office (phone: 800–647–
5527) is in the ADDRESSES section.
Comments will be available in the AD
docket shortly after receipt.
FOR FURTHER INFORMATION CONTACT:
Nancy Marsh, Aerospace Engineer,
Airframe Branch, ANM–120S, FAA,
Seattle Aircraft Certification Office
PO 00000
Frm 00012
Fmt 4700
Sfmt 4700
(ACO), 1601 Lind Avenue SW., Renton,
WA 98057–3356; phone: 425–917–6440;
fax: 425–917–6590; email:
nancy.marsh@faa.gov.
SUPPLEMENTARY INFORMATION:
Discussion
On January 18, 2014, we issued AD
2014–03–06, Amendment 39–17743 (79
FR 12368, March 5, 2014), for all the
Boeing Company Model 737–100, –200,
–200C, –300, –400, and –500 series
airplanes. AD 2014–03–06 required
repetitive inspections for cracking of the
aft support fitting for the main landing
gear (MLG) beam, and the rear spar
upper chord and rear spar web in the
area of rear spar station (RSS) 224.14;
and repair if necessary. AD 2014–03–06
resulted from reports of cracks found in
the aft support fitting, the rear spar
upper chord, and the rear spar web. We
issued AD 2014–03–06 to detect and
correct cracking of the aft support fitting
for the main landing gear (MLG) beam,
and the rear spar upper chord and rear
spar web in the area of rear spar station
(RSS) 224.14, which could grow and
result in a fuel leak and possible fire.
Actions Since AD 2014–03–06 Was
Issued
Since we issued AD 2014–03–06,
Amendment 39–17743 (79 FR 12368,
March 5, 2014), two incorrect paragraph
references were found. The references to
paragraphs (g) and (g)(1) in paragraph
(h)(2) of AD 2014–03–06 are incorrect.
The correct reference should be to the
introductory text of paragraph (h) and
paragraph (h)(1) of AD 2014–03–06.
Paragraph (h)(2) of AD 2014–03–06 is
the corrective action for the inspections
required by the introductory text of
paragraph (h) and paragraph (h)(1) of
this AD. In order to mandate the
corrective actions for the inspections
required by the introductory text of
paragraph (h) and paragraph (h)(1) of
this AD, we have revised the references
in paragraph (h)(2) of this AD.
FAA’s Determination
We are issuing this AD because we
evaluated all the relevant information
and determined the unsafe condition
described previously is likely to exist or
develop in other products of these same
type designs.
AD Requirements
This AD requires repetitive
inspections for cracking of the aft
support fitting for the MLG beam, and
the rear spar upper chord and rear spar
web in the area of RSS 224.14; and
repair if necessary. This AD corrects
these paragraph references.
E:\FR\FM\10JYR1.SGM
10JYR1
]]>Agencies
[Federal Register Volume 79, Number 132 (Thursday, July 10, 2014)]
[Rules and Regulations]
[Pages 39289-39300]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-15828]
========================================================================
Rules and Regulations
Federal Register
________________________________________________________________________
This section of the FEDERAL REGISTER contains regulatory documents
having general applicability and legal effect, most of which are keyed
to and codified in the Code of Federal Regulations, which is published
under 50 titles pursuant to 44 U.S.C. 1510.
The Code of Federal Regulations is sold by the Superintendent of Documents.
Prices of new books are listed in the first FEDERAL REGISTER issue of each
week.
========================================================================
Federal Register / Vol. 79, No. 132 / Thursday, July 10, 2014 / Rules
and Regulations
[[Page 39289]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 110
RIN 3150-AJ33
[NRC-2014-0007]
Export Controls and Physical Security Standards
AGENCY: Nuclear Regulatory Commission.
ACTION: Final rule.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its
regulations pertaining to the export and import of nuclear materials
and equipment. This rulemaking is necessary to conform the export
controls of the United States to the international export control
guidelines of the Nuclear Suppliers Group (NSG), of which the United
States is a member, and to incorporate by reference the current version
of the International Atomic Energy Agency's (IAEA) document, ``Nuclear
Security Recommendations on Physical Protection of Nuclear Material and
Nuclear Facilities (INFCIRC/225/Revision 5), January 2011.'' Also, this
final rule makes certain editorial revisions, and corrects
typographical errors.
DATES: The final rule is effective August 11, 2014, except that the
changes to Sec. 110.44(a) and (b)(1) and appendix M to 10 CFR part 110
are effective December 31, 2014. The incorporation by reference of the
material in this document is approved as of December 31, 2014.
ADDRESSES: Please refer to Docket ID NRC-2014-0007 when contacting the
NRC about the availability of information for this final rule. You can
access publicly-available information related to this final rule by any
of the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2014-0007. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this final rule.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. The
ADAMS accession number for each document referenced in this document
(if that document is available in ADAMS) is provided the first time
that a document is referenced.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Brooke G. Smith, Office of
International Programs, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001, telephone: 301-415-2347, email: Brooke.Smith@nrc.gov.
SUPPLEMENTARY INFORMATION:
Table of Contents
I. Background
II. Section-by-Section Analysis
III. Regulatory Flexibility Certification
IV. Regulatory Analysis
V. Backfitting and Issue Finality
VI. Plain Writing
VII. Environmental Impact Statement
VIII. Paperwork Reduction Act
IX. Congressional Review Act
X. Voluntary Consensus Standards
I. Background
The NSG is a group of like-minded States that seeks to contribute
to the nonproliferation of nuclear weapons through the implementation
of guidelines for nuclear exports and nuclear-related exports. As a
participating government in the NSG, the United States has committed to
controlling for export items on the NSG control lists. Participating
governments are charged with implementing the changes adopted to the
list as soon as possible after approval.
This final rule conforms the NRC's export and import regulations in
10 CFR part 110, ``Export and Import of Nuclear Equipment and
Material,'' and appendices A, B, C, D, E, F, G, H, I, J, K, N, and O,
which contain illustrative lists of items under the NRC's export
licensing authority, to current nuclear nonproliferation policies of
the Executive Branch. These revisions are necessary to implement
changes made to the NSG Guidelines, ``Guidelines for Nuclear Transfers
(INFCIRC/254/Revision 12/Part 1), June 2013,'' as adopted by the
governments participating in the NSG at the June 2012 and 2013 Plenary
Meetings. In addition, this rule amends Sec. 110.30, ``Members of the
Nuclear Suppliers Group,'' to add Mexico and Serbia as member countries
of the NSG that are eligible to receive radioactive materials under
certain general licenses for export. The NSG Guidelines can be found
at: www.nuclearsuppliersgroup.org.
In January 2011, the IAEA published the document titled, ``Nuclear
Security Recommendations on Physical Protection of Nuclear Material and
Nuclear Facilities (INFCIRC/225/Revision 5).'' This rule also amends
Sec. 110.44 and appendix M to 10 CFR part 110 to incorporate by
reference the update and recommendations contained in Revision 5 of
this IAEA document.
The NRC staff has determined that these changes are consistent with
current U.S. policy, and will pose no unreasonable risk to the public
health and safety or to the common defense and security of the United
States.
Because this rule involves a foreign affairs function of the United
States, the notice and comment provisions of the Administrative
Procedure Act do not apply (5 U.S.C. 553(a)(1)). In addition,
solicitation of public comments would delay the U.S. conformance with
its international obligations, and would be contrary to the public
interest (5 U.S.C. 553(b)). The final rule is effective August 11,
2014, except that the changes to Sec. 110.44(a) and (b)(1) and
appendix M to 10 CFR part 110 are effective December 31, 2014.
[[Page 39290]]
II. Section by Section Analysis
Section 110.2 Definitions
Paragraph (2)(ii) of the definition of ``Utilization facility'' is
amended to make conforming changes consistent with the changes to
appendix A to 10 CFR part 110.
Section 110.26 General License for the Export of Nuclear Reactor
Components
This rule amends Sec. 110.26 to make conforming changes to
paragraph (a) consistent with the changes to appendix A to 10 CFR part
110.
Section 110.30 Members of the Nuclear Suppliers Group
This rule amends Sec. 110.30 to update the list of NSG members by
adding Mexico and Serbia.
Section 110.42 Export Licensing Criteria
This rule amends Sec. 110.42 to make conforming changes to
Footnote 1 consistent with the changes to appendix A to 10 CFR part
110.
Section 110.44 Physical Security Standards
Paragraphs (a) and (b)(1) of Sec. 110.44 are amended to
incorporate by reference the most recent revision to INFCIRC/225/
Revision 5, ``The Physical Protection of Nuclear Material and Nuclear
Facilities.'' The effective date for these changes is delayed until
December 31, 2014, to provide adequate time for countries to meet the
recommendations in Revision 5. ``The Physical Protection of Nuclear
Material and Nuclear Facilities,'' INFCIRC/225/Revision 4 (corrected),
July 1999, will continue to be used as the physical protection standard
in recipient countries until the effective date for INFCIRC/225/
Revision 5, as incorporated by reference in 10 CFR part 110.
Appendices A, B, C, D, E, F, G, H, I, J, K, N and O to Part 110
These appendices are amended to reflect the updated guidelines of
the NSG consistent with the IAEA document, ``Guidelines for Nuclear
Transfers, (INFCIRC/254/Revision 12/Part 1).'' The appendices in 10 CFR
part 110 are illustrative only and are not meant to be inclusive lists
of facilities and equipment under the NRC's export licensing
jurisdiction.
Appendix M to Part 110--Categorization of Nuclear Material
Appendix M is amended to update the Categorization of Nuclear
Material table to be consistent with IAEA publication, INFCIRC/225/
Revision 5. The changes to appendix M of 10 CFR part 110 are effective
December 31, 2014.
III. Regulatory Flexibility Certification
As required by the Regulatory Flexibility Act of 1980 (5 U.S.C.
605(b)), the Commission certifies that this final rule will not have a
significant economic impact on a substantial number of small entities.
This rule affects only companies exporting nuclear equipment and
material to and from the United States and they do not fall within the
scope of the definition of ``small entities'' set forth in the
Regulatory Flexibility Act (5 U.S.C. 601(3)), or the Size Standards
established by the NRC (10 CFR 2.810).
IV. Regulatory Analysis
This rulemaking is necessary to reflect the nuclear
nonproliferation policy of the Executive Branch including U.S.
Government commitments to controlling export items on the NSG control
lists and the IAEA publication, INFCIRC/225/Revision 5. This final rule
is expected to have no changes in the information collection burden or
cost to the public.
V. Backfit Analysis and Issue Finality
The NRC has determined that a backfit analysis is not required for
this rule because these amendments do not include any provisions that
would impose backfits as defined in 10 CFR Chapter I.
VI. Plain Writing
The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal
agencies to write documents in a clear, concise, and well-organized
manner. The NRC has written this document to be consistent with the
Plain Writing Act as well as the Presidential Memorandum, ``Plain
Language in Government Writing,'' published June 10, 1998 (63 FR
31883).
VII. Environmental Impact: Categorical Exclusion
The NRC has determined that this final rule is the type of action
described in categorical exclusion 10 CFR 51.22(c)(1). Therefore,
neither an environmental impact statement nor an environmental
assessment has been prepared for the rule.
VIII. Paperwork Reduction Act Statement
This final rule does not contain new or amended information
collection requirements subject to the Paperwork Reduction Act of 1995
(44 U.S.C. 3501 et seq.). Existing requirements were approved by the
Office of Management and Budget (OMB) under approval number 3150-0036.
Public Protection Notification
The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection
requirement unless the requesting document displays a currently valid
OMB control number.
IX. Congressional Review Act
Under the Congressional Review Act of 1996, the NRC has determined
that this action is not a major rule and has verified this
determination with the Office of Information and Regulatory Affairs of
OMB.
X. Voluntary Consensus Standards
The National Technology Transfer and Advancement Act of 1995 (Pub.
L. 104-113) requires that Federal Agencies use technical standards that
are developed or adopted by voluntary consensus standards bodies unless
using such a standard is inconsistent with applicable law or otherwise
impractical. This final rule does not constitute the establishment of a
standard for which the use of a voluntary consensus standard would be
applicable.
List of Subjects in 10 CFR Part 110
Administrative practice and procedure, Classified information,
Criminal penalties, Export, Import, Incorporation by reference,
Intergovernmental relations, Nuclear materials, Nuclear power plants
and reactors, Reporting and recordkeeping requirements, Scientific
equipment.
For the reasons set out in the preamble and under the authority of
the Atomic Energy Act of 1954, as amended, the Energy Reorganization
Act of 1974, as amended, and 5 U.S.C. 552 and 553, the NRC is adopting
the following amendments to 10 CFR part 110.
PART 110--EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL
0
1. The authority citation for part 110 continues to read as follows:
Authority: Atomic Energy Act secs. 51, 53, 54, 57, 63, 64, 65,
81, 82, 103, 104, 109, 111, 126, 127, 128, 129, 161, 181, 182, 183,
187, 189, 223, 234 (42 U.S.C. 2071, 2073, 2074, 2077, 2092-2095,
2111, 2112, 2133, 2134, 2139, 2139a, 2141, 2154-2158, 2201, 2231-
2233, 2237, 2239, 2273, 2282); Energy Reorganization Act sec. 201
(42 U.S.C. 5841; Solar, Wind, Waste, and Geothermal Power Act of
1990 sec. 5 (42 U.S.C.2243); Government Paperwork Elimination Act
sec.
[[Page 39291]]
1704, 112 Stat. 2750 (44 U.S.C. 3504 note); Energy Policy Act of
2005, 119 Stat. 594.
Sections 110.1(b)(2) and 110.1(b)(3) also issued under 22 U.S.C.
2403. Section 110.11 also issued under Atomic Energy Act secs.
54(c), 57(d), 122 (42 U.S.C. 2074, 2152). Section 110.50(b)(3) also
issued under Atomic Energy Act sec. 123 (42 U.S.C. 2153). Section
110.51 also issued under Atomic Energy Act sec. 184 (42 U.S.C.
2234). Section 110.52 also issued under Atomic Energy Act sec. 186,
(42 U.S.C. 2236). Sections 110.80-110.113 also issued under 5 U.S.C.
552, 554. Sections 110.130-110.135 also issued under 5 U.S.C. 553.
Sections 110.2 and 110.42(a)(9) also issued under Intelligence
Authorization Act sec. 903 (42 U.S.C. 2151 et seq.).
0
2. In Sec. 110.2, revise paragraph (2)(ii) of the definition of
``Utilization facility'' to read as follows:
Sec. 110.2 Definitions.
* * * * *
Utilization facility means:
* * * * *
(2) * * *
(ii) Reactor primary coolant pump or circulator;
* * * * *
0
3. In Sec. 110.26, revise the introductory text of paragraph (a) to
read as follows:
Sec. 110.26 General license for the export of nuclear reactor
components.
(a) A general license is issued to any person to export to a
destination listed in paragraph (b) of this section any nuclear reactor
component of U.S. origin described in paragraphs (5) through (11) of
appendix A to this part if--
* * * * *
Sec. 110.30 [Amended]
0
4. Amend Sec. 110.30 by adding the words ``Mexico'' and ``Serbia'' in
alphabetical order.
0
5. In Sec. 110.42, revise footnote 1 to read as follows:
Sec. 110.42 Export licensing criteria.
* * * * *
\1\ Export of nuclear reactors, reactor pressure vessels, reactor
primary coolant pumps and circulators, ``on-line'' reactor fuel
charging and discharging machines, and complete reactor control rod
systems, as specified in paragraphs (1) through (4) of appendix A to
this part, are subject to the export licensing criteria in Sec.
110.42(a). Exports of nuclear reactor components, as specified in
paragraphs (5) through (11) of appendix A to this part, when exported
separately from the items described in paragraphs (1) through (4) of
appendix A to this part, are subject to the export licensing criteria
in Sec. 110.42(b).
0
6. In Sec. 110.44, revise paragraphs (a) and (b)(1) to read as
follows:
Sec. 110.44 Physical security standards.
(a) Physical security measures in recipient countries must provide
protection at least comparable to the recommendations in the current
version of IAEA publication, ``Nuclear Security Recommendations on
Physical Protection of Nuclear Material and Nuclear Facilities''
(INFCIRC/225/Revision 5), January 2011, which is incorporated by
reference in this part. This incorporation by reference was approved by
the Director of the Office of the Federal Register in accordance with 5
U.S.C. 552(a) and 1 CFR part 51. Notice of any changes made to the
material incorporated by reference will be published in the Federal
Register. Copies of INFCIRC/225/Revision 5 may be obtained from the
Marketing and Sales Unit, Publishing Section, IAEA, Vienna
International Centre, P.O. Box 100, 1400 Vienna Austria; Fax: 43 1 2600
29302; telephone: 43 1 2600 22417; email: sales.publications@iaea.org;
Web site: https://www.iaea.org/books. You may inspect a copy at the NRC
Library, 11545 Rockville Pike, Rockville, Maryland 20852-2738,
telephone: 301-415-4737 or 1-800-397-4209, between 8:30 a.m. and 4:15
p.m.; or at the National Archives and Records Administration (NARA).
For information on the availability of this material at NARA, call 202-
741-6030, or go to: https://www.archives.gov/federal-register/cfr/ibr-locations.html.
(b) * * *
(1) Receipt by the appropriate U.S. Executive Branch Agency of
written assurances from the relevant recipient country government that
physical security measures providing protection at least comparable to
the recommendations set forth in INFCIRC/225/Revision 5.
* * * * *
0
7. Revise appendix A to part 110 to read as follows:
Appendix A to Part 110--Illustrative List of Nuclear Reactor Equipment
Under NRC Export Licensing Authority
Note: A nuclear reactor basically includes the items within or
attached directly to the reactor vessel, the equipment which
controls the level of power in the core, and the components which
normally contain or come in direct contact with or control the
primary coolant of the reactor core.
(1) Reactor pressure vessels, i.e., metal vessels, as complete
units or major shop-fabricated parts, especially designed or
prepared to contain the core of a nuclear reactor and capable of
withstanding the operating pressure of the primary coolant.
(2) On-line (e.g., CANDU) reactor fuel charging and discharging
machines, i.e., manipulative equipment especially designed for
inserting or removing fuel in an operating nuclear reactor.
(3) Complete reactor control rod system, i.e., rods especially
designed or prepared for the control of the reaction rate in a
nuclear reactor, including the neutron absorbing part and the
support or suspension structures therefor.
(4) Reactor primary coolant pumps or circulators, i.e., pumps or
circulators especially designed or prepared for circulating the
primary coolant in a nuclear reactor.
(5) Reactor pressure tubes, i.e., tubes especially designed or
prepared to contain both fuel elements and the primary coolant in a
nuclear reactor.
(6) Zirconium tubes, i.e., zirconium metal and alloys in the
form of tubes or assemblies of tubes especially designed or prepared
for use as fuel cladding in a nuclear reactor.
(7) Reactor internals, e.g., core support structures, control
and rod guide tubes, fuel channels, calandria tubes, thermal
shields, baffles, core grid plates, and diffuser plates especially
designed or prepared for use in a nuclear reactor.
(8) Reactor control rod drive mechanisms, including detection
and measuring equipment to determine neutron flux levels within the
core of a nuclear reactor.
(9) Heat exchangers, e.g., steam generators especially designed
or prepared for the primary, or intermediate, coolant circuit of a
nuclear reactor or heat exchangers especially designed or prepared
for use in the primary coolant circuit of a nuclear reactor.
(10) External thermal shields especially designed or prepared
for use in a nuclear reactor for reduction of heat loss and also for
containment vessel protection.
(11) Any other components especially designed or prepared for
use in a nuclear reactor or in any of the components described in
this appendix.
0
8. Revise appendix B to part 110 to read as follows:
Appendix B to Part 110--Illustrative List of Gas Centrifuge Enrichment
Plant Components Under NRC's Export Licensing Authority
1. Assemblies and components especially designed or prepared for
use in gas centrifuges.
Note: The gas centrifuge normally consists of a thin-walled
cylinder(s) of between 75 mm and 650 mm diameter contained in a
vacuum environment and spun at high peripheral speed (of the order
of 300 m/per second and more) with the central axis vertical. In
order to achieve high speed, the materials of construction for the
rotating rotor assembly, and hence its individual components, have
to be manufactured to very close tolerances in order to minimize the
unbalance. In contrast to other centrifuges, the gas centrifuge for
uranium enrichment is characterized by having within the rotor
chamber a rotating disc-shaped baffle(s) and a stationary tube
arrangement for feeding and
[[Page 39292]]
extracting uranium hexafluoride (UF6) gas and featuring
at least three separate channels of which two are connected to
scoops extending from the rotor axis towards the periphery of the
rotor chamber. Also contained within the vacuum environment are a
number of critical items which do not rotate and which, although
they are especially designed, are not difficult to fabricate nor are
they fabricated out of unique materials. A centrifuge facility,
however, requires a large number of these components so that
quantities can provide an important indication of end use.
1.1 Rotating Components
(a) Complete Rotor Assemblies: Thin-walled cylinders, or a
number of interconnected thin-walled cylinders, manufactured from
one of the high strength-to-density ratio materials described in the
footnote to this section.
If interconnected, the cylinders are joined together by flexible
bellows or rings as described in Sec. 1.1(c) of this appendix. The
rotor is fitted with an internal baffle(s) and end caps, as
described in Sec. 1.1(d) and (e) of this appendix, if in final
form. However, the complete assembly may be delivered only partly
assembled.
(b) Rotor Tubes: Especially designed or prepared thin-walled
cylinders with thickness of 12 mm or less, a diameter of between 75
mm and 650 mm, and manufactured from one of the high strength-to-
density ratio materials described in the footnote to this section.
(c) Rings or Bellows: Components especially designed or prepared
to give localized support to the rotor tube or to join together a
number of rotor tubes. The bellows in a short cylinder of wall
thickness 3 mm or less, a diameter of between 75 mm and 650 mm,
having a convolute, and manufactured from one of the high strength-
to-density ratio materials described in the footnote to this
section.
(d) Baffles: Disc shaped components of between 75 mm and 650 mm
diameter especially designed or prepared to be mounted inside the
centrifuge rotor tube, in order to isolate the take-off chamber from
the main separation chamber and, in some cases, to assist the
UF6 gas circulation within the main separation chamber of
the rotor tube, and manufactured from one of the high strength-to-
density ratio materials described in the footnote to this section.
(e) Top Caps/Bottom Caps: Disc shaped components of between 75
mm and 650 mm diameter especially designed or prepared to fit to the
ends of the rotor tube, and so contain the UF6 within the
rotor tube, and in some cases to support, retain or contain as an
integrated part, an element of the upper bearing (top cap) or to
carry the rotating elements of the motor and lower bearing (bottom
cap), and manufactured from one of the high strength-to-density
ratio materials described in the footnote to this section.
Footnote
The materials used for centrifuge rotating components include
the following:
(a) Maraging steel capable of an ultimate tensile strength of
1.95 GPa or more.
(b) Aluminum alloys capable of an ultimate tensile strength of
0.46 GPa or more.
(c) Filamentary materials suitable for use in composite
structures and having a specific modulus of 3.18 x 10\6\ m or
greater and a specific ultimate tensile strength of 7.62 x 10\4\ m
or greater.
(``Specific Modulus'' is the Young's modulus in N/m\2\ divided by
the specific weight in N/m\3\ when measured at a temperature of 23
20 [deg]C and a relative humidity of 50 5
percent. ``Specific tensile strength'' is the ultimate tensile
strength in N/m\2\ divided by the specific weight in N/m\3\ when
measured at a temperature of 23 20 [deg]C and a
relative humidity of 50 5 percent.)
1.2 Static Components
(a) Magnetic Suspension Bearings: 1. Especially designed or
prepared bearing assemblies consisting of an annular magnet
suspended within a housing containing a damping medium. The housing
will be manufactured from a UF6 resistant material (see
footnote to Sec. 2 of this appendix). The magnet couples with a
pole piece or a second magnet fitted to the top cap described in
Sec. 1.1(e) of this appendix. The magnet may be ring-shaped with a
relation between outer and inner diameter smaller or equal to 1.6:1.
The magnet may be in a form having an initial permeability of 0.15
Henry/meter or more, or a remanence of 98.5 percent or more, or an
energy product of greater than 80,000 joules/m\3\. In addition to
the usual material properties, it is a prerequisite that the
deviation of the magnetic axes from the geometrical axes is limited
to very small tolerances (lower than 0.1 mm) or that homogeneity of
the material of the magnet is specially called for.
2. Active magnetic bearings especially designed or prepared for
use with gas centrifuges. These bearings usually have the following
characteristics:
(i) Designed to keep centred a rotor spinning at 600 Hz or more;
and
(ii) Associated to a reliable electrical power supply and/or to
an uninterruptible power supply (UPS) unit in order to function for
more than 1 hour.
(b) Bearings/Dampers: Especially designed or prepared bearings
comprising a pivot/cup assembly mounted on a damper. The pivot is
normally a hardened steel shaft polished into a hemisphere at one
end with a means of attachment to the bottom cap described in Sec.
1.1(e) of this appendix at the other. The shaft may, however, have a
hydrodynamic bearing attached. The cup is pellet-shaped with
hemispherical indentation in one surface. These components are often
supplied separately to the damper.
(c) Molecular Pumps: Especially designed or prepared cylinders
having internally machined or extruded helical grooves and
internally machined bores. Typical dimensions are as follows: 75 mm
to 650 mm internal diameter, 10 mm or more wall thickness, with a
length equal to or greater than the diameter. The grooves are
typically rectangular in cross-section and 2 mm or more in depth.
(d) Motor Stators: Especially designed or prepared ring shaped
stators for high speed multi-phase alternating current (AC)
hysteresis (or reluctance) motors for synchronous operation within a
vacuum at a frequency of 600 Hz or greater and a power of 40 volts
amps or greater. The stators may consist of multi-phase windings on
a laminated low loss iron core comprised of thin layers typically
2.0 mm thick or less.
(e) Centrifuge housing/recipients: Components especially
designed or prepared to contain the rotor tube assembly of a gas
centrifuge. The housing consists of a rigid cylinder of wall
thickness up to 30 mm with precision machined ends to locate the
bearings and with one or more flanges for mounting. The machined
ends are parallel to each other and perpendicular to the cylinder's
longitudinal axis to within 0.05 degrees or less. The housing may
also be a honeycomb type structure to accommodate several rotor
tubes.
(f) Scoops: Especially designed or prepared tubes for the
extraction of UF6 gas from within the rotor tube by a
Pitot tube action (that is, with an aperture facing into the
circumferential gas flow within the rotor tube, for example by
bending the end of a radially disposed tube) and capable of being
fixed to the central gas extraction system.
2. Especially designed or prepared auxiliary systems, equipment,
and components for gas centrifuge enrichment plants.
Note: The auxiliary systems, equipment, and components for a gas
centrifuge enrichment plant are the systems of the plant needed to
feed UF6 to the centrifuges to link the individual
centrifuges to each other to form cascades (or stages) to allow for
progressively higher enrichments and to extract the product and
tails of UF6 from the centrifuges, together with the
equipment required to drive the centrifuges or to control the plant.
Normally UF6 is evaporated from the solid using
heated autoclaves and is distributed in gaseous form to the
centrifuges by way of cascade header pipework. The ``product'' and
``tails'' of UF6 gaseous streams flowing from the
centrifuges are also passed by way of cascade header pipework to
cold traps (operating at about 203 K (-70 [deg]C)) where they are
condensed prior to onward transfer into suitable containers for
transportation or storage. Because an enrichment plant consists of
many thousands of centrifuges arranged in cascades, there are many
kilometers of cascade header pipework incorporating thousands of
welds with a substantial amount of repetition of layout. The
equipment, component and piping systems are fabricated to very high
vacuum and cleanliness standards.
Some of the items listed below either come into direct contact
with the UF6 process gas or directly control the
centrifuges and the passage of the gas from centrifuge to centrifuge
and cascade to cascade. Materials resistant to corrosion by
UF6 include copper, copper alloys, stainless steel,
aluminum, aluminum oxide, aluminum alloys, nickel or alloys
containing 60 percent or more nickel, and fluorinated hydrocarbon
polymers.
(a) Feed Systems/Product and Tails Withdrawal Systems:
Especially designed or prepared process systems or equipment for
enrichment plants made of or protected by materials resistant to
corrosion by UF6 including:
[[Page 39293]]
1. Feed autoclaves, ovens, or systems used for passing
UF6 to the enrichment process.
2. Desublimers, cold traps, or pumps used to remove
UF6 from the enrichment process for subsequent transfer
upon heating.
3. Solidification or liquefaction stations used to remove
UF6 from the enrichment process by compressing and
converting UF6 to a liquid or solid form.
4. ``Product'' and ``tails'' stations used for transferring
UF6 into containers.
(b) Machine Header Piping Systems: Especially designed or
prepared piping systems and header systems for handling
UF6 within the centrifuge cascades.
This piping network is normally of the ``triple'' header system
with each centrifuge connected to each of the headers. There is
therefore a substantial amount of repetition in its form. It is
wholly made of or protected by UF6 resistant materials
(see Note to this section) and is fabricated to very high vacuum and
cleanliness standards.
(c) Special shut-off and control valves:
1. Shut-off valves especially designed or prepared to act on the
feed, ``product'' or ``tails'' UF6 gaseous streams of an
individual gas centrifuge.
2. Bellows-sealed valves, manual or automated, shut-off or
control, made of or protected by materials resistant to corrosion by
UF6, with an inside diameter of 10 to 160 mm, especially
designed or prepared for use in main or auxiliary systems of gas
centrifuge enrichment plants.
Typical especially designed or prepared valves include bellow-
sealed valves, fast acting closure-types, fast acting valves, and
others.
(d) UF6 Mass Spectrometers/Ion Sources: Especially
designed or prepared mass spectrometers capable of taking on-line
samples from UF6 gas streams and having all of the
following:
1. Capable of measuring ions of 320 atomic mass units or greater
and having a resolution of better than 1 part in 320.
2. Ion sources constructed of or protected by nickel, nickel-
copper alloys with a nickel content of 60 percent or more by weight,
or nickel-chrome alloys.
3. Electron bombardment ionization sources.
4. Having a collector system suitable for isotope analysis.
(e) Frequency Changers: Frequency changers (also known as
converters or inverters) especially designed or prepared to supply
motor stators as defined under Sec. 1.2(d) of this appendix, or
parts, components, and subassemblies of such frequency changers
having all of the following characteristics:
1. A multiphase output of 600 Hz or greater; and
2. High stability (with frequency control better than 0.2
percent).
(f) Any other components especially designed or prepared for use
in a gas centrifuge enrichment plant or in any of the components
described in this appendix.
0
9. Revise appendix C to part 110 to read as follows:
Appendix C to Part 110--Illustrative List of Gaseous Diffusion
Enrichment Plant Assemblies and Components Under NRC Export Licensing
Authority
Note: In the gaseous diffusion method of uranium isotope
separation, the main technological assembly is a special porous
gaseous diffusion barrier, heat exchanger for cooling the gas (which
is heated by the process of compression), seal valves and control
valves, and pipelines. Inasmuch as gaseous diffusion technology uses
uranium hexafluoride (UF6), all equipment, pipeline and
instrumentation surfaces (that come in contact with the gas) must be
made of materials that remain stable in contact with UF6.
A gaseous diffusion facility requires a number of these assemblies,
so that quantities can provide an important indication of end use.
The auxiliary systems, equipment, and components for gaseous
diffusion enrichment plants are the systems of plant needed to feed
UF6 to the gaseous diffusion assembly to link the
individual assemblies to each other to form cascades (or stages) to
allow for progressively higher enrichments and to extract the
``product'' and ``tails'' UF6 from the diffusion
cascades. Because of the high inertial properties of diffusion
cascades, any interruption in their operation, and especially their
shut-down, leads to serious consequences. Therefore, a strict and
constant maintenance of vacuum in all technological systems,
automatic protection for accidents, and precise automated regulation
of the gas flow is of importance in a gaseous diffusion plant. All
this leads to a need to equip the plant with a large number of
special measuring, regulating, and controlling systems.
Normally UF6 is evaporated from cylinders placed
within autoclaves and is distributed in gaseous form to the entry
point by way of cascade header pipework. The ``product'' and
``tails'' UF6 gaseous streams flowing from exit points
are passed by way of cascade header pipework to either cold traps or
to compression stations where the UF6 gas is liquified
prior to onward transfer into suitable containers for transportation
or storage. Because a gaseous diffusion enrichment plant consists of
a large number of gaseous diffusion assemblies arranged in cascades,
there are many kilometers of cascade header pipework, incorporating
thousands of welds with substantial amounts of repetition of layout.
The equipment, components, and piping systems are fabricated to very
high vacuum and cleanliness standards.
The items listed below either come into direct contact with the
UF6 process gas or directly control the flow within the
cascade. All surfaces which come into contact with the process gas
are wholly made of, or lined with, UF6-resistant
materials. For the purposes of this appendix, the materials
resistant to corrosion by UF6 include copper, copper
alloys, stainless steel, aluminum, aluminum oxide, aluminum alloys,
nickel or alloys containing 60 percent or more nickel and
fluorinated hydrocarbon polymers.
1. Assemblies and components especially designed or prepared for
use in gaseous diffusion enrichment.
1.1 Gaseous Diffusion Barriers and Barrier Materials
(a) Especially designed or prepared thin, porous filters, with a
pore size of 10-100 nm, a thickness of 5 mm or less, and for tubular
forms, a diameter of 25 mm or less, made of metallic, polymer or
ceramic materials resistant to corrosion by UF6 (See Note
in Sec. 2 of this appendix).
(b) Especially prepared compounds or powders for the manufacture
of such filters. Such compounds and powders include nickel or alloys
containing 60 percent or more nickel, aluminum oxide, or
UF6-resistant fully fluorinated hydrocarbon polymers
having a purity of 99.9 percent by weight or more, a particle size
less than 10 [micro]m, and a high degree of particle size
uniformity, which are especially prepared for the manufacture of
gaseous diffusion barriers.
1.2 Diffuser Housings
Especially designed or prepared hermetically sealed vessels for
containing the gaseous diffusion barrier, made of or protected by
UF6-resistant materials (See Note in Sec. 2 of this
appendix).
1.3 Compressors and Gas Blowers
Especially designed or prepared compressors or gas blowers with
a suction volume capacity of 1 m\3\ per minute or more of
UF6, and with a discharge pressure of up to 500 kPa,
designed for long-term operation in the UF6 environment,
as well as separate assemblies of such compressors and gas blowers.
These compressors and gas blowers have a pressure ratio of 10:1 or
less and are made of, or protected by, materials resistant to
UF6 (See Note in Sec. 2 of this appendix).
1.4 Rotary Shaft Seals
Especially designed or prepared vacuum seals, with seal feed and
seal exhaust connections, for sealing the shaft connecting the
compressor or the gas blower rotor with the driver motor so as to
ensure a reliable seal against in-leaking of air into the inner
chamber of the compressor or gas blower which is filled with
UF6. Such seals are normally designed for a buffer gas
in-leakage rate of less than 1000 cm\3\ per minute.
1.5 Heat Exchangers for Cooling UF6
Especially designed or prepared heat exchangers made of or
protected by UF6 resistant materials (see Note to Sec. 2
of this appendix) and intended for a leakage pressure change rate of
less than 10 Pa per hour under a pressure difference of 100 kPa.
2. Auxiliary systems, equipment, and components especially
designed or prepared for use in gaseous diffusion enrichment.
Note: The items listed below either come into direct contact
with the UF6 process gas or directly control the flow
within the cascade. Materials resistant to corrosion by
UF6 include copper, copper alloys, stainless steel,
aluminum, aluminum oxide, aluminum alloys, nickel or alloys
containing 60 percent or more nickel, and fluorinated hydrocarbon
polymers.
2.1 Feed Systems/Product and Tails Withdrawal Systems
Especially designed or prepared process systems or equipment for
enrichment plants
[[Page 39294]]
made of, or protected by, materials resistant to corrosion by
UF6, including:
(1) Feed autoclaves, ovens, or systems used for passing
UF6 to the enrichment process;
(2) Desublimers, cold traps, or pumps used to remove
UF6 from the enrichment process for subsequent transfer
upon heating;
(3) Solidification or liquefaction stations used to remove
UF6 from the enrichment process by compressing and
converting UF6 to a liquid or solid form;
(4) ``Product'' or ``tails'' stations used for transferring
UF6 into containers.
2.2 Header Piping Systems
Especially designed or prepared piping systems and header
systems for handling UF6 within the gaseous diffusion
cascades. This piping network is normally of the ``double'' header
system with each cell connected to each of the headers.
2.3 Vacuum Systems
(a) Especially designed or prepared vacuum manifolds, vacuum
headers and vacuum pumps having a suction capacity of 5 m\3\ per
minute or more.
(b) Vacuum pumps especially designed for service in
UF6-bearing atmospheres made of, or protected by,
materials resistant to corrosion by UF6 (See Note to this
section). These pumps may be either rotary or positive displacement,
may have fluorocarbon seals, and may have special working fluids
present.
2.4 Special Shut-Off and Control Valves
Especially designed or prepared bellows-sealed valves, manual or
automated, shut-off or control valves, made of, or protected by,
materials resistant to corrosion by UF6, for installation
in main and auxiliary systems of gaseous diffusion enrichment
plants.
2.5 UF6 Mass Spectrometers/Ion Sources
Especially designed or prepared mass spectrometers capable of
taking on-line samples from UF6 gas streams and having
all of the following:
(a) Capable of measuring ions of 320 atomic mass units or
greater and having a resolution of better than 1 part in 320;
(b) ion sources constructed of or protected by nickel, nickel-
copper alloys with a nickel content of 60 percent or more by weight,
or nickel-chrome alloys;
(c) electron bombardment ionization sources; and
(d) having a collector system suitable for isotopic analysis.
3. Any other components especially designed or prepared for use
in a gaseous diffusion enrichment plant or in any of the components
described in this appendix.
0
10. Revise appendix D to part 110 to read as follows:
Appendix D to Part 110--Illustrative List of Aerodynamic Enrichment
Plant Equipment and Components Under NRC Export Licensing Authority
Note: In aerodynamic enrichment processes, a mixture of gaseous
UF6 and light gas (hydrogen or helium) is compressed and
then passed through separating elements wherein isotopic separation
is accomplished by the generation of high centrifugal forces over a
curved-wall geometry. Two processes of this type have been
successfully developed: The separation nozzle process and the vortex
tube process. For both processes, the main components of a
separation stage included cylindrical vessels housing the special
separation elements (nozzles or vortex tubes), gas compressors, and
heat exchangers to remove the heat of compression. An aerodynamic
plant requires a number of these stages, so that quantities can
provide an important indication of end use. Because aerodynamic
processes use UF6, all equipment, pipeline and
instrumentation surfaces (that come in contact with the gas) must be
made of, or protected by, materials that remain stable in contact
with UF6. All surfaces which come into contact with the
process gas are made of, or protected by, UF6-resistant
materials; including copper, copper alloys, stainless steel,
aluminum, aluminum oxide, aluminum alloys, nickel or alloys
containing 60 percent or more nickel by weight, and fluorinated
hydrocarbon polymers.
The following items either come into direct contact with the
UF6 process gas or directly control the flow within the
cascade:
(1) Separation nozzles and assemblies.
Especially designed or prepared separation nozzles and
assemblies thereof. The separation nozzles consist of slit-shaped,
curved channels having a radius of curvature less than 1 mm,
resistant to corrosion by UF6 and having a knife-edge
within the nozzle that separates the gas flowing through the nozzle
into two fractions.
(2) Vortex tubes and assemblies.
Especially designed or prepared vortex tubes and assemblies
thereof. The vortex tubes are cylindrical or tapered, made of, or
protected by, materials resistant to corrosion by UF6,
and with one or more tangential inlets. The tubes may be equipped
with nozzle-type appendages at either or both ends.
The feed gas enters the vortex tube tangentially at one end or
through swirl vanes or at numerous tangential positions along the
periphery of the tube.
(3) Compressors and gas blowers.
Especially designed or prepared compressors or gas blowers made
of, or protected by, materials resistant to corrosion by the
UF6/carrier gas (hydrogen or helium) mixture.
(4) Rotary shaft seals.
Especially designed or prepared rotary shaft seals, with seal
feed and seal exhaust connections, for sealing the shaft connecting
the compressor rotor or the gas blower rotor with the driver motor
to ensure a reliable seal against out-leakage of process gas or in-
leakage of air or seal gas into the inner chamber of the compressor
or gas blower which is filled with a UF6/carrier gas
mixture.
(5) Heat exchangers for gas cooling.
Especially designed or prepared heat exchangers, made of, or
protected by, materials resistant to corrosion by UF6.
(6) Separation element housings.
Especially designed or prepared separation element housings,
made of, or protected by, materials resistant to corrosion by
UF6, for containing vortex tubes or separation nozzles.
(7) Feed systems/product and tails withdrawal systems.
Especially designed or prepared process systems or equipment for
enrichment plants made of, or protected by, materials resistant to
corrosion by UF6, including:
(i) Feed autoclaves, ovens, or systems used for passing
UF6 to the enrichment process;
(ii) Desublimers (or cold traps) used to remove UF6
from the enrichment process for subsequent transfer upon heating;
(iii) Solidification or liquefaction stations used to remove
UF6 from the enrichment process by compressing and
converting UF6 to a liquid or solid form; and
(iv) ``Product'' or ``tails'' stations used for transferring
UF6 into containers.
(8) Header piping systems.
Especially designed or prepared header piping systems, made of
or protected by materials resistant to corrosion by UF6,
for handling UF6 within the aerodynamic cascades. The
piping network is normally of the ``double'' header design with each
stage or group of stages connected to each of the headers.
(9) Vacuum systems and pumps.
(i) Especially designed or prepared vacuum systems consisting of
vacuum manifolds, vacuum headers and vacuum pumps, and designed for
service in UF6-bearing atmospheres.
(ii) Especially designed or prepared vacuum pumps for service in
UF6-bearing atmospheres and made of, or protected by,
materials resistant to corrosion by UF6. These pumps may
use fluorocarbon seals and special working fluids.
(10) Special shut-off and control valves.
Especially designed or prepared bellows-sealed valves, manual or
automated, shut-off or control valves made of, or protected by,
materials resistant to corrosion by UF6 with a diameter
of 40 mm or greater for installation in main and auxiliary systems
of aerodynamic enrichment plants.
(11) UF6 mass spectrometers/ion sources.
Especially designed or prepared mass spectrometers capable of
taking on-line samples from UF6 gas streams and having
all of the following:
(i) Capable of measuring ions of 320 atomic mass units or
greater and having a resolution of better than 1 part in 320;
(ii) Ion sources constructed of or protected by nickel, nickel-
copper alloys with a nickel content of 60 percent or more by weight,
or nickel-chrome alloys;
(iii) Electron bombardment ionization sources; and
(iv) Collector system suitable for isotopic analysis.
(12) UF6/carrier gas separation systems.
Especially designed or prepared process systems for separating
UF6 from carrier gas (hydrogen or helium).
These systems are designed to reduce the UF6 content
in the carrier gas to 1 ppm or less and may incorporate equipment
such as:
(i) Cryogenic heat exchangers and cryoseparators capable of
temperatures of 153 K (-120 [deg]C) or less;
(ii) Cryogenic refrigeration units capable of temperatures of
153 K (-120 [deg]C) or less;
(iii) Separation nozzle or vortex tube units for the separation
of UF6 from carrier gas; or
[[Page 39295]]
(iv) UF6 cold traps capable of freezing out UF6.
(13) Any other components especially designed or prepared for
use in an aerodynamic enrichment plant or in any of the components
described in this appendix.
0
11. Revise appendix E to part 110 to read as follows:
Appendix E to Part 110--Illustrative List of Chemical Exchange or Ion
Exchange Enrichment Plant Equipment and Components Under NRC Export
Licensing Authority
Note: The slight difference in mass between the isotopes of
uranium causes small changes in chemical reaction equilibria that
can be used as a basis for separation of the isotopes. Two processes
have been successfully developed: Liquid-liquid chemical exchange
and solid-liquid ion exchange.
A. In the liquid-liquid chemical exchange process, immiscible
liquid phases (aqueous and organic) are countercurrently contacted
to give the cascading effect of thousands of separation stages. The
aqueous phase consists of uranium chloride in hydrochloric acid
solution; the organic phase consists of an extractant containing
uranium chloride in an organic solvent. The contactors employed in
the separation cascade can be liquid-liquid exchange columns (such
as pulsed columns with sieve plates) or liquid centrifugal
contactors. Chemical conversions (oxidation and reduction) are
required at both ends of the separation cascade in order to provide
for the reflux requirements at each end. A major design concern is
to avoid contamination of the process streams with certain metal
ions. Plastic, plastic-lined (including use of fluorocarbon
polymers) and/or glass-lined columns and piping are therefore used.
(1) Liquid-liquid exchange columns.
Countercurrent liquid-liquid exchange columns having mechanical
power input especially designed or prepared for uranium enrichment
using the chemical exchange process. For corrosion resistance to
concentrated hydrochloric acid solutions, these columns and their
internals are normally made of, or protected by, suitable plastic
materials (such as fluorinated hydrocarbon polymers) or glass. The
stage residence time of the columns is normally designed to be 30
seconds or less.
(2) Liquid-liquid centrifugal contactors.
Especially designed or prepared for uranium enrichment using the
chemical exchange process. These contactors use rotation to achieve
dispersion of the organic and aqueous streams and then centrifugal
force to separate the phases. For corrosion resistance to
concentrated hydrochloric acid solutions, the contactors are
normally made of, or protected by, suitable plastic materials (such
as fluorinated hydrocarbon polymers) or glass. The stage residence
time of the centrifugal contactors is designed to be short (30
seconds or less).
(3) Uranium reduction systems and equipment.
(i) Especially designed or prepared electrochemical reduction
cells to reduce uranium from one valence state to another for
uranium enrichment using the chemical exchange process. The cell
materials in contact with process solutions must be corrosion
resistant to concentrated hydrochloric acid solutions.
The cell cathodic compartment must be designed to prevent re-
oxidation of uranium to its higher valence state. To keep the
uranium in the cathodic compartment, the cell may have an impervious
diaphragm membrane constructed of special cation exchange material.
The cathode consists of a suitable solid conductor such as graphite.
These systems consist of solvent extraction equipment for
stripping the U+4 from the organic stream into an aqueous
solution, evaporation and/or other equipment to accomplish solution
pH adjustment and control, and pumps or other transfer devices for
feeding to the electrochemical reduction cells. A major design
concern is to avoid contamination of the aqueous stream with certain
metal ions. For those parts in contact with the process stream, the
system is constructed of equipment made of, or protected by,
materials such as glass, fluorocarbon polymers, polyphenyl sulfate,
polyether sulfone, and resin-impregnated graphite.
(ii) Especially designed or prepared systems at the product end
of the cascade for taking the U+4 out of the organic
stream, adjusting the acid concentration, and feeding to the
electrochemical reduction cells.
These systems consist of solvent extraction equipment for
stripping the U+4 from the organic stream into an aqueous
solution, evaporation and/or other equipment to accomplish solution
pH adjustment and control, and pumps or other transfer devices for
feeding to the electrochemical reduction cells. A major design
concern is to avoid contamination of the aqueous stream with certain
metal ions. For those parts in contact with the process stream, the
system is constructed of equipment made of, or protected by,
materials such as glass, fluorocarbon polymers, polyphenyl sulfate,
polyether sulfone, and resin-impregnated graphite.
(4) Feed preparation systems.
Especially designed or prepared systems for producing high-
purity uranium chloride feed solutions for chemical exchange uranium
isotope separation plants.
These systems consist of dissolution, solvent extraction and/or
ion exchange equipment for purification and electrolytic cells for
reducing the uranium U+6 or U+4 to
U+3. These systems produce uranium chloride solutions
having only a few parts per million of metallic impurities such as
chromium, iron, vanadium, molybdenum, and other bivalent or higher
multi-valent cations. Materials of construction for portions of the
system processing high-purity U+3 include glass,
fluorinated hydrocarbon polymers, polyphenyl sulfate or polyether
sulfone plastic-lined and resin-impregnated graphite.
(5) Uranium oxidation systems.
Especially designed or prepared systems for oxidation of
U+3 to U+4 for return to the uranium isotope
separation cascade in the chemical exchange enrichment process.
These systems may incorporate equipment such as:
(i) Equipment for contacting chlorine and oxygen with the
aqueous effluent from the isotope separation equipment and
extracting the resultant U+4 into the stripped organic
stream returning from the product end of the cascade; and
(ii) Equipment that separates water from hydrochloric acid so
that the water and the concentrated hydrochloric acid may be
reintroduced to the process at the proper locations.
B. In the solid-liquid ion-exchange process, enrichment is
accomplished by uranium adsorption/desorption on a special, fast-
acting, ion-exchange resin or adsorbent. A solution of uranium in
hydrochloric acid and other chemical agents is passed through
cylindrical enrichment columns containing packed beds of the
adsorbent. For a continuous process, a reflux system is necessary to
release the uranium from the adsorbent back in the liquid flow so
that ``product'' and ``tails'' can be collected. This is
accomplished with the use of suitable reduction/oxidation chemical
agents that are fully regenerated in separate external circuits and
that may be partially regenerated within the isotopic separation
columns themselves. The presence of hot concentrated hydrochloric
acid solutions in the process requires that the equipment be made
of, or protected by, special corrosion-resistant materials.
(1) Fast reacting ion exchange resins/adsorbents.
Especially designed or prepared for uranium enrichment using the
ion exchange process, including porous macroreticular resins, and/or
pellicular structures in which the active chemical exchange groups
are limited to a coating on the surface of an inactive porous
support structure, and other composite structures in any suitable
form including particles or fibers. These ion exchange resins/
adsorbents have diameters of 0.2 mm or less and must be chemically
resistant to concentrated hydrochloric acid solutions as well as
physically strong enough so as not to degrade in the exchange
columns. The resins/adsorbents are especially designed to achieve
very fast uranium isotope exchange kinetics (exchange rate half-time
of less than 10 seconds) and are capable of operating at a
temperature in the range of 373 K (100 [deg]C) to 473 K (200
[deg]C).
(2) Ion exchange columns.
Cylindrical columns greater than 1000 mm in diameter for
containing and supporting packed beds of ion exchange resin/
adsorbent, especially designed or prepared for uranium enrichment
using the ion exchange process. These columns are made of, or
protected by, materials (such as titanium or fluorocarbon plastics)
resistant to corrosion by concentrated hydrochloric acid solutions
and are capable of operating at a temperature in the range of 373 K
(100 [deg]C) to 473 K (200 [deg]C) and pressures above 0.7 MPa.
(3) Ion exchange reflux systems.
(i) Especially designed or prepared chemical or electrochemical
reduction systems for regeneration of the chemical reducing agent(s)
used in ion exchange uranium enrichment cascades.
[[Page 39296]]
The ion exchange enrichment process may use, for example,
trivalent titanium (Ti+3) as a reducing cation in which
case the reduction system would regenerate Ti+3 by
reducing Ti+4.
(ii) Especially designed or prepared chemical or electrochemical
oxidation systems for regeneration of the chemical oxidizing
agent(s) used in ion exchange uranium enrichment cascades.
The ion exchange enrichment process may use, for example,
trivalent iron (Fe+3) as an oxidant in which case the
oxidation system would regenerate Fe+3 by oxidizing
Fe+2.
C. Any other components especially designed or prepared for use
in a chemical exchange or ion exchange enrichment plant or in any of
the components described in this appendix.
0
12. Revise appendix F to part 110 to read as follows:
Appendix F to Part 110--Illustrative List of Laser-Based Enrichment
Plant Equipment and Components Under NRC Export Licensing Authority
Note: Present systems for enrichment processes using lasers fall
into two categories: The process medium is atomic uranium vapor and
the process medium is the vapor of a uranium compound, sometimes
mixed with another gas or gases. Common nomenclature for these
processes include: First category-atomic vapor laser isotope
separation; and second category-molecular laser isotope separation
including chemical reaction by isotope selective laser activation.
The systems, equipment, and components for laser enrichment plants
include: (a) Devices to feed uranium-metal vapor for selective
photo-ionization or devices to feed the vapor of a uranium compound
(for selective photo-dissociation or selective excitation/
activation); (b) devices to collect enriched and depleted uranium
metal as ``product'' and ``tails'' in the first category, and
devices to collect enriched and depleted uranium compounds as
``product'' and ``tails'' in the second category; (c) process laser
systems to selectively excite the uranium-235 species; and (d) feed
preparation and product conversion equipment. The complexity of the
spectroscopy of uranium atoms and compounds may require
incorporation of a number of available laser and laser optics
technologies.
All surfaces that come into direct contact with the uranium or
UF6 are wholly made of, or protected by, corrosion-
resistant materials. For laser-based enrichment items, the materials
resistant to corrosion by the vapor or liquid of uranium metal or
uranium alloys include yttria-coated graphite and tantalum; and the
materials resistant to corrosion by UF6 include copper,
copper alloys, stainless steel, aluminum, aluminum oxide, aluminum
alloys, nickel or alloys containing 60 percent or more nickel by
weight, and fluorinated hydrocarbon polymers. Many of the following
items come into direct contact with uranium metal vapor or liquid or
with process gas consisting of UF6 or a mixture of
UF6 and other gases:
(1) Uranium vaporization systems (atomic vapor based methods).
Especially designed or prepared uranium metal vaporization
systems for use in laser enrichment.
These systems may contain electron beam guns and are designed to
achieve a delivered power (1 kW or greater) on the target sufficient
to generate uranium metal vapour at a rate required for the laser
enrichment function.
(2) Liquid or vapor uranium metal handling systems and
components (atomic vapor based methods).
Especially designed or prepared systems for handling molten
uranium, molten uranium alloys, or uranium metal vapor.
The liquid uranium metal handling systems may consist of
crucibles and cooling equipment for the crucibles. The crucibles and
other system parts that come into contact with molten uranium,
molten uranium alloys, or uranium metal vapor are made of, or
protected by, materials of suitable corrosion and heat resistance,
such as tantalum, yttria-coated graphite, graphite coated with other
rare earth oxides, or mixtures thereof.
(3) Uranium metal ``product'' and ``tails'' collector assemblies
(atomic vapor based methods).
Especially designed or prepared ``product'' and ``tails''
collector assemblies for uranium metal in liquid or solid form.
Components for these assemblies are made of or protected by
materials resistant to the heat and corrosion of uranium metal vapor
or liquid, such as yttria-coated graphite or tantalum, and may
include pipes, valves, fittings, ``gutters,'' feed-throughs, heat
exchangers and collector plates for magnetic, electrostatic, or
other separation methods.
(4) Separator module housings (atomic vapor based methods).
Especially designed or prepared cylindrical or rectangular
vessels for containing the uranium metal vapor source, the electron
beam gun, and the ``product'' and ``tails'' collectors. These
housings have multiplicity of ports for electrical and water feed-
throughs, laser beam windows, vacuum pump connections, and
instrumentation diagnostics and monitoring with opening and closure
provisions to allow refurbishment of internal components.
(5) Supersonic expansion nozzles (molecular based methods).
Especially designed or prepared supersonic expansion nozzles for
cooling mixtures of UF6 and carrier gas to 150 K (-123
[deg]C) or less which are corrosion resistant to UF6.
(6) ``Product'' or ``tails'' collectors (molecular based
methods).
Especially designed or prepared components or devices for
collecting uranium product material or uranium tails material
following illumination with laser light.
In one example of molecular laser isotope separation, the
product collectors serve to collect enriched uranium pentafluoride
(UF5) solid material. The product collectors may consist
of filter, impact, or cyclone-type collectors, or combinations
thereof, and must be corrosion resistant to the UF5/
UF6 environment.
(7) UF6/carrier gas compressors (molecular based
methods).
Especially designed or prepared compressors for UF6/
carrier gas mixtures, designed for long term operation in a
UF6 environment. Components of these compressors that
come into contact with process gas are made of, or protected by,
materials resistant to UF6 corrosion.
(8) Rotary shaft seals (molecular based methods).
Especially designed or prepared rotary shaft seals, with seal
feed and seal exhaust connections, for sealing the shaft connecting
the compressor rotor with the driver motor to ensure a reliable seal
against out-leakage of process gas or in-leakage of air or seal gas
into the inner chamber of the compressor which is filled with a
UF6/carrier gas mixture.
(9) Fluorination systems (molecular based methods).
Especially designed or prepared systems for fluorinating
UF5 (solid) to UF6 (gas).
These systems are designed to fluorinate the collected
UF5 powder to UF6 for subsequent collection in
product containers or for transfer as feed for additional
enrichment. In one approach, the fluorination reaction may be
accomplished within the isotope separation system to react and
recover directly off the ``product'' collectors. In another
approach, the UF5 powder may be removed/transferred from
the ``product'' collectors into a suitable reaction vessel (e.g.,
fluidized-bed reactor, screw reactor or flame tower) for
fluorination. In both approaches, equipment is used for storage and
transfer of fluorine (or other suitable fluorinating agents) and for
collection and transfer of UF6.
(10) UF6 mass spectrometers/ion sources (molecular
based methods).
Especially designed or prepared mass spectrometers capable of
taking on-line samples from UF6 gas streams and having
all of the following characteristics:
(i) Capable of measuring ions of 320 atomic mass units or
greater and having a resolution of better than 1 part in 320;
(ii) Ion sources constructed of or protected by nickel, nickel-
copper alloys with a nickel content of 60 percent or more by weight,
or nickel-chrome alloys;
(iii) Electron bombardment ionization sources; and
(iv) Collector system suitable for isotopic analysis.
(11) Feed systems/product and tails withdrawal systems
(molecular based methods).
Especially designed or prepared process systems or equipment for
enrichment plants made of or protected by materials resistant to
corrosion by UF6, including:
(i) Feed autoclaves, ovens, or systems used for passing
UF6 to the enrichment process;
(ii) Desublimers (or cold traps) used to remove UF6
from the enrichment process for subsequent transfer upon heating;
(iii) Solidification or liquefaction stations used to remove
UF6 from the enrichment process by compressing and
converting UF6 to a liquid or solid; and
(iv) ``Product'' or ``tails'' stations used to transfer
UF6 into containers.
(12) UF6/carrier gas separation systems (molecular
based methods).
[[Page 39297]]
Especially designed or prepared process systems for separating
UF6 from carrier gas.
These systems may incorporate equipment such as:
(i) Cryogenic heat exchangers or cryoseparators capable of
temperatures of 153 K (-120 [deg]C) or less;
(ii) Cryogenic refrigeration units capable of temperatures of
153 K (-120 [deg]C) or less; or
(iii) UF6 cold traps capable of freezing out
UF6.
(13) Lasers or Laser systems.
Especially designed or prepared for the separation of uranium
isotopes.
The laser system typically contains both optical and electronic
components for the management of the laser beam (or beams) and the
transmission to the isotope separation chamber. The laser system for
atomic vapor based methods usually consists of tunable dye lasers
pumped by another type of laser (e.g., copper vapor lasers or
certain solid-state lasers). The laser system for molecular based
methods may consist of CO2 lasers or excimer lasers and a
multi-pass optical cell. Lasers or laser systems for both methods
require spectrum frequency stabilization for operation over extended
periods of time.
(14) Any other components especially designed or prepared for
use in a laser-based enrichment plant or in any of the components
described in this appendix.
0
13. Revise appendix G to part 110 to read as follows:
Appendix G to Part 110--Illustrative List of Plasma Separation
Enrichment Plant Equipment and Components Under NRC Export Licensing
Authority
Note: In the plasma separation process, a plasma of uranium ions
passes through an electric field tuned to the \235\U ion resonance
frequency so that they preferentially absorb energy and increase the
diameter of their corkscrew-like orbits. Ions with a large-diameter
path are trapped to produce a product enriched in \235\U. The
plasma, made by ionizing uranium vapor, is contained in a vacuum
chamber with a high-strength magnetic field produced by a
superconducting magnet. The main technological systems of the
process include the uranium plasma generation system, the separator
module with superconducting magnet, and metal removal systems for
the collection of ``product'' and ``tails.''
(1) Microwave power sources and antennae.
Especially designed or prepared microwave power sources and
antennae for producing or accelerating ions having the following
characteristics: Greater than 30 GHz frequency and greater than 50
kW mean power output for ion production.
(2) Ion excitation coils.
Especially designed or prepared radio frequency ion excitation
coils for frequencies of more than 100 kHz and capable of handling
more than 40 kW mean power.
(3) Uranium plasma generation systems.
Especially designed or prepared systems for the generation of
uranium plasma for use in plasma separation plants.
(4) Uranium metal ``product'' and ``tails'' collector
assemblies.
Especially designed or prepared ``product'' and ``tails''
collector assemblies for uranium metal in solid form. These
collector assemblies are made of, or protected by, materials
resistant to the heat and corrosion of uranium metal vapor, such as
yttria-coated graphite or tantalum.
(5) Separator module housings.
Especially designed or prepared cylindrical vessels for use in
plasma separation enrichment plants for containing the uranium
plasma source, radio-frequency drive coil, and the ``product'' and
``tails'' collectors.
These housings have a multiplicity of ports for electrical feed-
throughs, diffusion pump connections, and instrumentation
diagnostics and monitoring. They have provisions for opening and
closure to allow for refurbishment of internal components and are
constructed of a suitable non-magnetic material such as stainless
steel.
(6) Any other components especially designed or prepared for use
in a plasma separation enrichment plant or in any of the components
described in this appendix.
0
14. In appendix H to part 110, add a new paragraph (4) to read as
follows:
Appendix H to Part 110--Illustrative List of Electromagnetic Enrichment
Plant Equipment and Components Under NRC Export Licensing Authority
* * * * *
(4) Any other components especially designed or prepared for use
in an electromagnetic enrichment plant or in any of the components
described in this appendix.
0
15. Revise appendix I to part 110 to read as follows:
Appendix I to Part 110--Illustrative List of Reprocessing Plant
Components Under NRC Export Licensing Authority
Note: Reprocessing irradiated nuclear fuel separates plutonium
and uranium from intensely radioactive fission products and other
transuranic elements. Different technical processes can accomplish
this separation. However, over the years Purex has become the most
commonly used and accepted process. Purex involves the dissolution
of irradiated nuclear fuel in nitric acid, followed by separation of
the uranium, plutonium, and fission products by solvent extraction
using a mixture of tributyl phosphate in an organic diluent.
Purex facilities have process functions similar to each other,
including: Irradiated fuel element chopping, fuel dissolution,
solvent extraction, and process liquor storage. There may also be
equipment for thermal denitration of uranium nitrate, conversion of
plutonium nitrate to oxide metal, and treatment of fission product
waste liquor to a form suitable for long term storage or disposal.
However, the specific type and configuration of the equipment
performing these functions may differ between Purex facilities for
several reasons, including the type and quantity of irradiated
nuclear fuel to be reprocessed and the intended disposition of the
recovered materials, and the safety and maintenance philosophy
incorporated into the design of the facility. A plant for the
reprocessing of irradiated fuel elements includes the equipment and
components which normally come in direct contact with and directly
control the irradiated fuel and the major nuclear material and
fission product processing streams.
(1) Irradiated fuel element chopping machines.
Remotely operated equipment especially designed or prepared for
use in a reprocessing plant and intended to cut, chop, or shear
irradiated nuclear fuel assemblies, bundles, or rods. This equipment
breaches the cladding of the fuel to expose the irradiated nuclear
material to dissolution. Especially designed metal cutting shears
are the most commonly employed, although advanced equipment, such as
lasers, may be used.
(2) Dissolvers.
Critically safe tanks (e.g. small diameter, annular, or slab
tanks) especially designed or prepared for use in a reprocessing
plant, intended for dissolution of irradiated nuclear fuel and which
are capable of withstanding hot, highly corrosive liquid, and which
can be remotely loaded and maintained.
Dissolvers normally receive the chopped-up spent fuel. In these
critically safe vessels, the irradiated nuclear material is
dissolved in nitric acid and the remaining hulls removed from the
process stream.
(3) Solvent extractors and solvent extraction equipment.
Especially designed or prepared solvent extractors such as
packed or pulse columns, mixer settlers, or centrifugal contactors
for use in a plant for the reprocessing of irradiated fuel. Solvent
extractors must be resistant to the corrosive effect of nitric acid.
Solvent extractors are normally fabricated to extremely high
standards (including special welding and inspection and quality
assurance and quality control techniques) out of low carbon
stainless steels, titanium, zirconium, or other high quality
materials.
Solvent extractors both receive the solution of irradiated fuel
from the dissolvers and the organic solution which separates the
uranium, plutonium, and fission products. Solvent extraction
equipment is normally designed to meet strict operating parameters,
such as long operating lifetimes with no maintenance requirements or
adaptability to easy replacement, simplicity of operation and
control, and flexibility for variations in process conditions.
(4) Chemical holding or storage vessels.
Especially designed or prepared holding or storage vessels for
use in a plant for the reprocessing of irradiated fuel. The holding
or storage vessels must be resistant to the corrosive effect of
nitric acid. The holding or storage vessels are normally fabricated
of materials such as low carbon stainless steels, titanium or
zirconium, or other high quality materials. Holding or storage
vessels may be designed for remote operation and maintenance and may
have the following features for control of nuclear criticality:
(i) Walls or internal structures with a boron equivalent of at
least 2 percent, or
(ii) A maximum diameter of 175 mm (7 in) for cylindrical
vessels, or
[[Page 39298]]
(iii) A maximum width of 75 mm (3 in) for either a slab or
annular vessel.
(5) Neutron measurement systems for process control.
Neutron measurement systems especially designed or prepared for
integration and use with automated process control systems in a
plant for the reprocessing of irradiated fuel elements. These
systems involve the capability of active and passive neutron
measurement and discrimination in order to determine the fissile
material quantity and composition. The complete system is composed
of a neutron generator, a neutron detector, amplifiers, and signal
processing electronics.
The scope of this entry does not include neutron detection and
measurement instruments that are designed for nuclear material
accountancy and safeguarding or any other application not related to
integration and use with automated process control systems in a
plant for the reprocessing of irradiated fuel elements.
(6) Plutonium nitrate to plutonium oxide conversion systems.
Complete systems especially designed or prepared for the conversion
of plutonium nitrate to plutonium oxide, in particular adapted so as
to avoid criticality and radiation effects and to minimize toxicity
hazards.
(7) Plutonium metal production systems. Complete systems
especially designed or prepared for the production of plutonium
metal, in particular adapted so as to avoid criticality and
radiation effects and to minimize toxicity hazards.
(8) Process control instrumentation specially designed or
prepared for monitoring or controlling the processing of material in
a reprocessing plant.
(9) Any other components especially designed or prepared for use
in a reprocessing plant or in any of the components described in
this appendix.
0
16. In appendix J to part 110, add a new paragraph (c) to read as
follows:
Appendix J to Part 110--Illustrative List of Uranium Conversion Plant
Equipment and Plutonium Conversion Plant Equipment Under NRC Export
Licensing Authority
* * * * *
(c) Any other components especially designed or prepared for use
in a uranium conversion plant or plutonium conversion plant or in
any of the components described in this appendix.
0
17. Revise appendix K to part 110 to read as follows:
Appendix K to Part 110--Illustrative List of Equipment and Components
Under NRC Export Licensing Authority for Use in a Plant for the
Production of Heavy Water, Deuterium and Deuterium Compounds
Note: Heavy water can be produced by a variety of processes.
However, two processes have proven to be commercially viable: The
water-hydrogen sulphide exchange process (GS process) and the
ammonia-hydrogen exchange process.
A. The GS process is based upon the exchange of hydrogen and
deuterium between water and hydrogen sulphide within a series of
towers which are operated with the top section cold and the bottom
section hot. Water flows down the towers while the hydrogen sulphide
gas circulates from the bottom to the top of the towers. A series of
perforated trays are used to promote mixing between the gas and the
water. Deuterium migrates to the water at low temperatures and to
the hydrogen sulphide at high temperatures. Gas or water, enriched
in deuterium, is removed from the first stage towers at the junction
of the hot and cold sections and the process is repeated in
subsequent stage towers. The product of the last stage, water
enriched up to 30 percent in deuterium, is sent to a distillation
unit to produce reactor grade heavy water; i.e., 99.75 percent
deuterium oxide.
B. The ammonia-hydrogen exchange process can extract deuterium
from synthesis gas through contact with liquid ammonia in the
presence of a catalyst. The synthesis gas is fed into exchange
towers and then to an ammonia converter. Inside the towers the gas
flows from the bottom to the top while the liquid ammonia flows from
the top to the bottom. The deuterium is stripped from the hydrogen
in the synthesis gas and concentrated in the ammonia. The ammonia
then flows into an ammonia cracker at the bottom of the tower while
the gas flows into an ammonia converter at the top. Further
enrichment takes place in subsequent stages and reactor-grade heavy
water is produced through final distillation. The synthesis gas feed
can be provided by an ammonia plant that can be constructed in
association with a heavy water ammonia-hydrogen exchange plant. The
ammonia-hydrogen exchange process can also use ordinary water as a
feed source of deuterium.
C.1. Much of the key equipment for heavy water production plants
using either the GS process or the ammonia-hydrogen exchange process
are common to several segments of the chemical and petroleum
industries; particularly in small plants using the GS process.
However, few items are available ``off-the-shelf.'' Both processes
require the handling of large quantities of flammable, corrosive,
and toxic fluids at elevated pressures. Therefore, in establishing
the design and operating standards for plants and equipment using
these processes, careful attention to materials selection and
specifications is required to ensure long service life with high
safety and reliability factors. The choice is primarily a function
of economics and need. Most equipment, therefore, is prepared to
customer requirements.
In both processes, equipment which individually is not
especially designed or prepared for heavy water production can be
assembled into especially designed or prepared systems for producing
heavy water. Examples of such systems are the catalyst production
system used in the ammonia-hydrogen exchange process and the water
distillation systems used for the final concentration of heavy water
to reactor-grade in either process.
C.2. Equipment especially designed or prepared for the
production of heavy water utilizing either the water-hydrogen
sulphide exchange process or the ammonia-hydrogen exchange process:
(i) Water-hydrogen Sulphide Exchange Towers.
Exchange towers with diameters of 1.5 m or greater and capable
of operating at pressures greater than or equal to 2 MPa (300 psi)
especially designed or prepared for heavy water production utilizing
the water-hydrogen sulphide exchange process.
(ii) Blowers and Compressors.
Single stage, low head (i.e., 0.2 MPa or 30 psi) centrifugal
blowers or compressors for hydrogen-sulphide gas circulation (i.e.,
gas containing more than 70 percent H2S). The blowers or compressors
have a throughput capacity greater than or equal to 56 m\3\/second
(120,000 standard cubic feet per minute) while operating at
pressures greater than or equal to 1.8 MPa (260 psi) suction and
have seals designed for wet H2S service.
(iii) Ammonia-Hydrogen Exchange Towers.
Ammonia-hydrogen exchange towers greater than or equal to 35 m
(114.3 ft) in height with diameters of 1.5 m (4.9 ft) to 2.5 m (8.2
ft) capable of operating at pressures greater than 15 MPa (2225
psi). The towers have at least one flanged, axial opening of the
same diameter as the cylindrical part through which the tower
internals can be inserted or withdrawn.
(iv) Tower Internals and Stage Pumps Used in the Ammonia-
hydrogen Exchange Process.
Tower internals include especially designed stage contactors
which promote intimate gas/liquid contact. Stage pumps include
especially designed submersible pumps for circulation of liquid
ammonia within a contacting stage internal to the stage towers.
(v) Ammonia Crackers Utilizing the Ammonia-hydrogen Exchange
Process.
Ammonia crackers with operating pressures greater than or equal
to 3 MPa (450 psi) especially designed or prepared for heavy water
production utilizing the ammonia-hydrogen exchange process.
(vi) Ammonia Synthesis Converters or Synthesis Units.
Ammonia synthesis converters or synthesis units especially
designed or prepared for heavy water production utilizing the
ammonia-hydrogen exchange process.
These converters or units take synthesis gas (nitrogen and
hydrogen) from an ammonia/hydrogen high-pressure exchange column (or
columns), and the synthesized ammonia is returned to the exchange
column (or columns).
(vii) Infrared Absorption Analyzers.
Infrared absorption analyzers capable of ``on-line'' hydrogen/
deuterium ratio analysis where deuterium concentrations are equal to
or greater than 90 percent.
(viii) Catalytic Burners Used in the Ammonia-hydrogen Exchange
Process.
Catalytic burners for the conversion of enriched deuterium gas
into heavy water especially designed or prepared for heavy water
production utilizing the ammonia-hydrogen exchange process.
(ix) Complete Heavy Water Upgrade Systems or Columns.
Complete heavy water upgrade systems or columns especially
designed or prepared for
[[Page 39299]]
the upgrade of heavy water to reactor-grade deuterium concentration.
These systems, which usually employ water distillation to separate
heavy water from light water, are especially designed or prepared to
produce reactor-grade heavy water (i.e., typically 99.75 percent
deuterium oxide) from heavy water feedstock of lesser concentration.
D. Any other components especially designed or prepared for use
in a plant for the production of heavy water, deuterium, and
deuterium compounds or in any of the components described in this
appendix.
0
18. Revise appendix M to part 110 to read as follows:
Appendix M to Part 110--Categorization of Nuclear Material
Categorization of Nuclear Material
[From IAEA INFCIRC/225/Revision 5]
----------------------------------------------------------------------------------------------------------------
Material Form Category I Category II Category III \3\
----------------------------------------------------------------------------------------------------------------
1. Plutonium\1\............. Unirradiated \2\... 2 kg or more....... Less than 2 kg but 500 g or less but
more than 500 g. more than 15 g.
2. Uranium-235 (\235\U)..... Unirradiated \2\:
--Uranium 5 kg or more....... Less than 5 kg but 1 kg or less but
enriched to 20 more than 1 kg. more than 15 g.
percent \235\U
or more.
--Uranium ................... 10 kg or more...... Less than 10 kg but
enriched to 10 more than 1 kg.
percent \235\U
but less than
20 percent
\235\U.
--Uranium ................... ................... 10 kg or more.
enriched above
natural, but
less than 10
percent \235\U.
3. Uranium-233 (\233\U)..... Unirradiated \2\... 2 kg or more....... Less than 2 kg but 500 g or less but
more than 500 g. more than 15 g.
4. Irradiated Fuel (The ................... ................... Depleted or natural ...................
categorization of uranium, thorium
irradiated fuel in the or low enriched
table is based on fuel (less than 10
international transport percent fissile
considerations. The State content) 4 5
may assign a different
category for domestic use,
storage and transport
taking all relevant factors
into account).
----------------------------------------------------------------------------------------------------------------
\1\ All plutonium except that with isotopic concentration exceeding 80 percent in plutonium-238.
\2\ Material not irradiated in a reactor or material irradiated in a reactor but with a radiation level equal to
or less than 1 Gy/h (100 rad/h) at 1 m unshielded.
\3\ Quantities not falling in Category III and natural uranium, depleted uranium and thorium should be protected
at least in accordance with prudent management practice.
\4\ Although this level of protection is recommended, it would be open to States, upon evaluation of the
specific circumstances, to assign a different category of physical protection.
\5\ Other fuel which by virtue of its original fissile material content is classified as Category I or II before
irradiation may be reduced one category level while the radiation level from the fuel exceeds 1 Gy/h (100 rad/
h) at one meter unshielded.
0
19. In appendix N to part 110, add a new paragraph c. to read as
follows:
Appendix N to Part 110--Illustrative List of Lithium Isotope Separation
Facilities, Plants and Equipment Under NRC's Export Licensing Authority
* * * * *
c. Any other components especially designed or prepared for use
in a reprocessing plant or in any of the components described in
this appendix.
0
20. Revise appendix O to part 110 to read as follows:
Appendix O to Part 110--Illustrative List of Fuel Element Fabrication
Plant Equipment and Components Under NRC's Export Licensing Authority
Note: Nuclear fuel elements are manufactured from source or
special nuclear material. For oxide fuels, the most common type of
fuel equipment for pressing pellets, sintering, grinding and grading
will be present. Mixed oxide fuels are handled in glove boxes (or
equivalent containment) until they are sealed in the cladding. In
all cases, the fuel is hermetically sealed inside a suitable
cladding which is designed to be the primary envelope encasing the
fuel so as to provide suitable performance and safety during reactor
operation. Also, in all cases, precise control of processes,
procedures and equipment to extremely high standards is necessary in
order to ensure predictable and safe fuel performance.
(a) Items that are considered especially designed or prepared
for the fabrication of fuel elements include equipment that:
(1) Normally comes in direct contact with, or directly processes
or controls, the production flow of nuclear material;
(2) Seals the nuclear material within the cladding;
(3) Checks the integrity of the cladding or the seal;
(4) Checks the finished treatment of the sealed fuel; or
(5) Is used for assembling reactor fuel elements.
(b) This equipment or systems of equipment may include, for
example:
[[Page 39300]]
(1) Fully automatic pellet inspection stations especially
designed or prepared for checking final dimensions and surface
defects of fuel pellets;
(2) Automatic welding machines especially designed or prepared
for welding end caps onto the fuel pins (or rods);
(3) Automatic test and inspection stations especially designed
or prepared for checking the integrity of completed fuel pins (or
rods). This item typically includes equipment for:
(i) X-ray examination of pin (or rod) end cap welds;
(ii) Helium leak detection from pressurized pins (or rods); and
(iii) Gamma-ray scanning of the pins (or rods) to check for
correct loading of the fuel pellets inside.
(4) Systems especially designed or prepared to manufacture
nuclear fuel cladding.
(c) Any other components especially designed or prepared for use
in a fuel element fabrication plant or in any of the components
described in this appendix.
Dated at Rockville, Maryland, this 18th day of June, 2014.
For the Nuclear Regulatory Commission.
Mark A. Satorius,
Executive Director for Operations.
[FR Doc. 2014-15828 Filed 7-9-14; 8:45 am]
BILLING CODE 7590-01-P
