[Federal Register Volume 61, Number 131 (Monday, July 8, 1996)]
[Rules and Regulations]
[Pages 35600-35607]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-17236]
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NUCLEAR REGULATORY COMMISSION
10 CFR Part 110
RIN 3150-AF51
Export of Nuclear Equipment and Materials
AGENCY: Nuclear Regulatory Commission.
ACTION: Final rule.
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SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its
regulations pertaining to the export of nuclear equipment and
materials. These amendments are necessary to conform the export
controls of the United States to the international export control
guidelines of the Nuclear Suppliers Group, of which the United States
is a member, and to reflect the nuclear nonproliferation policies of
the Department of State.
EFFECTIVE DATE: August 7, 1996.
FOR FURTHER INFORMATION CONTACT: Elaine O. Hemby, Office of
International Programs, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001, telephone (301) 415-2341, e-mail [email protected].
SUPPLEMENTARY INFORMATION: The Nuclear Regulatory Commission (NRC) is
amending its regulations pertaining to the export of nuclear materials
and equipment. Cambodia and Vietnam are removed from the list of
embargoed destinations; Algeria, Comoros, Guyana, Mauritania, Niger,
St. Kitts, United Arab Emirates, Vanuatu, and Yemen Arab Republic are
removed from the list of restricted destinations; Brazil, New Zealand,
Republic of Korea, South Africa, and Ukraine are added as member
countries of the Nuclear Suppliers Group (NSG) eligible to receive
radioactive materials under certain general licenses for export;
Austria and Finland are added as eligible countries to receive nuclear
reactor components under general license for export; plants for the
conversion of uranium and especially designed or prepared equipment for
uranium conversion are added to the export controls of the NRC; the
kinds of uranium conversion equipment and uranium enrichment equipment
under NRC export licensing authority are added for clarification;
exports of less than one kilogram of source or special nuclear material
exported under the U.S.-IAEA Agreement for Cooperation no longer
require Executive Branch review before an NRC license is issued; a
general license to export source material and a general license for
import are amended to correct inadvertent errors; a reference is added
to clarify that some imports and exports of nuclear items are under
Department of State controls; and Appendices B and L to Part 110 are
amended to correct errors.
Section 110.1, which describes the scope of 10 CFR Part 110, is
revised to add a reference that nuclear items on the U.S. Munitions
List are subject to the export controls of the Department of State.
In Sec. 110.8, which lists the nuclear facilities and equipment
under NRC export authority, and in the appendices to Part 110, which
describe the especially designed and prepared equipment under NRC
export controls, the word ``specially'' where it appears is changed to
``especially'' to conform to the NSG guidelines.
Section 110.8 is amended to add uranium conversion plants and
especially designed or prepared equipment for uranium conversion plants
to the export authority of the NRC to conform to the NSG guidelines.
Recently, the United States and other member countries of the NSG
agreed to add to the NSG Trigger List (INFCIRC/254/Part 1) uranium
conversion plants. This includes conversion of uranium ore concentrates
to UO3, conversion of UO3 to UO2, conversion of uranium oxides to UF4
or UF6, conversion of UF4 to UF6, conversion of UF6 to UF4, conversion
of UF4 to uranium metal, and conversion of uranium fluorides to uranium
oxides. The nuclear materials and equipment designated as ``trigger
list'' items are controlled by the NRC. Conversion of uranium is an
essential step of the nuclear fuel cycle for both civil and military
programs, including the production of highly enriched uranium and
plutonium. In Sec. 110.2, a definition of ``conversion facility'' is
added for clarification.
Exports of uranium conversion plants and equipment are presently
controlled by the Department of Commerce (DOC). The addition of uranium
conversion plants to the NRC licensing authority will allow the DOC to
remove this item from its nuclear referral list. Accordingly,
Sec. 110.1(b)(3), which describes nuclear-related commodities that are
subject to DOC export controls, is revised to remove the reference to
DOC controls on conversion plants.
In Sec. 110.22, paragraph (c) is amended to delete the word ``not''
where it first appears. This action is necessary to correct an
inadvertent error in a final rule published July 21, 1995 (60 FR
37556). As corrected, Sec. 110.22(c) authorizes the export of uranium
or thorium, other than U-230, U-232, Th-227, or Th-228, in individual
shipments of one kilogram or less to any country listed in Sec. 110.29,
not to exceed 100 kilograms per year to any one country, except for
source material in radioactive waste.
In Sec. 110.26, Austria and Finland are added as eligible
recipients of nuclear reactor components under the NRC's general
license authority for export. These countries are now members of
EURATOM. EURATOM has provided the necessary written assurances to the
U.S. Government to permit these kinds of exports.
In Sec. 110.27, which describes the general licenses for import,
paragraph (4) is amended to delete the term ``advance'' to describe the
kind of notification required. For some activities under Sec. 73.27,
advance notification would not apply.
In Sec. 110.28, which lists the embargoed destinations, Cambodia
and Vietnam are removed. Because President Clinton lifted the U.S.
general trade embargo against Vietnam on February 3, 1995, and the
embargo restrictions for Cambodia in 1993, the Executive Branch
recently recommended that Cambodia and Vietnam be removed from the
embargoed destinations. Both Cambodia and Vietnam are adherents to the
Treaty on the Non-Proliferation of Nuclear Weapons (NPT). Exports to
Cambodia and Vietnam now qualify for the NRC general licensing
authorizations specified in Secs. 110.21 through 110.25.
In Sec. 110.29, Algeria, Comoros, Guyana, Mauritania, Niger, St.
Kitts, United Arab Emirates, Vanuatu, and Yemen Arab Republic are
removed from
[[Page 35601]]
the restricted destinations. The Executive Branch recently recommended
that these countries be removed because they are NPT adherents.
Accordingly, exports to these countries now qualify for the NRC general
licensing authorizations specified in Secs. 110.21 through 110.25.
In Sec. 110.30, Brazil, New Zealand, Republic of Korea, South
Africa, and Ukraine are added as members of the NSG. Accordingly, these
countries are eligible to receive radioactive materials under NRC
general licenses.
In Sec. 110.41, paragraph (4) is amended to reflect the Executive
Branch judgment that any export of less than one kilogram of source or
special nuclear material which is exported under the provisions of the
U.S.-IAEA Agreement for Cooperation does not require review by the
Executive Branch.
In Appendix B to Part 110, which describes the gas centrifuge
equipment under NRC licensing authority, the footnote to section 1 is
amended to change the specifications for filamentary materials suitable
for gas centrifuge rotating components. This action is necessary to
correct errors when the equations were converted from English to metric
units. The current level of control catches items with a wide variety
of non-nuclear, non-sensitive applications. Section 1.2 of Appendix B
is amended to clarify the kinds of static components NRC controls to
reflect the NSG Guidelines.
New appendices to Part 110 are added to clarify the uranium
enrichment equipment and uranium conversion equipment under NRC export
licensing authority to reflect the guidelines of the NSG. The
appendices are illustrative only and not inclusive. Corresponding
changes are made to Sec. 110.8.
In Appendix L, which lists the byproduct materials under NRC
licensing controls, the entry ``Tungsten 185 (w 85)'' is corrected to
read ``Tungsten 185 (W 185).''
The NRC has determined that this rule is necessary to reflect the
Executive Branch's nuclear non-proliferation policies and to conform
the export controls of the United States to the international export
control guidelines of the NSG, of which the United States is a member.
The rule also corrects several minor, inadvertent errors from previous
rulemakings.
Because the substance of 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 United States
conformance with its international obligations and would thus be
contrary to the public interest (5 U.S.C. 553(b)).
Small Business Regulatory Enforcement Fairness Act
In accordance with the Small Business Regulatory Enforcement
Fairness 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. The rule is necessary to
conform the nuclear nonproliferation policies of the United States with
international export guidelines.
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) and (c)(2).
Therefore, neither an environmental impact statement nor an
environmental assessment has been prepared for this final rule.
Paperwork Reduction Act Statement
This final rule does not contain a new or amended information
collection requirement subject to the Paperwork Reduction Act of 1995
(44 U.S.C. 3501 et seq.). Existing requirements in Secs. 110.26,
110.31, 110.32, 110.53 and the use of Form NRC 7 were approved by the
Office of Management and Budget, approval numbers 3150-0036 and 3150-
0027.
Public Protection Notification
The NRC may not conduct or sponsor, and a person is not required to
respond to, a collection of information unless it displays a currently
valid OMB control number.
Regulatory Analysis
The final rule eliminating the requirement for a specific license
in some circumstances should have a positive economic effect on U.S.
export business. U.S. exporters can ship nuclear equipment and
materials under the NRC general license authority to additional foreign
markets without the expense of license application fees, the paperwork
burden, time delays, and uncertainties in delivery. For the first time,
Cambodia and Vietnam are eligible to receive certain NRC nuclear
materials under general license. Austria and Finland are now eligible
to receive nuclear reactor equipment under NRC general license. In
addition, Brazil, New Zealand, Republic of Korea, South Africa,
Ukraine, Algeria, Comoros, Guyana, Mauritania, Niger, St. Kitts, United
Arab Emirates, Vanuatu, and Yemen Arab Republic can now receive certain
nuclear materials under NRC general licenses.
In transferring export authority of uranium conversion plants and
equipment from the DOC to NRC export authority, the Commission was
aware of a potential detrimental impact on exporters because of the
license fee imposed by NRC for each license application submitted.
However, according to DOC export licensing data, the DOC issued only
one export license for conversion equipment in the past five years, at
a value of $317,000. In view of this information, the NRC continues to
believe that the economic impact of the rule on U.S. companies is not
significant.
There are no alternatives for achieving the stated objective. This
rule conforms NRC's export controls to the international export
guidelines of the NSG. Thus, the regulation is required to satisfy
international obligations of the United States. The foregoing
discussion constitutes the regulatory analysis for this final rule.
Backfit Analysis
The NRC has determined that a backfit analysis is not required for
this final rule because these amendments do not include any provisions
that would require backfits as defined in 10 CFR 50.109(a)(1).
List of Subjects in 10 CFR Part 110
Administrative practice and procedure, Classified information,
Criminal penalties, Export, Import, 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: Secs. 51, 53, 54, 57, 63, 64, 65, 81, 82, 103, 104,
109, 111, 126, 127, 128, 129, 161, 181, 182, 183, 187, 189, 68 Stat.
929, 930, 931, 932, 933, 936, 937, 948, 953, 954, 955, 956, as
amended (42 U.S.C. 2071, 2073, 2074, 2077, 2092-2095, 2111, 2112,
2133, 2134, 2139, 2139a, 2141, 2154-2158, 2201, 2231-2233, 2237,
2239); sec. 201, 88 Stat. 1242, as amended (42 U.S.C. 5841); sec. 5,
Pub. L. 101-575, 104 Stat. 2835 (42 U.S.C. 2243).
[[Page 35602]]
Sections 110.1(b)(2) and 110.1(b)(3) also issued under Pub. L.
96-92, 93 Stat. 710 (22 U.S.C. 2403). Section 110.11 also issued
under sec. 122, 68 Stat. 939 (42 U.S.C. 2152) and secs. 54c and 57d,
88 Stat. 473, 475 (42 U.S.C. 2074). Section 110.27 also issued under
sec. 309(a), Pub. L. 99-440. Section 110.50(b)(3) also issued under
sec. 123, 92 Stat. 142 (42 U.S.C. 2153). Section 110.51 also issued
under sec. 184, 68 Stat. 954, as amended (42 U.S.C. 2234). Section
110.52 also issued under sec. 186, 68 Stat. 955 (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 sec. 903, Pub. L. 102-496
(42 U.S.C. 2151 et seq.).
2. In Sec. 110.1, paragraph (b)(2) is revised, paragraphs (b)(3)
and (b)(4) are redesignated as paragraphs (b)(4) and (b)(5), the
redesignated paragraph (b)(4) is revised, and a new paragraph (b)(3) is
added to read as follows:
Sec. 110.1 Purpose and scope.
* * * * *
(b) * * *
(2) Persons who export or import U.S. Munitions List nuclear items,
such as uranium depleted in the isotope-235 and incorporated in defense
articles. These persons are subject to the controls of the Department
of State pursuant to 22 CFR 120-130 ``International Traffic in Arms
Regulations'' (ITAR), under the Arms Export Control Act, as authorized
by section 110 of the International Security and Development
Cooperation Act of 1980;
(3) Persons who export uranium depleted in the isotope-235 and
incorporated in commodities solely to take advantage of high density or
pyrophoric characteristics. These persons are subject to the controls
of the Department of Commerce under the Export Administration Act, as
authorized by section 110 of the International Security and Development
Cooperation Act of 1980;
(4) Persons who export nuclear referral list commodities. These
persons are subject to the licensing authority of the Department of
Commerce pursuant to 15 CFR part 799, such as bulk zirconium, rotor and
bellows equipment, maraging steel, nuclear reactor related equipment,
including process control systems and simulators; and
* * * * *
3. In Sec. 110.2, a definition for Conversion facility is added in
alphabetical order to read as follows:
Sec. 110.2 Definitions.
* * * * *
Conversion facility means any facility for the transformation from
one uranium chemical species to another, including: conversion of
uranium ore concentrates to UO3, conversion of UO3 to UO2, conversion
of uranium oxides to UF4 or UF6, conversion of UF4 to UF6, conversion
of UF6 to UF4, conversion of UF4 to uranium metal, and conversion of
uranium fluorides to UO2.
* * * * *
4. Section 110.8 is revised to read as follows:
Sec. 110.8 List of nuclear facilities and equipment under NRC export
licensing authority.
(a) Nuclear reactors and especially designed or prepared equipment
and components for nuclear reactors. (See appendix A to this part.)
(b) Plants for the separation of isotopes of uranium (source
material or special nuclear material) including gas centrifuge plants,
gaseous diffusion plants, aerodynamic enrichment plants, chemical
exchange or ion exchange enrichment plants, laser based enrichment
plants, plasma separation enrichment plants, electromagnetic enrichment
plants, and especially designed or prepared equipment, other than
analytical instruments, for the separation of isotopes of uranium. (See
appendices to this part for lists of: gas centrifuge equipment--
Appendix B; gaseous diffusion equipment--Appendix C; aerodynamic
enrichment equipment--Appendix D; chemical exchange or ion exchange
enrichment equipment--Appendix E; laser based enrichment equipment--
Appendix F; plasma separation enrichment equipment--Appendix G; and
electromagnetic enrichment equipment--Appendix H.)
(c) Plants for the separation of the isotopes of lithium and
especially designed or prepared assemblies and components for these
plants.
(d) Plants for the reprocessing of irradiated nuclear reactor fuel
elements and especially designed or prepared assemblies and components
for these plants. (See Appendix I to this part.)
(e) Plants for the fabrication of nuclear reactor fuel elements and
especially designed or prepared assemblies and components for these
plants.
(f) Plants for the conversion of uranium and especially designed or
prepared assemblies and components for these plants. (See Appendix J to
this part.)
(g) Plants for the production, separation, or purification of heavy
water, deuterium, and deuterium compounds and especially designed or
prepared assemblies and components for these plants. (See Appendix K to
this part.)
(h) Other nuclear-related commodities are under the export
licensing authority of the Department of Commerce.
Sec. 110.22 [Amended]
5. In Sec. 110.22(c), remove the word ``not'' where it appears
between ``country'' and ``listed.''
Sec. 110.23 [Amended]
6. In Sec. 110.23, paragraph (a)(1), ``Appendix F'' is revised to
read ``Appendix L.''
Sec. 110.26 [Amended]
7. In Sec. 110.26, paragraph (a)(2) is amended by adding
``Austria'' and ``Finland'' in alphabetical order.
8. In Sec. 110.27, paragraph (d) is revised to read as follows:
Sec. 110.27 General license for imports.
* * * * *
(d) A person importing formula quantities of strategic special
nuclear material (as defined in Sec. 73.2 of this chapter) under this
general license shall provide the notifications required by Sec. 73.27
and Sec. 73.72 of this chapter.
Sec. 110.28 [Amended]
9. Section 110.28 is amended by removing ``Cambodia'' and
``Vietnam.''
Sec. 110.29 [Amended]
10. Section 110.29 is amended by removing ``Algeria,'' ``Comoros,''
``Guyana,'' ``Mauritania,'' ``Niger,'' ``St. Kitts,'' ``United Arab
Emirates,'' ``Vanuatu,'' and ``Yemen Arab Republic.''
Sec. 110.30 [Amended]
11. Section 110.30 is amended by adding ``Brazil,'' ``New
Zealand,'' ``Republic of Korea,'' ``South Africa,'' and ``Ukraine'' in
alphabetical order.
Sec. 110.41 [Amended]
12. In Sec. 110.41, paragraph (a)(4) is revised to read as follows:
(a) * * *
(4) One kilogram or more of source or special nuclear material to
be exported under the US-IAEA Agreement for Cooperation.
* * * * *
13. In Sec. 110.44, paragraph (b)(2), ``Appendix G'' is revised to
read ``Appendix M.''
Appendix A to Part 110 [Amended]
14. In Appendix A to Part 110, paragraph (9), remove the word
``specially'' and add in its place the word ``especially.''
15. In Appendix B to Part 110, paragraph (c) of the Footnote to
section 1 is revised and paragraphs (e) and (f) are added to section
1.2 to read as follows:
[[Page 35603]]
Footnote
The materials used for centrifuge rotating components are:
* * * * *
(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
2320C and a relative humidity of 505%.
``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 2320C and a relative humidity of
505%.)
* * * * *
1.2 Static Components.
* * * * *
(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 (1.2in) 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. The housings are made of or protected by materials resistant
to corrosion by UF6.
(f) Scoops: Especially designed or prepared tubes of up to 12 mm
(0.5in) internal diameter 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. The tubes are
made of or protected by materials resistant to corrosion by UF6.
* * * * *
Appendices D, E, F, and G to Part 110 [Redesignated as Appendice I, K
through M of Part 110]
16. Appendix D to Part 110 is redesignated Appendix I to Part 110
and Appendices E through G to Part 110 are redesignated as Appendices K
through M to Part 110.
17. A new Appendix D to Part 110 is added 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 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, stainless steel, aluminum, aluminum
alloys, nickel or alloys containing 60% or more nickel and UF6-
resistant fully 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 nozzles that consist of slit-
shaped, curved channels having a radius of curvature less than 1 mm
(typically 0.1 to 0.05 mm). The nozzles are resistant to UF6
corrosion and have 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 that are
cylindrical or tapered, made of or protected by materials resistant
to UF6 corrosion, have a diameter of between 0.5 cm and 4 cm, a
length to diameter ratio of 20:1 or less 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 axial, centrifugal, or positive
displacement compressors or gas blowers made of or protected by
materials resistant to UF6 corrosion and with a suction volume
capacity of 2 m \3\/min or more of UF6/carrier gas (hydrogen or
helium) mixture. These compressors and gas blowers typically have a
pressure ratio between 1.2:1 and 6:1.
(4) Rotary shaft seals.
Especially designed or prepared 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 UF6 corrosion.
(6) Separation element housings.
Especially designed or prepared separation element housings,
made of or protected by materials resistant to UF6 corrosion, for
containing vortex tubes or separation nozzles.
These housings may be cylindrical vessels greater than 300 mm in
diameter and greater than 900 mm in length, or may be rectangular
vessels of comparable dimensions, and may be designed for horizonal
or vertical installation.
(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 UF6
corrosion, 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 UF6 corrosion, 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.
Especially designed or prepared vacuum systems having a suction
capacity of 5 m\3\/min or more, consisting of vacuum manifolds,
vacuum headers and vacuum pumps, and designed for service in UF6-
bearing atmospheres.
Especially designed or prepared vacuum pumps for service in UF6-
bearing atmospheres and made of or protected by materials resistant
to UF6 corrosion. These pumps may use fluorocarbon seals and special
working fluids.
(10) Special shut-off and control valves.
Especially designed or prepared manual or automated shut-off and
control bellows valves made of or protected by materials resistant
to UF6 corrosion with a diameter of 40 to 1500 mm for installation
in main and auxiliary systems of aerodynamic enrichment plants.
(11) UF6 mass spectrometers/ion sources.
Especially designed or prepared magnetic or quadrupole mass
spectrometers capable of taking ``on-line'' samples of feed,
``product'' or ``tails'', from UF6 gas streams and having all of the
following characteristics:
(i) Unit resolution for mass greater than 320;
(ii) Ion sources constructed of or lined with nichrome or monel
or nickel plated;
(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:
[[Page 35604]]
(i) Cryogenic heat exchangers and cryoseparators capable of
temperatures of -120 deg.C or less;
(ii) Cryogenic refrigeration units capable of temperatures of
-120 deg.C or less;
(iii) Separation nozzle or vortex tube units for the separation
of UF6 from carrier gas; or
(iv) UF6 cold traps capable of temperatures of -20 deg.C or
less.
18. A new Appendix E to Part 110 is added 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 (i.e., pulsed columns with sieve plates, reciprocating
plate columns, and columns with internal turbine mixers), 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
made of or protected by suitable plastic materials (such as
fluorocarbon polymers) or glass. The stage residence time of the
columns is designed to be short (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 made of
or are lined with suitable plastic materials (such as fluorocarbon
polymers) or are lined with 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, fluorocarbon 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 100 deg.C to 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
100 deg.C to 200 deg.C and pressures above 0.7 MPa (102 psia).
(3) Ion exchange reflux systems.
(i) Especially designed or prepared chemical or electrochemical
reduction systems for regeneration of the chemical
[[Page 35605]]
reducing agent(s) used in ion exchange uranium enrichment cascades.
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.
19. A new Appendix F to Part 110 is added 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. Common
nomenclature for these processes include: first category-atomic
vapor laser isotope separation (AVLIS or SILVA); second category-
molecular laser isotope separation (MLIS or MOLIS) and chemical
reaction by isotope selective laser activation (CRISLA). 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 photo-dissociation or chemical activation; (b) devices to
collect enriched and depleted uranium metal as ``product'' and
``tails'' in the first category, and devices to collect dissociated
or reacted compounds as ``product'' and unaffected material as
'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 technologies.
All surfaces that come into 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, stainless steel, aluminum, aluminum
alloys, nickel or alloys containing 60% or more nickel and UF6-
resistant fully 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 (AVLIS).
Especially designed or prepared uranium vaporization systems
that contain high-power strip or scanning electron beam guns with a
delivered power on the target of more than 2.5 kW/cm.
(2) Liquid uranium metal handling systems (AVLIS).
Especially designed or prepared liquid metal handling systems
for molten uranium or uranium alloys, consisting of crucibles and
cooling equipment for the crucibles.
The crucibles and other system parts that come into contact with
molten uranium or uranium alloys 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
(AVLIS).
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 (AVLIS).
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 (MLIS).
Especially designed or prepared supersonic expansion nozzles for
cooling mixtures of UF6 and carrier gas to 150 K or less which are
corrosion resistant to UF6.
(6) Uranium pentafluoride product collectors (MLIS).
Especially designed or prepared uranium pentafluoride (UF5)
solid product collectors consisting of filter, impact, or cyclone-
type collectors, or combinations thereof, which are corrosion
resistant to the UF5/UF6 environment.
(7) UF6/carrier gas compressors (MLIS).
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 (MLIS).
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 (MLIS).
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 to MLIS units 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 (MLIS).
Especially designed or prepared magnetic or quadrupole mass
spectrometers capable of taking ``on-line'' samples of feed,
``product'' or ``tails'', from UF6 gas streams and having all of the
following characteristics:
(i) Unit resolution for mass greater than 320;
(ii) Ion sources constructed of or lined with nichrome or monel
or nickel plated;
(iii) Electron bombardment ionization sources; and
(iv) Collector system suitable for isotopic analysis.
(11) Feed systems/product and tails withdrawal systems (MLIS).
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 (MLIS).
Especially designed or prepared process systems for separating
UF6 from carrier gas. The carrier gas may be nitrogen, argon, or
other gas.
These systems may incorporate equipment such as:
(i) Cryogenic heat exchangers or cryoseparators capable of
temperatures of -120 deg.C or less;
(ii) Cryogenic refrigeration units capable of temperatures of
-120 deg.C or less; or
(iii) UF6 cold traps capable of temperatures of -20 deg.C or
less.
(13) Lasers or Laser systems (AVLIS, MLIS and CRISLA).
Especially designed or prepared for the separation of uranium
isotopes. The laser system for the AVLIS process usually consists of
two lasers: a copper vapor laser and a dye laser. The laser system
for MLIS usually consists of a CO2 or excimer laser and a
multi-pass optical cell with revolving mirrors at both ends. Lasers
or laser systems for both processes require a spectrum frequency
stabilizer for operation over extended periods.
20. A new Appendix G to Part 110 is added to read as follows:
[[Page 35606]]
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 large-diameter
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, which may contain high power strip or scanning
electron beam guns with a delivered power on the target of more than
2.5 kW/cm.
(4) Liquid uranium metal handling systems.
Especially designed or prepared liquid metal handling systems
for molten uranium or uranium alloys, consisting of crucible and
cooling equipment for the crucibles.
The crucibles and other system parts that come into contact with
molten uranium or uranium alloys are made of or protected by
corrosion and heat resistance materials, such as tantalum, yttria-
coated graphite, graphite coated with other rare earth oxides or
mixtures thereof.
(5) 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.
(6) 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.
21. A new Appendix H to Part 110 is added to read as follows:
Appendix H to Part 110--Illustrative List of Electromagnetic Enrichment
Plant Equipment and Components Under NRC Export Licensing Authority
Note--In the electromagnetic process, uranium metal ions
produced by ionization of a salt feed material (typically UCL4) are
accelerated and passed through a magnetic field that has the effect
of causing the ions of different isotopes to follow different paths.
The major components of an electromagnetic isotope separator
include: a magnetic field for ion-beam diversion/separation of the
isotopes, an ion source with its acceleration system, and a
collection system for the separated ions. Auxiliary systems for the
process include the magnet power supply system, the ion source high-
voltage power supply system, the vacuum system, and extensive
chemical handling systems for recovery of product and cleaning/
recycling of components.
(1) Electromagnetic isotope separators.
Especially designed or prepared for the separation of uranium
isotopes, and equipment and components therefor, including:
(i) Ion Sources--especially designed or prepared single or
multiple uranium ion sources consisting of a vapor source, ionizer,
and beam accelerator, constructed of materials such as graphite,
stainless steel, or copper, and capable of providing a total ion
beam current of 50 mA or greater;
(ii) Ion collectors--collector plates consisting of two or more
slits and pockets especially designed or prepared for collection of
enriched and depleted uranium ion beams and constructed of materials
such as graphite or stainless steel;
(iii) Vacuum housings--especially designed or prepared vacuum
housings for uranium electromagnetic separators, constructed of
suitable non-magnetic materials such as stainless steel and designed
for operation at pressures of 0.1 Pa or lower.
The housings are specially designed to contain the ion sources,
collector plates and water-cooled liners and have provision for
diffusion pump connections and opening and closure for removal and
reinstallation of these components; and
(iv) Magnet pole pieces--especially designed or prepared magnet
pole pieces having a diameter greater than 2 m used to maintain a
constant magnetic field within an electromagnetic isotope separator
and to transfer the magnetic field between adjoining separators.
(2) High voltage power supplies.
Especially designed or prepared high-voltage power supplies for
ion sources, having all of the following characteristics:
(i) Capable of continuous operation;
(ii) Output voltage of 20,000 V or greater;
(iii) Output current of 1 A or greater; and
(iv) Voltage regulation of better than 0.01% over an 8 hour time
period.
(3) Magnet power supplies.
Especially designed or prepared high-power, direct current
magnet power supplies having all of the following characteristics:
(i) Capable of continuously producing a current output of 500 A
or greater at a voltage of 100 V or greater; and
(ii) A current or voltage regulation better than 0.01% over an 8
hour time period.
22. A new Appendix J to Part 110 is added to read as follows:
Appendix J to Part 110--Illustrative List of Uranium Conversion Plant
Equipment Under NRC Export Licensing Authority
Note--Uranium conversion plants and systems may perform one or
more transformations from one uranium chemical species to another,
including: conversion of uranium ore concentrates to UO3, conversion
of UO3 to UO2, conversion of uranium oxides to UF4 or UF6,
conversion of UF4 to UF6, conversion of UF6 to UF4, conversion of
UF4 to uranium metal, and conversion of uranium fluorides to UO2.
Many key equipment items for uranium conversion plants are common to
several segments of the chemical process industry, including
furnaces, rotary kilns, fluidized bed reactors, flame tower
reactors, liquid centrifuges, distillation columns and liquid-liquid
extraction columns. However, few of the items are available ``off-
the-shelf''; most would be prepared according to customer
requirements and specifications. Some require special design and
construction considerations to address the corrosive properties of
the chemicals handled (HF, F2, CLF3, and uranium fluorides). In all
of the uranium conversion processes, equipment which individually is
not especially designed or prepared for uranium conversion can be
assembled into systems which are especially designed or prepared for
uranium conversion.
(1) Especially designed or prepared systems for the conversion
of uranium ore concentrates to UO3.
Conversion of uranium ore concentrates to UO3 can be performed
by first dissolving the ore in nitric acid and extracting purified
uranyl nitrate using a solvent such as tributyl phosphate. Next, the
uranyl nitrate is converted to UO3 either by concentration and
denitration or by neutralization with gaseous ammonia to product
ammonium diuranate with subsequent filtering, drying, and calcining.
(2) Especially designed or prepared systems for the conversion
of UO3 to UF6.
Conversion of UO3 to UF6 can be performed directly by
fluorination. The process requires a source of fluorine gas or
chlorine trifluoride.
(3) Especially Designed or Prepared Systems for the conversion
of UO3 to UO2.
Conversion of UO3 to UO2 can be performed through reduction of
UO3 with cracked ammonia gas or hydrogen.
(4) Especially Designed or Prepared Systems for the conversion
of UO2 to UF4.
Conversion of UO2 to UF4 can be performed by reacting UO2 with
hydrogen fluoride gas (HF) at 300-500 deg.C.
(5) Especially Designed or Prepared Systems for the conversion
of UF4 to UF6.
[[Page 35607]]
Conversion of UF4 to UF6 is performed by exothermic reaction
with fluorine in a tower reactor. UF6 is condensed from the hot
effluent gases by passing the effluent stream through a cold trap
cooled to -10 deg.C. The process requires a source of fluorine gas.
(6) Especially Designed or Prepared Systems for the conversion
of UF4 to U metal.
Conversion of UF4 to U metal is performed by reduction with
magnesium (large batches) or calcium (small batches). The reaction
is carried out at temperatures above the melting point of uranium
(1130 deg.C).
(7) Especially designed or prepared systems for the conversion
of UF6 to UO2.
Conversion of UF6 to UO2 can be performed by one of three
processes. In the first, UF6 is reduced and hydrolyzed to UO2 using
hydrogen and steam. In the second, UF6 is hydrolyzed by solution in
water, ammonia is added to precipitate ammonium diuranate, and the
diuranate is reduced to UO2 with hydrogen at 820 deg.C. In the third
process, gaseous UF6, CO2, and NH3 are combined in water,
precipitating ammonium uranyl carbonate. The ammonium uranyl
carbonate is combined with steam and hydrogen at 500-600 deg.C to
yield UO2. UF6 to UO2 conversion is often performed as the first
stage of a fuel fabrication plant.
(8) Especially Designed or Prepared Systems for the conversion
of UF6 to UF4. Conversion of UF6 to UF4 is performed by reduction
with hydrogen.
Appendix L to Part 110 [Amended]
23. In newly redesignated Appendix L to Part 110, the entry
``Tungsten 185 (W 85)'' is revised to read ``Tungsten 185 (W 185).''
Dated in Rockville, MD, this 28th day of June 1996.
For the Nuclear Regulatory Commission.
James M. Taylor,
Executive Director for Operations.
[FR Doc. 96-17236 Filed 7-5-96; 8:45 am]
BILLING CODE 7590-01-P