[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