Export of Nuclear Equipment and Materials

Federal RegisterJul 8, 1996

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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.)

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:

* * * * *

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.