ML23156A433

PR-110 - 55FR30449 - Export of Components for Use in Gaseous Diffusion Enrichment Plants

ML23156A433
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Issue date:	07/26/1990
From:	Taylor J NRC/EDO
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PR-110, 55FR30449
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ADAMS Template: SECY-067 DOCUMENT DATE: 07/26/1990 TITLE: PR-110 - 55FR30449 - EXPORT OF COMPONENTS FOR USE IN GASEOUS DIFFUSION ENRICHMENT PLANTS CASE

REFERENCE:

PR-110 55FR30449 KEYWORD: RULEMAKING COMMENTS Document Sensitivity: Non-sensitive - SUNSI Review Complete

STATUS OF RULEMAKING PROPOSED RULE: PR-110 OPEN ITEM (Y/N) N RULB NAME: EXPORT OF COMPONENTS FOR USE IN GASEOUS DIFFUSION ENRICHMENT PLANTS PROPOSED RULB FED REG CITE: 55FR30449 PROPOSED RULE PUBLICATION DATE: 07/26/90 NUMBER OF COMMENTS: 0 ORIGINAL DATE FOR COMMENTS: 07/26/90 EXTENSION DATE: I I FINAL RULE FED. REG. CITE: 55FR30449 FINAL RULE PUBLICATION DATE: 07/26/90 NOTU OH ISSUED AS FINAL RULE. FILE LOCATED ON Pl.

STA'l'US OF RULE TO FIND THB STAFF CONTACT OR VIEW THE RULEMAKING HISTORY PRESS PAGE DOWN KEY HISTORY OF THE RULE PART AFFECTED: PR-110 RULE TITLE: EXPORT OF COMPONENTS FOR USE IN GASEOUS DIFFUSION ENRICHMENT PLANTS ROPOSED RULE PROPOSED RULE DATE PROPOSED RULE SECY PAPER: SRM DATE: I I SIGNED BY SECRETARY: 07/13/90 FINAL RULE FINAL RULE DATE FINAL RULE SECY PAPER: SRM DATE: I I SIGNED BY SECRETARY: 08/22/90 STAFF CONTACTS ON THE RULE CONTACTl: ELAINE O. HEMBY MAIL STOP: 3-B-5 PHONE: 49-20341 CONTACT2: JOANNA M. BECKER MAIL STOP: 15-B-18 PHONE: 49-21740

l"\CKET NUMBER PR PROPOSED RULE // O

(_55 F~ 36 t.f 1 V DOCKEiED USNRC Gopy to secy-- , ~ ...'-- [7590-01]

Original sent to tht NUCLEAR REGULATORY COMMISSION *90 AUG 17 p 4 :Q7 Offtee of the Fedesal lleQII:*

for~tatlon 10 CFR PART 11 0 RIN: 3150-AD59 Export of Components for Use in Gaseous Diffusion Enrichment Plants: Correction AGENCY: Nuclear Regulatory Commission.

ACTION: Final rule: Correction.

SUMMARY

In the Federal Register on July 26, 1990 (55 FR 30449), the Nuclear Regulatory Commission issued a final rule which clarifies the coverage of special ly designed or prepared nuclear assemblies and components for use in a gaseous diffusion enrichment plant. As part of the final rule, portions of NRC's export regulations were restructured. However, the amendments necessary to change the references to these restruct ured provisions were inadvertently omitted . As a result, parts of the export l icensing regulations now contain erroneous references. This action is necessary to correct the inconsistent references and reflect the restructured portions of the export regulations.

EFFECTIVE DATE: July 26, 1990.

FOR FURTHER INFORMATION CONTACT: Elaine 0. Hemby, Of fice of Governmental and Public Affairs, U.S. Nuclear Regulatory Commission, Washington, DC 20555, telephone 301-492-0341, or Joanna M. Becker, Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555, telephone 301-492-1740.

1. In §110.1, paragraph {a) is revised to read as follows:

§11

0.1 Purpose and Scope

(a) The regulations in this part prescribe licensing, enforcement, and rulemaking procedures and criteria, under the Atomic Energy Act, for the export of nuclear equipment and material, as set out in §110.8 and §110.9, and the import of nuclear equipment and material , as set out in §ll0.9a.

2. Section 110.5 is revised to read as follows:

§110.5 License requirements.

Except as provided under Subpart B, no person may export any nuclear equipment or material listed in §110.8 and §110.9, or import any

- nuclear equipment or material listed in §110.9a, unless authorized by a general or specific license issued under this part.

3. In §110.6, paragraph (a) is revised to read as follows:

§110.6 Retransfers.

(a) Retransfer of any nuclear equipment or material listed in §110.8 and §110.9, including special nuclear material produced through the 2

use of U.S.-origin source material or special nuclear material, requires authorization by the Department of Energy, unless the export to the new destination is authorized under a specific or general license or an exemption from licensing requirements. Under certain agreements for cooperation, Department of Energy authorization also is required for the retransfer of special nuclear material produced through the use of non-U.S.-supplied nuclear material in U.S.-supplied uti l ization facil ities.

4. In §110.26, paragraphs (a) and (c)(l) are revised to read as follows:

§110.26 Export of nuclear reactor components.

(a) A general license is issued to any person to export any nuclear reactor component listed in Appendix A (5) through (9) for use in any light or heavy water-moderated power or research reactor in any of the following countries:

Canada Phil ippines 2

EURATOM Spain Indonesia Sweden Japan Switzerland South Korea Taiwan 2Belgium, Denmark, France, Greece, Ireland, Italy, Luxembourg, the 3

Netherlands, the United Kingdom and West Germany.

(c) * * *

(1) A description of the components keyed to the categories listed in Appendix A.

5. In §110.42, Footnote 4 is redesignated as Footnote 3 and the text of Footnote 3 is revised to read as follows:

§110.42 Export licensing criteria.

3 Exports of complete nuclear reactors, complete reactor pressure vessels, primary coolant pumps, control rods, and reactor fuel charging and discharging machines are subject to the comprehensive export criteria in §ll0.42(a). A complete nuclear reactor includes those parts and components, as specified in Appendix A, which are within or attached directly to the reactor vessel, which control the level of power in the reactor core or which normally contain or come in direct contact with or control the primary coolant of the reactor. Nuclear reactor parts and components (other than complete pressure vessels, primary coolant pumps, 4

control rods, or fuel charging and discharging machines) when exported separately are subject to the export criteria in §110.42(b).

6. In §110.43, the introductory text of paragraph (a) and paragraphs (b) and (c) are revised to read as follows:

§110.43 Physical security standards *.

(a) Commission determinations on the adequacy of physical security programs in recipient countries for Category 1 quantities of nuclear material (see Appendix E) are based upon the following:

(b) Commission determinations on the adequacy of physical security programs in recipient countries for Category II and III quantities of material (see Appendix E) are based on available relevant information and written assurances from the recipient country or group of countries that physical security measures providing, as a minimum, protection comparable to that set forth in INFCIRC/225 will be maintained.

(c) Commission determi nations on the adequacy of physical security programs in recipient countries for exported facilities are made in accordance with *the categories of material (see Appendix E) in use or in storage at the exported facilities and are based on available relevant information and written assurances from the recipient country or group of 5

countries that physical security measures providing, as a minimum, protection comparable to that set forth in INFCIRC/225 will be maintained.

7. In Appendix A, a new paragraph (9) is added to read as follows :

Appendix A - Illustrative List of Nuclear Reactor Equipment Under NRC Export Licensing Authority (9) Any other components speci ally designed or prepared for use in a nuclear reactor or in any of the components described in this Appendix.

Dated at Rockville, Maryland, this /27 ~ ay o f ¥ - -

• 1990.

For the Nuclear Regulatory Commission 6

.. _*.-;s COPY to See'/** . .- .

Original sent to dthe I Raois~r Office of the Fe era . ~

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for publication U!:> NHC

• U.S. NUCLEAR REGULATORY COMMISSION 10 CFR PART 110 *90 JUL 24 AlO :36 RIN: 3150-AD59 0~' rct GF Si.CK! f:.t, uiJCKi. l ING & '*f t 'IU Export of Components for Use in BRANCh Gaseous Diffusion Enrichment Plants AGENCY: U.S. Nuclear Regulatory Commission.

ACTION: Final rule.

SUMMARY

The U.S. Nuclear Regulatory Commission {NRC) is amending its export licensing regulations to clarify the coverage of specially designed or prepared nuclear assemblies and components for use in gaseous diffusion enrichment plants. This action is necessary to implement the decision of the multilateral Non-Proliferation Treaty Nuclear Exporters Group (Zangger Committee) to add new definitions to its international export control "Trigger List" covering gaseous diffusion enrichment components. The NRC also is r estructuring portions of its regulations in order to present the provision i n a clear manner.

EFFECTIVE DATE: (Upon .publication in the Federal Register)

FOR FURTHER INFORMATION CONTACT: Elaine 0. Hemby, Office of Governmental and Public Affairs, U.S. Nuclear Regulatory Commission, Washington, DC 20555, telephone 301-492-0341, or Joanna M. Becker, Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555, telephone 301-492-1740.

2 SUPPLEMENTARY INFORMATION: During the past several years, the United States 6

and other nuclear supplier governments have engaged in discussions within the f~amework of the International Atomic Energy Agency's (IAEA) Zangger Committee to clarify the coverage of the international nuclear export control "Trigger list" for specially designed or prepared assemblies and components for use in gaseous diffusion enrichment plants. The purpose of the clarification is to improve the administration of export controls over these items. Recently Zangger Committee members have agreed to specify certain additional components jn its control list for these nuclear components.

Currently, all specially designed or prepared gaseous diffusion enrichment assemblies and components are subject in the United States to export licensing by the NRC under its export/import licensing regulations provisions of IO CFR 110.B(b). As a result of the Zangger Committee's action, the Department of

,State, as the responsible U.S. Government agency for undertaking the Zangger 4I t~nnnittee negotiations, has requested the Commission to implement the Zangger Comrnittee 1 s decision by publishing an interpretative rule in the Federal Register listing the new specified assemblies and components in 10 CFR Part 110.

In support of the decision to add new definitions of gaseous diffusion

• enrichment components, the Zangger Colllllittee also prepared an 'introductory note which further clarifies the basis for exercising export controls over the equipment specified. This note reads as follows:

3 Note - Gaseous Diffusion Trigger List In the gaseous diffusion method of uranium isotope separation, the main technological assembly is a special porous gaseous diffusion barrier, heat exchanger for cooling the gas (which is heated by the process of compression),

seal valves and control valves, and pipelines. Inasmuch as gaseous diffusion technology uses uranium hexafluoride (UF 6 ), all equipment, pipeline and instrumentation surfaces (that come in contact with the gas) must be made of materials that remain stable in contact with UF 6

• A gaseous diffusion facility requires a number of these assemblies, so that quantities can provide an important indication of end use.

The auxiliary systems, equipment and components for gaseous diffusion enrichment plants are the systems of plant needed to feed UF 6 to the gaseous

.diffusion assembly to link the individual assemblies to each other to form cascades (or stages) to allow for progressively higher enrichments and to extract the "product" and "tails" UF 6 from the diffusion cascades. Because of the high inertial properties of diffusion cascades, any interruption in their operation, and especially their shut-down, leads to serious consequences.

Therefore, a strict and constant maintenance of vacuum in all technological systems, automatic protection from accidents, and precise automated regulation of the gas flow is of importance in a gaseous diffusion plant. All this leads to a need to equip the plant with a large number of special measuring, regulating, and controlling systems.

4 Normally UF 6 is evaporated from cylinders placed within autoclaves and is distributed in gaseous form to the entry point by way of cascade header pipework. The "product" and "tails" UF 6 gaseous streams flowing from exit points are passed by way of cascade header pipework to either cold traps or to compression stations where the UF 6 gas 1s liqu1f1ed prior to onward transfer into suitable containers for transportation or storage. Because a gaseous diffusion enrichment plant consists of a large number of gaseous diffusion assemblies arranged in cascades, there are many kilometers of cascade header pipework, incorporating thousands of welds with substantial amounts of repetition of layout. The equipment, components and piping systems are fabricated to very high vacuum and cleanliness standards. The items listed below either come into direct contact with the UF 6 process gas or directly control the flow within the cascade. All surfaces which come into contact with the process gas are wholly made of, or lined with, UF 6 resistant materials.

For the purposes of this annex the materials resistant to corrosion by UF 6 include stainless steel, aluminum, aluminum alloys, aluminum oxide, nickel or alloys containing 60 percent or more nickel, and UF 6 -resistant fully fluorinated hydrocarbon polymers.

Waiver of Notice and Comment Because this amendment involves a foreign affairs function of the United States, the notice and co11111ent provisions of the Administrative Procedure Act do not apply pursuant to 5 U.S.C. 553(a)(l). The amendments are effective upon publication in the Federal Register. Good cause exists to dispense with

5 the usu a1 30-day de 1ay in the* effective date because the State Department has requested expeditious action on this amendment in order to meet international commitments.

Environmental Impact: Categorical Exclusion The NRC has determined that this final rule in Part llO is the typ~ of action described as a categorical exclusion under 10 CFR 51.22(c)(l).

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 1980 (44 U.S.C. 3501 et seq.). Existing requirements were approved by the Office of Management and Budget under approval number 3150-0036.

Regulatory Analysis NRC already controls exports of gaseous diffusion enrichment plants and specially designed assemblies and components thereof. The amendments are necessary in order for the nuclear export controls of the United States to be consistent with United States supported international nuclear export control guidelines. The clarification will clearly reflect the nature of the enhanced multilateral export controls of the United States for this category of

6 equipment. No other NRC regulatory actions or alternative actions by other agencies address thi~ matter nor are any alternative courses of action feasible. While ti,e amendments impact all potential exporters of gaseous diffusion enrichment components, they are not expected to result in any increased regulatory burden since they essentially clarify the scope of existing NRC export licensing controls. To date, NRC has neither received an application to export any gaseous enrichment components nor are any such applications expected in the foreseeable future.

Regulatory Flexibility Certification As required by the Regulatory Flexibility Act (5 U.S.C. 605(b)), the Commission certifies that this rule does not have a significant economic impact on a substantial number of small entities. The final rule is an interpretative rule only and, as such, does not, of itself, impose additional

• -0bligations on the public.

Backfit Analysis The NRC has determined that the.*backfit rule, 10 CFR 50.109, does not apply to t~is final rule, and, therefore, a batkfit analysis. is not required for this final rule because these amendments do not involve any provisions which would impose backfits as defined in 10 CFR 50.109(a)(l).

7 List of Subjects in 10 CFR Part 110 Admini~Lrdtive p~actice and procedures, Classified information, Criminal penalty, Export, Import, Incorporation by reference, Intergovernmental relations, Nuclear materials, Nuclear power plants and reactors, Reporting and recordkeeping requirements, Scientific equipment.

8 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:

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, 2t39, 2139a, 2141, 2154-2158, 2201 1 2231-2233, 2237, 2239); sec. 201, 88 Stat. 1242, as amended (42 U.S.C. 5841).

Section 110.l(b)(2) 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. il52) and secs. 54c and 57d., 88 Stat. 473, 475, (42 U.S.C. 2074).

8 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 110.30-110.35 also issued under 5 U.S.C. 553.

For the purposes of sec. 223, 68 Stat. 958,*as amended {42 U.S.C.

2273); secs. 110.20-110.29, 110.50, and 110.120-110.129 also issued under secs. 161 band i, 68 Stat. 948, 949, as amended (42 U.S.C. 2201 (b) and (i)); and secs. 110.7a and 110.53 are also issued under sec. 161(0), 68 Stat. 950, as amended (42 U.S.C. 2201(0)).

2. Section 110.8 is revised to read as follows:

§110.8 List of Nuclear equipment under NRC export licensing authority.

(a) Nuclear reactors.

(b) Plants for the separation of the isotopes of source material, special nuclear material or lithium, including gas centrifuge plants, gaseous diffusion plants, jet nozzle plants, vortex plants, laser isotope separation plants, and chemical separation plants.

(c) Plants for the reprocessing of irradiated nuclear reactor fuel elements.

9 (d) Plants for the fabrication of nuclear reactor fuel elements.

(e) Plants for the production of heavy water, deuterium, and deuterium compounds. (See paragraph (f) of this section.}

(f) Any specially designed or prepared assemblies and components for nuclear reactors (see paragraph (a) of this section} and for the plants listed in paragraphs {b) through (e) of this section. (See Appendices A, B, C, and D to Part 110 for an illustrative listing of specially designed or prepared equipment for a nuclear reactor and gas centrifuge, gaseous diffusion, and reprocessing plants.}

§110.9 {Redesignated)

3. Section 110.9 is redesignated as §110.9a.

4. A new §110.9 is added to read as follows:

§110.9 List of Nuclear Material under NRC export licensing authority.

(a) Special Nuclear Material (b) Source Material

{c) Byproduct Material (d) Deuterium

{e) Nuclear grade graphite

10 Appendix B (Redesignated)

5. Appendix~ is redesignated as Appendix E.

Appendix A (Redesignated)

6. Appendix A is redesignated as Appendix~-

7. A 'new Appendix A is added to .read as follows:

APPENDIX. A - ILLUSTRATIVE LIST OF NUCLEAR REACTOR EQUIPMENT UNDER NRC EXPORT LICENSING AUTHORITY.

Not~ - A nuclear reactor basically includes the items within or atiached_directly to the reactor vessel, the equipment which controls the level of power in the core, and the components which normally contain or come in direct contact with or control the primary coolant.of the reactor core.

(1) Reactor pressure vessels, i.e., metal vessels, as complete units or major shop-fabric~ted parts, specially designed or prepared to contain the core of a nuclear reactor and capable of withstanding the operating pressure of the primary coolant.

(2) On-line (e.g., CANDU) reactor fuel charging and discharging machines, i.e., manipulative equipment specially designed for inserting or removing fuel in an operating nuclear reactor.

11 (3) Reactor control rods, i.e., rods specially designed or prepared for the control of the reaction rate in a nuclear reactor.

{4) Reac~or primary coolant pumps, i.e., pumps specially designed or prepared for circulating the primary ~oolant fn a nuclear reactor.

(5) Reactor pressure tubes, i.e., tubes specially designed or prepared to contain fuel elements and the primary coolant in a nuclear reactor at an. operating pressure in excess of 50 atmospheres.

(6) Zirconium tubes, i.e., zirconium metal and alloys in the form of tubes or assemblies of tubes specially designed or prepared for use in a nuclear reactor.

(7) Reactor internals, e.g., core support structures, control and rod guide tubes, thermal shields, baffles, core grid plates and diffuser plates specially designed or prepared for use in a nuclear reactor.

(8) Reactor control rod drive mechanisms, including detection and measuring equipment to determine flux levels.

8. A new Appendix C is added to read as follows:

APPENDIX C - ILLUSTRATIVE LIST OF GASEOUS DIFFUSION ENRICHMENT PLANT ASSEMBLIES AND COMPONENTS UNDER NRC EXPORT LICENSING AUTHORITY.

Note - In the gaseous diffusion method of uranium isotope separation, the main technological assembly is a special porous gaseous diffusion barrier, heat exchanger for cooling the gas (which is heated by the process of compression), seal valves and control valves, and pipelines.

Inasmuch ~s gaseous diffusion technology uses uranium hexafluoride (UF 6 ),

12 all equipment, pipeline and instrumentation surfaces (that come in contact with the gas) must be made o( materials that remain stable in contact wtth UF 6

• A gaseous dirfusion facility requires a number of these assemblies, so that quantities can providi an important iridication of end use.

The auxiliary systems, equipment and components for gaseous diffusion enrichment plants are the systems of plant needed to feed UF6 to the gaseous diffusion assembly to link the individual assemblies to each other to form cascades (or stages) to allow for progressively higher enrichments and to extract the "product" and "tails" UFi tram the diffusion cascades.

Because of the high inertial properties of diffusion cascades, any interruption in their operation, and especially their shut-down, leads to serious consequences. Therefore, a *strict and constant maintenance of vacuum i~ all technological systems, automatic protection from accidents, and precise automated regulation of the gas flow is of importance in a

• gaseous diffusion plant. All this leads to a need to equip the plant with a large number of special measuring, regulating, and controlling systems.

Normally UF 6 is evaporated from cylinders placed within autoc]aves and is distributed in gaseous, form to the entry po.int by way of cascade header pipework. The "product" and "tails" UF 6 gaseous streams flowing from exit points are passed by way of cascade head_er pipework to either cold traps or to compression stations where the UF6 gas is liquified prior to onward transfer into suitable containers for transportation or storage.

Because a gaseous diffusion enrichment plant consists of a large number of gaseous diffusion assemblies arranged in cascades, there are many

13 kilometers of cascade header pipework, incorporating thousands of welds with substantial amounts of repetition of layout. The equipment, components and piping systems are fabricated to very high vacuum and cleanliness standards.

The items listed below either come into direct contact' w-ith the UF6 process gas or directly control the flow within the cascade. All surfaces which come into contact with the process gas are wholly made of, or lined with; UF 6 resistant materials. For the purposes of this appendix the materials resistant to corrosion by UF 6 include stainless steel, aluminum, aluminum alloys, aluminum oxide, nickel or alloys containing 60 percent or more nickel, and UF6 -resistant fully fluorinated hydrocarbon polymers.

I.* Asse'mb lies and components especially designed or prepared for use in gaseous diffusion enrichment.-

• 1.1 Gaseous Diffusion Barriers.

Especially designed or prepared thin, porous filters, with a pore size of 100-1000 A (angstroms), a thickness of 5 mm or less, and for tubular forms, a diameter of 25 mm or less, made of metallic, polymer or ce.ramic materials resistant to*corrosion by UF6 , and especially prepared compounds or powders for the manufacture of such filters. Such compounds and powders include nickel or alloys containing 60 percent or more nickel, aluminum oxide, or UF6 -

resistant fully fluorinated hydrocarbon polymers having a purity of

14 99.9 percent or more, a particle size less than 10 microns, and a high degree of particle size uniformity, which are especially prepared ~or the manufacture of gaseous diffusion barriers.

1.2 Diffuser Housings.

Especially designed or prepared hermetically sealed cylindrical

• vessels greater than 30 cm in diameter and greater than 90 cm in length, or rectangular vessels of comparable dimensions, which have an inlet connection and two outlet connections all of which are greater than 5 cm in diameter, for containing the gaseous diffusion barrier, made of or lined with UF6 resistant materials and designed for horizontal or vertical installation.

1.3 Compressors and Gas Blowers.

Especially designed or prepared axial, centrifugal, or positive displacement compressors, or gas blowers with a suction volume capacity of I nr/min or more of UF 6 , and with a discharge pressure of up to several hundred kN/m2 {100 PSI), designed for long-term operation in the UF6 environment with or without an electrical motor of appropriate power, as well as separate assemblies of such compressors and gas blowers. These compressors and gas blowers have a pressure ratio between 2/1 and 6/1 and are made of, or lined with, materials resistant to UF6

• 15 1.4 Rotary Shaft Seals.

Especially designed or prepared vacuum seals, with seal feed and seal exhaust connections, for sealing the shaft connecting the compressor or the gas blower rotor with the driver motor so as to ensure a reliable seal against in-leaking of air into the inner chamber of the compressor or gas b1ower which is filled with UF6

• Such seals are normally designed for a buffer gas in-leakage rate Qf less than 1000 cm3/min.

1.5 Heat Exchangers for Cooling UF6

• Especially designed or prepared heat exchangers made of or lined with UF6 resistant materials (except stainless steel) or with copper or any combination of those metals, and intended for a leakage pressure change rate of less than 10 N/m2 (0.0015 PSI) per hour under a pressure, difference of 100 kN/m2 (15 PSI).

2. Auxiliary systems, equipment and components especially designed or prepared for use in gaseous diffusion enrichment.

2.1 Feed Systems/Product and Tails Withdrawal Systems.

Especially designed or prepared process ~ystems, capable of operating at pressures of 300 kN/m2 (45 PSI} or less, including:

16

1. Feed autoclaves (or systems), used for passing UF 6 to the gaseous diffusion cascades;

2. Desublimers (or cold traps) used to remove UF6 from diffusion cascades;

3. Liquefaction stations where UF6 gas from the cascade is

• compressed and cooled to form liquid UF6 ;

4. "Product" or "tails" stations used for transferring UF6 into containers.

2.2 Header Piping Systems.

Especially designed or prepared piping systems and header systems for handling UF6 within the gaseous diffusion cascades. This piping network is normally of the "double" header system with each cell connected to each of the headers.

2.3 Vacuum Systems.

(a} Especially designed or prepared large vacuum manifolds, vacuum headers and vacuum pumps having a suction capacity of 5 m3/min or more.

{b) Vacuum pumps especially designed for service in UF 6 -bearing atmospheres made of, or lined with, aluminum, nickel, or alloys

17 bearing more than 60 percent nickel. These pumps may be either rotary or positive displacement, may have fluor-0carbon seals, and may have spec~al working fluids present.

2.4 Special Shut-Off and Control Valves.

Especially designed or prepared manual or automated shut-off and

• control bellows valves made of UF6 resistant materials with a diameter of 4 cm to 1.5 m for installation in main and auxiliary systems of gaseous diffusion enrichment plants.

2.5 UF6 Mass Spectrometers/Ion Sources.

Especially designed or prepared magnetic or quadruple mass spectrometers capable of taking Ron-line" samples of feed, product or

• tails, from UF 6 gas streams and having all of the following characteristics:

(a} unit resolution for mass greater than 320; (b} ion sources constructed of or lined with nichrome or monel or nickel plated; (c) electron bombardment ionization sources; (d} having a collector system suitable for isotopic analysis.

9. A new Appendix Dis added to read as follows:

18 APPENDIX D - ILLUSTRATIVE LIST OF REPROCESSING PLANT COMPONENTS UNDER NRC EXPORT LICENSING AUTHORITY.

Note - Reprocessing irradiated nuclear fuel separates plutonium and uranium from intensely radioactive fission products and other transuranic elements. Different technical processes can accomplish this separation.

However, over the years Purex has become the most convnonly used and accepted process. Purex involves the dissolution of irradiated nuclear fuel in nitric acid, followed by separation of the uranium, plutonium, and fission products by solvent extraction using a mixture of tributyl phosphate in an organic diluent.

Purex facilities have process functions similar to each other, including: irradiated fuel element chopping, fuel dissolution, solvent extraction, and process liquor storage. There may also be equipment for

• thermal denitration of uranium nitrate, conversion of plutonium nitrate to oxide metal, and treatment of fission product waste liquor to a form suitable for long term storage or disposal. However, the specific type and configuration of the equipment performing these functions may differ between Purex facilities for several reasons, including the type and quantity of irradiated nuclear fuel to be r~processed and the intended disposition of the recovered materials, and the safety and maintenance philosophy incorporated into the design of the facility. A plant of the reprocessing of irradiated fuel elements, includes the equipment and components which normally come in direct contact with and directly control the irradiated fuel and the major nuclear material and fission product

19 processing streams.

(l} Fuel ~lement chopping machines, i.e., remotely operated equipment specially designed or prepared to cut, chop, or shear irradiated nuclear reactor fuel assemblies, bundles, or rods.

(2) Critically safe tanks, i.e., small diameter, annular or slab tanks specially designed or prepared for the dissolution of irradiated

• nuclear reactor fuel.

(3} Solvent extraction equipment.

Especially designed or prepared solvent extractors such as packed or pulse columns, mixer settlers or centrifugal contactors for use in a plant for the reprocessing of irradiated fuel. Because solvent extractors must be resistant to the corrosive effect of nitric acid, they are normally fabricated to extremely high standards (including special welding and inspection and quality assurance and quality control techniques) out of

• low carbon stainless steels, titanium, zirconium or other high quality materials.

{4) Chemical holding or storage vessels.

Especially designed or prepared holding or storage vessels for use in a plant for the reprocessing of irradiated fuel,. Because holding or storage vessels must be resistant to the corrosive effect of nitric acid, they are normally fabricated of materials such as low carbon stainless steels, titanium or zirconium, or other high quality materials. Holding or storage vessels may be designed for remote operation and maintenance and may have the following features for control of nuclear criticality:

(i) Walls or internal structures with a boron equivalent of at least

20 2 percent, or (ii) A maximum diameter of 7 inches (17.78 cm) for cylindrical vessels, or I *

(iii) A maximum width of 3 inches (7.62 cm) for either a slab or annular vessel.

(5) Plutonium nitrate to plutonium oxide conversion systems.

Complete systems especially designed or prepared for. the conversion of

• plutonium nitrate to plutonium oxide, in particular adapted so as to avoid criticality and radiation effects and to minimize toxicity hazards.

(6) Plutonium metal production systems.

Complete systems especially designed or prepared for the production of plutonium metal, in particular adapted so as to avoid criticality and radiation effects and to minimize toxicity hazards.

(7) Process control instrumentation specially designed or prepared for monitoring or controlling the processing of material in a reprocessing

• plant .

Dated at Rockville, Maryland, this 13thday of July, 1990.

For the Nuclear Regulatory Commission.

for Operations.