ML20247E779
| ML20247E779 | |
| Person / Time | |
|---|---|
| Issue date: | 07/20/1989 |
| From: | Peterson M NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA) |
| To: | Thorne C STATE, DEPT. OF, BUREAU OF OCEANS & INTL. ENVIRONMENT |
| References | |
| NUDOCS 8907260311 | |
| Download: ML20247E779 (1) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
<p h ASHINGTON, D. C. 20555
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.0012 o Ig Mr. Carlton E. Thorne, Director '
Office of Nuclear Export and Import Contr'o1 1
Bureau of Oceans and International d
Environmental and Scientific Affairs l
U.:S. Department of State Washington, D.C.
20520
Dear Mr.-Thorne:
Enclosed please' find a letter from Nissho Iwai American Corporation requesting an amendment to export license XSNM01779 to increase the quantity of uranium authorized for export for use-in the JRR-2 Research Reactor in Japan by an additional 25.07 kilograms of uranium and 11.18 kilograms of uranium-235 (45%
enriched).
Rather than amend export license XSNM01779, we have assigned a new license number XSNM02468.
Before taking action on this request, weould appreciate your views, in accordance with established procedures ai' from the overall perspective of the Executive Branch, as to whether the p m osed export meets the applicable criteria in the Atomic Energy Act of 1954., amended by the Nuclear Non-Proliferation Act of 1978.
Sincerely, e
Marvin R. Peterson, Assistant Director for International Security, Exports, and Materials Safety International Programs Office of Governmental and Public Affairs
Enclosure:
Ltr. dtd 6/29/89 l
(XSNM02468 - Japan) cc wf
Enclosure:
-T. Hart, DOE R. DeLaBarre, DOS 4
N. Martin, DOE l
M. Rosenthal, ACDA i
G. Brubaker, 000 G. Kuzmycz, DOC J. Matos, ANL i
s907260311. e90720 PDR XPORl PDC XSNM-2468
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GNT-89-020
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' NW twei Amencan i CuTuali0n
)(SA//hdcN June 29, 1989 1211 Aenue of the Amencas New Myk NY.10036
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h Mr. R..Neal Moore, I
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Direct 'Numbe' Sr. Licensing Officer A
212-704-6768 Export / Import and International Safeguard U.S.
Nuclear Regulatory Commission Telex Numbers.
Office of International Programs HCA 232641/ 233567 Washington, DC 20555
-ITT 420405-TWj[gc252
Subject:
APPLICATION OF E/L AMENDMENTS No. 5 WUo 126110 /12329 LICENSE NO. XSNM01779 Brancn othces
Dear Mr. Moore:
Archorage Atbnta In regard to t he Export License, this is to request Amendment No. 5 per below:
Chicago cteveland E/L No.:
XSNM01779 Detrat estm CURRENT AMENDMENT REMARKS Z,n^"if' 1Amtes!mseLb 41
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Portland (Kgs)
(Kgs)
(Kgs) san o, ego San Francssco yranium 76.28 101.35 y
seane increased stlouis by 25.07
_ ha"$ ton oc Uranium-235 34.63 45.81 ty 9
increased by 11.18 A check list filled out by JAERI is attached for your reference.
Thank you for your cooperation, in advance.
Very truly yours, NISSHO IWAI AMERICAN CORPORATION s,'
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Yoshimura Q
Manager-Nuclear Energy & Equipment
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Gas & Nuclear Dept.
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.%f cc: NIC TK ATOMB-2 GNT FILE i
Attach.
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(JRR-2 M. ~ Mr fuels)
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Date: June, 1989 1
CHECKLIST FOR USE IN REVIEW OF REQUESTS FOR HEU TO DETERMINE l
TECHNICAL AND ECONOMIC JUSTIFICATION (for amendment to the application) i 1.
Name of reactor and facility Japan Research Reactor No. 2 (JRR-2) i 1
2.
Location Tokai-sura, Naka gun, Ibaraki-Ken, Japan 3.
Quantity of uranium requested (increment)25.07 (total)101.35 (kgsU) 4.
Enrichment in the isotope 45%
U-235 5.
Quantity of uranium requested (increment) 11.18 (total)45.81 (kgsU-235) 6.
Type of fuel element and form Cylindrical type, UAix-Al dispersion i
of uranium 7.
Current reactor power level 10 (MWth) 8.
Duty factor, average burnup 0.395, 25%
9a. Current core loading (1)MEU: 4.2kg as of Jan. 13, 1989 (kgsU-235)
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9b. Amount of fuel per element (2)MEUD.220
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M, 9c. Number of elements in core 24 2.
g
.2 9d. Average core life approx. 6 months 7
a (1) HEU: 93% enriched uranium (2) MEU: 45% enriched uranium
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(JRR-2 M. ~ M7 fuels)
Date:' June, 1989 y,.
9e. Active core dimensions 152 cmd x 60 coh.
p (mm) k 9f. Neutron flux Steady State Average Thermal:
8 x 10" n/cer see b
.10.'Annualfeulusage(kgsU-235) approx. 2.1
- 11. Annual' spare fuel requirement, Not applicable if any (kgs U-235)
- 12. Plans to increase, decrease None reactor power level
'13.
Estimated annual. supply of 48 elements current fuel request
- 14. Required manufacture's working Not applicable stock, if any, included in this request (kgsU-235)
- 15. Fabrication loss, if any, 0.62 kg included in this tequest (kgsU-235)
- 16. Names of converter and fabricator DOE, U.S.A. and CERCA, France of fuel i
- 17. Location 00E:
CERCA: 9-11 Rue George Cedex, France l
- 18. Inventory I
IEa. Quantity of scrap U-235, Not applicable
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useable non-useable (kgsU-235)
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(JRR-2 M. ~Mr fuels) j.
Date: June,1989 18b. Quantity of fabricated unirradiated HEU: 1.17 kg as of Jan. 13, 1989 storedfuelavailable(kgsU-235)
MEU: 9.21 kg as of Jan. 13, 1989 18c. Quantity of unirradiated non-fabricated None stored fuel '(which will be available from-fabrication planned or in process)
(kgsU-235) 18d. Amount of spent fuel stored HEU: 3.73 kg as of Jan.:13,1989 (kgsU-235)
MEU: 1.63 kg an of Jan. 13, 1989
- 19. Date at which current inventory, Aug. 1989 including a.b.c will be expended
- 20. Date at which current requested fuel Oct. 1991 will be needed at reactor
- 21. Date at which current requested fuel Fabricator: Mar. 1990 will be needed by convertor /
fabricator 22a. Time taken for shipment from 3-4 weeks per shipment USA tp convertor / fabricator 22b. Lead time for ordering in USA Approx. 13 months
- 23. Date at which current requested Feb. 1993 fuel will be expended i.e., when a further HEU supply will be needed at reactor i
- 24. Dates at which reactor could To 45% fuel: Nov. 1987 be converted to 45% fuel; to 20% fuel, including time required for licensing procedure
Sep. 28, 1983 L- ___ _
- - _ - _ = _ _ _ _
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(JRR-2 M. ~ M7 fuels)
Date: June, 1989-
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- 26. Amount of fuel of U.S.-origin 31.258 kg U-235 previously consumed during as of Jan. 13, 1989 j
operation of reactor
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- 27. Status of cooperation between reactor operator and Argonne National Laboratory in reduced enrichment program (RERTR); and n-,
- 28. Status of agreement between reactor operator and ANL to reduce enrichment JAERI and ANL embarked on a joint study program, "ANL-JAERI JOINT STUDY ON THE USE OF REDUCED ENRICHMENT FUELS ON THE JAERI RESEARCH REACTORS", in January 1980 to assess the feasibility of converting the JAERI reactors to use of fuels with reduced uranium enrichment, both with currently qualified fuels and with fuels that are expected to become qualified in the near future. The Joint Study consists of three phases: Phase A, Phase B and Phase C.
Phase A, the first stage of the Joint Study was through in March,1981. The main subjects of the Phase A were calculational studies on the use of fuels with less than 20% en richment and 45% enrichment, and preparations for critical experiments and burn-up test with 45% and 20% enrichment. Under the Joint Study, ANL and JAERI agreed to accept experts to exchange information and to observe experiments on the RERTR Program.
Phase 8, following the end of Phase A, terminated in March,1984, where some tasks originally scheduled for Phase B were transferred to Phase C.
The Phase B included the hydraulic tests at JAERI, the critical experiments in the JMTRC (45%), the burn-up tests and further feasibility and analytical studies.
Phase C, now underway, is characterized by the various experiments of uranium silicide LEU fuels. The full-core demonstration test (45%) in JMTR took place in July,1986.
Since the beginning of Joint Study, exchange of personnel of JAERI and ANL has been made, when expedient under the circumstances, for calculation works, observation of the related tests and discussion. Such activities have helped expedite the Program.
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(JRR-2 M. ~Mr fuels)
Date: June, 1989 e
- 29. Status of cooperation between reactor operator and IAEA reduced enrichment program JAERI has been cooperation greatly with the IAEA activities on reduced enrichment program by means of contributing to the "RESEARCH REACTOR CORE CONVERSION FROM THE USE OF HIGHLY ENRICHED URANIUM TO THE USE OF LOW ENRICHED URANIUM FUELS GUIDEBOOK (IAEA, 1980)"," Guide book on Safety and Licensing issues Related to Research Reactor Core Conversion to Use LEU instead of HEU" and " Guidebook on the Core Conversion of Heavy Water Research Reactor". In October,1984 JAERI sponsored "the International Meeting on Reduced Enrichment for research and. Test Reactors", where outline and present status of our program to reduced enrichment were given and discussion among participants was performed. JAERI will continue to cooperate with IAEA in these activities, including dispatch of its personnel.
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