ML20133M878
| ML20133M878 | |
| Person / Time | |
|---|---|
| Issue date: | 08/07/1985 |
| From: | Moore R NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP) |
| To: | Busick E STATE, DEPT. OF, BUREAU OF OCEANS & INTL. ENVIRONMENT |
| References | |
| NUDOCS 8508130299 | |
| Download: ML20133M878 (1) | |
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T NG 7 1985 Mrs. Eleanor Busick, Acting Director Office of Nuclear Export / Import Control Bureau of Oceans and International Environmental & Scientific Affairs U.S. Department of State, Room 4327A Washington, D.C.
20520
Dear Mrs. Busick:
Enclosed please find an application from Transnuclear. Inc. for a license to export HEU to France for use in the High Flux Reactor at Grenoble.
Before taking action on this license application, we would appreciate your views, in accordance with established procedures, as to whether the proposed export meets the applicable criteria in the Atomic Energy Act, as amended by the Nuclear Non-Proliferation Act of 1978.
Inasmuch as the original EURATOM analysis was dated December 8,1978, we would appreciate receiving an updated analysis.
Sincerely.
I Original Signed by R. Neal Koote R. Neal Moore, Acting Assistant Director Export / Import and International Safeguards Office of International Programs 1
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Enclosure:
Appl. dtd. 8/2/85,(XSNM02241)
I cc w/ enclosure:
DISTRIBUTION:
Mr. Ted Hart, DOE IP r/f Ms. Nataly Martin, DOE IPEI r/f Mr. Robi DeLaBarre, DOS EDO r/f Mr. Gerald Oplinger, D0D WJDircks, E00 Mr. Gary Bray, ACDA pDR JBecker, ELD LWirfs, NMSS DSayles, NMSS GProco, OR00 Qsponn, M 8508130299 850807 JRussell, OR00 PDR XPORT j
XSNM-2241 PDR BStout, MM o,nc,p
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c-co Mr. Neal Moore Nuclear Regulatory Q2mtissicn Office of International Programs mil Stop 414-A East-West / South 'Itw.r Building 4340 East-West Highway Bethesda, Maryland 20815 i
Re: Export License Application
'IN Ref: 'INi-463
Dear Mr. MJore:
Enclosed is an export application for your handling on the follcw2ng:
25.0 Kgs U-235, contained in 26.9 Kgs Uranium, enriched to 93.30 w/o max 2mtrn i
'Ihank you for your cooperation.
Very truly yours,
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M1 nager - Washingtcri Operaticns i
Encl: as stated abcne OC:
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FALLS CHURCH. VIRGINf A 22041 3976 ONE SKYLINE PLACE
- 5205 LEESBURG PIKE CABLE TRANSNUC FSCH
- TELEX 64493 TELEPHONE 703-820-2450
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U.S. NUCLE AO CEEULATOGY COMMISSION APPREVED CY CAD COMM NRC.7 APPLICATION FOR LICENSE TO EXPORT NUCLEAR
$hn lia MATERIAL AND EQUIPMENT (see trutructions On Rewar/ ML{ j f/ddf 7,DeCKETNO.8 7
- 1. APPLDCANTS
- e. DATE OF APPUCATION D. APPLIC ANT'S NEFERENCE 2.NRC pse.
2 s-6 Afdip?
USE r
USE 2 AtyTust 1985
'HE-433 l ras A SUPPLIER'S NAME AND ADDRESS Ris
- 3. APPLICANT *E NAME AND ADDRESS rComoke of anotant u not aeoter er meannt) 1CAME U.S.D.O.E.
C/O Transnuclear, Inc.
a NAME x GTAEE T ADDRESS Gxdvear Atcmic Coro.
One North Brm&av STATE 21P CODE D. STREET ADDRESS
- c. CITY White Plains NY 10601 Ibute One STATE ZIP CODE 4 CITY
- e. T E LE PHONE NUM BE R (Ares Gods - 4.,ew - EsameJon/
- cPIIASE CAIL 703-820-2450 UKN ISSUANCE Piketon m
45661
- 8. PRDPOSED LICENSE
- 9. US. DEPARTMENT OF ENERGY
- 4. FIN AL SHIPMENT 7. APPLICANT *S CONTRACTUAL SCHEDULED SCHEDULED DELIVERY DATE EXPIR ATION D ATE CONTR ACT NO. (if Knoans S. FI, ST SHIPMENT 3 years frun January 3986 N/A Same as Itm 5 date of issuance Unk nen I
bM ' '."Ir.12*1
- 11. ULTIMATE END USE
- 10. ULTIMATE CONSIGNEE (Incivor plant or facolity namel Will be used in the High Flux Reactor at
& NAMEInstitut Max Von Laue.-Paul largevin D. CTREE T ADDRESS Grenoble (see attached E.U.S.)
Avenue des Furtyrs
& CITY - sT ATE - COUNTRY 156 X - 38042 Grenoble-Cedex-France tie. EST. DATE OF FIRST USE
- 12. INTEEMEDI ATE CONSIGNEE bM
~. M b Witj 13. INTERMEDIATE END USE
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n NAME For conversion (NUKEM) and fabricatico NUKEM -Hanau-F.R.G.
(CERCA and NUKEM) of fuel o, eTuEET ADDRESS CERCA - R2rans - France
- s. CITY - ST ATE - COUNTRY 13e EST. DATE OF FIRST USE
- 13. INTEEMEDI ATE CONSIGNEE l.45 177W '
8." ",15. INTERMEDIATE END USE
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For transport purposes only
& NAMETransnuklear GmbH D. STRE ET ADDRESS D-6450 Hanau II
- e. CITY - ST ATE - COUNTRY
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15a. EST. DATE OF FIRST USE
- 18. MAX. ELEMENT 19. MAX. 20. MAX 21.
- 17. DESCRIPTION lineIvor chemico!and physical form of nuciev matenal; pre dottar enive oI wEICHT WT. %
1SOTOPE WT.
UNIT 16.
NRC USE nuckar equipment and components)
Uraniun in the foun of uraniun hexafluoride, (U)
(U-235) g.
r 26.9 93.30 25.0 Kgs I u
[~ h, enriched to 93.30 w/o rnax2 nun
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- 22. COUNTRY OF ORIGIN.-
E '1 U I 23. COUNTRY OF ORIGINrSNM l
-l 24. COUNTRIES WHICH ATTACH l
SAFEGUARDS ///Known)
WHERE ENRICHED OR PRODUCED SOURCE MATERI AL EURATUi
- see below U.S.A.
- 25. ADDITION AL INFORM ATION (usa separere sheet if,-.eary)*At this time it is unknown whether there will be ho w ver Transnuclear will advise NBC if such is the case.
ri ormat in this e of Fyderal Regulations.WM ', N } }y-G L 9) f the mety w6th T[rtle 10f 2s. Two ep,i.e.ni eart6fi.e in.i this applicet6on is prepared in conf
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f appincetion is correct to the best of his/her knowledee.
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dQ ger - Washincton Operations
- 27. AUTHORIZED OFFICIAL y
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Grenob!e. le July 10, 1985 v3enre eu etre retemnce a rapoeier MJ/ek-ES/256 i
END USE STATEMENT We certify that the following quantities based on contra:tual figures, and including DOE allowabic tolerances on Uraniu weight and enrichtent:
Kg U Kg U 235 Maxin:ur enrich =ent 26,9 25 93,30 %
which application for export licence will be applied by Transnuklear G bH will be used in the High Flux Reactor located at GRENOBLE.
For the Director of the INSTITUT LAUE - LANGEVIN ee '
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INST 4 TUT Grenoble July 10, 1985 wam vos Laue P AUL LANGCVIN e
CHECKLIST FOR USE IN REVIEW OF REQUESTS FOR HEU TO DETERMINE TECHNICAL AND ECONOMIC JUSTIFICATION 1.
Name of reactor and f acilit;- : REacteut & Haut Flux (High Flux Reactor) at INSTITUT LAUE-LANGEVIN (ILL)
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2.
Location : CRENOBLE (France) 3.
Quantity of Uranium requested (kg U)
- 26,9 kg 4.
Enrichment in the isotope U-235 : 93 I 5.
Quantity of uranium requested (kg U-235)
- 25 kg 6.
Type of fuel element and fcrm of uraniu: : M T R, U A1x 7.
Current reactor power level (MW th) : 57 MW th 8.
Duty factor, average burn-up : Duty factor : 74 % - Average burn-up : 40 %
9a. Current core loading (kg U-235) : 8.5 kg 9b. Amount of fuel per element (kg U-235) : 8.5 kg 9c. Number of elements in core : 1 9d. Average core life : 44 days 9e. Active core dimensions : dia=eter : 390 m= - Length : 813 mm 9f. Neutron flux : 1.2 x 1015 n/cm2/s 10.
Annual fuel useage (kg U-235) : 6 fuel elements x 8.5 kg = 51 kg 11.
Annuel spare fuel requirement, if any (kg U-235) : 2 x 8.5 - 17 kg 12.
Plans to increase, decrease reactor power level : None 13.
Estimated annual supply of current fuel request : 51 kg 14.
Required manufactur's working stock, if any, included in this request (kg U-235) :
CERCA :
30 kg NUKEM :
15 kg
.../...
a 15.
Fabrication loss, if any, included in this request (kg U-235) : I kg (for 25 kg)
- 16. and 17.
Names of convertor and fabrication of fuel : Convertor : NLTEM (Germany)
Fabricator of fuel : NUKEM (Germany) and CERCA (France) 18a. Quantity of scrap U-235, useable, non-useabic (kg U-235) :
Quantities of scrap U-235 useable are included in manufacture's working stock (see 14). Quantity of scrap U-235 non-useable are 2 kg per year.
I6b. Quantity of fabricated unirradiated stored fuel available:
I fuel element (8.5 kg) at CERCA 4 fuel elements (34 kg) at ILL 18c.
Quantity of unirradiated non-fabricated stored fuel (which will be available from fabrication planned or in process) :
at CERCA - 55 kg at NUKEM - 25,4 kg 18d. Amount of spent fuel stored (kg U-235): - at ILL 2 x 5.1 kg = 10.2 kg
- at SPR for reprocessing:
6 x 5.1 kg - 30.6 kg
- at Portsmouth enrichment plant:
50,5 kg 19.
Date at which current inventory, including a, b, c, will be expended:
March 1987 20.
Date current requested fuel vill be needed at reactor:
Beginning of 1987 21.
Date current requested fuel will be needed by convertor and fabricator:
in fabricator's hand: April 1986 in convertor's hand : February 1986 22a. Time taken for shipment from USA to convertor / fabricator : 1 month 22b. Lead time for ordering in USA : 6 months 23.
Date at which current requested fuel vill be expended i.e., when a further HEU supply will be needed at reactor : Mid of 1987 (Fabrication : Mid of 1986).
24.
Date at which reactor could be converted to 45% fuel; to 20% fuel, including time required for licensing procedure:
Unknown (until now no technical possibility)
.../...
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25.
History and dates of previous HEU supplies by the U.S.
Licence No.
Quantity Arrival date Observations (kg U-235) in Europe XSNM 02143 50,5 Estimated Recovered from reprocessing Sept. 85 at SRP XSNM 02012 23,2 11/15/83 Fresh Uranium XSR4 1924 26,1 08/20/82 Recovered from reproces-sing at SRT XSNM 1764 23,2 12/18/81 Fresh Uranium XSNM 1536 23,2 12/18/81 Fresh Uranium XSNM 1521 30,6 12/10/81 Recovered from reproces-sing at SRP XSNM 1362 67,7 10/23/80 Recovered from reproces-sing 26.
Amount of fuel of U.S. origin previously consumed during operation or reactor:
Amount of fuel of U.S. origin consumed since the first start up in December 1971: 68 fuel elements x 3.4 kg = about 231 kg.
27.
Status of cooperation between reactor operator and Argonne National Laboratory in reduced enrichment program (RERTR) :
Close cooperation, e.g.
- December 12, 1979 : Visit at ILL Grenoble by D. STAHL and J.L. SNELGROVE (accompanied by MM. CEJA and MATTERN of U.S. DOE).
- May 7, 1980 :
Visit at ARGONNE by MM. GRILLO and JACQUEMAIN (MM. TRAVELLI, STAHL, MATIOS, SNELGROVE)
- September 23, 1981: Visit at ILL Grenoble by Dr. Jchn DARDIS, State Department
- May 4, 1982 : Visit at ILL Grenoble by MM. TRAVELLI and J.E. MATTOS, with exchange of documents and technical data.
.../...
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I 28.
Status of agreement between reactor operator and ANL to reduce enrichment 1
Until now no formal agreement.
29.
Status of cooperation between reactor operator and IAEA reduced enrichment program:
No direct cooperation between ILL and IAEA. However, connections by the ILL associates : French CEA and German KfK and also by the ILL's fuel elements suppliers : CERCA (Fr) and NUKEM (Gerenay).
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