ML20043B685
| ML20043B685 | |
| Person / Time | |
|---|---|
| Issue date: | 05/24/1990 |
| From: | Peterson M NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA) |
| To: | Thorne C STATE, DEPT. OF, BUREAU OF OCEANS & INTL. ENVIRONMENT |
| References | |
| NUDOCS 9005310127 | |
| Download: ML20043B685 (1) | |
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UNITED STATES
- l' NUCLEAR REGULATORY COMMISSION e
wAsntNotON, D. C. 20565
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g 5tY to m Mr. Carlton E. Thorne, Director
)
Office of Nuclear Export Control
'1 Bureau of Oceans and International Environmental and Scientific Affairs U.S. Department of State Washington, D.C.
20520
Dear Mr. Thorne:
Enclosed are two (2) applications for an export license (XSNM02534), recently received by the Nuclear Regulatory Commission, for the export of high enriched uranium for use as fuel in the HFR Grenoble research reactor in France Before taking action on this request, we would ap)reciate your views, in accordance witn established )rocedures and from tie overall perspective of the Executive Branch, as to whetier the proposed export meet the applicable criteria in the Atomic Energy Act of 1954 as ammded by the Nuclear Non-proliferation Act of 1978.
Sincerely, p
arv n R. Peterson, Assistant Director for International Security, Exports and Materials Safety International Programs Office of Governmental and Public Affairs
Enclosure:
Appl. dtd. 5/15/90 (XSNM02534 France) ccw/
Enclosure:
T. Hart, DOE R. DeLaBarre, DOS l
N. Martin, DOE I
M. Rosenthal, ACDA l
G. Brubaker, D00-G. Kuzmycz, 000 J. Matos, ANL l
9005310127 900524 PDR XPORT XSNM-2534 PDC
- $c[
poRM NRc.t v3. NuCLaA3 c t@pLATORY 00tatWS40N it2.Tsi APPROvt0 DY O Ao to Ce R sie APPL 6 CATION FOR LICENSE TO EXPORT NUCLEAR "8""
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MATERIAL AND EOUIPMENT /seeiterructiDIN Dn Ac.orar/
- t. APPUCANT'$ je. DATE OF APruC ATtDN b. APruC ANT s atplatwas 2.NRC 4 7/Y)d4'72, - N'eNtd8 NDJ May 15, 1990 TNP-512 uSE ~
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- s. APeuCANTs NAME AND ADoRFes l Ris
- s. sureuem s NAME AND'ADoREes hus (cow,en it an, ment a not An oiw et mowseu Transnuclear, Inc.
U.S.D.O.E.
b $Tet t1 ADDMt 68 e.NAME Two Skyline Drive e/o Martin Marietta Fnergy Systems, Inc.
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- c. CIT Y STATE IIP CDDt D. STME ET ADDRES$
Hawthorne NY 10532 3930 State Route 23 South A. Y t LE PHON E NUM9 4 81 (Aree Coor ^"- ^ - - Ea OProJoh/
- t. Clf Y
$ TATE KIP CDDE (914) 347-2345 Ext. 3056 Piketon OH 45661
- 6. FIR $T SHIPMENT
- 6. F 8N AL SHIPME NT 7. APPLICANT *5 CONTRACTUAL 3. PROPOSED LICENSE
- 0. U A. DEPARTMENT Or ENEROY SCHE DULE D SCHEDULED DELIVERY DATE EXPIRAflON DATE CONTM ACT NO. tit Knonni Three years fron ASAP N/A Same as item 5 date of issuance To be determined
- 10. ULTIMATE CONSIGNE E l GW
- 11. ULTIMATE END USE l
yyg lincluor paent or tecihry nome)
Institut Max Von Laue - Paul Langevin Will be used in the RHF Reactor at
- b. sTME t T ADDetss Grenoble Avenut aes Martyrs (See attached end use 'tatement) s
- 6. CIT Y - ST ATL - CDUNT HY 156X-38042 Grenoble-Cedex - France tie. EsT.oATE or rimsf Ust
- 12. SNTE RMEDI ATE CONT 10NE E
[ agg l 13. INTERMEDI ATE END USE l
e NAue COGEMA, Pierrelatte, France For conversion of fuel elements
- b. ST Mit T ADDME&S and and
- c. etT Y - $T ATE - CDUNT RY is.or fabrication of f.u.el elements F
CERCA. Romans. France Est. DATE or riRsT Usr Is attmehort and inal
- 14. INTERMEDIATE CONSIGNEE ISW '
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- 15. INTERMEDIATE END USE l
8.NAME Transnucleaire. L A.
For transport purposes only
- b. STREET ADDPESS 11 bis rue Christophe Colomb
- t. CITY - ST ATE - CDUNT M Y 75008 Paris. France ise. E T.oATE or r RsT ust 16.
1T. DE SCRIPfl0N
- 10. MAX. ELEMENT 19. MAX. 20. MAX 21.
NRC linclude chemice!and physice! term et nucw mowne!. 98.s dolW *efue et USE nuewsr oquipment ene canoonena; 9VElGHT WT. %
SSOTO*E WT.
UNIT 3..
(U)
(U-235)
Uranium, in the form of Uranium Hexafluoride.
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enriched to 93.3 w/o maximum 24.522 93.3 22.879 Kgs.
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- 32. COUNTRY OF ORIGIN.-
LOS M *d 23. COUNTRY OF ORIGlWrtighd 8 E EUO94. COUNTRIES WH6CH ATTACH br1r -
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i SOURCE MATERIAL WHERE ENRICHED OR PRDOUCED GAFEOU ARDS (19 Kneen)
USA EURATOM
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- 2. ADolTIONAL INFORM ATlON /use superen ansetitnecessary/
9' i d W 'S T) n7 aim 3u
~ wet F'eIsret Resuistiona.end that all information in this
- 36. The appiesent earteress that thh appl 6enteen is t lty etch '
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-TQ sepunee m met to the best et hwher k
'7 AuTwoRiztDorr CIAL
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RECEIVED MAY u 4 33 j
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W/REF t DT/MOG/SM/90-603 TRAMBNUCLEAR INC.
l Two Skyline b ive Newthorne RE t NBU ehipment for New Yorit 10831-2120 000EMA/ZLL O/tla als April SS, 90 ETATS-UNES
/
parts, April 26, 1990
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For the attention of Mrs BEVERLY JOSEPHS and Mrs PATTY OUAIN Messieurs, plaasa find herewith enclosed :
I
- checx list and End-Use Statement for 32 kg Uranium
- eheck list and End-Use Statement for 24,4 kg Uranium l
Could you please confirm receipt and date of application.
Fisase note that uranium will be provided by DOE as UF6.
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Yours faithfully l
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'.._.INSTI1Vr IADE 1ANGEVIN cas-EB/od-90-2(aM2.63 !
a DEPARTEMENT REAC'i3UR Indice 1 2 I 21 mars 1990 lIONb -
'c 41 c.V to tGEM IT RY CONCEM se USE stwnseur 6
the undersigned certify that the following maxim m quantities, i.e.
24.40 i 0.10 kg of Uranium 93.15 1 0.15 W o U-235 enriched e
22.73 1 0.10 kg of U-235 content
.in the form of metal i
will'be furnished to us under a short-term rimedhitment Contract with DOE and will be used as fuel in the HPR -
reacter at GRENOBLE.
CER(N RCHANS (FRANCE) shall perform the manufacturing of the fuel elements.
We authorise 00GEMA, V611ty (France), to apply for the U.U.
export license.
Forthe Director of ILL h, h M g[
b Date Signatures :
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BAUER G. COLLET
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rurmST MR USE IN REVIBf OF REQLESTS PCR HELI 10 DEngMDE!: TRONICAL Ato BLXMOWC JUSTIFICP.TICM
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1.
Name of reactor and facility : R6acteur & Haut Flux - High Flux Reactor at'INSTIRTT IAUE - IAICEVIN (ILL).
1 2.
Location : GRhMOBLE (France).
3.
Quantity of Uranium requested (kg U) : 24.40 1 0.10 kg.
4.
Enrichment in the isotope U-235 : 93.15 % i 0.15 %.
5.
Quantity of Uranium requested (kg U-235) : 22.73 i 0.10 kg.
t 6.
Type of fuel element and form of Uranium : M T R, U ALx.
7.
Current reactor power level (m th) : 57 m 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.
l-9d. Average core life : 44 days.
9e. Active core dimensions : diameter : 390 mm, length : 813 m.
(.
- 10. Annut.1 fuel usage (kg U-235) : 6 fuel elements x 8.5 kg =
51 kg.
- 11. Annual spare fuel requirement, if any (kg U-235) : 3 x 8.5 -
l 2L 5 kg.
- 12. Plans to increate, decrease reactor power : None.
- 13. Estimated annusi supply of current fuel request : $1 kg.
L 14.
Required manufacturer's,wqrpi.pg Atock, if any, included in this L
WM 7-I INI request (kg U-235{dudWI 180dX3 a
CERCA : 55.8 kg' LC Zd BL AW O6',/2.
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15.
Fabrication loss, if an 1 kg for 25 kg Uranium,y, included in this request (kg U-235):
1 i
- 16. Names of convertor and fabrication of fuel :
and Convertor : 00GDIA (FRANCE).
- 17. Fabrication atach (France).
i 18a. Quantity of scrap U-235, usable, non-usable (kg U-235) :
Quantitles of scrap U-235 usable are included in manufacturer's working stock (see 14). Quantity of scrap U-235 non-i usable are 2 kg per year.
18.b Quantity of fabricated unitradiated stored fuel available :
None.
18c. Quantity of unitradiated non-fabricated stored fuel (which will be available from fabrication planned or in process) :
At CERCA : 177.3 kg U-235 i
At NUKEM : 10.2 kg U-235 : Pejected platas and compacts.
U aust be recovered by chemical treatment. Date of availability unknown.
18d. Amount of spent fuel stored (kg U-235) :
At ILL 12 x 5.1'kg = 41.2 kg At SRP for reprocessing : 4 x 5.1 kg = 20.4 kg At Enrichment Plant : None.
- 19. Date at which current inventory, including a, b, c, will be expended : june 1991.
y
- 20. Date current requested fuel will be needed at reactor :
August 1991.
l
- 21. Date current requested fuel will be needed by convertor and fabricator :
In fabricator's hand : December 1990.
In convertor's hand : September 1990.
22a. Time taken for shipment from USA to convertor / fabricator :
1 month, 22b.14ad time for ordering in USA : 6 months.
- 23. Date at which current r sted fuel will be expended i.e.,
then a further Hnj s ' 1 l bWineeded at reactor :
~
. December 1991' (rat
- i B0 eW&nber 1990).
- 24. Date at which rep.ctpf M edionverted to 45 % fuel to 20 %
fuel, includingLtiano r fM H WWr licensing procedure :
Unknown (until now no,tpegcp possibility).
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- 25. IListory and daims of previous IEJ supplies by the US :
.s Licence n' Ouantity Arrival date abservaticas (kg U-235) in Europe XSm 02454 29.7 october 89 Fresh Uranium XSm 02315-2 20.7 october 89 Fresh Uranium l
(29,8) and recovered from reprocessing at SRP (40.9)
UE - EU 7 32.5 Unknown us-Doe to 00Ge m before 1978 under contract UE-EU7 XSm 02315 23.2 October 88 Fresh Uranium XSm 02241/1 48.8 October 88 43.2 recovered from reprocessing at SRP
+
5.6 kg Fresh Uranium XSNM 02241 25 04/03/86 Fresh Uranium XSNM 02143 50.5 10/09/85 Recovered from re-processing at SRP XSNM 02012 23.2 11/15/83 Fresh Uranium i
XSNM 1924 26.1 08/20/82 Recovered from re-processing at SRP XSNM 1764 23.2 12/18/81 Fresh Uranium
[
t XSNM 1536 23.2 12/18/81 Fresh Uranium XSNM 1521 30'.6 12/10/81 Recovered from re-processing at SRP XSNM 1362 67.7 10/23/80 secovered from re-processing
- 26. Amount of fuel of U.S.
origin previously consumed during opeation of reactor :
Amount of fuel of U.S. ori in cor,sumed since the first start up in December 1971usi9119
& & ts x 3.4 kg = about 316.2 kg.
.LU0dWI180dX3
- 27. Status of cooperation between reactor operator and Argonne National Labora
,ng grichmentprogram(RERTR):
Close cooperation e.g. :
December 12, 1979 YM (Grenoble by D. STAHL and F.-U.'
(accompanied by MM. CEJA and MNMERN of US DOE).
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May 7, 1980 visit at Argonne by W.. GRILLO and i
JACQUEMAIN (MM. TRAVELLI, STAHL, MMOS, SNEIMNE).
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September 23, 1981 Visit at ILL GRDOBLE by Dr. John EERDIS, State Department.
~ y 4, 1982 Visit at ILL GENOBLE by MM. TRAVELLI and Ma J.E. MMOS with exchange of documents and i
technical data.
s Octobre 23, 1987 Visit at ILL GRENOBLE by M. TRAVELLI, RERTR Program Manager, for discussions about the feasability of using fuels with reduced entichment in the RHP.
- 28. Status of agreement between reactor operator and ANL to reduce enrichment t entil now no formal agreement.
- 29. Status of cooperation between reactor opeator and IAEA reduced enrichment program :
No direct cooperation between ILL and IAEA.
- Homver, connections by the ILL associates : French CEA and German KFK and also by the ILL's fuel elements supplier : CERCA (France).
r E. BAUER m
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.LU0dWI 180d)'3 BE:Zd Bi1W 05 1 u 'd 's 'n 03A1333W
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rEd FORulehe-7 us.neuctsAn As:ULATORY COMMMSDON gpPROVE3 SY C AD No'C5 iso
,4 APPLICAT60N FOR LICENSE TO EXPORT NUCLEAR sm2mRmti MATERIAL AND EOUlPMENT (see tivtruerdons en ne.wse)
- 1. APPLeCANT'$ e DAf t of APPLICATION b. APPLIC ANT'S RtrtRENCE 2.NRC
,a i
ust -
May 15, 1990 TNP-513 ust -
1T O M M Ndbr
- 3. APPLICANTS teAME AND ADDRES$
l Alt
- 4. SUPPLIER'8 NAME AND ADORES $
,M wenw or r
mo u.nr a not Awa er mewwi Transnuclear, Inc.
U.S.D.O.E.
6 STmitT ADDRi&B e.NAME Two Skyline Drive e/o Martin Marietta Energy Systems, Inc.
- c. CIT Y STATE IIP CODE D. STmtET ADDRass Hawthorne NY 10532 3930 State Route 23 South 4.1 L LE P HONt NvWet h (A ree Cocer - Alvumber - f assrosen/
- c. CIT Y STATE ElrCDDE (914) 347-2345 Ext. 3056 Piketon OH 45661
- 6. FIR $1 $N6PMENT
- 6. FINAL GHIPMtNT 7. APPLlCANT'$ CONTRACTUAL 6. PROPOSED LlCENSE
- 9. Li%. DEPARTMENT OF ENERGY SCHE DULE D 3CHEDULED DEllVE RY DAf t EXPIRATION DATE CONTR ACT NO. IIf Knoem>
Three years from ASAP N/A Same as item 5 date of issuanct To be determined to. ULTIMATE CON $iCNEt l GS
.l 11. ULTIMATE IND USE I
e umg (inctuor plant or tecihty neme)
Institut Max Von Laue - Paul Lanoevin Will be used in the RHF Reactor at
- m. Stat ti ADDats:
Grenoble Avenue dog h etvrg (Seeattachedendusestatement)
- 4. Cli v - ST AT E - COU5T RY 156X-38042 Greroble-Cedex - France sie. esi. sate Or riRst uSE it. INTE Ruf oi ATE CONsio=t E I aus
_4is. serishesEo ATE END usE I
- 4. N Ahst COGEMA. Pierrelatte, France For conversion of fuel elements
- b. STRilT ADDMESS l
and and
- s. CIT V - ST ATE - COUNTRY For fabrication of #u.el leme mInchnts.naneAi CERCA. Romans. % nce it T. oAir or riRai tar It.
tse a
- 14. INTERMEDI ATE CONS 4it
-M V0
- 16. INTERMEDIATE END USE
[m o hAME Transnucleaire. S.A.
For transport purposes only
- b. STMt 'T ADDRESS 11 bis rue Christophe Colomb
- t. CIT Y - ST ATE - COUNT RY 75008 Paris, France ise. E T.DATE Or rlRsv use it.
- 17. DESCRIPTION
- 18. MAX ELEMENT 19. MAX. 20. &RX 31.
NC
( luorchem wdp ocol form of nuctew meterw. gm coster retue et WEIGHT WT. %
$50TO*E WT.
UNii Uranium, in the fonn of Uranium Hexafluoride, (U)
(U-235) enriched to 93.3 w/o maximum 32.16 93.3 30.0 Kgs.
fCM? " ^ ' :
7p 20dV0033VS 1.lNl IMqJUt lunjyn
- 22. COUNTRY OF OR?CIN.-
M h'd 23. COUNTRI6F'6tll'GlidifiM " year #d 24. COUNTRIES WHICH ATTACH Rft
- i I
SOURCE MA7ERI AL WHERE ENRICHED OR PRODUCED SAFEOUARDS (if Knoem) 05K:2d El it fK LURATOM
' '. ADDITIONAL INFORMATION (use esperew sheet J/ necessary)
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- 36. The applement eartifies that thh applesetten b propered in Jersnity with Tie of Federal Reeviettens, and thet oli intermetten la thin appliestion is sorrect to the best of hie /her knowledge Q
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I hfficCoordinator AumORl2ED OF FICIAL g
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Two Skyline b ive Newthorne
.4 RE NEU shipment for New York 10832-2120 COGENA/2LL 0/tla $13 April 25, 90 ETATS-UNES I
Paris, April 28, 1990 t
For the attention of Mrs BEVBRLY JOSEPHS end Mrs PATTY 00AIN Massieurs, Please find harewith enclosed :
- check list and End-Vee Statement for 32 kg Uranium
- check liet and End-Use Statement for 24,4-kg Uranium could you please confirm receipt and date of application.
Ple.ase note that uranium will be provided by DOE as UF6.
Yours faithfully
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INSTIRFt IAUE 1ANGEVIN DRe-Eas/od-90-201 1106 DEPARUBENT IWihC'NlUR Indice X 21 mars 1990 TF 40 10 MBOM IT MAY CONCENf 30 USE SUMBENT the undersigned certify that the following maximum quantities, i.e.
32.00 10.10 kg of Uranium 93.15 1 0.15 w/o U-235 enriched 29.81 1 0.10 kg of U-235 content in the form of metal will be furnished to us under a short-tern Fixou-crunnitment Contract with DOE and will be used as fuel in the HrR -
reactor at GN! NOBLE.
CERCA/ ROMANS (FRANCE) shall perfona the manufacturing of the fuel elements.
i He authorise coGEMA, v611ry (France), to apply for the U.S.
export license.
Forthe Director of ILL f f &hh Date s Signatures :
bf
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E. BAUER G. COLLET h
- -0BVnD33YS 7.1NI 180dWI180dX3 BE:Zd 9L Ani 06,
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CEECKLIST FOR USE IN REVIEW OF REQUESTS FOR BRU l
TO DETERMINE TEC NIF.AL AND ECONOMIC JUSTIFICATION J
t 1.
Name of reactor and facility : R6actcar & Haut Flux - High riux i
Reactor at.INSTIT.UT LAUE - LAi!GEVIN (ILL).
2.
Location : GRENOBLE (France).
3.
Quantity of Uranium requested (kg U) : 32.00 1 0.10 is:.
4.
Enrichment in the isotope U-235 : 93,15 % 1 0.15 %.
5.
Quantity of Uranium requested (kg U-235) 29.81 1 0.10 kg.
6.
Type of fuel element and form of Uranium : MTR, U ALx.
7.
Current reactor power level (MW th) : 57 MW th, 8.
Duty factor, average burn-up : Duty factor : 74 %
Average burn-up 40 %.
i 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 : diameter : 390 mm, lencth : 813 mm.
10.
Annual fuel usage (kg U-235) 6 fuel elemerna x 8.5 kg =
51 kg.
l 11.
Annual spare fuel requirement, if any (kg U-235) : 3 x 8.5 =
l 25.5 kg.
12.
Plans to increase, decrease reactor power
- None.
13.
Estimated annual supply of current fuel request
- 51 kg.
14.
F.equired manufacturer's working stock, if any, included in this l
request (kg U-235) :
508VnD33YS Ic1NI CERCA : 55.8 kg 180dWI180dX3
./2.
80 Zd Bl Adi 06
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itcp4303 15.
Febrication loss, if any, included in this request (kg U-235):
1 kg for 25 kg Uranium.
16.
Names of convertor and fabrication of fuel and convertor : COGEKA (FRANCE).
17.
Fabrication CERCA (France).
18a. Quantity of scrap U-235, usable, non-usable (kg U-235)
Quantities of scrap U-235 usable are included in manufacturer's working stock (see 14). Quantity of scrap U-235 non-usable are 2 kg per year.
18.b Quantity of fabricated unitradiated stored foal available None.
18c. Quantity of unitradiated non-fabricated stored fuel (which will be available from fabrication planned or in process)
At CERCA : 177.3 kg U-235 At NUKEM :
10.2 kg U-235 : Rejected plates and compacts.
U aust be recovered by chemical treatment. Date of availability unknown.
18d. Amount of spent fuel stored (kg U-235)
At ILL : 12 x 5.1 kg = 61.2 kg At SRP for reprocessing : 4 x 5.1 kg = 20.4 kg At Enrichment Plant : None.
19.
Date ht which current inventory, including a,
b, c,
will be expended : June 1991.
20.
Date current requested fuel will be needed at reactor :
February 1992.
21.
Date current requested fuel will be needed by convertor and fabricator :
In fabricator's hand : December 1990.
In convertor's ' hand : September 1990.
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 will be expended i.e.,
when a further HEU supply will be needed at reactor :
June 1992 (Fabrication : December 1990).
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 US :
Licence n' Quantity Arrival date observations (kg U-235)_
in Europe XSNM 02454 29.7 October 89 Fresh Uranium XSNM 02315-2 20.7 october 89 Fresh Uranium (29.8) and recovered from reprocessing at SRP (40.9)
UE - EU 7 32.5 Unknown US-DOE to COGEMA before 1978 under contract UE-EU7 XSNM 02315 23.2 October 88 Fresh Uranium XSNM 02241/1 48.8 October 88 43.2 recovered from reprocessing at SRP
+
5.6 kg Presh Uranium XSNM 02241 25 04/03/86 rresh Uranium XSNM 02143 50.5 10/09/85 Recovered from re-processing at SRP XSNM 02012 23.2 11/15/83 Fresh Urar.ium l
.XSNM 1924 26.1 08/20/82 Recovered from re-i processing at SRP XSNM 1764-23.2 12/18/82 Fresh Uranium XSNM 1536 23.2 12/18/81 Fresh Uranium XSNM 1521 30.6 12/10/81 Recovered from're-
~
processing at SRP XSNM 1362 67.7 10/23/80 Recovered from re-processing
- 26. Amount of fuel of U.S.
origin previously consumed during opeation of reactor :
Amount of fuel of U.S.
origin consumed since the first start up in December 1971 : 93 fuel elements x 3.4 kg = about 316.2 kg.
00
- 27. Status of coope' a I
r reactor operator and Argonne National Laborator e
nrichment program (RERTR) :
Close cooperatio$[ eld, g[13. g December 12, 1979 Visit at ILL (Grenoble by D. STAHL and J.L.TSidQGROVE (accompanied by MM. CEJA and MA 6 $f US DOE).
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,May 7, 1980 Visit at Argonne by MM. GRILLO and JACQUEMAIN (MM. TRAVELLI, STAHL, MATOS, SNELGROVE).
September 23, 1981 Visit at ILL GRENOBLE by Dr. John DARDIS, State Department.
May 4, 1982 Visit at ILL GENOBLE by MM. TRAVELLI and l
J.E.
MATOS with exchange of documents and technical data.
Octobre 23, 1987 Visit at ILL GRENOBLE by M.
TRAVELLI, RERTR Program Manager, for discussions about the feasability of using fuels with reduced enrichment in the RHF.
- 28. Status of agreement between reactor operator and ANL to reduce enrichment :
Until now no focaal agreement.
- 29. Status of cooperation between reactor opeator and IAEA reduced enrichment program :
No direct cooperation between ILL and IAEA.
- However, connections by the ILL associates : French CEA and German RFK and also by the ILL's fuel elements supplier
- CERCA (France),
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Xf'JmoM34 0004303 May 15, 1990 United States Nuclear Regulatory Comission One White Flint North Mail Stop 3-H-5 Washington, DC 20555
.l Attn: Mrs. Betty Wright Re:
Export License Application for ILL-Grenoble f
TNY Ref: TNP 512 and TNP 513
Dear Betty:
l Enclosed are two export license applications and their corresponding end use statements and reactor checklists, for your handling of the following:
TNP 512:
22.879 Kgs U235 contained in 24.522 Kgs Uranium, in the form of Uranium Hexafluoride, enriched to 93.3 w/o maximum 1
and l
'TNP 513:
30.0 Kgs U235 contained in 32.16 Kgs Uranium, in the form of Uranium Hexafluoride, enriched to 93.3 w/o maximum l.
The above figures include tolerences.
Please call if you have any questions.
Very truly'yours, TRA INC.\\
'N P ricia B. Quain Traffic Coordinator D/C l NI JudWI.LU0dX3 PBQ' Enclosures.
g gd g g (g, T "d'.i'S'O 03Al333W TWO SKYUNE DRIVE
- HAWTHORNE, NEW YORK 10632 2120 TT.LEPHONE: W14447 2345
- FAX: 9144472346
- TELEX: 8818082 a >< - /-,,
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