ML20196A617
| ML20196A617 | |
| Person / Time | |
|---|---|
| Issue date: | 06/24/1988 |
| From: | Peterson M NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA) |
| To: | Thorne C STATE, DEPT. OF, BUREAU OF OCEANS & INTL. ENVIRONMENT |
| References | |
| NUDOCS 8806300074 | |
| Download: ML20196A617 (1) | |
Text
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UNITED STATES j,
["
g NUCLEAR REGULATORY COMMISSION ij WASHINGTON, D. C. 20555 1/
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1 JUN 2 41988 i
j Mr. Carlton E. Thorne, Director Office of Nuclear Export and Import Control i
Bureau of Oceans and International Environmental and Scientific Affairs U.S. Department of State Washington, D.C.
20520
Dear Mr. Thorne:
Enclosed please find a request from Transnuclear, Inc. for the export of 12.6 kilograms of high enriched uranium (93.15%) to West Gennany for use in BER-II Research Reactor.
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 of 195t as amended by the Nuclear Nonproliferation Act of 1978.
Sincerely,
/n n D-J v.yu m Marvin R. Peterson, Assistant Director for International Security Office of Governmental and Public 4
Affairs
Enclosure:
Appi dtd 6/20/88 (XSNM02388-Argentina) j cc w/
Enclosure:
Mr. Ted Hart, DOE Mr. Robin DeLaBarre, DOS Ms. Nataly Martin, DOE j
Mr. Gary Bray, ACDA Mr. Gerald Oplinger, D00 8806300074 880624 PDR XPORT XSNM-2388 DCD
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rDIM NRC 7 U.S. NUCLEAR REGULATORY COMMISSION 112 78)
APPROVED BY C AO toCrAvio APPLICATION FOR LICENSE TO EXPORT NUCLEAR e.1eo22s(Roser) 1 MATERIAL AND EQUIPMENT (seeInsteverions on neversel
- 1. APPLIC ANT *S le. D ATE OF APPLiC ATION
- b. APPLIC ANT'S REFERENCE 2. NRC l a. DOCKET NO.'.
t4 LICLNSE No.'
USE
/ /00 ffef e/
)(SN/Td C3 &
wne nn. 14RR mm-4 9 4 USE
- 3. APPLIC ANT'S NAME AND ADDRESS l RlS
- 4. SUPPLIER'S NAME AND ADDRESS l Rit (Complete if soolocant is not svoolse of marevist) tran=nucinar. Inc.
- b. STREET ADDRESS a.NAME Two Skyline Drive ffA.D.O.E.
c/o
- c. CITY STATE 2IP CODE
- b. STREET ACORESS Hawthorne N.Y.
10532 Martin Marietta Enercy Systems, Inc.
- o. T E LE PHON E N V M 9 E R thed Code - humbW - b renson)
- c. CITY Y-12 Plant, ORNL STATE zie CooE
- Please call 914-347-2345 upon issuance **
cav utann T.N.
37831 S. FIRST SHIPMENT
- 6. FINAL SHIPMENT '7 APPLICANT'S CONTR ACTUA L 8. PROPOSED LICENSE
- 9. US. DEPARTMENT OF ENERGY SCHE DULE D SCHEDULED DELIVERY DATE EXPIRATION DATE CONTR ACT NO. fitKnow/
ASAP after 3 years from license issued N/A Same as item 5 a2+n nf innuance Unknown
- 10. ULTIMATE CONSIGNEE l Alt
- 11. ULTIMATE END USE l-e.NAME II""#* O'*"' 0' Y*'E'Y "***I Berliner Experimentier Reaktor (BER-II)
Will be used as fuel for the BER-II
- b. STREET AcoRESS at the Hahn-Meitner-Institut reactor in Berlin, West Germany r:14 n n i ck o r Mtr. 100
- c. CI TY - S T A TE - COU N T R Y (See attached End Use Statement) n innn unr14n
't 4 Unet
- 12. INTERMEDIATE CONSIGNEE
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norm nv 11a. EST. DATE OF FIRST USE
' ' l R it'
. 13. INTERMEDIATE END USE l
a.NAME CERCA
- b. STREET ADDRESS For Conversion and manufacturing (CERCA)
- c. CIT Y - ST ATE - COUNTR y (See attached End Us'e Statement)
Deann. France 13a. EST. DATE OF FIRST USE
- 14. INTERMEDI ATE CONSIGNEE l Alt b'; 15. INTER *dEDI ATE END USE l
4 s NAME Transnucleaine, S.A.
Intermediate for transport purposes
- b. STREET ADORESS only 11_ h4e vno
(*h r i n t ophe Colomb
- c. CITY - ST ATE - COUNTR Y 16.
~ par 4e R.
France 15s. EST. DATE OF FIRST USE u
- 17. DESCRIPTION
- 18. MAX. ELEMENT 19. MAX. 2o. M AX 21.
NRC (inctuce chemical and physicso form o1 nucirat morerrat;gm cortar,sive of USE nucere rovoomen t one component,)
M M
iSOTDPE W UW j
(U)
(U235) b
\\
F Urapium in the form of metal,
.. 2
~E enhiChed to 93.15 w/o maximum 12.6 93.15 11.737 Kgs.
h.-
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. b
.b.
C m
3 22. COUNTRY OF ORIGIN.-
l.hte' 23. COUNTRY OF ORIGIN.-SNM l 'h > ' 24. COUNTRIES WHICH ATTACH l 'o W
E N
- See below Will advise when known
)
- 25. ADDITION A L INFORM ATION (uss sepaare a%eet,f necesasy)
(
- At this time it is unknown whether there will be any Australian or Canadian origin material, however, Transnuclear, Inc. will advise NRC is such is the case, s
- 26. Th. ppl.eeni c.,iit that the oi.e.i
- 6. P,
,.e in cone,m,iy.,ih T 6 10. Coo. of F.o.i R ui.i
.no th..si inv.,m.i.n.n in..
.ppucai..n es coer.ci to th. b.si f hdh., k nown. deen p
. g ls 27. AUTHORIZED OFFICIAL Patricia B.{OYaing
- b. TITLE
.. SIGN ATUR E Traffic Coordinator
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TRANSNUCLEAR,INC.
June 20, 1988 U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 3-H-5 Washington, D.C.
20555 Attn Mrs. Betty Wright Re Export License Application TN Ref NUK-484
Dear Betty:
Enclosed are an export application and corresponding end use statement with checklist for your handling:
11.737 Kgs. Uranium-235, contained in 12.6 Kgs. Uranium, enriched to 93.15 w/o maximum.
At the present time, the country of origin of material is unknown as this material will be used against credits from Savannah River Plant. We will advise you once known.
Thank you for your cooperation.
Nst truly y rs, l
D.
dlLCS N
Patricia B. Quain Traffic Coordinator Q
h PBQ y
Enclosures s
cct C. Flingou/ Euratom TWO SKYLINE DRIVE
- HAWTHORNE, NEW YORK 10532 2120 TELEPHONE: 914 347 2345
- FAX: 914 347 2346
- TELEX: 6818082 Q Q? //, / A Lll a
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M NMKCM Wh NUKEM GmbH Zweigniederlassung Alzenau IndustriestraSe 13 PottfAch till 4elefax - o pagww D 8755 Altenau Telefon(06023)300 0 Transnuclear Inc.
Telex 416S233 nuka d Telefat (06023) 500214 Havthorne Teletex 602391 nuka d a t t. n. : Mrs. P. Quain 15.06.1988 Rn/the Application for Exportlicense for HMI We have received an order from EMI Berlin for the supply of 12 kg HEU fror. US DOE.
Please find attached copy of the corresponding End USE Statement and the Checklist. Ve request you to apply for the necessary exportlicense.
Please note that the matter is rather urgent, since we intend a combined shipment of several quantities probably in auto:r..
We hope that for the time being a copy of the documents is sufficient for applying the license.
Originals are in mail to us from HMI. We will sent them it.T.ediately after receipt by courict, if you believe this necessary.
Thanks for your efforte.
.N 2 m A
j Best regards
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Vortuender des Adsatwates: Gen Bedar J
-aln-Ve':ner-nsti:u :
3 erin Gm a-Itm!
Bere'ch Kernchemie und Reaktor HaSn Mr.ne les11st Pcst'e:5 39 0178. 010N De# 39. Gir. eke Stre% $00 Te?. f4 8 M 91 Tla.185 763 evzowm.N. wum law IWw W5t N t033 ao% m:
om e ra e02 15.6.1988 To b'HOM IT MAY CONCERN END USE STATEMENT The undersigned certify that the following material, i.e.
12.000 kg of uranium in the form of metal nom. 93.15 w/o U-235 nom. 11.178 kg U-235 will be f urnished to us under a Short-Term Fixed-Commitment Contract with DOE and will be used for the BER-2 Reactor at Berlin.
CERCA, Romans, France, shall perform manufacturing of the fuel
- elements, h*c authori::e Transnuclear, Inc., Falls Church, Va. to apply for the US export license.
Dates AY.G.fC Signatures P -
Dr.A.Axmann Dr.
ttes elm Hahn-Meitner-Institut Berlin GmbH f.5
!3 3
9
Ch,cklist for Use in Review of R'qu9sts for HEU to D7tormine Technical and Economic Justification i.
Namo of reactor and facility Berliner Experimentier Reaktor (BER II) at the Hahn-Meitner-Institut 2.
Location Glienicker Str. 100, D 1000 Berlin 39 The location is in the vostern part of the city and within the American Sector 3.
Quantity of uranium requested (kg U) 12 kg U 4.
Enrichment in the isotope U-235 93 %
5.
Quantity of uranium requested (kg U-235) 11 kg U-235 6.
Type of fuel elemont and form of uranium MTR fuel oloment with U-Alx i
7.
Current reactor power level (MW th)
S MWth up to now, but at the moment upgrading of the system to go to 10 MWth 8.
Duty factor, averago burnup We had operated the reactor in the past at about 4000 h/a with a 5 shifts operating group. Now wo have increased the operating group to 6 shifts in order to achieve 5-6000 h/a 9a.
Current core leading (kg U-335)
The core is presently unloaded because of total reconstruc-tion 9b.
Amount of fuel por element (kg U-235) 0.180 kg U-235 per standard element 9c.
Number of elements in core See appendix for standard and compact core 9d.
Average core life Standard core 600 mwd, compact core 330 mwd cycle length between reloading actions 9e.
Active core dimensions Grid plato dimension: 6x7 positions, core loading: see fi-gures in tho' appendix 9f.
Neutrop flux
~ 10-A4 sec-1 cm-2
-s-e e 10.
Annual fuel usage (kg U-225) 5500 h/a = 2300 mwd, 2300 mwd x 1.24 = 2852 g U-235 40% burn-up for compact coro and 180 g U-235 per element 2852/0.4 180 = 40 elements annual fuel usage 7130 g U-235 11, Annual spare fuel raquirement, if any (kg U-235)
Not more than requested in no. 5 because of conversion to LEU material 12.
Plans to increase, decrease reactor power level The BER II is under upgrading for an increase from 5 to "10 MW, upgrading is close to an end, the licence is expected in Sept. 1988 13.
Estimated annual supply of current fuel request The conversion to LEU is intended as soon as possible 14.
Required manuf acture's working stock, if any, included in this request (kg U-235) 3 6, i.e. 0.33 kg U-235 15.
Fabriction loss, if any, included in this request (kg U-235) 2%, i.e. 0.22 kg U-235 16.
Names of converter and fabricator of fuel CERCA 17.
Location France, Romans sur Isbre 18.
Inventory see appendix 18a. Quantity of scrap u-235, uscable, non-useable (kg U-235) none 10b. Quantity of fabricated unirradiated stored fuel available i
(kg U-235) 7.677 kg U-235 18c. Quantity of unirradiated non-fabricated stored fuel (which will be available from fabrication planned or in process)
(kg U-2351 nono 1
18d. Amount of spent fuel stored (kg U-235) i 4.668 kg U-235 19.
Date at which current inventory, including a, b, c will be
~~
expended March 1990 l
)
w s
20.
Dato curront rcquast d futl will be n:Odtd at rccctor March 1990 21.
Data current requested fucl Will bo nooded by convertor and' fabricator April 1989 (at CERCA/ Romans in form of Metall) 22a. Time taken for shipment from USA to"convertor / fabricator Shipping arrangements can last up to 6 months 22b. Lead time for ordering in USA 7 months 23.
Date at which current requested fuel will be expended 1.e.,
when a further HEU supply will be needed at reactor Beyond 1991 if licensing procedure for conversion is unduoly delayed 24.
Dates at which reactor could be converted to 45% fuel; to 20% fuel, including time required required for licensing procedure We will apply for conversion to 20% fuel after rocciving the licence for 10 MW operation that means not before Sept. 1980.
An optimistic guess for the licensing procedure is not less than 2 years, adding
~
22a. =
1 year 22b.
=
fabrication 20% fuel elemento are not availablo before Sept.1991 25.
.91 story and dates of previous HEU supplies by the U.S.
1971 6.8 kg of U 90 % from USAEC 1971 30.5 kg of U 44 % from USAEC 1974 5.0 kg of U 90 % from Reactorcentrum Nederlande (surplus) 1977 5.8 kg of U 93 % from Goodyear 1979 7.1 kg of U 93 % from UNL 1981 6.8 kg of U 93 % from ERDA 26.
Amount of fuel of U.S.-origin previously consumed during operation of reactor 78 MTR elements shipped for reprocessing.; initial amount of U-233: 12.702 kg; delivered for reprocessing: G.214 kg.
The 44 % material was used for UZrH test elements. They were not suitable for power operation and sent immediately after test for reprocessing.
27.
Status of cooperation between reactor operator and Argonne National Labgfatory in reduced enrichment program (RERTR) i EMI had agreed to introduce 20% material and to start with two test elements. These two elements containing each 737 g
')
i
n-o) s U-238 and 180 g U-235 w3re fabricct:d cnd shipp:d to thc l
station in 1981. The chemical form of the uranium is U 0.
38 But our licensing authority did not allow to insert the LEU elements into the core, because there was no reprocesing as-surance from the USA. Since August 1985 the BER II is out of operation for reconstruction.
28.
Status of agreement between reactor"operator and ANL to re-duce enrichment HMI intended to convert to LEU in the form U Si2 3
29.
Status of agreement between reactor operator and IAEA to re-duced enrichment program i
There is no cooperation with the IAEA, because our reactor is not in operation. For the future we are open for exchange i
of experience and data.
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Berin Gma-Bere'ch Kernchem'e und Reaktor m!
sawv.we.t>cin.cn sa ei n. cacco s.n n a9. o>ewr sumoo v rAz a ce r,.i ta in re3 Cav OmasuggM evze um,sa: /: ten wwze May 25, 1988 TO WHOM IT MAY CONCERN Arguments for HEU material supply in the near future The BER II is the research reactor of the Hahn-Meitner-Institut.
This laboratory is one of the 13 National Laboratories of the German Federal Republic. Its legal status is that of a limited liability company. The financing is shared between the Federal Republic and the State of Berlin in a ratio of 9 to 1, respectively.
The location of the Hahn-Meitner-Institut is in the American Sector of Berlin (West). Licensing authority is "Sonator filr Wirtschaft und Arbeit", a Department of the State Government. All linconoing documents have to be approved by the Allied Kom:nandan-tura and the U.S.
authorities responsible for the American Sector i
of Berlin (West).
On August 15, 1985 the liconco for an important upgrading program of the BER II was issued by the Senat of Berlin. The aim of this program is to transform the BER II to a medium flux beam tube reactor. The power of the reactor will be increased from 5 to 10 MW.
The licence to operato at 10 MW is expected around October 1988.
In addition, we applied for a licence to install and run a Cold Ncutron Source. We hope to receive this licence together with that for operating the reactor. Meanwhile most of the rebuilding is finished and tests of components and systems are started.
1
/.../
Hahn Menner-institut BedinGrnbH 3
3,n se, m.n-n May 25,1988 l
~
In 1979, at the time when we started the licence procedure of our l
uograding program, the research program on LEU-fuel-elements was still in progres and it was not possible to specify LEU fuel elements. Therefore we were obliged to apply for an operating li-cence for the upgraded reactor with HEU fuel. Meanwhile our con-tractor Interatom has been asked to study the conversion of the BER 11 core from HEU to LEU material. Because our licensing autho-rity is in the moment preparing the licence for 10 MW operation, it'will not accept any other application which touch this licence.
That means for the conversion from HEU to LEU we have to start a new licensing procedure and a.) application can be filed not beforo the licence to 10 MW operation is cleared by the authorities; this will not happen before September 1988. Taking into account two years for licencing procedure, which seems to be realistic under the aspect that we have to switch to a new fuel manufacturer (Cerca) and an additional year for fuel fabrication and procure-ment, LEU fuel elements could be available to us in the second part of 1991.
In the appendix the total inventory of our nuclear material as of today is given. Tnere are 36 standard elements each 180g U-235 93%, 9 control elements each U-235 93% unirradiated and 36 par-tially burned-up fuel elements in storage position. Assuming an average burn-up of 40%, which might be possibl-by running the compact core (see appendix), 2931 mwd can be generated with the HEU material. According to a duty cycle of 5-6000 h/a, 2931 mwd are equivalent to about 15 months of operation. Starting in October 1988 and adding 3 months for zero power measurements, we run out of the HEU material at the end of March 1990. Because there is more then one year of 10 MW operation not covered by fuel, we need the corresponding amount for that time in HEU mate-rial. Our calculation shows that we need additional 60 HEU MTR standard elements each with 180g U-235 (total anount of likg U-233, to cover the 18 months of operation after our existing element have been used up.
The SER II operation with HEU material should continue until the date of approval to convert to LEU, otherwise the experiments on the moat sophisticated research reactor in Germany had to be in-terrupted fornearly two years. At this time ten beam tubes and eight experiments on neutron guides fed by the cold neutron source will be used by more than 60 scientists. Besides, two irradiation dr. vi c e s, one running at liquid nitrogen atmosphere and the other at high temperature of 1000' C, could not be used. The close co-operation with inrarnational institutions and with a number of Co-reign guests would be distorted, other research programs. e.g.
medical aspects of rare elemencs in the human body, could not be continued.
We are not interesied to use HFU material beyond 1991.
In case the licence procedure would progress f aster than expected, making additional HEU material unnecessary, we would cayyel our request.
Eerlin, May 25, 1988 g
77.M. dt'esheim Dr.
A. Axmann e
1 APPENDIX CHECK LIST '
e Inventory HEU.$'.ateriali number m(kg U-235]
EJ C 1,). mikg U-2'35). EU(%)
36 unirradiated stored fuel 6.480 0
" 3.888 40 sted:rd cite.ont 9
unirradiated stored fuel 1.197 0
0.718 40 control element
~
38 irradiated stored fuel 4.068 32 4.104 40 studed ele:nant 83 12.345 8.,710 present after 2931 VAd Nyerageburn-upof404forall83 elements will be obtained after 2931 VAd operation s') 6.:rn-up 4
0 e
e
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4
APPE3iDIX CHECK LIST 1
2 3
4 5
6 A
0 13.0 25.2 0
s 1
8 0
! 35.9 ; 32.8 40.8 14.3 0
l, c
17.7 30.3 40.6 37.4 13.7 l
l 25.0 jl 39.2 i 43.2 46.9 15.2 13.9 0
1 l
i E
18.4 33.6 44.3 43.8 26.2 y
n
>r F
14.0 0I 30.0 38.3 0 (
0 i
N 25.7 :
~ N G
0 13.3 0
Fuele!.cment -
Refleetor-element I
Control-Irradiation
,c l
element device Standard HEU Core Fuel Burn-up at BOL in percent Loss
avewou caen uur n
1 2
3 4
'5 6
1 i
i A
13.2 25.1 36.1 13.1
/
B 13.5 l 46.4 44.0 51.9 27.2 13.5 i
I u
c 29.5 41.8 52.3 48.9 26.2 o
36.9 50.7, 55.3 58.6 30.0 l 27.4-E 30.2 45.6.
55.9 54.0 37.9 F
26.0 l 14.2 ' 42.6 49.2 14.9 14.2 l
1.
1 l
c 13.2 25.6 37.0 13.7 Standard HEU Core EOL 600hW
APPENDIX CilECK LIST l
1 2
3 4
5 6
A 10.5 0.
O.
/'N lO.
h Of; 10. 5 10.5 B
0.
I C
10.5 21.0 21.0 D
21.0 21.0 21.0 21.0 E
10.5 21.0 21.0 /
F;
\\
F o,
10,3 l.}.
o,
)0,S 1
\\
/
G 0.
10.5 0.
/
Co.Tpact HEU Core BOL k
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hahn-meitner-institut herLin attn. cr. nuchholz Ialsoaocok heu inventory bal.ance we confirm that we have in our odot of fabrication material inventory of annrox. 100 o of uranium of hmi.
j however the inventory w'.LL be eliminated beCause of the out-E standinq deduction of fabrication Losses for the Last oroduction of 2C fuel ei.e-ents and o control elements, the official inventory nalance wiLL he sent as soon as
.ssible.
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