ML20247D774
| ML20247D774 | |
| 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 8907250302 | |
| Download: ML20247D774 (1) | |
Text
.
jo UNITED STATES g
E NUCLEAR REGULATORY COMMISSION o
5 l;E WASHINGTON, D. C. 20555 j[
JUL 2 01999 Mr. Carlton E. Thorne, Director l
Office of Nuclear Export and Import Control Bureau of Oceans and International Environmental and Scientific Affairs U. S. Department of State Washingtcn, D.C.
20520
Dear Mr. Thorne:
Enclosed please find a letter.from Nissho Iwai American Corporation requesting Amendment No. 07 to export license application XSNM01778 to increase the quantity of uranium authorized for export for use in the JMTR Research' Reactor in Japan by an additional'85.56 kilog?ams of uranium and 38.50 kilograms of.
uranium-235(45% enriched).
Rather than amend export licenst X$NM01778, we have assigned a new license number XSNM02467.
Before taking action on this request, we would appreciate ycur views, in accordance with established procedures and from the'overall perspective of the Executive Branch, as.to whether the proposed export meets the' applicable criteria in the Atomic Energy Act of 1954 as amended by the Nuclear Non,
Proliferation Act of 1978.
Sincerely,
/7 Marvin, feter's'an, Assistant' Director for International Security, Exports, and Materials Safety International Programs
' Office of Governmental and~Public Affairs
Enclosure:
I Ltr. dtd 6/29/89 (XSNM02467 - Japan) cc w/
Enclosure:
T. Hart, DOE R. DeLaBarre, DOS N. Martin, DOE M. Rosenthal, ACDA G. Brubaker, 00D G. Kuzmycz, DOC J. Matos, ANL 8907250302 890720-PDR XPORT XSNM-1778 PDC j
{i L
r * ',i g g e t t *" O I
i g
-9 GNT-89-021 j
1 Nesholwai -
U ".., i n r 6
{
AmericaD June 29, 1989 j
X S N /h o d ' M 7 i 1211 Aanue of the Amencas New Wrk, N.Y 10036 '
Mr.
R. Nea( Moore,
/ / o o W'75 212/704 200 ~
Sr. Licensing Officer
. Export / Import and International Safeguard IMTR t
g,,, y.
U.S. Nuclear Regulatory Commission 2'i2-704-6768 fp
- f Office of International Programs Washington, DC 20555 Telex Numbers.
HCA 232641/ 233567
Subject:
APPLICATION OF E/L AMENDMENTS NO. 7 i
hYS816252 LICENSE NO., XSNM01778 WUI 620 012 WUo 126110 /12329
Dear Mr. Noore:
Branch Offices In regard to the E'xport License, this.is to request
)
1
$ age Amendment No. 7 per below:
senevue 1
soston E/L No.: XSNM01778 1
CNcago.
)
Cleveland CURRENT AMENDMENT REMARKS fil IHandmsnt_ h,62
___.Ng;,Z, Los Anges (Kgs)
(Kgs)
(Kgs)
Nashytk Portkind sance9o Uranium 412.41 497.97
-ty San Francisco sa increased 3
b y 8 'i. 5 6 Tamm Uranium-235 184.14 224.64 ty j
wasNngm oc increased 1
by 38.50
~
J 1
~.
A check list filled out by JAERI is attached for your reference.
Than.k you for your cooperation, in advance.
Very truly yours, 1
NISSHO IWAI AMERICAN CORPORATION
/
o f f ~_ _ _ _ __ _. MD - _
"p T.
Yoshimura E
Manager-Nuclear _ Energy & Equipment g
i Gas & Nuclear' Dept.
2, i
cc:
NIC TK ATOMB-2 GNT FILE Attach.
[ m ~ mn fh -
(JMTR Mac ~M3s fuels)
Date: June, 1989 CHECKLIST FOR USE IN REVIEW OF REQUESTS FOR HEU TO DETERMINE TECHNICAL AND ECONOMIC JUSTIFICATION (for amendment to the application) 1.
Name of reactor and facility Japan Meterials Testing Reactor (JMTR) 2.
Location Garai-machi, Higashiibaraki gun, Ibaraki-ken, Japan 3.
Quantity of uranium requested (increment)85.56 (total) 497.97 1
(kgsU) 4.
Enrichment in the isotope 45%
U-235 j
l 5.
Quantity of uranium requested (increment) 38.50 (total) 224.64 i
(kgsU-235) i 6.
Type of fuel element and form Modified ETR type
)
of uranium a
4 7.
Current reactor power level (MW th) 50 8.
Duty factor 0.33 I
Average burnup 25%
Sa. Current cere loading 7.849 as of 1 June, 1989 (kgsU-235) e3 l
c
-m 9b. Amount of fuel per element Standard Fuel:0.310 (kgsU-235)
Fuel Fo110wer:0.205
^
E h
m Sc. Number of elements in core 27 hk 9d. Average core life 5 weeks
l (JMTR M2..~ Mrs fuels)
Date: June, 1989 9e. Active core dimensions (mm) 540 x 386 x 750 9f. Neutron flux 4 x 10" n/ car See (Averaged., in fuel region)
- 10. Annual fuel usage (kgs U-235)
Approx. 7(fuel consumed)
- 11. Annual spare fuel requirement, Not applicable if any (kgs U-235)
I
- 12. Plans to increase, decrease None reactor power level
- 13. Estimated annual supply of Standard Fuel 100 ct.rrent fuel request Fuel Follower 25
- 14. Required manufacture's working Not applicable z
stock, if any, included in this request (kgs U-235)
I
- 15. Fabrication less, if any, (increment)1.54 l
included in this request (kgsU-235) i
- 16. Names of converter and fabricator CERCA, France of fuel 1
1
- 17. Location DOE:
CERCA: 9-11 Rue Georges Enesco 94008
.x Creteil Cedex, France
- 18. Inventory 18a. Quantity of scrap U-235, Not applicable l
useable non-useable l
(kgs U-235) 1
-g-
( M R Mr. - Mas fuels)
Date: June, 1989-( .
i 186. Quantity of fabricated unirradiated 4.337 as-of 1 June, 1989 j
stored fuel available (kgs U-235) 18c. Quantity of unirradiated non-febricated 0
stored fuel (which will be available from I
i fabrication planned or in process)
(kgsU-235) l j
q l
18d. Amount of ' spent fuel stored 66.735 as of 1 June, 1989
)
(kgsU-235)
- 19. Date at which current inventory,
.Nov. 1989 including a.b.c will be expended
- 20. Date at which current requested fuel May. 1991 will be needed at reactor
- 21. Date at which current requested fuel Fabricator: July, 1990 will be needed by convertor /
I fabricator 22a. Time taken for shipment from Fabricator USA tp convertor / fabricator 3-4 weeks per shipment 22b. Lead time for ordering in USA Approx. 8 months
- 23. Date at which current requested May, 1991 fuel will be expended i.e.,
when a further HEU supply will be needed at reactor
- 24. Dates at which reactor could To 45% fuel: July, 1986 be converted to 45% fuel; to To 20% fuel: approx, 1993
'20% fuel, including time required for licensing procedure
- 25. History and dates of previous Since 1%8, the initial criticality i
HEU supplies by the U.S.
440.6 kg U-235 as of 31 March, 1987
.- 3 --
a (JMTR M2 ~ M2 fuels)
Date: June, 1989 i
- 26. Amount of fuel of U.S.-origin -
45.221 kg of U-235 as of June, 1989 s
previously consemed during
'l operation of reactor 1
- 27. Status of cooperation between reactor operater and Argonne National Laboratory in reducedenrichmentprogras(RERTR);and
- 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% enrichment and 45% enrichment, anc 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.
l Phase B, 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 tes.ts and further feasibility and analytical studies.
I The Phase C, now underway, is characterized by the various experiments of uranium silicide LEU fuels. With the full-core demonstration test (45%) in July,1986, JMTR is now in operation with use of fuels of 45% enrichment.
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.
s.
(JMTR M24 ~ M2 s fuel s)
Date: June, 1989 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 COWERSION 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 'reditted enrichment were given and discussion among participants' was performed.
JAERI will continue to cooperate with IAEA in these activities, including dispatch of its personnel.
An expert opf JAERI has been taking part in. Steering Committee of RERTR Program since 1988.
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