ML20151W601
| ML20151W601 | |
| Person / Time | |
|---|---|
| Site: | (XSNM-2382) |
| Issue date: | 04/27/1988 |
| From: | Peterson M NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA) |
| To: | Rooney J ENERGY, DEPT. OF |
| References | |
| NUDOCS 8805030437 | |
| Download: ML20151W601 (1) | |
Text
c5 m[g UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 5
ij WASHINGTON, D. C. 20555
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APR 2 71988 Mr. John Rooney, Director Technical Policy Division Office of Classification and Technology Policy U.S. Department of Energy Washington, D.C.
20585
Dear Mr. Roone):
Enclosed is an application for an export license received recently by the NRC for low-enriched uranium for post-irradiation examination in Japan. A letter of assurance is required that the material will be subject to all of the terms and conditions of an agreement for cooperation.
Your assistance in obtaining the necessary assurance letter will be appreciated.
Sincerely,
[]
p Marvin Ri.Tekerson,WAssistant Director i
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w v7 for Internation61 Security Office of Governmental and Public Affairs
Enclosure:
Appl dtd 4/25/88 (XSNM02382-Japan) 8805030437 880427 PDR XPORT XSNM-2382 PDR
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NRC FORM 7 U.S. NUCLE AR l'EGULATORY COMMISSION APPROVED BY OM8 k,
11241) 3154 0027 10 cFR 110 APPLICATION FOR LICENSE TO EXPORT NUCLEAR EXPIRES 12 31 87 4.
MATERI AL AND EQUIPMENT /seeInstructions on Reverse 1
- 1. APPLIC ANT'S la. D ATE OF APPLIC ATION
- b. APP LIC ANT'S REFERENCE 2.NRC
- a. DOC KET NO.
- b. LICENSE NO.
uSE ll6ifL} g yty Q Afjpg O M M 4.g6.ff uSE
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- 3. APPLICgNT'S NAME AND ADDRESS ^
l RIS
- 4. SUPPLIER'S N AME AND ADDRESS lM 4
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(Complete if apphcant is not suppher of trateriali mum K h Lasur -0 W Ch. M GcI0ezi1L FH&Tk t L. On -
b.' STR E E T ADDR E SS a.NAME
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- c. CITY STATE ZIP CODE
- b. STREET ADDRESS
$$A 55
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- o. T E LE P HON E NUM 8 E R (Area Code - humber - Estensaon/
- c. CITY STATE ZIP CODE Yol " $W" [8,2$
$61WlhAl 0s 0h
- 5. FIRST SHIPMENT
- 6. FINAL NIPMENT 7. APPLICANT'S CONTRACTUAL 8. PROPOSED LICENSE
- 9. US. DEPARTMENT OF ENERGY SCHEDULED SCHE DUL E D DELIVERY DATE EXPIRATION DATE CONTR ACT NO. (If Known/
c AJ E BOA ?
Sh *PM4fLn AS//f Y$,),'Ye
- 10. ULTIMATE CONSIGNEE I RES
- 11. ULTIMATE END USE l# _
(Include plant or facshty name)
/A idC$ 6AE El &dE HDNE fZc Rin~:i t tt TG b G ^ n 'n !N A T d b STft E E T A Dp b u I
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- c. CITY - ST ATE - COUNTR Y g
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MNI IPi hg /7Mg 11a. EST. DATE OF FIRST USE 12.#1NTERMEDI ATE CONSIGNEE l R18
- 13. INTERMEDIATE END USE
['
s NAME
- b. STREET ADDRESS N
- c. CIT Y - ST ATE - COU -T P Y w
13a EST. DATE OF FIRST USE
- 14. INTERMEDIATE CONSIGNEE l RT
- 15. INTERMEDI ATE END USE l
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e.NAME J
- b. STRE ET ADDRESS
- c. CITY - ST ATE - COUNT R Y 15a. EST. DATE OF FIRST USE 16.
- 17. DESCRIPTION
- 18. MAX ELEMENT 19. MAX. 20. MAX 21.
NRC (Incluce chemocaland ohystal form or nacier maternal;gwe dottu va!ve of WElGHT WT.%
ISOTOPE WT.
UNIT USE nucinar equipment and cmonents)
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- 22. COUNTRY OF ORIGIN.-
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- 23. COUNTRY OF ORIGINr$NM l
' 24. COUNTRlliS WHICH ATTACH l^
SOURCE MATERI AL WHERE ENRICHED OR PRODUCED SAFEGUARDS (if Knoan) usR u5A N'M a W '
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- 25. ADDITIONAL INFORMATION /use separate sheetif necessary/
E5 4 h6 Of5kT fuh [tll b 5 ~ AlfD /2FREGMM W
- 26. The applicant certifies that this apphcation is prepared m conf ormrty with Title 10, Code of Federal Regulations, and that all mformatson in th s application es correct to the best of hit' hee knowledge.
AUTHOR 12E D O F FICI AL
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40V'gi2V~PJ03 Apr 21.88 12 i 35 P.02 1
s CENERAL ELECTRIC COMPANY AND NIPPON NUCLEAR MJEL DEVEl4PMENT COMPANY, LTD.
BOILING WATER REACTOR (BVR) FUEL DEVE14PMENT JOINT PROGRAM hackground General Electric Company (GE) concluded an agreement With the Nippon Nuclear Fuel Development Company (NTD) in 1966 for a joint study of the response of zirconju:n barrier fuel to power cycling conditions. The program plan included the refabrication of four irradiated GE BWR fuel segments into eight short rodlets.
The rodlets were sent to Norway in 1987 for testing in the reactor at Halden.
After irradiation tests at Halden are complete, all rodlets will be returned to CE's Vallecitoa Nuclear Center (VNC), Pleasanton, California. Three of the rodlets will then be sent to NFD in Japan.
In accordance with the program plan, these rodlets will be subjacted to post. irradiation examination at NFD as part of the irradiation test evaluation.
Exoort to Jaoan GE is planning to apply for an export license in the near future to allow export of the rodlets to Japan.
Source Fuel The rodlets were refabricated from fuel rod segments taken from Barrier Lead Test Assembly (BLTA) rods irradiated in the Quad Cities 1 power plant. The BLTA rode were manufactured in GE's Wilmington, North Carolina, facilities. The retabrication work was performed at the CE Vallecitos Nuclear Center, Pleasanton, California. C5 is the owner of the fuel.
EvarPination at N!*Q
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g The rodlets and specimens taken frors the rodlets will be the subjeit of th$
Tf, following measurements and examinations at NFr!
2; n
z
- 1) Visual examination S
h 2,
Profilometry
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3)
Neutron radiography Me 4)
Eddy Current
- 5) Axial ganas scan 6)
Fieston gas analysis 7)
Burnup g
GE TEL No.
408 925 2903 Apr 21.88 12:35 P.03 2
i, 4
Examination at_JifA (continued) 8)
N 1 density 9)
Fuel retained fission gas 10). Meta 11ography and ceramography 11)
Scannin5 electron microscopy 12)
Fuel pellet radial micro gacra scan 13)
Fuel electron probe microacalysis 14) cladding exanination by transmission electron microscopy
- 15) Cladding fatigue testing Items 1 through 5 above are tests and exaninations which are nondestructive in nature - that is, these tests will be parformed on the entire original rodlet.
Items 6 through 15 require small specimens taken fro:n the rodlet materials, both cladding and fuel. These specimens will be prepared by selective sectioning of each rodlet.
Discosal of Fuel After all the pit.nned measurements and tests at NPD are complete, the redlet cladding and fuel materials will be disposed of in Japan, in accordance with applicable Japanese rules and re8ulations.
Description of Rodlats Individual rodlet data:
g Len5th:
20 inches a
Outside clameter:
0.484 inches a
Fuel column length:
12.3 inches d
Original weight of UO in rodlet: Approximately 280 g M
original enrichment, weight t U 235:
2.6 to 3,0 Current enrichment range, weight % U 235: 0.56 to 1,48*
C Fuel exposure ran5*: 22 !Nd/kgU (2 rodlets)*,
{
-42 HVd/kgU (1 rodlet)*
2
\\ Total nuclear material weight in three (3) rodlets:
Total U:
698 gn ms*
Total U 235:
8 grams
- Total Pu:
5 grams *
- These data describe the rodlets before irradiation at Halden The values will change slightly (less than 104) as a result of the Halden irradiation.
i l
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408 925 2903 GE TEL No.
403 925 2903 Apr 21,88 12:34 P.01 j
4A
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Q H T EL E_C_0 P_Y C 0_V E R _ S H'E E T st DATE: 4 M /7 TIME:
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FROM:
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_ (4083925-5325 TELECOPY 082925-2903 DIAL Cort: _
_8_" 425-5325 OfAL COFN: 8 88 425-2903 L PLUS COVER SHEET NJMBER 0: PAGES_
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