ML19343D599
| ML19343D599 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 01/14/1981 |
| From: | Kaplan A GENERAL ELECTRIC CO. |
| To: | Partlow J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 18310, NUDOCS 8105050466 | |
| Download: ML19343D599 (2) | |
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'70 -IIIs GENERAL Je ELECTRIC NUCLEAR ENERGY q\\ W!'
PRODUCTS DIVISION y
WILMINGTON MANUFACTURING g
DEPARTMENT cASTLI HAYNE ROAO.'P. O. BOX 780. WILMINGTO
.C.28 500 JM 2 P 1981 a,
- E, January 14, 1981
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D Office of Nuclear 3!aterials Safety &
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-,7 o\\4 U. S. Nuclear Regulatory Commission
%'ltJAN 2 8 jg3l > --l Tashington, D. C.
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NM55 hQ Attention:
'tr. James G. Partlow, Chief MAIL SECUCN
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11aterial Control Licensing. Branch DOCKET CLE.w
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Dear Sir:
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Reference:
NRC License SN51-1097, Docket #70-1113
Subject:
SHIP.'JENT OF USED PELLET PRESSES TO CO11BUSL
- ENGINEERING With reference to activities authorized by SNM-1097 at the General Electric fuel fabrication plant in Wilmington, North Carolina, and pursuant to my telephone conversation with you on January 12, 1981, I understand that we are authorized on a one-time basis to ship to Combustion Engineering., Inc. in Windsor, Connecticut, two used pellet presses containing small quantities of special nuclear material (SN'.1 ), with values for.these quantities obtained from average values of measured smear tests made on the presses, and with these quantities used as our shipper's values.
This 'atter is for your information, to describe and document the measurement method used.
The method used for deter. Lining the average measured values was to obtain thirty-three smear readings from seventeen diff erent zones on each press, both inside and outside.
The surface area of each zone for each press was calculated.
Then, based on the smear readings, the quantities were applied to each area and an aggregate quantity of SN11 was obtained for each press.
There were no hidden surfaces or cavities that could not be visibly inspected or that could not be cleaned and/or wipe tested.
An isotopic value of 2.5% was used for determining the grams U-235.
Based on the above method, the quantities were determined to be approximately 24 grams urani
- 0. 6 gram uranium-235 for one press, and approximately y, 9 tium and 0.4 gram uranium-236 C
for the other press.
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GENER AL $ ELECTRIC-Director-ONMSS January 14, 1981-Page 2 If you require further information related to this matter, please contact me.
i Very truly yours,-
GENERAL ELECTRIC COMPANY-Arthur L. h pian,' Manager Licensing & Complie.nce Audits M/C J26 7
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