ML19350C397
| ML19350C397 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 12/16/1980 |
| From: | Kaplan A GENERAL ELECTRIC CO. |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 18074, NUDOCS 8104010408 | |
| Download: ML19350C397 (3) | |
Text
.
7%iHJ G E N E R A L h. E L E CT R I C l
NUCLEAR ENERGY PRODUCTS EHVISION e
WILMINGTON MANUF ACTURING DEPARTMENT CASTLE HAYNE ROAD. P.O. BOX 780. WILMINGTON, N. C. 28401 1919) 343 5000 December 16, 1980 Director Of fice of Nuclear Materials Saf ety & Saf eguards U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555 Attention:
Mr.
W.
T.
Crow, Section Lecder Uranium Process Licensing Section M/S 396-SS
Dear Sir:
Reference:
NRC License SNM-1097, Docket #70-1113 Subj ect :
APPLICATION AMENDMENT N-10, AUTHORIZED PRODUCT PROCFSSING OPERATION ACTIVITIES With reference to activities authorized by SNM-1097 at the GE fuel fabrication plant in Wilmington, N.
C.,
General Electric Company hereby requests authorization to remove the restriction from scrap recovery in Section 1.1(c) of Appendix A in the application of 12/19/75 for License SNM-1097, which requires scrap for reprocess-ing to be received from GE owned or controlled plants.
An amended Page A-1 of Appendix A is attached.
Specifically, General Electric is requesting authorization to include in its scrap recovery activity the reprocessing of scrap received from any location, provided that the nuclear safety chmxcteristics 9r identical to Wilmington plant scrap and that the enrichment sur veillance requirements in Section 5.2.2(a) in the license application for SNM-1097 are met.
Pursuant to 10 CFR 170.31, enclosed is a General Electric check for S150 for processing this amendment request.
General Electric personnel would be pleased to discuss this matter further with you and your staff as you may deem necessary.
Very truly yours, GENERAL ELE _CTRI COM ANY
" lh L
Arthur L. Kapla, ?!anager Licensing & Compliance Audits M/C J26 ALK:bmw NSD-L A t tac hmen t s p r_.
y y m.
Y 8104010 M g
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APPEN!:1X A LICENSE CONDITIONS FOR THE WIL"INGTON SITE Set forth herein are the requirements governing the receipt, possession and use of the special nuclear material subject to licensing and regulation by the U. S. Nuclear Regulatory Commission (hereinafter referred to as the Commission) in activities at General Electric's site in Wilmington, North Carolina.
L.0 AUTHORIZED ACTIVITIES The following types of activities are authorized:
1.1 Product Processing Operations (a) UF Conversion: Conversion of uranium hexafluoride to 6
uranium oxides.
(b) Fuels Manufacture:
Fabrication of nuclear reactor fuels containing uranium.
(c). Scrap Recovery:
Processing of Wilmington plant uranium compounds and mixtures. Reprocessing of scrap with nuclear safety characteristics identical to Wilcington plant scrap, e
provided that the enrichment surveillance requirements of Section 5.2.2(a) are met.
1.2 Process Technology Operations
' (a) Development and f abrication of reactor fuel, fuel elements and fuel assemblies in small amounts or of advanced design.
(b) Scrap recovery as stated above in 1.1(c).
(c ) Determination of interaction between fuel additives and fuel materials.
License No.
Sm 1097 Docket No.
70-1) ] 3. _
5.et. No.
1.?teT Pa ge Appendix A Amend. No.
N-10 c e,,
12/16/80 A-end e 5.et.(s) 1 1(CI A-1
L.
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L I
>{
APPENDIX A I
b !
LICENSE CONDITIONS I
r FOR THE W.
VILMINOTON SITE if l
p4 Set forth herein are the require =ents governing the receipt, possession and see of the special nuclear =aterial subice: to licensing and reEulatica by the 6h
- 9. S. Nuclear Regulatcry Co==issica (hereinaf ter referred to as the Ce :ission) t; (if in activities at General Electric's site in Wiltingten, North Carolina.
[f.I La
,.I 1.0 AUTHCRIZED ACTIVITIES r
2 P.. )
The folleving types of activities are authoriced:
r :[
).1 Preduct Proce= sinc Operatiens 11 (a) UF Conversica: Conversion cf uraniu hexafluoride to uraniu:
I.
p 4
oxides.
.it (b)
Fuels Manufacture:
Fabrication of nuclear reactor fuels centaining f) ct uraniu=.
%b (c)
Scrap Recovery: Pro;essing of Wilting ca plant uraniu= cc=peunds and cixtures.. Reprocessing of scrap vich nuclear safety characteristics
-7
}
identical to Vil=ington plant scrap, provided such -taterisl-is-received
'fi
- i
[
u y-j f-ro:-CE--owned-or-controlled-9 ants-and the enrich =ent surveillance
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1 c
N*
require =ents of Section 5.2.2(a) are met.
-m"
.2 Process Technolcev Operations O
i (a) Develop =ent and fabrication of reacter fuel, fccl ele ents and fuel
(
asse:blies in s all a:custs cr of advanced design.
f.f.(
(b)
Scrap recovery as stated above in 1.1 (c).
(f)
(c) Deter =ination of interaction between fuel additives and fuel =aterials.
A. S?'i-1997 De ck et A.
70-1113 Sect. No.
I "' " ? a -
F o;.
Appendix A f*,
- Decc ber 19. 1975
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g Arend e se ct.(s)
A-1
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