ML20036A799
| ML20036A799 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 05/12/1993 |
| From: | Tokar M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Kersteen G ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| References | |
| TAC-L21620, NUDOCS 9305170008 | |
| Download: ML20036A799 (2) | |
Text
Docket 70-1100 s
License SNM-1067 MAY I 2 1993 Mr. Gary C. Kersteen Uranium Plant Manager Windsor Nuclear Fuel Manufacturing I
Combustion Engineering, Inc.
1000 Prospect Hill Road Windsor, Connecticut 06095-0500
Dear Mr. Kersteen:
SUBJECT:
EMERGENCY PLAN (TAC NO. L21620)
This refers to your application dated June 27, 1991, requesting an amendment to your Emergency Plan to reflect the results of the revised nuclear accident analysis for Buildings 6 and 17. CE believes that the ' application serves to satisfy License Condition 21 which requires, in part, that the licensee expand its Emergency Plan to include the criteria and methodology for emergency response for all affected employees at the site.
Our review of your application has identified additional information that is needed before final action can be taken on your request. The additional information, specified in the enclosure, should be provided within 30 days of the date of this letter.
If you have any questions regarding this matter, please contact Sean Soong of my staff at (301) 504-2604 or me at (301) 504-2590.
Sincerely, Mi h a,
ection Leader Licensing Section 2 Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS
Enclosure:
As stated cc w/encls:
Mr. J. F. Conant, Manager Nuclear Materials Licensing
'})* Docket No.
r Distribution:
w/ encl. (Control No. 360S) 70-1100 PDR NRC File Center -
NMSS R/F FCSS R/F FCLB R/F Region 1 JRoth, RI Madams JGreeves ETenEyck
- See previous concurrence OFC FCLB:
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DATE 5/ /93:
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Request for Additional Information Application Dated June 27, 1991 l
Combustion Engineering, Inc.
Docket 70-1100 i
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The revised analysis indicates that a nuclear accident in either' Building 6 or 17 I
would not result in e.xposures outside controlled areas in excess of the 1 rem dose criterion in 10 CFR 70.22(i)(1), and therefore, all "affected" personnel would be within a i
controlled area and are therefore covered by the Emergency Plan.
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Since the calculated dose outside Building 6-A (non-nuclear) exceeds 1 rem,. CE should
- provide a communication system which can quickly warn personnel inside the Building of an i
emergency that requires sheltering or other action.
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