ML19347D503
| ML19347D503 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/20/1981 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8103260288 | |
| Download: ML19347D503 (2) | |
Text
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OYSTER CREEK NUCLEAR GENERATING STATION JCP&b GPU MLc%'se (609)693-6000 P.O. BOX 388
- FORKED RIVER
- 08731
- */L M
wu March 20, 1981 Director Nuclear Reactor Regulation E.
U.S. Nuclear Regulatory Commission 2
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Washington, D.C. 20555
Dear Sir:
U s
Subject:
Oyster Creek Nuclear Generat Docket No. 50-219 Appendix R Requirements We have reviewed the provisions of 10 CFR 50.48 including 10 CFR 50 Appendix R with regard to the Oyster Creek Station.
The following information, including a request for extension, is submitted in accordance with 10 CFR 50.48 (c) (5).
In relation to 10 CFR 50.48 (c) (2) we have initiated the engineering work necessary to provide the emergency lighting capabilities in accordance with the criteria presented in item III.J of 10 CFR 50 Appendix R.
The modifications necessary to provide this capability will be completed by November 17, 1981.
With regard to section 10 CFR 50.48 (c) (4) we have previously developed an engineering proposal for providing an alternate shutdown capability; however, in light of the new criteria established in Appendix R in relation to safety, hot shutdown, and cold shutdown systems, it is necessary to perform an in depth review of our fire hazards analysis in order to determine what exemptions, if any, will be required considering the criteria given in section G.2. of Appendix R.
Prior to this review, it is not possible to identify the need for exemptions [as per 10 CFR 50.48 (c) (6)] if, in fact, such exemptions should be required.
Nor is it possible to determine the effect of the new criteria on the alternate shutdown system proposal.
It is therefore requested that the date [as per 10 CFR 50.48 (c) (5)] for submittal of plans and schedules for completion of the alternate shutdown system and the submittal of exemption requests be delayed until January 17, 1982, in order to allow for tho aforementioned review of our fire hazards analysis and identification of any exemptions that may be required.
In summary, the foregoing presents our response to the requirements of 10 CFR 50.48 and Appendix R items III.G and 810 3 260#T g
1
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f III.J.
Item III.0 does not apply to the Oyster Creek Station since the primary containment is inerted.
Further-more, all other items of Appendix R have been reviewed and found to be non-applicable to the Oyster Creek Station since the previously issued Nuclear Regulatory Safety Evaluation Report, and supplements thereto, of our Fire Protection Program have accepted the provisions of this program as satisfying the provisions of Appendix A to Branch Technical Position BTP APCSB 9.5-1.
If you should have any questions, please contact Mr James Knubel at (201) 455-8753.
Very truly yours, dW Ivan R.
Fin rock, Jr.
Vice President - JCP5L Director - Oyster Creek Station O
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