PY-CEI-NRR-0741, Advises That Util Currently Evaluating Present Configuration of RCIC Sys Steam Line,Previous Configuration & Alternate Configuration,Per 870401 Amend 3 to License NPF-58.Results of Configurations Will Be Transmitted by 871231
| ML20236J238 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/30/1987 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| PY-CEI-NRR-0741, PY-CEI-NRR-741, NUDOCS 8711050221 | |
| Download: ML20236J238 (1) | |
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l THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY l,
P.O HOX 97 m
PERRY, OHIO 44081 e TELEPHONE (216) 259-3737 s ADDRESS - 10 CENTER ROAD Serving The Best Location in the Nation
, Murray R.
Edelman PERRY NUCLEAR POWER PLANT 8R. YKI PRf alDENT NUCLf,A R October 30, 1987 PY-CEI/NRR-0741 L Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Perry Nuclear Power Plant Docket No. 50-440 Configuration of RCIC System Steam Line Centlemen:
By letter dated April 1,1987 the NRC issued Amendment 3 to Facility Operating License No. NPF Sd for the Perry Nuclear Power Plant. This amendment allowed the RCIC inboard isolation valve, IE51-F063, to be changed f rom normally closed, DC powered to normally opened, AC powered.
In their SER, the NRC staff stated that they were currently pursuing Generic Issue 87 :
" Failure of HPCI Steam Line Without Isolation". The staf f had questioned CEI as to the reliability of the F063 valve under flow conditions expected during a break in the RCIC steam line.
As a result, CEI comnitted to further evaluate the proposed design configuration, as well ns alternative configurations, to determine the most desirable design.
CEI is evaluating various valve and power supply configurations to maximize system reliability and availability.
Presently, we are evaluating the present configuration, the previous configuration, and an alternative configuration.
This alternative would utilize a normally closed, DC powered valve as the outboard containment isolation valve. The evaluation of these configurations will be completed, and transmitted to the NRC by December 31, 1987.
If you I
have any questions, please feel free to call me.
Very truly yours, Murray R. Edelman l
1 Senior Vice President Nuclear Group i
l MRE: cab i
ec:
T. C. Colburn K. A. Connaughton USNRC, Region III g
8711050221 871030 i
PDR ADOCK 05000440 10 p
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