ML20127D247
| ML20127D247 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 06/19/1985 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-85-20, NUDOCS 8506240172 | |
| Download: ML20127D247 (1) | |
Text
r-1 SNUPPS Standardized Nuclear Unit Power Plant System 5 Choke Cherry Road Nicholas A. Petrick vil Ma land 20850 Executive Director June 19, 1985 SLNRC 85 20 FILE: 0671.1 SUBJ: Fire Protection Review Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Docket Nos.: 50-482 and 50-483
Reference:
SLNRC 84-0109, dated 8/23/84: Same Subject
Dear Mr. Denton:
The reference letter provided the "SNUPPS Response Plan for Immediate Evacua-tion of the Control Room Due to Fire" which is applicable to Callaway Plant Unit No. I and Wolf Creek Generating Station, Unit No. 1.
In the response plan phase C actions, it was indicated that an electrical isolation switch would be installed for Component Cooling Water (CCW) system valve EG-HV-70B.
This switch would assure the isolation of CCW flow to nonessential services in the Radwaste Building following a postulated fire in the Control Room.
The purpose of this letter is to inform the NRC staff that the function of isolating CCW flow to the Radwaste Building can be accomplished by closing either valve EG-HV-70A or valve EG-HV-70B in the CCW system. These valves are both powered from the same Class lE electrical separation group. There-fore, the plant modifications for electrical isolation switch installation l
can be effected for either valve with the same consequences regarding plant i
shutdown following the postulated control room fire.
l Very ruly yours, 8506240172 850619 PDR ADOCK 05000482
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\\.<it ( N c 1cholas A. Petrick
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cc:
G. L. Koester KGE J. M. Evans KCPL D. F. Schnell UE J. Cummins USNRC/WC B. Little USNRC/ CAL
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G. C. Wright USNRC/RIII COP i
R. P. Denise USNRC/RIV l
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