05000266/LER-1997-020, Forwards LER 97-020-01,describing Plant Conditions in Which Ability to Achieve & Maintain Safe Shutdown in Event of Postulated Fire May Have Been Adversely Affected

Forwards LER 97-020-01,describing Plant Conditions in Which Ability to Achieve & Maintain Safe Shutdown in Event of Postulated Fire May Have Been Adversely Affected

ML20211P604
Person / Time
Site:	Point Beach
Issue date:	10/14/1997
From:	Dante Johnson WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211P610	List: 05000266/LER-1997-020, Forwards LER 97-020-01,describing Plant Conditions in Which Ability to Achieve & Maintain Safe Shutdown in Event of Postulated Fire May Have Been Adversely Affected
References
NPL-97-0632, NPL-97-632, NUDOCS 9710210034
Download: ML20211P604 (1)

LER-2097-020, Forwards LER 97-020-01,describing Plant Conditions in Which Ability to Achieve & Maintain Safe Shutdown in Event of Postulated Fire May Have Been Adversely Affected

Event date:
Report date:
2662097020R00 - NRC Website

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l-l Wisconsin Electnc POWER COMPANY Point Beoch Nuclear Plant 6610 Nuclear Rd.Two %ert WI 54241 (414) 755-2321 NPL 97-0632 October 14,1997 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mai! Station PI-137 Washington, D. C. 20555 I adies/ Gentlemen:

DOCKETS 50 266 AND 50-301 LICENSEE EVENT REPORT 97-020-01 CONDITIONS OUTSIDE 10 CFR 50 APPENDIX R SAFE SHUTDOWN ANALYSIS POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 Enclosed is supplemental Licensee Event Report 97-020-01 for Point Beach Nuclear Plant, Units 1 and 2. This report is provided in accordance with 10 CFR 50.73(a)(2)(v)(A),"Any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to shut down the reactor and maintain it in a safe shutdown condition." This report provides information to supplement the original report, particularly to describe the status of corrective actions and compensatory measures. This report replaces LER 266/97-020-00 in its entirety. This report describes plant conditions in which the ability to achieve and maintain safe shutdown in the event of a postulated fire may have been adversely affected.

If you require additional information, please contact us. g

~y Sincerely, ' & 1 Douglas F. Johnson Manager, Regulatory Services & Licensing ffhfff[//g'f!l 9710210034 971014 I ' b.

Enclosure PDR ADOCK 05000266 S PDR ,

cc: NRC Resident inspector PSCW NRC Regional Administrator INPO Support Service A subsWhyWHkuunEngCayratu

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