05000266/LER-1997-018, Forwards LER 97-018-00 Which Describes Potential to Overpressurize Isolated Section of Pipe Between Two Residual Heat Removal Valves Inside Each Containment,During Design Basis Accident

From kanterella
Jump to navigation Jump to search
Forwards LER 97-018-00 Which Describes Potential to Overpressurize Isolated Section of Pipe Between Two Residual Heat Removal Valves Inside Each Containment,During Design Basis Accident
ML20140H107
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 05/05/1997
From: Dante Johnson
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20140H111 List:
References
NPL-97-228, NUDOCS 9705120338
Download: ML20140H107 (1)


LER-2097-018, Forwards LER 97-018-00 Which Describes Potential to Overpressurize Isolated Section of Pipe Between Two Residual Heat Removal Valves Inside Each Containment,During Design Basis Accident
Event date:
Report date:
2662097018R00 - NRC Website

text

.- .

1 .

4 '

Wisconsin Electnc POWER COMPANY 4

{

Point Beoch Nuclear Plant (414) 755-2321 6610 Nuclear Rd., Two Rivers. WI 54241

) NPL 97-228 May 5,1997 4

Document Control Desk

,' US NUCLEAR REGULATORY COMMISSION 1

Mail Station PI-137 Washington, DC 20555 t

l Gentlemen:

DOCKET 50-266 AND 50-301

LICENSEE EVENT REPORT 97-018-00 i

POTENTIAL RESIDUAL HEAT REMOVAL SYSTEM OVERPRESSURE DURING ACCIDENT CONDITIONS POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 Enclosed is Licensee Event Report 97-018-00 for Point Beach Nuclear Plant, Units 1 and 2. This report is provided in accordance with 10 CFR 50.73(a)(2)(i), "Any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident." This report describes a potential to overpressurize the isolated section of

_ pipe between two residual heat removal (RHR) valves inside each containment, during a design basis accident. Any significant damage to the affected pipe or valves could have inhibited the RHR system's capability to achieve and maintain a cold shutdown condition, which is required for certain accidents.

This condition is a latent characteristic of the original plant design.

If you require additional information, please contact us.

S.mcerely.

9705120338 970505 PDR ADOCK 05000266 S PDR

,n

,g. , $ / / l l $

. W- T

"'" ~ Douglas F. Johnson Manager I Regulatory Services and Licensing closure /

cc: NRC Resident Inspector NRC Regional Administrator 13M3 Llllll!lil!llllllillllljlllllllllll

-nan en