05000266/LER-1998-022, Forwards LER 98-022-00 Re Discovery of Procedural Inadequacy Which Alone Has Potential to Prevent Fulfillment of Safety Function of Structures or Sys Needed to Mitigate Consequences of Accident,Per 10CFR50.73(a)(2)(iv)

Forwards LER 98-022-00 Re Discovery of Procedural Inadequacy Which Alone Has Potential to Prevent Fulfillment of Safety Function of Structures or Sys Needed to Mitigate Consequences of Accident,Per 10CFR50.73(a)(2)(iv)

ML20237B565
Person / Time
Site:	Point Beach
Issue date:	08/13/1998
From:	Kaminskas V WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20237B567	List: 05000266/LER-1998-022, Forwards LER 98-022-00 Re Discovery of Procedural Inadequacy Which Alone Has Potential to Prevent Fulfillment of Safety Function of Structures or Sys Needed to Mitigate Consequences of Accident,Per 10CFR50.73(a)(2)(iv)
References
NPL-98-0670, NPL-98-670, NUDOCS 9808190045
Download: ML20237B565 (1)

LER-2098-022, Forwards LER 98-022-00 Re Discovery of Procedural Inadequacy Which Alone Has Potential to Prevent Fulfillment of Safety Function of Structures or Sys Needed to Mitigate Consequences of Accident,Per 10CFR50.73(a)(2)(iv)

Event date:
Report date:
2662098022R00 - NRC Website

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Wisconsin i Electnc POWER COMPANY t

Point Beoch Nuclear Plant (920) 755-2321 6610 Nuclear Rd., Two Rivers. WI 54241 NPL 98-0670 August 13,1998 Document Control Desk 10 CFR 50.73 U.S. NUCLEAR REGULATORY COMM.ISSION Mail Station PI-137 Washington, DC 20555 Ladies / Gentlemen:

~ DOCKETS 50-266 AND 50-301 LICENSEE EVENT REPORT 1998-022-00 TECHNICAL SPECIFICATION LCOs FOR SAFETY INJECTION AND RESIDUAL HEAT REMOVAL OPERATION POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 Enclosed is Licensee Event Report 1998-022-00 for Point Beach Nuclear Plant, Unit I and 2. This report is provided in accordance with 10 CFR 50.73(a)(2)(vi) as the discovery of a procedural inadequacy which alone has the potential to prevent the fulfillment of the safety function of .

structures or system needed to mitigate the consequences of an accident. This report describes the j discovery that although the Technical Specification Limiting Conditions for Operation (LCOs) permit having one component of the safety injection (SI) system out of service at the same time as one component from the opposite train of the residual heat removal (RHR) system, existing plant )

procedures were not written for cross train alignment of RHR discharge to the SI system for containment sump recirculation. j Please contact us if you require additional information. l L Sincerely,

/$.NWb l Vito A. Kaminskas  !

I Manager, Regulatory Services & Licensing }f CWK/dms l. s v.9 g/,-

Enclosure cc: NRC Resident Inspector PSCW INPO Support Services NRC Regional Administrator 9808190045 PDR 980813 ADOCK 05000266 8 PDR n _ ., .dsawsh Exy0%w

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