05000334/LER-1980-067-01, /01T-0:on 800912, Determined That Branch Line of 24-inch Reactor Plant Component Cooling Water Header Will Be Subj to Overstress During Seismic Event.Caused by Dead Weight & DBE Loading Factors

/01T-0:on 800912, Determined That Branch Line of 24-inch Reactor Plant Component Cooling Water Header Will Be Subj to Overstress During Seismic Event.Caused by Dead Weight & DBE Loading Factors

ML19338E070
Person / Time
Site:	Beaver Valley
Issue date:	09/17/1980
From:	Lacey W DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19338E067	List: 05000334/LER-1980-065-01, /01T-0: on 800912,determined That Both River Water Supply Lines Will Be Subj to Overstress During Seismic Event.Caused by Dead Weight & DBE Loading Factors.Corrective Actions Underway 05000334/LER-1980-066-01, /01T-0:on 800912,determined That a Steam Generator Steam Outlet Pipe Hangers Will Be Subj to Overstress During Seismic Event.Caused by Dead Weight & DBE Loading Factors.Hanger Mods Completed 05000334/LER-1980-067-01, /01T-0:on 800912, Determined That Branch Line of 24-inch Reactor Plant Component Cooling Water Header Will Be Subj to Overstress During Seismic Event.Caused by Dead Weight & DBE Loading Factors ML19338E066
References
LER-80-067-01T, LER-80-67-1T, NUDOCS 8009240461
Download: ML19338E070 (2)

LER-1980-067, /01T-0:on 800912, Determined That Branch Line of 24-inch Reactor Plant Component Cooling Water Header Will Be Subj to Overstress During Seismic Event.Caused by Dead Weight & DBE Loading Factors

Event date:
Report date:
3341980067R01 - NRC Website

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'N NRC FORM 384 U. S. NUCLEAA REGULATORY COMMISSION i

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- 8 60 63 00CKET NWSER tdl 63 EVkNT QATE 74 75 REPORT DATE 80 EVENTDESCRfPTION AND PROBABLE CONSECUENCES h

,. Io12l l It has been determined that an overs' tress condition exists'at a two (2) inch

__j c o ;3l l branch line off the 24 inch reactor plant component cooling water header during a l

lo#Ai l design basis earthquake. Consequences of the loss of this line would lead to a l

L i o, s 1 l los's of Residu:rl Heat Removal (RHR) because of the need to isolate the whole l

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liliI I earthauake loadinc factors. Pipe support modifications to alleviate this condition i

i, i 31 l will be cCapleted prior to startup.

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Attachment To LER 80-67/01T-Beaver Valley Power Station Duquesre Light Company Docket No. 50-334 No further information is available or needed*to satisfy the reporting requirement.

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