05000334/LER-1980-073-01, /01T-0:on 801017,Westinghouse Notification Received Re Blowdown of All Three Generators & Loss of Heat Sink During Single steam-line Break.No Corrective Actions Necessary

/01T-0:on 801017,Westinghouse Notification Received Re Blowdown of All Three Generators & Loss of Heat Sink During Single steam-line Break.No Corrective Actions Necessary

ML20008E261
Person / Time
Site:	Beaver Valley
Issue date:	10/17/1980
From:	Lacey W DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20008E258	List: 05000334/LER-1980-073-01, /01T-0:on 801017,Westinghouse Notification Received Re Blowdown of All Three Generators & Loss of Heat Sink During Single steam-line Break.No Corrective Actions Necessary
References
LER-80-073-01T, LER-80-73-1T, NUDOCS 8010240473
Download: ML20008E261 (2)

LER-1980-073, /01T-0:on 801017,Westinghouse Notification Received Re Blowdown of All Three Generators & Loss of Heat Sink During Single steam-line Break.No Corrective Actions Necessary

Event date:
Report date:
3341980073R01 - NRC Website

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0 Attachment To LER 80-73/01T Beaver Valley Power Station Duquesne Light company Docket No. 50-334 A break was postulated in the header of the Residual Heat Release (RIIR) valve resulting in three 3-inch steam generator uncontrolled blowdowns.

Based upon-a run-out test conducted at Beaver Valley Unit 1, each motor-driven auxiliary feedvater put is capable of supplying 750 gpm to the depressurizing steam generator. To conservatively bound the core thermal response, an additional 900 gpm of auxiliary feedwater was assumed to be supplied by the turbine-driven feed pump. All other initial conditions and assumptions madg in the analysis were equivalent to those specified in the ANS Condition IV double ended steamline rupture presented in Beaver Valley Unit 1 FSAR Chapter 14 accident analysis results.

No operator action was assumed until at least 10 minutes after reactor trip and sarety injection initiation. At that time, the' operator is assumed to take appropriate action to control the auxiliary feedwater flow to the depressurized steam generators in order to restore / maintain water level in the normal range.

The analysis showed that the maximum return.to power following the rupture was 1.8 percent of r,ated power. At the core thermal conditions exhibited following the incident, no fuel damage is expected to occur. As a result, the core thermal response and the subsequent radiological releases are conservatively bounded.by the results of the double ended steamline rupture presented in the Beaver Valley Unit 1 FSAR.

The long term cooling capability was also investigated and found not to be a problem for the reasons specified in the above reference.

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