ML19347B673

RO:80-075/01P:on 801008,analysis Revealed Overstress Condition Existed at Pipe Support H-43 on Reactor Coolant Fill Header from High Head Charging Pumps.Cause Not Determined.Mod Will Be Completed Prior to Plant Startup

ML19347B673
Person / Time
Site:	Beaver Valley
Issue date:	10/08/1980
From:	Werling J DUQUESNE LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
BVPS:JAW:1002, IEB-79-14, RO-80-075-01P, RO-80-75-1P, NUDOCS 8010150534
Download: ML19347B673 (3)

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'** DUQUESNE LIGHT COMPANY Beaver Valley Power Station

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Post.0ffice Box 4

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Shippingport, PA 15077 October 8, 1980 BVPS: JAW:1002

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Beaver Valley Power Station, Unit No. 1 l

Docket No. 50-334, License No. DPR-66

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LER 80-075/OlP

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Mr. B. H. Grier, Director of Regulation United States Nuclear Regulatory Commission Region 1 l 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

In accordance with Appendix A, Beaver Valley Technical Specifications, Licensee Event Report LER 80-075/0lP, Technical Specification 6.9.1.8, ,

Administrative Controls, is submitted. This occurrence was reported to j

Mr. J. Hegner, the Beaver Valley Resident Inspector, at 0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br /> on l October 8, 1980.

Evaluation and reanalysis required by IE Bulletin 79-14 have shown that the following piping and support has less conservatism than assumed for the safety analysis and, therefore, requires remedial action. .

The overstress condition occurs at pipe support'H-43 on the reactor coolant fill header from the high head charging pumps. Loss of this line at this location would result in a loss of all three charging pumps during a seismic event. This overstress condition has been calculated for the summed loading factors of, deadweight, thermal and design basis earthquake loads.

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Mr. B. H. Grier l October 8, 1980 .

BVPS

JAW: 1002

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l The plant is currently in Operational Mqde 5. A pipe break at this location could be quickly isolat d and t%e low head safety injection pumps

would be available to provide reactor coolant makeup if needed. Therefore, the health and safety of the general public would not be jeopardized.

Modification of the pipe support needed to alleviate this condition will be l done prior to plant startup.

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Very truly yours,

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J. A. Werling Superintendent i

• cc: Director Of Manage =ent & Program Analysis United States Nuclear Regulatory Commission Washington, D. C. 20555 W. J. Ross, BVP,S Licensing Project Manager w/'

United States Nuclear Regulatory Co= mission Washington, D. C. 20555 .

D. A. Beckman, Nuclear Regdlatory Com=ission, BVPS Site Inspector P. Higgins, Secretary, Prime Movers Committee - EEI Nuclear Safety Analysis Center, Falo Alto, California Mr. John Alford, PA Public Utilities Commission, Harrisburg, PA

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