ML19345A953

LER 80-078/01T-0:on 801114,determined That,If Safety or Relief Valves Challenged W/Water Loop Seals on Inlet, Downstream Piping Could Be Overstressed.Caused by Inadequate Design.Loop Seal Drains Installed

ML19345A953
Person / Time
Site:	Beaver Valley
Issue date:	11/19/1980
From:	Lacey W DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19345A946	List: ML19345A945 ML19345A953
References
LER-80-078-01T, LER-80-78-1T, NUDOCS 8011250470
Download: ML19345A953 (4)

Text

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REPOMTDATE 8J J 4 6J et OoCKET N6MeER *A EVENT CE5CmPT10N ANO PROSA8LE CONSECUENCES h (TTTIl In the event that the safety or relief valves are challenced with water loon seals !

[~iTTT l on the inlet . the safety and power onerated relfof valvo Munatrevi ninine cauhi l i t, # 41 [ be overstressed. Probable consequences could be a nressurizer nozzle break or a i e

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13 joll The cause was inadequate design leading to the overstress condition if a l 1i;i} l valve actuates. Present corrective actions have been to install loon seal drains. I a

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Attachment To LER 80-78/01T Beaver Valley Power Station Duquesne Li;;ht Company Docket No. 50-334 BVPS Unit 1 LER 80-078/01P should be used for supplemental information.

This report is included as an attachment to this LER (LER 80-078/01T).

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- Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077 Ndvember 17, 1980 1 BVPS: JAW: 1024 Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 LER 80-078/0lP 9

Mr. B. H. Crier. Directer of Regulation United States Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, Pennsylvania 19405 ,

Dear Mr. Crier:

In accordance with Appendix A, Beaver Valley Technical Specifications, Licensee Event Report LER 80-078/0lP, Technical Specification 6.9.1.8.1, Analysis of Structures, is submitted. This occurrence was reported to the BVPS NRC Resident Inspector, Mr. D. A. Beckman, at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on November 14, 1980.

In the event that the Code safety valves are challenged with a water loop seal on the inlets, the pressurizer safety and power-operated relief valve piping would be overstressed.' A long-term analytical solution was required to resolve ,

this problem. Analysis determined that these conditions would not exist if the loop seals were drained. The inlets to the Code safe' tics and power-operated relief valves have been provided with continuous drains until the final analysis is complete and modifications are designed.

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Mr. B. II. Crier November 17, 1980.

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Page 2 Further analysis has been used to determine that operation of the power operated relief valves, with a water seal, will not result in an overstressed condition. A loop. seal will be reestablished for these valves on the first scheduled station outage of sufficient duration to complete the task.

Analysis is continuing on modifications required to reestablish loop seals

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on the Code safety valves.

Very truly yours,

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J. A. Werling Superintendent cc: Director Of Management & Program Analysis United States Nucleac Regulatory Co= mission Washington, D. C. 20555 W. J. Ross, BVPS Licensing Project Manager ,

United States Nuclear Regulatory Commission Washington, D. C. 20555 -

D. A. Beckman, Nuclear Regulatory Cocnission, BVPS Site Inspector P. Higgins, Secretary, Price Movers Committee - EEI Nuclear Safety Analysis Center, Palo Alto, California Mr. John Alford, PA Public Utilities Co= mission, Harrisburg, PA e

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