ML20042B449

ROs 82-007/01P & 82-008/01P:during Update of Analysis Required by IE Bulletin 79-14,overstress Condition Found on a Steam Generator Steamline.Condition Analyzed in FSAR & Addressed Through Emergency Procedures

ML20042B449
Person / Time
Site:	Beaver Valley
Issue date:	03/15/1982
From:	Williams H DUQUESNE LIGHT CO.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-SSINS-6820 IEB-79-14, ND1SS1:534, RO-82-007-01P, RO-82-008-01P, RO-82-7-1P, RO-82-8-1P, NUDOCS 8203250325
Download: ML20042B449 (3)

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("*,"""' DUQUESNE LIGHT COMPANY Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077 March 15, 1982 NDISSI:534 deaver Valley Power Station, Unit No. 1 {gco Docket No. 50-334, License No. DPR-66 ,

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LER 82-007/0lP, 82-008/0lP '

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i. >m,. C LB Mr. R. C. Haynes, Regional Administrator l~ "? np United States Nuclear Regulatory Commission Region 1 k

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[S 631 Park Avenue s p King of Prussia, Pennsylvania 19406 ,

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Dear Mr. Haynes:

In accordance with Appendix A, Beaver Valley Technical Specification 6.9.1.8, Administrative Controls, Licensee Event Reports LER 82-007/0lP and LER 82-008/0lP are submitted. These occurrences were reported to Mr. R. R.

Kiemig, the NRC Region I Duty Officer, at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on March 12, 1982, and to Mr. D. A. Beckman, the BVPS NRC Resident Inspector, at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on March 15, 1982.

During records update of the analysis required by IE Bulletin 79-14, an overstress condition was found to exist on the "A" Steam Generator main steamline upstream of its isolation valve at monoball support H-2. The failure of this support, which has a safety factor of 3 versus a required safety factor of 4, could result in the loss of secondary coolant to the "A" Steam Generator. This condition has been analyzed in the Final Safety Analysis Report and addressed through emergency procedures.

Required modifications to bring the support to within acceptable limits will be made through Design Change Package (DCP) 305. The work will be completed prior to plant startup.

An o erstress condition has also been determined to exist on the Component Cooling Water line upstream of the "lC" Reactor Plant Component cooling water pump suction isolation valve at supports H-15 and H-16. The f ailure of these supports, which have a safety factor of 2.5 versus a required safety factor of 5.0, could result in the loss of the Component Cooling Water System.

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Mr. R. C. limynes March 15, 1982 Page 2 NDISSI:534 Required modifcations to bring supports H-15 and H-16 to within acceptable limits will be made through DCP 305. The work will be completed prior to startup.

Additional details on the support modifications will be submitted with the fourteen day follow-up reports.

Very truly yours,

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11. P. Williams Station Superintendent ilPW:tav

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, Mr.._R. C._Haynes March 15,'1982-

- Page 3 NDISS1:534 cc: Director Of-Management & Program Analysis United S:ates Nuclear ^ Regulatory Commission Washington, D. C. 20555 J. Hultz, Ohio Edison -

Director, Office of Inspection and Enforcement Headquarters

' United States Nuclear Regulatory Commission' Washington, D. C. 20555 D.- A. Chaney, BVPS Licensing ' Project Manager United States Nuclear Regulatory _ Commission Washington, D. C. 20555

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D. A. Beckman, Nuclear Regulatory Commission, BVPS Site Inspector Mr. Alex Timme, CAPCO Nuclear Projects Coordinator, Toledo Edison Records Center, Institute of Nuclear Power Operations Atlanta, Georgia G. E. Muckle, Factory Mutual Engineering, Pittsburgh

. Arthur Alford, Stone & Webster / Boston Mr. John Alford, PA Public Utilities Commission, Harrisburg, PA

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