ML20086H992

AO 75-25:on 750409,excessive Leakage Found of Drywell Oxygen Analyzer Sample Line Check Valve 276Y Found.Caused by Scratch on Valve Seat.Valve Seat & Disc Lapped.Valve Satisfactorily Leak Tested & Returned to Svc

ML20086H992
Person / Time
Site:	Peach Bottom
Issue date:	04/18/1975
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Giambusso A Office of Nuclear Reactor Regulation
References
AO-75-25, NUDOCS 8401230033
Download: ML20086H992 (2)

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PHILADELPHIA ELECTRIC COMPANY '

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2301 MARKET STREET <c.p ,

PHILADELPHI A. PA.19101

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(2151 e414000 April 18, 1975 Nih!1 Mr. A. Giambusso Director.

Division of Reactor Licensing Office of Nuclear Reactor Operations tinited States Nuclear Regulatory Commission Washington, DC 20555

Subject:

Abnormal Occurrence The following occurrence was reported to Mr. Walt Bauneck, Region 1, Office of Inspection and Enforcement, Unitcd States Nuclear Reguletory Commission on April 10, 1975 Written notification was made to Mr. James P. O'Reilly, Region 1, Of fice of Inspection and Enforcement, Uniterf St ates Nise lear Regiealtory Onmmiccinn en A,n'- i l 11, 1975 In accordance with Section 6.7 2.A of the Technical Specifications, Appendix A of DPR-44 for Unit 2 Perch Bottom Atomic Power Station, the following report is being submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.

Reference:

License Number DPR-44 Technical Specification

Reference:

4.7.A.2.f Report No.: 50-277-75-25 Report Date: April 18, 1975 Occurrence Date: April 9, 1975 Facility: Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 i-l Identification of Occurrence:

Excessive leakage of Drywell 02 Analyzer Sample Line check valve (1" - 276Y). ,

Conditions Prior to Occurrence:

Unit 2 at approximately 100% power.

Description of Occurrence:

During a routine local leak rate test of the Drywell 02 Analyzer Sample Isolation Valves, the inboard check isolation valve was fnund to leak in excess of 200 cc/ min.

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Mr.A.Giambus()

April 18, 1975 Paga 2 Desionation of Apparent Cause of Occurrence:

The cause of this leakage was found to be a scratch on the volve seat.

Analysis of Occurrence:

The safety implications of this occurrence are minimal since the downstream isolation valve SV-2960 was found to close and seal satisfactorily.

Corrective Action:

The valve seat and disc were both lapped. The valve was satisfactorily leak tested and returned to service.

Failure Data:

J None previous.

B Very truly yours, y,. )* fa

• M. . Cooney y Ass't Gen'1 Superintendent Generation Division cc: Mr. J. P. O'Reilly, Director Region 1 Office of Inspection and Enforcement U. S. Nucicar Regulatory Cannission 631 Park Avenue King of Prussia, PA 19406 i

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