ML20086K553

AO 75-3:on 750115,outboard RHR B Containment Spray Valve MO-2-10-26B Found Leaking.Caused by Small Screatches on Valve Seat & Disc.Scratches on Seat & Disc Removed

ML20086K553
Person / Time
Site:	Peach Bottom
Issue date:	01/25/1975
From:	Meyer R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Giambusso A Office of Nuclear Reactor Regulation
Shared Package
ML20086K556	List: ML20086K553 ML20086K558
References
AO-75-3, NUDOCS 8401270244
Download: ML20086K553 (2)

Text

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PHILADELPHIA ELECTRIC COMPANY '

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, f January 25, 1975 , ^J

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Mr. A. Giambusso Deputy Director of Reactor Projects '

United States Atomic Energy Commission Directorate of Licensing Washington, DC 20545

Subject:

. Abnormal Occurrence ,

The following occurrence was reported to Mr. Don Caphton, A.E.C.

Region 1 Regulatory Operations Office on January 16, 1975 Written noti-fication was made to Mr. James P. O'Reilly, Region 1 Regulatory Operations Office on January 16, 1975.- In accordance witn Section 6.7 2.A of the Technical Specifications, Appendix A of DPR-44 for Unit 2 Peach Bottom Atomic Power Station the followina report is beina submitted to the Directorate of Licensing as an Abnormal Occurrence.

Reference:

License Number DPR-44 Technical Specification

Reference:

4.7.A.2.f Report No.: 59-277-75-3 Report Date: January 25, 1975 Occurrence Date: January 15, 1975 Facility: Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:

Unit 2 outboard RHR 'B' containment spray valve (M0 10-26B) leak.

Conditions Prior to Occurrence:

The reactor was shutdown and a maintenance outage was in prog-ress.

Description of Occurrence:

As a result of performing a local leak rate test, this valve was found to leak.

8401270244 750125 PDR ADOCK 05000277 S PDR SOS

Mr. A. G i ambusso January 25,~1975

'h Page 2 Designation of Apparent Cause of ' Occurrence:

. Inspection of the disassembled valve revealed small scratches on the valve seat and disc.

Analysis of Occurrence:

The other isolation valve in this line was verified to close properly and was lef t in the closed pos.ition. For this reason, the" occurrence has minimal safety implications.

Corrective Action: '

The scratches on the seat and disc were removed. The local leak rate testing was then completed satisfactorily.

Failure Data:

No previous leakage has been reported on this* valve.

Very truly yours, m

[.'h$[ J R . D. Meyer General Superintendent Generation Division cc: Mr. J. P. O'Reilly Director, Region i United States Atomic Energy Commission 631 Park Avenue King of Prussia, PA 19406 6

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