ML20086H992
| ML20086H992 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/18/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| References | |
| AO-75-25, NUDOCS 8401230033 | |
| Download: ML20086H992 (2) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 4.,
2301 MARKET STREET
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PHILADELPHI A. PA.19101
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(2151 e414000 Nih!1 April 18, 1975 Mr. A. Giambusso Director.
Division of Reactor Licensing Office of Nuclear Reactor Operations tinited States Nuclear Regulatory Commission Washington, DC 20555
Dear hr. Giambusso:
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 A,n'- i l 11, 1975 In en 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()
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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:
None previous.
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Very truly yours, y,.
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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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