ML20086H052
| ML20086H052 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/07/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H055 | List: |
| References | |
| AO-75-71, NUDOCS 8401130374 | |
| Download: ML20086H052 (2) | |
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PHILADELPHIA ELECTRIC COMPANY.M.7f),
g 4-gr 2301 MARKET STREET
'[g1g PHILADELPHIA. PA.19101 4
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November 7,1973 g
Mr. Roger S. Boyd, Acting Director Division of Reactor Licensing Office of Nuclear Reactor Regulations United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Boyd:
Subiect: Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, Region 1, Office of Inspection and Enforcement, Uni ted Sta tes Nuclear Regulatory Commission, on October 30, 1975. ' Written notification was made to Mr. James P. O'Reilly, Office of ' Inspection and Enforcement, Region 1, United States tJucicar Regulatory Commission on October 31, 1975 In accordance wi th Section 6.7.2.A of the Technical Specifica-tions, Appendix A of DPR-56 for Unit 3 Peach Bottom Atomic Power Station, the following report is being submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-56 Technical Specification
Reference:
4.7.D.1 Report No.:
50-278-75-71 Report Date:
November 7,1975 Occurrence Date: October 30, 1975 Faci li ty:
Peach Bottom Atomic Power Station R.D. #1, Del ta, Pennsylvania 17314 Identification or Occurrence:
Failure of the drywell 02 Analyzer ' Sample System Outer Isolation Valve (SV-39788).
Conditions Prior to Occurrence:
Uni t 3 at 56% power.
Description of Occurrence:
4 During a routine surveillance test this outboard isolation valve failed to fully close.
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v Mr. Roger S. Boyd 50-278-75-71 November 7,1975 Page 2 Designetion of Apparent Cause of Occu rence:
Disassembly of the valve revealed dirt on the seat and in the body uf the valve, preventing tight seating.
Analysi s of Occurrence:
The safety implication of this occurrence is minimal, be-cause the inner isolation valve SV-3671B was found to operate satisfactorily.
In addition, the upstream manual isolation valve was closed until the valve was repaired and retested.
Corrective Action:
The valve internals and seat were c1 caned. The valve disc, piston rings, and bonnet 0-ring were replaced. The valve was leak tested and f ound satisf actory.
Failure Data:
Similar failures were reported as Abnormal Occurrence Report 50-278-75-11 and also on November 9,1973 Very truly yours,
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JL&)L (y-M. p. Cooney Superintendent Generation Division - Nuclear cc:
Mr. J. P. O'Reilly Director, Region i Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 r
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