ML20086H897
| ML20086H897 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/22/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| References | |
| AO-75-33, NUDOCS 8401200319 | |
| Download: ML20086H897 (2) | |
Text
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9 RHILADELPHIA ELECTRIC COMPANY l
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2301 MARKET STREET y
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9 (215) 8414ooo N
May 22, 1975 Mr. A. Giambusso, Di rector Division of Reactor Licensing Office of Nuclear Reactor Regulations United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Wal t Baunack, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Comission on May 13, 1975. Wri tten noti fication was made to Mr. James P. O'Reilly, Office of Inspection and Enforcement, Region 1, United States Nuclear Regulatory Comission on May 13, 1975. In accordance wi th Section 6.7.2.A of the Technical Specifications, Appendix A of DPR-44 for Unit 2 Peach Bottom Atomic Power Station, the following occurrence 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.:
50-277-75-33 Report Data:
May 22, 1975 Occurrence Date: May 12, 1975 Faci li ty:
Peach Bottom Atomic Power Station R.D. #1, Delta, Pennsylvania 17314 Identi fica tion of Occurrence:
Excessive leakage of 1" 276Y check valve f rom penetration N-22.
Condi tions Prior to Occurrence:
Unit 2 at approximately 100% power.
Description of Occurrence:
During local leak rate testing of the
'A' Instrument Nitrogen Header Isolation Valves, the outboard check isolation valve was found toleakinexcessof2000cc/ min.
8401200319 750322 PDR ADOCK 05000277 s
pDR 77 1
.1
4 Mr. A. Giambusso 50-277-75-33
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-May 22, 1975 Page 2 Designation of Apparent Cause of Occurrence:
The cause of this leakage is under investigation.
Analysis of Occurrence:
The safety implication of this occurrence is minimal because the upstream control valve A0-2969A was found to operate satisfactorily and be leak tight. This valve has been closed to preclude any leakage.
Corrective Action:
This valve will be disassembled, repaired or replaced, and -
retested during the present outage.
Failure Data:
^
Report 50-277-75-25.
Very truly yours, m
M.
. Cooney-A st. Geni. Superintendent-Generation Division cc:
Mr. James P. O'Rei lly, Di rector Office of Inspection and Enforcement, Region 1 Uni ted States Nuciaar_ Regulatory Commission 7
631 Park Avenue 7
- King of Prussia, PA 19406
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