ML20086H075
| ML20086H075 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/31/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H079 | List: |
| References | |
| AO-75-68, NUDOCS 8401130401 | |
| Download: ML20086H075 (2) | |
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U PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET 9
PHILADELPHI A. PA.19101
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October 31, 1975
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Mr. Roger S. Boyd DS d
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Dear Mr. Boyd:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, Region i, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission on October 21, 1975 Written notification was made to Mr. James P. O'Reilly, Office of Inspection and Enforcement, Region 1, United States Nuclear Regulatory Conmission on October 21, 1975 In accordance with Section 6.7 2.A of the Technical Specifications, Appendix A of OPR-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:
Table.3 7 4 Report No.:
50-278-75-68 Report Date:
October 31, 1975 Occurrence Date:
October 21, 1975 Faci li ty:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identif3ation of Occurrence:
Excessive leakage through the nitrogen inerting system drywell purge supply isolation valve A0-3523 - penetration N-25 Conditions Prior to Occurrence:
Reactor at 55% power.
Description of Occurrence:
During local leak rate testing, the torus makeup supply isolation valve A0-3523 was found to leak in excess of 2000 cc/ min.
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f Mr. Roger S. Boyd 50-278-75-68 0' tober 31, i975 Page 2 c
Designation of Apparen_t Cause of Occurrence:
The closing spring of the valve was not providing sufficient force to fully close the valve.
Analysis of Occurrence:
The safety implications of this occurrence are minimal since the manual isolation valve was closed when the leakage was detected.
Corrective Action:
The manual ' isolation valve was verified to be leak tight in the closed condition. The closing spring of the valve was adjusted and the local leak rate test of the valve was repeated. The leak rate of the valve af ter repair was satisf actory.
Failure Data:
Not applicable.
Very truly yours, I.
M.
. Cooney Su intendent Generation Division - Nuclear cc:
Mr. J. P. O'Reilly Director, Region 1 l
Office of Inspection and Enforcement United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 i
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