ML20086J037
| ML20086J037 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/11/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086J040 | List: |
| References | |
| AO-75-8, NUDOCS 8401230065 | |
| Download: ML20086J037 (2) | |
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l February 11, 1975 Mr. A. Giambusso Director, Division of Reactor Licensing Office of Nuclear Reactor Regulations United States Nuclear Regulatory Commission Wa shi ng ton, D.C.
20555
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, N.R.C. Region 1 Office of Inspection and Enforcement on February 2, 1975. Written notification was made to Mr. James P. O'Reilly, Region 1 Office of Inspection and Enforcement on February 3,1975.
In accordance wi th Section 6.7.2.A of the Technical Speci fica tions, Appendix A of DPR-56 for Unit 3 Peach Bottom Atomic Power Station, the following report is being submitted to the Directoraie of Reactor Licensing as an Abnormal Occurrence:
Reference:
License Number DPR-56 Technical Specification Reference 4.7.A.2.f Report No.
50-278-75-8 Report Date:
February 11, 1975 Occurrence Date: February 1, 1975 Faci li ty:
Peach Bottom Atomic Power Station R.D. ni, Delta, Pennsylvania 17314 Identification of Occurrence:
Excessive leakage of RCIC inboard steam supply valve (MO Conditions Prior to Occurrence:
Unit 3 shutdown for piping inspection.
Description of Occurrence:
During a routine local leak rate test of the RCIC steam supply valves, MO-3-13-15 indicated a leakage in excess of 2000 cc/ min.
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February 11, 1975 Page 2 4
Designation of Apparent Cause of Occurrence:
Worn packing.
Analysi s of Occurrence:
The safety implications of this occurrence are minimal since the outer isolation valve, M0-3-13-16 was found to leak no more than 120cc/ minute.
Corrective Action:
The valve was repacked.
Local leak rate testing was per-formed following the repacking and indicated a negligible leak rate.
Failure Data:
A previous failure of this type was reported as Abnormal Occurrence Report number 50-277-75-7.
Very truly yours, 7,w M.
. Cooney Asst. Gen 1. Superintendent Generation Division cc: Mr. James P. O'Reilly Director Office of Inspection and Enforcement Region 1 United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
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