ML20086K520
| ML20086K520 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/29/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20086K523 | List: |
| References | |
| AO-75-7, NUDOCS 8401270193 | |
| Download: ML20086K520 (2) | |
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PHILADELPHIA ELECTRIC COMPANY
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taisi e414ooo January 29, 1975 u
Mr. A. Giambusso Director, Division of Reactor Licensing Office of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Washington, DC 20555-
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. E. J. Brunner, N. R. C. Region 1, Reactor Operations Branch on January 19, 1975 Written notification'was made to Mr. James P. O'Reilly, Region 1,
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Office of Inspection and Enforcement on Januar~y 20, 1975 In accordance with Section 6.7 2.A of the Technical Specifications, Appendix A of DPR-44 for Unit 2 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-44 Technical Specification
Reference:
4.7.A.2.f Repor t No.:
50-277-75-7 Report Date:
January 29, 1975 Occurrence Date:
January 19, 1975 Facility:
Peach Bottom Atomic Power Station R.D.
1, Delta, Pennsylvania 17314
_I_dentification of Occurrence:
Inboard RCIC Steam Supply Valve (M0 13-I S) leaks.
Conditions Prior to Occurrence:
Unit 2 shutdown; a maintenance outage is in progress.
Description of Occurrence:
l-During a routine local leak rate test of the RCIC steam supply valves, M0-2-13-15 was found to leak in excess of 2000 cc/ min.
8401270193 750129 PDR ADOCK 05000277 S
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Mr. A. Giambusso January 29, 1975 Page 2 Designation of Apparent Cause of' Occurrence:
The cause for this increased valve leakage appeared to be the result of two minor surface scratches in the valve seat.
Analysis of Occurrence:
The safety implications of this occurrence are minimal since the outer isolation valve, MO-2-13-16, was found to be leak tight.
Corrective Action:
The valve seat and disc were maintained to remove minor surface scratches. Local leak rate testing after the repair indicated a negligible Icakage rate.
Very truly yours, Q'O {$liefC<,
t M. J. Cooney
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Ass' t Gen' t Superintendent Generation Division i
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Mr. James P. O'Reilly Director o Office of Inspection and Enforcement Region i United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 eh G
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