ML20086H802
| ML20086H802 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/28/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H806 | List: |
| References | |
| AO-75-39, NUDOCS 8401200246 | |
| Download: ML20086H802 (2) | |
Text
,
_~
4
-. -i
)-
I PHILADELPHIA ELECTRIC COMPANY 7{
Q'
/t utbt 2301 MARKET STREET ID JW;2,1975 -
f
,",.{,
55 PHILADELPHI A. PA.19101 n
e..
... a,
h M3d 38#"**
(215)041 4000 May 28, 1975 Mr. A. Giambusso Director Division of Reactor Licensing Office of Nuclear Reactor Regulations United States Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, j
Region 1, Of fice of Inspection and Enf orcement, United States Nuclear l
Regulatory Commission on May 19, 1975 Written notification was made to Mr. James P. O'Reilly, Region 1, Office of Inspection c.nd Enforcement,
[
United States Nuclear Regulatory Commission on May 19, 1975 In accord-ance with Section 6.7 2.A of the Technical Specifications, Ap'pendix 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 OPR-44 Technical Specification
Reference:
4 7.A.2.f Report No.:
50-277-75-39 Report Date:
May 28, 1975 Occurrence Date: May 18, 1975 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence _:
Excessive leakage through the "A" loop RHR inboard and out-beard torus cooling valves (MO-2-10-34A and MO-2-10-39A).
Conditions Prior to Occurrence:
Unit 2 shutdown.
Description of Occurrence:
During a routine local leak test of the RHR A" loop torus cooling valves, valves MO-2-10-34A and M0-2-10-39A were found to leak.
DO O
5907 e
Mr. A. Ciambuss H y 28, 1975 277-75-39 g Page 2 The preliminary test performed, which identified the leak, was with water; later testing with air confirmed the leakage rate to be in excess of 6000 cc/ min.
Designation of Apparent Cause of Occurrence:
Under investigation.
Analysis of Occurrence:
Normal operating pressure of the RHR pumps d.uring the design basis accident is greater than 49.1 psig thereby precluding outleakage into the RHR system.
However, if the containment atmosphere leaked back through these valves, the leakage would enter the RHR systern which is 6 closed system and was tested satisfactorily es part of the Type A ILR T.
Safety implications of this occurrence are therefore minimal.
Corrective Action:
The valves wereedisassembled for inspection and minor seating surface imperfections were observed. The valves will be repaired, re-assembled, and retested as soon as possible.
Failure Data:
None.
Very traly yours,
[,i J !: L (-L l d L
/
/
2t 7
M. J. Cooney g
Ass' t General Superintendent Generation Division cc:
Mr. J. P. 0'Reilly Director, Region 1 Office of Inspection and Enforcement United States Nuclear Regulatory Conmission 631 Park Avenue Ki'ng of Prussia, PA 19406 i