ML20086K553
| ML20086K553 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/25/1975 |
| From: | Meyer R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086K556 | List: |
| References | |
| AO-75-3, NUDOCS 8401270244 | |
| Download: ML20086K553 (2) | |
Text
- _-
0 V
PHILADELPHIA ELECTRIC COMPANY
' l ? h-s,
'[t M
23O1 MARKET STREET
~l;( lYlh \\(b
~
r t[i.]/p*-[O[ ': u Ql
/
PHILADELPHIA, PA.19101
,.w h..
J,. [Q izisi e414ooo a
\\.
~
f January 25, 1975
,.'.l ff '
^J Mr. A. Giambusso Deputy Director of Reactor Projects United States Atomic Energy Commission Directorate of Licensing Washington, DC 20545
Dear Mr. Giambusso:
Subject:
. Abnormal Occurrence The following occurrence was reported to Mr. Don Caphton, A.E.C.
Region 1 Regulatory Operations Office on January 16, 1975 Written noti-fication was made to Mr. James P. O'Reilly, Region 1 Regulatory Operations Office on January 16, 1975.- In accordance witn Section 6.7 2.A of the Technical Specifications, Appendix A of DPR-44 for Unit 2 Peach Bottom Atomic Power Station the followina report is beina submitted to the Directorate of Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-44 Technical Specification
Reference:
4.7.A.2.f Report No.:
59-277-75-3 Report Date:
January 25, 1975 Occurrence Date:
January 15, 1975 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
Unit 2 outboard RHR 'B' containment spray valve (M0 10-26B) leak.
Conditions Prior to Occurrence:
The reactor was shutdown and a maintenance outage was in prog-ress.
Description of Occurrence:
As a result of performing a local leak rate test, this valve was found to leak.
8401270244 750125 PDR ADOCK 05000277 S
PDR SOS
'h Mr. A. G i ambusso January 25,~1975 Page 2 Designation of Apparent Cause of ' Occurrence:
. Inspection of the disassembled valve revealed small scratches on the valve seat and disc.
Analysis of Occurrence:
The other isolation valve in this line was verified to close properly and was lef t in the closed pos.ition. For this reason, the" occurrence has minimal safety implications.
Corrective Action:
The scratches on the seat and disc were removed. The local leak rate testing was then completed satisfactorily.
Failure Data:
No previous leakage has been reported on this* valve.
Very truly yours, m[.'h$[
J R. D. Meyer General Superintendent Generation Division cc:
Mr. J. P. O'Reilly Director, Region i United States Atomic Energy Commission 631 Park Avenue King of Prussia, PA 19406 6
L_m
_1
. _,