ML20086K416
| ML20086K416 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/06/1975 |
| From: | Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20086K411 | List: |
| References | |
| AO-75-14, NUDOCS 8401270078 | |
| Download: ML20086K416 (1) | |
Text
-
^
idAm.
r c -%
glLADELPHIAELECTRICCOMPANY O w dath
- WF Feach Bottoss Atoatic Power Station _
\\
Delta, Pennsylvania 17314 Qr. James P. O'Reilly, Director Waited States Atomic Energy Cossaission Ihnelace 2egulatory Constission b31 Park Avenue King of Prussia, Pennsylvania 19405
]_
OuMeet:
Abnormal Occurrence 24 Hour Notification l Confirming W. T. U11 rich's conversation with Mr. Walt Baunack, A.E.C. Region 1
,Nucicer Regulatory Commission on February 6, 1975.
geforance:
License Number VPR-44 Technical Specification
Reference:
3.nii Coport No.:
50-277-75-14 Report Dates February 6, 1975 Occurranc,e Date:
February 5, 1975 Facility:
Fesch Bottom Atomic Power Station R.D. 1. Delta. Pennsylvania 17314 Identification of Occurrence Unit 2 Recirculation System Sample valve, A0-2-39, failure to fully. slose.
Conditions Prior to Occurrence:
Plant at 99.5% power.
3cocription of occurrence Following completion of sampling, the switches for the Recirculation System esmple valves, A0-2-39 and A0-2-40, were placed in the closed position.
It waa cbsorved that the indicating lamps showed the valve A0-2-39 had not fully closed.
Cycling of the valva while observing the flow at the sampling station confirmed that the valve was not fully closing.
De::ignation of ' Apparent Cause of Occurrencer Unknown, but +ould be excessive packing friction.
Analysio of Occurrence:
he safety implication of,this failure is minimal because the other redundant valva in series with AO-2-$9 did fully close and would have isolated if necessary.
Corroctive Actions Further opening and closing of A0-2-39 resulted in stopping flow completely,'but the indicating lamps were still incorrect.
The limit switches for this valve will be inspected during the next outage.
Fcituto Data 8401270078 750215 A0-278-74-23.
PDR ADOCK 05000277 S
PDR Vory truly yours.
NlW~l W. T. Ullrich, superintendent Pcach Botton Atomic Power Station REGULATORY OPERATIONS FILE COPi,