ML20086G006
| ML20086G006 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/27/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086G009 | List: |
| References | |
| AO-75-57, NUDOCS 8401090787 | |
| Download: ML20086G006 (2) | |
Text
Q O
v V
j O
PHILADELPHIA ELECTRIC' COMPANY 2301 MARKET STREET PHILADELPHIA PA.19101 12151 841 4o00 August 27, 1975 u,
JI Mr. Roger S. Boyd
(
. c.
Acting Director Division of Reactor Licensing Office of Nuclear Reactor Regulations United States Nuclear Regulatory Commission
~
Washington, DC 20555
Dear Mr. Boyd:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Jim Partlow, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission on August 17, 1975. Written notification was made to Mr. James P. O'Reilly, Office of Inspection and Enforcement, Region 1 United States Nuclear Regulatory Commission on August 18, 1975 In accor-dance 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.
Re ference : License Number DPR-44 Technical Specification
Reference:
3.7.D.2, Table 3.7.1 Report No.:
50-277-75-57 Report Date:
August 27, 1975 Occurrence Date: August 17, 1975 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrencc:
Reactor Recirculation System Outboard Sample Isolation Valve, A0-2-2-40 failure to close during test.
Conditions Prior to Occurrence:
Unit 2 reactor shutdown.
Description of Occurrence:
i During the performance of ST 1.3, the PCIS Logic System Functional t
Test, valve A0-2-2-40 failed to close.
8401090787 750827 297
/
PDR ADOCK 05000277
$' PY SENTREGION iw
/
S PDR h
^
g 50-277-75-57 l
Mr. R. S. Boyd *
' August 27, 1975 ()
()
P:ga 2 Designation of Apparent Cause of Occurrence:
Stuck aolenoid valve.
Analysis of Occurrence:
The safety significance of this occurrence is minimal because the inboard isolation valve A0-2-2-39 was found to close satisfactorily, i
Corrective Action:
The solenoid valve was disassembled and cleaned. The valve was retested satisfactorily after repair. In the interim, the inboard isolation valve A0-2-2-39 was maintained closed.
t Failure Data:
Previous failures of this type were reported as: A0-50-227-75-14, and A0-50-278-74-23.
Very truly yours, h ((Cf bL
(%
M. J. Cooney Ass't Gen't Superintendent Generation Division P
cc: Mr. J. P. O'Reilly Director, Region 1 Office of Inspection and Enforcement United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 i
9 0
1 e
4 l
4
.L