ML13330A798
| ML13330A798 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/27/1979 |
| From: | Curran J Southern California Edison Co |
| To: | |
| References | |
| IEB-79-14, NUDOCS 7912030176 | |
| Download: ML13330A798 (2) | |
Text
REGULATORY *ORMATION DISTRIBUTION SYSAM (RIDS)
ACCESSION NBR:7912030176 DOCDATE: 79/11/27 NOTARIZED: NO DOCKET #
PACIL:50-206 San Onofre Nuclear Station, Unit 1, Southern Californ 05000206 AUTHNAME AUTHOR AFFILIATION CURRANJM.
Southern California Edison Co, RECIPNAME RECIPIENT AFFILIATION ENGELKENRH, Region 5, San Francisco, Office of the Director
SUBJECT:
RO-791127:on 791127,as result of insp per IE Bulletin 79-14, missing valve operator support & incorrectly installed valve operator support identified for valve CV-528 on Line 2014-3 inch*151R seal water return line.Problem corrected.
DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR.IENCL J0 SIZE:
TITLE: Incident Reports NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODENAME LTTR ENCL ID CODE/NAME LtTR ENCL ACTION:
05 BC 4
INTERNAL: 0
-FILE 1
.02 NRC PDR 1
09 I&E 2
11 MPA 3
14 TA/EDO 1
15 NUVAK/KNIEL 1
16 EEb 1
17 AD FOR ENGR 1
18 PLANT SYS BR 1
19 I&C SYS BR I
20 AD PLANTISYS 1
22 REAC SAFT BR 1
23 ENGR BR 1
24 KREGER I
25 PWR SYS BR 1
26 AD/SITE ANAL 1
27 OPERA LIC BR 1
28 ACDENT ANLYS 1
29 AUX SYS BR 1
E JORDAN/IE 1
HANAUER,1.
I 1
STS GROUP LEADR 1
TMl-tlSTREET 1
1 EXTERNAL: 03 LPDR 1
04 NSIC 1
29 ACRS 16 11 TOTAL NUMBER OF COPIES REQUIRED: LTTR
-4 ENCL w r'
41.0. sC* too November 27, 1979
,44v U. S. Nuclear Regulatory Commission Region V Office of Inspection and Enforcement Suite 202, Walnut Creek Plaza Walnut Creek, Calffornia 94596 Attention: Mr. R. H. Engelken Director DOCKET No.60-206 4!6 SAN ONOFRE - UNIT 1
Dear Sir:
This letter describes a reportable occurrence as defined in Section 6.9.2 of Appendix A to the Provisional Operating License DPR-13.
In accordance with E Bulletin 79-14 a field verification/inspectlon was conducted on line 2014-316-151R. the seal water return ifne. As a result of this Inspection, a missing valve operator support and an incorrectly installed valve operator support were identified for valve CV-528. The subject valve is a remote manual valve providing containment isolation. As required by the Bulletin a two day engineering evaluation was undertaken to determ~ine the operability of the system following a seismic event.
The evaluation results indicate that the-system will be stressed above code allowable stresses. As indicated to your office these supports were properly installed concurrent with the engineering evaluation and the conf iguration, now conforms to the seismic analysis input Information..
A complete report on this matter together with a Licensee Event Report will be forwarded within two weeks.
Sincerely, V6 Curran Plant Manager 7A20dh 7exsose '7