ML20028D956

Forwards LER 82-165/03L-0.Detailed Event Analysis Submitted

ML20028D956
Person / Time
Site:	San Onofre
Issue date:	01/07/1983
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20028D957	List: ML20028D956 ML20028D961
References
NUDOCS 8301200145
Download: ML20028D956 (2)

Text

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l he Southern California Edison Company S AN ONOFRE NUCLE AR GENER A TING ST ATION IS03 4, WE

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P.O. BO X 12 8 i s AN C LEMENTE. C A LIFORNI A 92672 Qf H. 8. R A Y T'tEPHONE

$$r' January 7,1983 l .v AvlON AN Aaca m m m oo i

U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement 4 Region V 1450 Maria Lane, Suite 210 [

l Walnut Creek, California 94596-5368 Attention: Mr. R. H. Engelken

Subject:

Docket No. 50-361 30-Day Report Licensee Event Report No.82-165 San Onofre Nuclear Generating Station, Unit 2 1.

Pursuant to Section 6.9.1.13.b of Appendix A Technical Specification to Facility Operating License NPF-10 for San Onofre Unit 2, this submittal provides the required 30-day written report and copy of Licensee Event Report (LER) for an occurrence involving the snubbers.

On December 9,1982, at 1515 while in Mode 1 and while the piping thermal expansion and vibration verification at the 50% power plateau was in

. progress, it was observed that two snubbers which are components of pipe i support S2-FW-189-H013 were damaged. This pipe support is located imme-

, diately downstream of the main feedwater check valve to Steam Generator i E088 inside the containment at the 63-1/2 foot level. The snubbers were declared inoperable.

l Limiting Condition for Operation (LCO) 3.7.6 requires these snubbers to i be operable in Modes 1 through 4. The Action Statement associated with LC0 3.7.6 requires the inoperable snubbers to be replaced or restored to

! operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and an engineering evaluation to be performed in accordance with Technical Specification Section 4.7.6.g.

We have been unable to identify the exact cause of the damage to the snubbers. The engineering analysis defined by Technical Specification Section 4.7.6.g was completed and it was determined that no adverse effect on the feedwater piping or steam generator resulted from this

, occurrer.ce. The two snubbers were replaced within the allowable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, thus satisfying the Action Statement associated with LC0 3.7.6.

The enclosed LER 82-165 addresses this event. No further corrective actions are planned 'since this was an isolated incident.

4 8301200145 830107

PDR ADOCK 05000361

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Mr. R. H. Engelken January 7,1983 Public health and safety were not affected by this event. If there are any questions regarding the above, please contact me.

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Sincerely, "

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Enclosure:

LER 82-165 cc: A. Chaffee (USNRC Resident Inspector, San Onofre, Units 2 and 3)

R. Pate (USNRC Resident Inspector, San Onofre, Units 2 and 3)

U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission '

Office of Management Information and Program Control (MIPC)

Institute of Nuclear Power Operations (INPO) 1 1

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