05000361/LER-1982-158, Forwards LER 82-158/03L-0.Detailed Event Analysis Submitted

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Forwards LER 82-158/03L-0.Detailed Event Analysis Submitted
ML20064J074
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 12/20/1982
From: Ray H
SOUTHERN CALIFORNIA EDISON CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20064J077 List:
References
NUDOCS 8301170494
Download: ML20064J074 (2)


LER-1982-158, Forwards LER 82-158/03L-0.Detailed Event Analysis Submitted
Event date:
Report date:
3611982158R00 - NRC Website

text

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December 20, 1982 U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596-5368 Attention:

Mr. R. H. Engelken, Regional Administrator

Dear Sir:

Subject:

Docket No. 50-361 30-Day Report Licensee Event Report No.82-158 San Onofre Nuclear Generating Station, Unit 2 This submittal is in accordance with the reporting requirements of Section 6.9.1.13b of Appendix A to Facility Operating License NPF-10.

It describes a reportable occurrence involving Limiting Condition for Operation (LCO) 3.4.5.2 associated with Reactor Coolant System (RCS) operational leakage. A completed copy of LER 82-158 is enclosed.

On December 2,1982 at 1430, while in Mode 1 during surveillance testing in accordance with S023-3-3.37, the RCS water inventory balance indicated 1.91 gpm unidentified leakage, exceeding LC0 3.4.5.2b and invoking Action Statement b.

As required by this Action Statement, the leakage was reduced to within limits by isolating Chemical and Volume Control System (CVCS) charging pump P-192 at 1504 on December 2,1982. A second RCS water inventory balance completed at 173b on the same day indicated a total leakage of 0.4 gpm.

Subsequent investigation revealed that the CVCS charging pump leak was a result of excessive plunger wear. After replacing the plungers and other pump internals, the pump was restored to operable status on December 7, 1982. This was an isolated occurrence and no further corrective action is warranted.

8301170494 821220 PDR ADOCK 05000361 S

PDR 3 - 12, 82-44

r R. H. Engelken December 20, 1982 The leakage was identified and reduced to within limits in the allowable time constraints, hence there was no impact on plant operation or the health and safety of plant personnel or the public.

If there are any questions regarding the above, please contact me.

i Sincerely, H6F<7 /ruhn4 Enclosure: LER 82-158 A. E. Chaffee (USNRC Resident Inspector, San Onofre Unit 2) cc:

U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Office of Management Information and Program Control Institute of Nuclear Power Operations i

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