05000361/LER-1982-118, Forwards LER 82-118/03L-0.Detailed Event Analysis Submitted

Forwards LER 82-118/03L-0.Detailed Event Analysis Submitted

ML20069J408
Person / Time
Site:	San Onofre
Issue date:	10/15/1982
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20069J409	List: 05000361/LER-1982-118, Forwards LER 82-118/03L-0.Detailed Event Analysis Submitted 05000361/LER-1982-118-03, /03L-0:on 820917,low Nitrogen Actuator Pressure Discovered in Steam Generator Feedwater Isolation Valve 2HV-4052.Caused by Leakage at Plug to Check Valve Located on Accumulator.Temporary Instrument Valve Installed
References
NUDOCS 8210250137
Download: ML20069J408 (2)

LER-1982-118, Forwards LER 82-118/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
3611982118R00 - NRC Website

text

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4 Southern California Ea'ison Company ; ~ ;.

55 5 AN ONOFR E NUC L C AR GE NE R A T tNG S T A TION PO.904 128 5 4*. C L EME N T E. C A LIF C A NI A 92672 H. S. R A Y tt.tenomt natio~=a~aaca October 15, 1982 m.i.n "a U. S. Nuclear Regulatery 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-Cay Repcri Licensee Event Report No.82-118 San Onofre Nuclear Generating Station, Unit 2 This submittal is in acccrdance with the reporting requirements of Section 6.9.1.13b of Appendix A to Facility Operating License NPF-10.

It describes a reportable ccndition involving Limiting Condition for Operation (LCO) 3.6.3 associated with containment isolation valves. A completed copy of LER 82-118 is enclosed.

On September 17, 1982, while in Mode 2 during routine operator inspection, steam generator feedwater Isolation valve 2HV 4052 was observed to have low nitrogen actuatcr pressure. The valve was declared inoperable at 1800 and LCO 3.6.3 Action Statement b was initiated. As required by this Action Statement, the penetration was isolated by shutting redundant valve 2HV-4051.

Subsequent investigation revealed that the trouble was due to nitrogen leakage at the plug to the check valve located on the nitrogen accumulator.

This prevented the accumulator trom holding the required nitrogen pressure with the valve fully closed. After installing a temporary instrument valve at this plug, and re-charging the actuator to the required nitrogen pressure, the valve was declared operable in accordance with SO23-3-3.31 at 2140 on September 17, 1982. Repair of the check valve will be completed during the next cutage of extended duration. This failure was an isolated occurrence and no f urther corrective action is warranted.

8210250137 821015 PDR ADOCK 05000361 M-Q O

PDR 8:L -255 8'

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O R. H. Engelken October 15, 1982 Since the penetration was isolated by securing the redundant valve in the closed position, there was no impact on health and safety of plant personnel or the public.

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

Sincerely, lj

&Vf Enclosure: LER 82-118 cc:

A. E. Chaf fee (USNRC Resident inspector, San Onof re Unit 2)

U. S. Nuclear Regulatory Commission Of fice of Inspection and Enforcement U. S. Nuclear Regulatory Commission Office of P.unagement Information & Program Control Institute of Nuclear Power Operations