05000361/LER-1982-076, Forwards LER 82-076/03L-0.Detailed Event Analysis Submitted

Forwards LER 82-076/03L-0.Detailed Event Analysis Submitted

ML20064M745
Person / Time
Site:	San Onofre
Issue date:	08/24/1982
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20064M748	List: 05000361/LER-1982-076, Forwards LER 82-076/03L-0.Detailed Event Analysis Submitted
References
NUDOCS 8209080094
Download: ML20064M745 (2)

LER-2082-076, Forwards LER 82-076/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
3612082076R00 - NRC Website

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. Southern California Edison Company  ? jhh 5 AN ONOFRE NUCLE AR GENER A TfMG ST A TION "

v- P .O. B O M 128

• S AN C L EMEN TE. C A LIFORNI A 92672 _

H. B. R AY TELEPHONE Star oN u ANAGE, August 24, 1982 ,,,,,,,,.,,,,

j U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596-5368 i

Attention: Mr. R. H. Engelken, Regional Administrator

Subject:

Docket No. 50-361 30-Day Interim Report Licensee Event Report No.82-076 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 Licence NPF-10.

It describes a reportable condition involving Limiting Condition for

, Operation (LCO) 3.3.1 associated with the Reactor Protection System i

(RPS). A preliminary copy of LER 82-076 is enclosed.

i While in Mode 4, at 1011 on July 25, 1982, the once a shift surveillance in accordance with procedure S023-3-2.25 was in progress. During this survelliance, steam generator AP indicator 2PDI-0979-1 failed to meet the channel check test. Although the Action Statement associated with

LCO 3.3.1 is not applicable in I4)de 4, the steam generator #2 low flow trip for channel A was immediately bypassed, since Mode 2 entry was anticipated within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. LCO 3.3.1 does not prohibit change of modes.

The plant entered Mode 2 at 1349 on July 26, 1982. Upon entering Mode 2, the' Action Staiement associated with LCO 3.3.1 became applicable.

The Action Statement associated with LCO 3.3.1 (Technical Specification Table 3.3-1, Action 2) requires that with the number of operable RPS channels one less than the total number of channels, startup (Mode 2) may continue provided the inoperable channel is placed in the bypassed 4 or tripped condition within I hour. Additionally, the Action Statememt requires that the inoperable channel be returned to operable status no later than during the next cold shutdown.

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.. R. H.-Engelken

- August 24, 1982-The first requirement of the Action' Statement was satisfied when the plant was operating in Mode 4.- The remaining requirement was satisfied on July 31,-1982 when the Indicator was valved back in, tested in accordance with S023-3-3.25 and returned to service.

Upon investigation, it was determined that the Indicator had been valved out. The. valve line-up was corrected and the. indicator restored to an operable status, investigation into the cause of-the incorrect valve line-up is ongoing. A completed LER and final report will be provided as soon as the cause is determined, and in any event, on or about September 30, 1982.

Since the RPS contains 4 channels for reactor coolant low flow indication for each steam generator and only 3 channels (al_1 of which remained functional throughout the event) are required for operability, 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, cc: U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Office of Management Information & Program Control Institute of Nuclear Power Operations A. E. Chaf fee (USNRC Resident inspector, San Onof re Unit 2)