05000362/LER-1982-003, Forwards LER 82-003/03L-0.Detailed Event Analysis Submitted

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Forwards LER 82-003/03L-0.Detailed Event Analysis Submitted
ML20064H626
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 12/27/1982
From: Ray H
SOUTHERN CALIFORNIA EDISON CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20064H631 List:
References
NUDOCS 8301170364
Download: ML20064H626 (2)


LER-2082-003, Forwards LER 82-003/03L-0.Detailed Event Analysis Submitted
Event date:
Report date:
3622082003R00 - NRC Website

text

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Southern California Edison Company 5 AN ONOFRE NUCLE A R GENER A TtNG S T A TION

$5 P .O. B O X 128 S AN C LEMENTE, C ALIFORNI A 92672 H. B. R A Y

.,Ar,oN.ANA... December 27, 1982 , ,";'l," ,' ',,

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. 50-362 30-Day Report Licensee Event Report No.82-003 San Onofre Nuclear Generating Station, Unit 3 This submittal is in accordance with the reporting requirements of Section 6.9.1.13b of Appendix A to Facility Operating License NPF-15.

It describes a reportable occurrence involving Limiting Condition for Operation (LCO) 3.9.2 associated with nuclear instrumentation. A completed copy of LER 82-003 is enclosed.

On November 27,1982, at 1104 with the plant in Mode 6, Channel 2 Startup Monitor 3JI-0006 was observed to have lost visual indication.

The monitor was declared inoperable and LC0 3.9.2 Action statement a was invoked. Since no core alterations or positive reactivity changes were in progress at this time, the requirements of the Action statement were satisfied.

Subsequent investigation revealed that the monitor inoperability was attributable to loss of power. The power to the monitor is provided from 480/120 VAC Distribution Panel 3Q0612 via non-Class lE Motor Control Center (MCC) 3BN. This MCC had been taken out of service for maintenance and testing. The operators did not recognize that one of the startup monitors required by LC0 3.9.2, would be affected. The MCC and the monitor were returned to service at 1622 on November 27, 1982.

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Mr. R. H. Engel ken December 27, 1982 As corrective action to prevent recurrence, responsible Operations personnel have reviewed the circumstances of this event and have been directed to perform a more detailed review of the impact of de-energizing a MCC and its associated loads on plant equipment and instrumentation.

This detailed review will include assessment of the impact on plant equipment for the existing mode and the effect on planned plant mode changes. To facilitate this review, Station Engineering will investigate the information available in the Control Room on loads from the various MCC's and provide additional load listings if needed.

Since the redundant monitor remained operable and no cot e alterations or positive reactivity changes took place during this event, 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.

Sincerely, novy l9%/s

Enclosure:

LER 82-003 cc: A.E. Chaffee (USNRC Resident Inspector, San Onofre, Units 2 and 3)

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

U.S. Nuclear Regulatory Commission Office of Management Information and Program Control (MIPC)

Institute of Nuclear Power Operations (INP0) l l

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