05000361/LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Submitted

Forwards LER 82-048/03L-0.Detailed Event Analysis Submitted

ML20062K825
Person / Time
Site:	San Onofre
Issue date:	08/06/1982
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20062K827	List: 05000361/LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Submitted 05000361/LER-1982-048-03, /03L-0:on 820708,while in Mode 4,containment Airborne Monitor 2RT-7804-1 Declared Inoperable Due to Failure to Meet Surveillance Requirements.Caused by de-energizing of Containment Isolation Valve 2HV-7801
References
NUDOCS 8208180024
Download: ML20062K825 (2)

LER-1982-048, Forwards LER 82-048/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
3611982048R00 - NRC Website

text

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

Mr. R. H. Engelken, Regional Administrator Do::r Cir:

Subject: Docket No. 50-361 30-day Report Licensee Event Report No.82-048 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 condition involving Limiting Condition for Operation (LCO) 3.4.5.1 associated with the Reactor Coolant Leakage Detection System.

A completed copy of LER 82-048 is enclosed.

l While in Mode 4, at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> on July 7, 1982, the monthly safety injection tank operability test was in progress.

Because of an error in the governing procedure (S023-3-3.8), Containment Airborne Monitor 2RT-7804-1 was rendered inoperable. The cause was misidentification of a j'

fuse to be pulled during the tesi. The wrong fuse was pulled and replaced deenergizing valve 2HV-7801 isolating the monitor and tripping the sample pump. The fuse was replaced, but the sample pump' motor was l

not restarted, nor was the monitor reset. The monitor remained in-operable.

Additional tests required by procedures S023-3-3.26 and S023-3-3.21 i-resulted in identification of this condition on July 8,1982 at 0530 i

hours. The alarm was reset, the motor started, and the monitor returned to service.

l During the period of inoperability of 2RT-7804-1 however, redundant t

monitor 2RT-7807-2 was out of service for calibration. As a result, the Action Statement of Section 3.4.5.1 was implemented until 2R-7804-1 was returned to operation.

8208180024 820806 DR-ADOCK05000g g_p

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Mr. R. H. Engelken August 6, 1982 The fuse numbering has been corrected by a change to Surveillance Test Procedure S023-3-3.8.

The inoperability of the monitor 2RT-7804-1 was not annunciated in the Control Room. An engineering study is underway to establish the advisability of adding this annunciation on loss of flow.

There was no irradiated fuel in the core and no containment purging occurred during this event, hence public health and safety were not affected.

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

Sincerely,

/ 8

Enclosure:

LER 82-048 cc:

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

U. S. Nuclear Regulatory Commission Offi:e of Inspection and Enforcement U. S. Nuclear Regulatory Commission Office of Management Inf'.mation & Program Control institute of Nuclear Power Operations