05000361/LER-1982-159, Forwards Updated LER 82-159/03L-1.Detailed Event Analysis Submitted

Forwards Updated LER 82-159/03L-1.Detailed Event Analysis Submitted

ML20064M889
Person / Time
Site:	San Onofre
Issue date:	01/31/1983
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20064M892	List: 05000361/LER-1982-159, Forwards Updated LER 82-159/03L-1.Detailed Event Analysis Submitted 05000361/LER-1982-159-03, Pressure Indicator 2PI-8300 for Steam Generator E-088 on Essential Plant Parameter Monitoring Sys Panel 21-411 Read Greater than Similar Indicator on Control Room Panel CR-52.Cause Unknown
References
NUDOCS 8302150674
Download: ML20064M889 (2)

LER-1982-159, Forwards Updated LER 82-159/03L-1.Detailed Event Analysis Submitted

Event date:
Report date:
3611982159R00 - NRC Website

text

.e..a hWO g%SCE Southern California Edison Company S AN ONOFRE NUCLEA R GENER ATING ST A TION pf

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P.O. BO K 12 8 S A N C LEMENT E, C A LIFOR Nf A 92672 7(..

tJ H. B. R AY

. TELEPHONE STATION M AN AGE R (714)492-7700 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.82-159 San Onofre Nuclear Generating Station, Unit 2

Reference:

Letter, H.B. Ray (SCE) to R.E. Engelken (NRC),

dated December 28,1982, "30-Day Follow-Up Report -

Licensee Event Report No.82-159" This letter provides the follow-up to the referenced report which was made in accordance with Section 6.9.1.13.b of Appendix A, Technical Specifications to Facility Operating License NPF-10, for San Onofre Unit 2.

The reported occurrence involved Limiting Condition for Operation (LCO) 3.3.3.5 associated with Remote Shutdown Instrumentation.

As stated in the referenced letter, during performance of the monthly channel check surveillance on November 28, 1982, pressure indicator 2PI-8300 was observed to be reading more than 120 psia greater than a similar indicator located in the Control Room on Panel CR-52. The referenced letter erroneously indicated that 2PI-8300 was located on the Remote Shutdown Panel rather than the correct location on Essential Plant Parameter Monitoring System (EPPMS) panel 2L-411. As a result of the 120 psia discrepancy, 2PI-8300 was declared inoperable.

The indicator was replaced, calibrated and returned to service on November 29, 1982. We have been unsuccessful in determining the cause of the failure. This failure was an isolated occurrence and no further corrective action is planned. A final copy of LER 82-159 is enclosed.

8302150674 830131 gDRADOCK05000 gg b6-L}Q

R. H.

Engelkin January 31, 1983 Since the redundant indicator on Control Room Evacuation Shutdown Panel 2L-042 remained operable and the inoperable indicator was returned to service within the allowable time constraints, 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, H 6Il<y /11 anna Enclosure: LER 82-159 cc:

A. E. Chaffee (USNRC Resident Inspector, San Onofre Units 2 & 3)

R. J. Fate (USNRC Resident Inspector, San Onofre Units 2 & 3)

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