ML20063K564

Forwards LERs 82-075/03l-0,82-078/03l & 82-081/03l-0. Detailed Event Analyses Submitted

ML20063K564
Person / Time
Site:	San Onofre
Issue date:	08/27/1982
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20063K569	List: ML20063K564
References
NUDOCS 8209080110
Download: ML20063K564 (2)

Text

_ _ _ _ . . . .

f'}

o

, ..~

Southern California Edison Company a' .

&=

F S AN ONOF R E NUC LE A R GE NER A TING S T A TION P .O . M O R 128 S A N C LEMEN T E. C A LIFORNI A 92672 l

H. B. R A Y intspooNE

"^" " " ^ " ^ "

August 27, 1982 " " ' ' " " "

U. S. Nuclear Regulatory Conmission Office of Inspection and Enforcement Region V 1450 hbria Lane, Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. R. H. Engelken, Regional Administrator

Subject:

Docket No. 50-361 30-Day Reports Licensee Event Report No.82-075, 82-078 and 82-081 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 three (3) reportable conditions involving Limiting Condition for Operation (LCO) 3.3.1 associated with the Reactor Protection System (RPS). Completed LER's82-075, 82-078 and 82-081 are enclosed.

As a result of Technical Specification surveillance testing in Mode 2, the following RPS channels were deceared inoperable and subsequently returned to service.

On July 27, 1982 Channel A Local Power Density (LPD) did not function properly during testing and was declared to be inoperable.

On J u l y 31, 1982 Channel A Departure from Nucleate Boiling Ratio (DNBR),

Channel C DNBR and Channel C LPD likewise f ailed to test out properly and were declared to be inoperable.

On August 8, 1982 Channel A DNBR was returned to service. Channel C DNE'.R and LPD were returned to service on August 9, and Channel A LPD was res tored to service on August 18, 1982.

Technical Specification Table 3.3-1 Action Statements 2 and 3 were implemented as appropriate throughout these events.

8209080110 920827 PDR ADOCK 05000361

[b8/

e S PDR O2-M(

. . . . .m #

R. H. Engelken August 27, 1982 The causes of these failures included the fact that a Channel A RTD (feeds DNBR), a Channel C temperature transmitter (feeds DNBR and LPD),

and a Channel A bar graph display module (displays LPD) failed. These were repaired / replaced as necessary to restore the channels as identified above.

During this period a minumum of "one-out-of-two" trip logic was retained hence, there was no impact on health and safety of plant personnel or the public.

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

Sincerely,

//,

Enclosure:

LER No.82-075, 82-078 and 82-081 cc: A. E. Chaffee (USNRC Resident inspector, San Onofre Unit 2)

U. S. Nuclear Regulatory Commission Office of inspection and Enforcement U. S. Nuclear Regulatory Commission Of fice of Management information and Program Control Institute of Nuclear Power Operations