05000361/LER-1982-077, Forwards LER 82-077/03L-0.Detailed Event Analysis Submitted

Forwards LER 82-077/03L-0.Detailed Event Analysis Submitted

ML20064M925
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
ML20064M927	List: 05000361/LER-1982-077, Forwards LER 82-077/03L-0.Detailed Event Analysis Submitted 05000361/LER-1982-077-03, /03L-0:on 820725,containment Pressure Indicators 2P1-0351-2 & 2P1-0352-2 Failed Channel Check Test.Caused by Instrument Drift.Indicators Recalibr
References
NUDOCS 8209080157
Download: ML20064M925 (2)

LER-1982-077, Forwards LER 82-077/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
3611982077R00 - NRC Website

text

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t S AN ONOF RE NUCLE AR GENER A TING S T A TION P.O. B O X 128 S A N C LEMEN T E. C A LIFORNI A 92672 H. B. R A Y veteenOur sv a riON = ANa*'"

August 24, 1982

""'"2-"*a 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 S i r:

Subject:

Docket No. 50-361 30-Day Peport Licensee Event Report No.82-077 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 Conditions for Operation ( LCO) 3.3.1 and 3.3.2 associated with the Reactor Protection System (RPS) and the Engineered Safety Feature Actuation System (ESFAS),

respectively.

The RPS and ESFAS form the Plant Protection System (PPS).

A completed copy of LER 82-077 is enclosed.

While in hbde 4, at 0445 on July 25, 1982, the once a shift surveillance in accordance with procedure S023-3-3.25 was in progress.

During this surveillance, containment pressure indicators 2PI-0351-2 (channel B narrow range) and 2PI-0352-2 (channel B wide range) failed to meet the channel check tests. Although the Action Statements associated with LCO's 3.3.1 and 3.3.2 are not applicable in Mode 4, the high containment pressure trips and the high-high containment pressure trip of the PPS were bypassed immediately, since hbde 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's 3.3.1 and 3.3.2 do not prohibit change of modes.

8209080157 820824 gDRADOCK05000

,y 712-301

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R.-H. Engelken-August 24, 1982 The plant entered Mode 2 at 1349 on July 26, 1982. _ Upon entering Mode 2, the-Action Statements associated with'LCO's 3.3.1 and 3.3.2 became applicable. -The Action Statements associated with both LCO's 3.3.1 (Technical Spectfication Table 3.3-1, Action 2) and 3.3.2 (Technical Specification Table 3.3-3, Action 9) require that with the number of operable RPS or ESFAS channels one less than the total number of channels, startup (Mode 2) may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Additionally, these Action Statements require that the inoperable channel be returned to operable status no later than during the next cold shutdown.

The first requirement of the Action Statements was satisfied when the plant was operating in Mode 4.

The remaining requirement was satisfied on July 30, 1982 when the indicators were recalibrated, tested in accordance with S023-3.3.25 and returned to service.

Investigation into the cause of indicator inoperability resulted in the conclusion that the failed channel checks are attributable to normal Instrument drif t.

Since the indicators were recalibrated and returned to service, further corrective action is not deemed necessary.

Since the RPS and ESFAS contain 4 channels for containment pressure indication and only 3 channels (all of which remained functional through-out 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, d

Enclosure:

LER 82-077 A. E. Chaffee (USNRC Resident inspector, San Onofre Unit 2) 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