05000311/LER-1982-061, Forwards LER 82-061/03X-1.Detailed Event Analysis Encl

Forwards LER 82-061/03X-1.Detailed Event Analysis Encl

ML20063N823
Person / Time
Site:	Salem
Issue date:	09/22/1982
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20063N824	List: 05000311/LER-1982-061, Forwards LER 82-061/03X-1.Detailed Event Analysis Encl 05000311/LER-1982-061-03, /03X-1:on 820716,steam Generator Level Channel II Indication Erratic.Caused by Leakage Past Packing on Root Valve 21BF28.Valve Repacked & Leakage Stopped
References
NUDOCS 8210070254
Download: ML20063N823 (3)

LER-1982-061, Forwards LER 82-061/03X-1.Detailed Event Analysis Encl

Event date:
Report date:
3111982061R00 - NRC Website

text

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' 'O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station September 22, 1982 Mr.

R.

C. Haynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-061/03X-1 SUPPLEMENTAL REPORT Pursuant to the requirements of Salem Generating Station Unit No. 2 Technical Specifications, Section 6.9.1.9.b, we are submitting supplemental Licensee Event Report for Reportable Occurrence 82-061/03X-1.

Sincerely yours,

,vv H.

J. Midura General Manager -

Salem Operations RF:ks d

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Distribution i

('B210070254 820922'

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The Energy People 95 2189 COM) 1181

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82-061/03X-1 Report Date:

09-22-82 Occurrence Date:

07-16-82 Facility:

Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

No. 21 Steam Generator Level Channel II Instrument - Inoperable.

This report was initiated by Incident Report 82-182.

CONDITIONS PRIOR TO OCCURRENCE:

LMode I - Rx Power 83% - Unit Load 900 MWe.

DESCRIPTION OF OCCURRENCE:

At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, July 16, 1982, during routine operation, the Control Room Operator noticed that No. 21 Steam Generator Level Channel II indication was erratic.

The channel.was declared inoperable, and Limiting Conditions for Operation 3.3.1 Action 7 and 3.3.2 Action 14 were entered.

All bistables associated with the channel were immediately placed in the tripped condition.

The redundant channels were operable through-out the occurrence.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The erratic operation of the instrument was due to leakage past the packing on Root Valve.21BF28.

The resulting variations in sensing line pressure caused the level indication to drift.

ANALYSIS OF OCCURRENCE:

The steam generator level channel II instruments are utilized in'the Reactor Trip and' Engineered Safety Feature Actuation Systems.

A reactor trip resulting from a low steam generator level insures a minimum DNBR of 1,30 during normal operation and' anticipated transients.

Automatic initiation of-auxiliary feedwater-insures thag the Reactor Coolant System can be cooled down to less than.350 F in the event of a total' loss of offsite power.

Due to.the operability of the redundant channels, no risk to the health or' safety of the public was involved.

The occurrence constituted operation in a degraded mode permitted by a-limiting condition for operation and is reportable in accordance with Technical Specification 6.9.1.9.b.

LER 82-061/03X-1,

• t, ANALYSIS OF OCCURRENCE:Limiting Conditions for Operation 3.3.1 Action 7 and 3.3.2 Action 14 requires:

With the number of operable channels one less than the total number of channels, power operation may proceed until performance of the next required channel functional test, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

CORRECTIVE ACTION

As noted, the bistables associated with the instrument were placed in the tripped condition.

The root valve was repacked and the leakage was stopped.

The channel was recalibrated and was returned to service.

No. 21 S/G Level Channel II was declared operable, and Limiting Conditions for Operation 3.3.1 Action 7 and 3.3.2 Action 14 were terminated at 0807 hours0.00934 days <br />0.224 hours <br />0.00133 weeks <br />3.070635e-4 months <br />, July 18, 1982.

FAILURE DATA:

No. 21 S/G Level Channel II instrument had failed twice previously on February 9 and February 19, 1982 (see LER's82-012 and 82-014);

the failures were apparently unrelated.

Rockwell-International 3/4" Globe Valve Type 3624, Mark FA-99 Prepared By R.

Frahm

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Ge(eraf Manager -

Salem Operations SORC Meeting No.

82-85