05000338/LER-1980-097-03, /03L-0:on 801114,while Operating in Mode 1,LI-1474 Indicated Greater than 5% Higher than Average of Three Channels.Caused by High Transmitter Output,Due to Leaking Isolation Valve.Valves Furmanited.Channel Check Performed

/03L-0:on 801114,while Operating in Mode 1,LI-1474 Indicated Greater than 5% Higher than Average of Three Channels.Caused by High Transmitter Output,Due to Leaking Isolation Valve.Valves Furmanited.Channel Check Performed

ML20002B075
Person / Time
Site:	North Anna
Issue date:	12/03/1980
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20002B068	List: 05000338/LER-1980-097, Forwards LER 80-097/03L-0 05000338/LER-1980-097-03, /03L-0:on 801114,while Operating in Mode 1,LI-1474 Indicated Greater than 5% Higher than Average of Three Channels.Caused by High Transmitter Output,Due to Leaking Isolation Valve.Valves Furmanited.Channel Check Performed
References
LER-80-097-03L, LER-80-97-3L, NUDOCS 8012090408
Download: ML20002B075 (2)

LER-1980-097, /03L-0:on 801114,while Operating in Mode 1,LI-1474 Indicated Greater than 5% Higher than Average of Three Channels.Caused by High Transmitter Output,Due to Leaking Isolation Valve.Valves Furmanited.Channel Check Performed

Event date:
Report date:
3381980097R03 - NRC Website

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d LICENSEE EVENT REPORT

. CONTROL BLOCK / / / / / / / (1)

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 4

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LICENSEE CODE LICENSE NUMBER LICENSE TYPE CAT

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EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (1(;

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On November 14, 1980, while operating in Mode 1, LI-1474 indicated greater than/

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5% higher than the average of the three channels, thereby providing a non-

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conservative reading in the event of a low ' team generator level signal.

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addition, thia non-conservative reading was logged previously and the channet /

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not declared inoperable. Since there were two redundant channels available

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to trip the reactor in the event of a low steam generator level, the health

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and safety of the public were not affected.

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SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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SEQUENTIAL OCCURRENCE REPORT REVISION LER/R0 EVENT YEAR REPORT NO.

CODE TYPE NO.

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ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER j

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CAUSE DESCRIPTION ANE 20RRECTIVE ACTIONS (27)

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The cause of this event was high transmitter output due to a leaking root

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isolation valve. The corrective action was to furmanite the leaking isolation /

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successful, and the chann 1 placed lack in service.

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FACILITY METHOD OF STATUS

% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION (32)

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Operator Observation

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ACTIVITY CONTENT RELEASED

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LOCATION OF RELEASE (36)

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PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (39)

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PERSONNEL INJURIES l

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J LOSS OF.OR DAMAGE TO FACILITY (43)

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I NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151 801209o M

e Virginia Electric and Pow,~ Company North Anna Power Station, Uni t 1

Attachment:

Page 1 of I Docker No. 50-338 Report No. LER 80-097/03L-0

Description of Event

On November 14, 1980 while operating in Mode 1, it was discovered that LI-1474, Steam Generator Level Channel 1 - Protection, was indicat-ing >5% higher than the average of the three channels, thereby providing a non-conservative reading in the event of a low steam generator level.

In addition, the non-conservative channel was logged twice previously without the affected channel being declared inoperable and placed in trip within one hour. This event is applicable to T.S. 3.3.1.1 and reportable pursuant to T.S. 6.9.1.9.a,c.

Probable Consequences of Occurrence Since there were two redundant channels available to trip the reactor in the event of a low steam generator level, the health and safety of the public were not affected.

Cause of Event

1-FW-LT-1474, Steam Generator Level Channel 1 - Protection, indicat-ed 5% greater than the average of the three channels due to a transmitter with excessive high outpu'. caused by a steam leak on the root isolation valve.

Immediate Corrective Action

Within one hour after discovering that the affected channel had been out of spec for the last 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, a channel calibration check was performed and c.he affected channel declared inoperable, and placed in trip.

Subsequent to being placed in trip, the transmitter was found to have an abnormally high outpet due to a steam leak on a root isslation valve.

The transmitter was isolated and the valve furmanited to seal the leak. The channel was returned to operation and a comparative channel check was successfully performed. The affe *ed channel was then declared operable and returned to service.

Scheduled Corrective Action There was no scheduled corrective action.

Actions Taken to Prevent Reccurrence All personnel involved in the incident were counseled on the impor-tance of carefully reviewing data from all logs for acceptability. No further corrective action was required.

Generic Implications There are no generic implications.