05000339/LER-1980-040-03, /03L-0:on 800723,during Mode 3 Operation,Primary Containment Structure Temp Exceeded Tech Spec Limit.Caused by Temporary Loss of Component Cooling Water Flow to Shroud Cooler.Cooling Valve Reopened & Flow Restored

/03L-0:on 800723,during Mode 3 Operation,Primary Containment Structure Temp Exceeded Tech Spec Limit.Caused by Temporary Loss of Component Cooling Water Flow to Shroud Cooler.Cooling Valve Reopened & Flow Restored

ML19344A456
Person / Time
Site:	North Anna
Issue date:	08/14/1980
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19344A453	List: 05000339/LER-1980-040, Forwards LER 80-040/03L-0 05000339/LER-1980-040-03, /03L-0:on 800723,during Mode 3 Operation,Primary Containment Structure Temp Exceeded Tech Spec Limit.Caused by Temporary Loss of Component Cooling Water Flow to Shroud Cooler.Cooling Valve Reopened & Flow Restored
References
LER-80-040-03L-01, LER-80-40-3L-1, NUDOCS 8008200370
Download: ML19344A456 (2)

LER-1980-040, /03L-0:on 800723,during Mode 3 Operation,Primary Containment Structure Temp Exceeded Tech Spec Limit.Caused by Temporary Loss of Component Cooling Water Flow to Shroud Cooler.Cooling Valve Reopened & Flow Restored

Event date:
Report date:
3391980040R03 - NRC Website

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wO U.S. NUCLEAR REGULATORY COMfISSION LICENSEE EVENT REPORT C0hTROL BLOCK / / / / / / / (1)

(PLEASE PRINT OR TYPE ALL REQUIRED IhTORMATION)

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DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10) g/2],

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On July 23, 1980, during Mode 3 operation, the temperature within the primary /

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containment structure exceeded the Technical Specification limit of 105'F.

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Because the containment average air temperature was restored to allowable

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limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the health and safety of the general public were not

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affected. This event is reportable pursuant to T.S. 6.9.1.9.b.

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SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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

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ACTION FUTURE EFFECT SHUTDOWN ATTACHMEh7 NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANLTACTURER

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

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Containment temperature exceeded the upper limit due to temporary loss of

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component cooling water flow to the "B" shroud cooling coil. This occurred

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when containment isolation valve TV-CC204B was isolated to repair an air leak /

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on the valve.

Corrective action was to restore flow to the shroud cooler by

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reopening the component cooling valve.

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FACILITY METHOD OF STATUS

% POWER OTHER STATUS DISCOVERY DESCRIPTION (32)

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LOCATION OF RELEASE (36)

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PUBLICITY ISSUED DESCRIPTION (45)

NRC USE ONLY

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NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151 80082003JD

Virginia Electric and Power Company North Anna Power Station, Unit #2 Attachment: Page 1 of 1 Docket No. 50-339 Report No. LER 80-040/03L-0

Description of Event

On July 23, 1980, with the unit in a hot standby condition, the average air temperature of the containment building exceeded the upper limit of 105'F.

This is contrary to T.S. 3.6.1.5 and reportable pursuant to T.S. 6.9.1.9.b.

Probable Consequences of Event The average bulk air temperature of the containment air fluctuates between a maximum temperature of 105'F and a minimum of 86*F during normal operation. The containment structure is designed to withstand an internal pressure of 45 psig and a temperature of 280'F.

Since contain-ment average air temperature was restored to allowable limits within eight hours of going above 105*F, the health and safety of the general public were not affected.

Cause of Event

Containment air temperature exceeded the upper Technical Specifica-tion llait due to isolation of component cooling valve TV-CC204B for repair of an air leak. The isolating of the valve not only affected the flow of component cooling water to "B" reactor coolant pump, which was shutdown at the time, but also restricted flow to the "B" shroud cooling coil which was not foreseen.

Immediate Corrective Action

The containment isolation valve for the component cooling line (TV-CC204B) was immediately reopened to restore flow to the shroud cooler.

Scheduled Corrective Action No scheduled corrective action is required.

Actions Taken to Prevent Recurrence Personnel involved were instructed to review applicable prints more closely when changing the status of equipment to ensure that plant safety will not be compromised.

Generic Implications There are no generic implications associated with this event.

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