05000338/LER-1981-047-03, /03L-0:on 810601 & 03,containment Average Air Temp Exceeded Tech Spec Limit.Caused by Loss of Chilled Water to Containment Recirculation Air Cooling Coils While Changing Valve Lineup from Mechanical to Steam Chiller

/03L-0:on 810601 & 03,containment Average Air Temp Exceeded Tech Spec Limit.Caused by Loss of Chilled Water to Containment Recirculation Air Cooling Coils While Changing Valve Lineup from Mechanical to Steam Chiller

ML20005A195
Person / Time
Site:	North Anna
Issue date:	06/24/1981
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20005A194	List: 05000338/LER-1981-047, Forwards LER 81-047/03L-0 05000338/LER-1981-047-03, /03L-0:on 810601 & 03,containment Average Air Temp Exceeded Tech Spec Limit.Caused by Loss of Chilled Water to Containment Recirculation Air Cooling Coils While Changing Valve Lineup from Mechanical to Steam Chiller
References
LER-81-047-03L, LER-81-47-3L, NUDOCS 8106300028
Download: ML20005A195 (2)

LER-1981-047, /03L-0:on 810601 & 03,containment Average Air Temp Exceeded Tech Spec Limit.Caused by Loss of Chilled Water to Containment Recirculation Air Cooling Coils While Changing Valve Lineup from Mechanical to Steam Chiller

Event date:
Report date:
3381981047R03 - NRC Website

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U.S. NUCLEAR REGULATORY COMMISSION g

LICENSEE EVENT REPORT CONTROL BLOCK / / / / / / / (1)

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UR DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)

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During full power operation on June 1 and 3, 1981, containment average air

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temperature exceeded the upper limit of 105'F for 20 minutes and 2 minutes

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respectively. Since the containment average air temperature was restored to

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within the limit of T.S. 3.6.1.5 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on each occasion, the public

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health and safety were not affected. This event is reportable pursuant to

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T.S. 6.9.1.9.b.

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SYSTEM

CAUSE

CAUSE COMP.

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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 LX/ (18) LZ/ (19) LZ/ (20)

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Z CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

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The first high containment temp. was caused by temporary loss of chilled water /

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to the recire air cooling coils while changing valve line-up from the mechani- /

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cal chiller to the steam chiller and the second high temp. resulted when the

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steam chiller was secured and the mechanical chiller was placed in service. In /

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each case,cantainment temp. vas reduced by valving in the desired chiller _ unit./

FACILITY METHOD OF STATUS

% POWER OTHER STATUS DISCOVERY DESCRIPTION (32)

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OPERATOR OBSERVATION

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LOCATION OF RELEASE (36)

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LOSS OF OR DAMAGE TO FACILITY (43)

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PUBLICITY ISSUED DESCRIPTION (45)

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Virginia Electric and Power Company North Anna Power Station, Unit #1 Attachment: Page 1 of 1 Docket No. 50-338 Report No. LER 81-047/03L-0

Description of Event

During full power operation on June 1 and 3, 1981, the containment average air temperature exceeded the upper Technical Specification limit of 105*F for a 20 minute and 2 minute duration respectively.

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

Probable Consequences of Occurrence Since containment average air temperature was restored to within the limit of T.S. 3.6.1.5 within the allowed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on both occasions, the health and safety of the general public were not affected.

Cause of Event

The high containment air temperature on June 1 was caused by a temporary loss of chilled water flow to the containment recirculation air cooling coils while changing valve line-up from the mechanical chiller to the steam chiller. The high temperature on June 3 resulted when the steam chiller was secured and the mechanical chiller was-placed in service on the Unit I containment in parallel with Unit 2.

Immediate Corrective Action

In each case, the containment air temperature was reduced by valving in the desired chiller unit to provide the required chilled water flow.

Scheduled Corrective Action A higher heat load appears to exist on Unit I containment.

Corrective action will be to inspect insulation on various components such as the reactor head and steam generator supports during the next refueling.

Actions Taken to Prevent Recurrence No further actions are required.

Generic Implications There are no generic implications assaciated with this occurrence.

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