ML20027D702

LER 82-061/03L-0:on 820929,fan Damper Operator on Industrial Cooler Failed,Resulting in Reactor Bldg Average Air Temp Exceeding 130 F.Caused by Water in Instrument Air Sys Due to Personnel Failing to Close Valve FSV-250.Dampers Wired Open

ML20027D702
Person / Time
Site:	Crystal River
Issue date:	10/29/1982
From:	Hughes P FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20027D695	List: ML20027D694 ML20027D702
References
LER-82-061-03L, LER-82-61-3L, NUDOCS 8211080261
Download: ML20027D702 (2)

Text

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EVENT MECRIPTION AND PROBABLE CONSEQUENCES h rn m 10n 9-29-82 water in the instrument air (IA) system caused a fan damner i

$ 0 innoratne nn tho inductrial enn1nr tn fn41 rna.ic4nn +he rgint nr nn14nn i O 4 lair available to the reactor buildino (RBl. Thus at 0048. while takina l l o i daily surveillence data, it was discovered that the RB average air temp- i E l oraturo pyrooded l'40 donrone F limit nf T R ') 61 G Rv 0061 tomnoraturn I g t was reduced below 130 F using another cooler. There was no effect on i j , ,, ipublic health or safety. This is the 8th occurrence under T.S.3.6.1.5. i I

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f SUPPLEMENTARY INFORMATION REPORT NO: 50-302/82-061/03L-0 FACILITY: Crystal River Unit #3 REPORT DATE: October 29,1982 OCCURRENCE DATE: September 29,1982 IDENTIFICATION OF OCCURRENCE:

Reactor Building average air temperature exceeded the 1300F limit of Technical Specification 3.6.1.5.

CONDITIONS PRIOR TO OCCURRENCE:

MODE 1 (97% RATED THERMAL POWER).

DESCRIPTION OF OCCURRENCE:

On September 29, 1982, water in the instrument air system caused a fan damper operator on the Industrial Cooler to fail. This failure caused a reduction in the amount of cooling air avaliable for the Reactor Building, thus causing the Reactor Building temperature to exceed the 1300F limit. Additional cooling was initiated so that by 0051 the Reactor Building temperature was reduced below the 1300F limit.

DESIGNATION OF APPARENT CAUSE:

This event was caused by personal error. On September 21, 1982, personnel were using an inappropriate document (flow diagram) to determine the correct position of FSV-250 rather than the approved procedure (OP-207). FSV-250 is the valve isolating Fire Service water from the Instrument Air System. iseaving FSV-250 open allowed water from Fire Service to back up into Instrumend Air. Although water was drained from the Instrument Air System and the valve closed, enough water apparently remained in the Instrument Air System to cause the damper operator to fail.

ANALYSIS OF OCCURRENCE:

There was no effect on public health or safety. Containment temperature was reduced to within the limit within the time frame required by the Action Statement of Specification 3.6.1.5.

CORRECTIVE ACTION:

Personnel were instructed on the importance of using approved documents and procedures. The dampers were wired open until the system was returned to operability late September 29, 1982. An engineering evaluation has been initiated to determine if further corrective actions are required.

FAILURE DATA:

This is the eighth time the Reactor Building temperature has exceeded the 1300F limit of Specification 3.6.1.5.