05000366/LER-1980-140-03, /03L-0:on 801009,suppression Chamber Drywell Vacuum Breakers Were Not Tested During Safety Relief Valve G Operation.Caused by Operator Error.Breakers Were Tested Upon Discovery of Error

/03L-0:on 801009,suppression Chamber Drywell Vacuum Breakers Were Not Tested During Safety Relief Valve G Operation.Caused by Operator Error.Breakers Were Tested Upon Discovery of Error

ML19338G632
Person / Time
Site:	Hatch
Issue date:	10/23/1980
From:	Baxley S GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19338G631	List: 05000366/LER-1980-140, Forwards LER 80-140/03L-0 05000366/LER-1980-140-03, /03L-0:on 801009,suppression Chamber Drywell Vacuum Breakers Were Not Tested During Safety Relief Valve G Operation.Caused by Operator Error.Breakers Were Tested Upon Discovery of Error
References
LER-80-140-03L, LER-80-140-3L, NUDOCS 8010310410
Download: ML19338G632 (2)

LER-1980-140, /03L-0:on 801009,suppression Chamber Drywell Vacuum Breakers Were Not Tested During Safety Relief Valve G Operation.Caused by Operator Error.Breakers Were Tested Upon Discovery of Error

Event date:
Report date:
3661980140R03 - NRC Website

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LICENSEE EVENT REPORT COf '7Hol OLOCX:

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60 01 DOCKET NUMBEn 68 63 EVENT DATE 14 h

REPCf tT DAIF tiJ LVENT DEFCRIPTION AND PROBABLE CONSEQUENCES h FTilTI IDuring recovery of flatch Unit 2 following a reactor scram, the safety relief valve 1

injajl"G" was operated.

Tech. Specs. section 4.6.4.1.a requires that each suppression I

[O l4 l l chamber - drywell vacuum breaker to be dcmonstrated operable by cycling each valve i

g [through at least one test cycle within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after any discha'rge of steam to the I

joic.j l suppression chamber. fio significant occurrence took place due to this event.

This isl [irJT] l not a repetitive event. There were no effects upon public health and safety due to l

[o ia ; i this event.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS li 101 LO_p_er_a_ tors used safety relief valve "G" to reduce pr_ essure in reactor vessel so I

e 11 111 I main steam ioolation valves could be opened.

Suppression chamber - drywell I

i, i;,, l vacuum breaker s were tested when missed surveillance was discovered.

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LER #:

50-366/1980-140

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Licensee:

Georgia Power Company facility flame:

Edwin I. Hatch Docket #:

50-366 flarrative Report for LER 50-366/1980-140 On October 9,1980, with the reactor in hot shutdown, following a reactor scram and closure of MSIV's, the suppression chamber - drywell vacuum breakers were not tested within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> as required by Tech. Specs. sec-tion 4.6.4.1.a.

The safety relief valve "G" was operated and this re-quired vacuum breaker surveillance to be performed at 0450, 10-9-80.

Operability of vacuum breakers was not performed until 2330 on 10-9-80.

f No significant occurrence took place as a rcsult of this event.

There were no effects upon public health and safety due to this event.

This is not a repetitive event.

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