ML19330B585

LER 80-027/01T-0:on 800716,during Tour by Plant Mgt & NRC Personnel,Reactor Bldg to Suppression Chamber Vacuum Breaker Inlet Pipe Found Covered W/Plastic.Caused by Personnel Error.Plastic Removed from Vacuum Breaker Inlet Opening

ML19330B585
Person / Time
Site:	Oyster Creek
Issue date:	07/31/1980
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19330B584	List: ML19330B583 ML19330B585
References
LER-80-027-01T, LER-80-27-1T, NUDOCS 8008050076
Download: ML19330B585 (3)

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U. S. NUCLEA3 REGULATORY COMMISSION h NRkRM 366 Q ,/ d.7li LICENSEE EVENT REPORT (PLEASE PRINT OR TYPE ALL REQUtRED INFORMATION:

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E% ENT OATE 74 75 REPORT DATE 80 7 8 60 63 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 101211 On July 16, 1980, during a tour by plant manacement and NRC nersonnel. 1

[o Iai I the reactor building to suppression chamber vacuum breaker inlet nipe 1 was found to be covered by a plastic bae in violation of T. S. 3.5.A.4 a. I Io14l l io is t l The plastic bag had apparentiv been in place since June 7, 1980. It had l 10 is i l been placed over the pipe by Technical Group encineers to check for I 1017] I leakage past the vacuum breakers durine the primary containment integrat- I l0tal I ed leak rate test and was not removed when testin:r was comoleted. I 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUSCODE COMPONENT CODE SUSCODE SU8 CODE 1019]

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34 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS I i I 01 I The cause of the occurrence enn he netriburga en pa ve ne n t aven, Tu l Iil1 II i m edinte enrrective nctinn wns en remnv. the plusc cnu vi,, g tu ,m - 1 l1 ;7l l uum breaker inlet opening. An addition will be incorporated into the I I1 1a t I appropriate procedures to ensure any leak rate detection devices install- l LLL4j i ed during the performance of the test are removed at the end of the test. l 7 a 9 80

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OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey. 08731-License Event Report Reportable Occurrence No. 50-219/80-27/1T Report Date .

' July 31, 1980 Occurrence Date July 16, 1980 Identification of Occurrence .

Violation of the Technical Specifications, paragraph 3.5. A.4.a when the Reactor Building to Suppression Chamber vacuum breaker system inlet pipe was found to be blocked by a plastic bag.

This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.a(6) .

Conditions Prior to Occurrence-The plant conditions during the time period involved varied between cold shutdown and steady state power operation at '100 MWe output following a -

refueling . outage. The following data is provided for the steady state power operation experienced during this time.

Power: Reactor 300 MWe Electrical 100 MWe 4

Flow: Recirculation 5.2 x 10 gpm -

Feedwater 8 x 105 lb/hr Pressure 1000 psig Stack Gas 6.46 x 103 uCi/sec Description of Occurrence On Wednesday,~ July 16, 1980 at approximately 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> during a tour by plant management and NRC personnel, the reactor building to suppression 3

chamber vacuum breaker inlet pipe was found to be covered by a plastic bag.. -The plastic bag had apparently been in place since June 7,1980 while performing the Primary Containment Integrated Leak Rate Test.

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jC 1-Reportable Occurrence Page 2 Report No. 50-219/80-27/1T Apparent Cause of Occurrence The cause of occurrence can be attributed to personnel error. The plastic bag had been placed over the pipe by the Technical Group engineers to check for leakage past the vacuum breakers during the . performance of the Primary Containment Integrated Leak Rate Test. The personnel performing the test failed to remove the plastic when the testing was complete.

Analysis of Occurrence The vacuum relief system from 'the reactor building to the suppression chamber consists of two 100% vacuum relief breaker subsystems (two (2) parallel sets of two (2) valves in series). These two sets of vacuum relief valves share a common header which is open to the reactor building atmosphere.

, The purpose of the vacuum relief valves is to equalize the pressure between the reactor building and suppression chamber so that containment external design pressure limits are not exceeded. Operation of either subsystem will maintain the suppression chamber external pressure less than one half of its design pressure.

The possibility exists that the plastic covering the pipe may have prevented the vacuum relief system from preventing the pressure from approaching or exceeding the external design pressure of the primary containment.

Corrective Action Immediate corrective action was to remove:the-plastic covering the vacuum breaker = inlet opening. An addition will' be incorporated into the appropriate procedures to ensure any leak rate detection devices installed during the performance of the test are removed at the end of the. test.

Failure Data Not applicable e

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