ML20090D854

Preliminary AO-50-219/74-58:on 741108,isolation Valves V-28-5 & 6 Did Not Indicate Closed.Caused by Rust Accumulations on Piston Lands & Cylinder Walls.Rust Removed

ML20090D854
Person / Time
Site:	Oyster Creek
Issue date:	11/11/1974
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
AO-50-219-74-58, NUDOCS 8303030273
Download: ML20090D854 (3)

Text

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t To:

James P. O'Reilly Directorate of Regulatory Op.crations Region I G31 Park Avenue King of Prussia, Pennsylvania 19406 Pron:

Jersey Central Power 6 Light Co::pany Oyster Creek Nucicar Generating Station Docket 650-219 Forked River, New Jersey 08731

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Subject:

Abnor::a1 Occurrence Report No. 50-219/74/58;;,

.y The following is a prolininary report being subnitted in cos::pliance with~ t'he Technical Specifications, paragraph 6.6.2.

Prolininary Approval:

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8303030273 741111 PDR ADOCK 05000219 S

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11/9/74 Occurrence:

11/8/74

' Initin! Ifritton O

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Report Date:

11/11/74 Occurrenco:

1630-l OYSTER CREEK KUCLEAR GENERATING STATION FORKED RIVER, NEW JER3EY 08731 Abnorcal Occurrence l

Report No. 50-219/74/ 58 IDEITI'IFICATION Violation of the Technical Specifications, paragraph 3.5.B.1, OF OCCURRElK'B:

failure to caintain secondary containr,ent integrity (as defined in paragraph 1.14 of the Technical Specifications) with the reactor operating at power.

This event is considered to be an abnomal occurrence as de-

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fined in the Technical Specifications, paragraph 1.15B.

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CONDITIONS PRIOR x Stendy State Power Routine Shutdown W OCCURRENCE:

Hot Standby Operation Cold Shutdown

_ Load Changes During Refueling Shutdown Routino Power Operation Routino Startup Other (Specify) i Operation Power:

Reactor, 1907.51 fat Bloctric, 655 F.de Flow:

Rocire., 15.6 X 107 gpn Poed., 7.12 X 106 lb/hr Reactor Prossure:

1019 psig Stack Gas:

18,1S0 pCi/sce DESCRIPTION At approxinately 1630 on November 8,1974, while performing 0F OCCURRENCE:

secondary containment Icak rate testing, it was noted that iso-lation valvos V-28-5 and V-28-6 did not indicate closed following isolation of the reactor building ventilation system.

Investi-gation revealed that V-28-6 was not in the fully closed position.

'Iho rodundant valve, V-28-5, was found to be in the fully closed position.

It is noted that the test results were acceptable

/

,AbornalOchrtence

. Report No. 50-219/74/58 Pago 2 1

i even with V-28-6 partially opon.

APPAREITT CAUSE Design proceduro OP OCCURREh'CE:

thnufacturo x Unusual Servico Condition

~ Installation /

Inc. Environtental Construction Co:ponent Failuro Operator

..,,,,.,4;ig.,, q

,0 thor (Specify),

It is felt that condensation on the valve operator cot:ponents resulted in the observed rust accu =ulations.

ANALYSIS OF Re safety significance of this event is the loss of isolation OCCURRE!;CE:

valve redundancy. Although V-28-6 did not fully close, the redundant isolation valvo, V-28-5, functioned norns11y and closed fully.

CORRECTIVE R o valvo operator for V-28-6 was disassenb1cd by the raintenance ACTION:

department and small rust accumulations were found on the piston lands and cylinder walls. This rust accumulation caused the parts to bind which prevented the valve fron closing fully. The rust was renoved and the operator reassembled. V-28-6 was satis-factorily tested and returned.to service at 0400 on November 9, 1974.

PAILURB DATA:

thnufacturcr - Rockwell Typo - 14" Butterfly Valve (Air Operated)

Prepared by:

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11/11/74 p

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