ML19254E513

LER 79-057/03X-1:on 790717,during Normal Power Operation, Safety Relief Valve F013E Lifted & Reset Approx Five Minutes Later at 970.Cause Unknown.Electrical Check Made of Valve Operator.Valve Solenoid Replaced

ML19254E513
Person / Time
Site:	Brunswick
Issue date:	10/29/1979
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19254E503	List: ML19254E502 ML19254E513
References
LER-79-057-03X, LER-79-57-3X, NUDOCS 7911010411
Download: ML19254E513 (2)

Text

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74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 12 l During normal power operation, safety relief valve FCl3E lif ted and reset approximatelt o al 1 five minutes later at 970# for no apparent reason and with no indication of previous O 4 l leakage. Plans were made to shutdown for F013E repair the next weekend. Two days l ITTTI l later, F013E lif ted at 980# and reset at 915# af ter power had been reduced to 537.. A 10 is I normal reactor shutdown was then commenced to. repair the valve and prevent any further of7 l chance of inadvertant valve operation. l 0 8 l Technicc1 Specification 3.4.2, 6.9.1.9b l 7 8 9 80 E CODE SUSC E COMPONENT COC 1 SUB ODE S E g

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l l2 0g 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1 O l An electrical check of the valve opcrater indicated no electrical fault. The valve g l solenoid was replaced as a precautionary meas tre. The valve operator was replaced andi g the failed operator was sent to Wyle Laboratory for failure evaluation. Wyle Labora- l 3 3 l tory reported that the pilot valve assembly was leak tested with nitrogen prior te g l disassembly. Leakage was beyond measurement capability of the bench test. (CON'T) l 7 8 9 30 STA  % POWER oTHER STATUS blS O RY DISCOVERY DESCRIPTION A WQ l 0l 9l 4l@l NA l { @l Operator Surveillance 80 l

AblVITY CO TENT RELEASED OF RELEASE AMOU. OF ACTIVITY LOCATION cF RELEASE 1 6 @ l 2, l@l NA l lNA l PERSONNEt ExPOSMES NUM8ER TYPE DESCRIPTION i

7 Ql 0 l 0 l@l Z l@l NA l PERSONNE L INJU IES NUMBER DESCRIPTION Q l 0l U 0 l@l NA 1281 011 i .

i 7 8 9 11 12 80 LoS$ OF OR DAMAGE TO FACILITY TYPE DESCRIPTION 1 9 7 8 9

@ltoNA l go PUBLICITY // NRC USE ONLY ISSUE D DESCRIPTION 45 7911010 ,

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NAME OF PREPARER A. C. Tollison. Jr. PHONE: 919-457-4521 E

LER CONTINUATION -- RO# 2-79-057

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Facility: BSEP Unit No. 2 Event Date: 7-17-79 CAUSE DESCRIFTION AND CORRECTIVE ACTIONS:

Moderate steam cuttin,c . the seat and disk were verified during disassembly.

Target Rock's opinion is that the steam cutting of the seat and disk was the cause of the inadvertant operation of the valve. Target Rock recomends in-stalling model 7567F main steam relief valv( , which are insensitive to pilot leakage. We are awaiting field evaluation of these valves before consideration is made for us to use them.

1281 012