ML20024B982

LER 83-056/03L-0:on 830606,feedwater Flow Transmitter (FT-468) Steam Generator B Failed Low.Caused by Failure of Power Supply Card.Card replaced.W/830701 Ltr

ML20024B982
Person / Time
Site:	Summer
Issue date:	07/01/1983
From:	Bouknight R, Dixon O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
LER-83-056-03L, LER-83-56-3L, NUDOCS 8307120081
Download: ML20024B982 (2)

Text

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n as FO 3SS U.C. MUCL2A2 CG1ULATS2Y CC MMISSI1N A PP., 4V 4:3LY4M; 8 ** ' I UCENSEE EVENT REPORT S',$yt,.3 .:

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= l I'l@l 01 5 l0 i oj o 3 l 9l5 jg; o j6 l 0;6 l8 l 3 gl i l l l l lg EVENT OESCRIPTION ANO PROSABLE CONSEQUENCES O10 l o l2 l l 0n June 6,1983, with the Plant in M6de 1, Feedwater Flow Trammitter (FT-486) B l g l Steam Generator failed low. There were no adverse consequences due to this event. l ,

, , l The inoperable channel was placed in the tripped position within one (1) hour as l l, g ; ; required by Action Statenent 6 of Table 3.3-1, Technical Specification 3 3.1, l

, g l l " Reactor Trip System Instrumentation". 'Ihe minimum rumber of channels as required l

, by the aforementioned Technical Specification, Item 14, Table 3.3-1 was satisfied. ;

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l t j o l l The failure of FT-486 was due to the failure of the power supply card. 'Ibe card l l t l 1 l l was replaced, the applicable surveilhnce test procedure satisfactorily perfonned, l

[ i l 2 l l and the unit &chred operable on June 6,1983. No additional corrective action l ,

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o. w. omo.. u. 83 dllt 7 A9 33 VICE PREssOENT nuettan on . Tion. July 1, 1983 Mr. James P. O'Reilly Regional Administrator U.S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N.W.

Atlanta, Georgia 30303

SUBJECT:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Thirty Day Written Report LER 83-056

Dear Mr. O'Reilly:

Please find attached Licensee Event Report #83-056 for Virgil C.

Summer Nuclear Station. This Thirty Day Report is required by Technical Specification 6.9 1.13.(b) as a result of entry into Action Statement 6 of Technical Specification 3.3.1 (Table 3 3-1,-

Item 14), " Reactor Trip System Instrumentation," on June 6,1983 Should there be any questions, please call us at your convenience.

Very truly yours, O. W. ixon .

RJB:0WD/dwr

. Attachment cc: V. C. Summer C. L. Ligon (NSRC)

E. H. Crews, Jr. G. J. Braddick T. C. Nichols, Jr. ,/0. W. Dixon, Jr. J. C. Miller E. C. Roberts J. L. Skolds

H. N. Cyrus J. B. Knotts, Jr.

Group / General Managers I&E (Washington)

O. S. Bradham Document Management R. B. Clary Branch C. A. Price INPO Records Center A. R. Koon NPCF D. A. Lavigne File (Lic./Eng.)

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