05000395/LER-1982-039, Forwards LER 82-039/03L-0.Detailed Event Analysis Encl

Forwards LER 82-039/03L-0.Detailed Event Analysis Encl

ML20070D555
Person / Time
Site:	Summer
Issue date:	12/08/1982
From:	Dixon O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20070D558	List: 05000395/LER-1982-039, Forwards LER 82-039/03L-0.Detailed Event Analysis Encl 05000395/LER-1982-039-03, /03L-0:on 821108,steam Generator Steam Flow Transmitter (FT-476) Power Supply Found Defective.Caused by Failure on Transmitter Power Supply (FQY-476).Channel Placed in Tripped Condition.Circuit Board Replaced & Tested
References
NUDOCS 8212150097
Download: ML20070D555 (2)

LER-1982-039, Forwards LER 82-039/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3951982039R00 - NRC Website

text

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SOUTH CAROLINA ELECTRIC & GAS COMPANY 7 4 p;.^

l post orracE 7s4 CotuusiA, south CAROLINA 29218 O. W. OlxoN. JR.

h December 8, -1985 c 13 M:

Vice PREseDENT

" " * " ^ ^ ' ' " ' ' ' "

• Mr. J ames P. O ' Reilly, Director U.S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street, N.W.

Atlanta, Georgia 30303

SUBJECT:

Virgil C. Summer Nuclear Station Docket No. 50/395 Ope rating License No. NPF-12 Thirty Day Written Report LER 82-039

Dear Mr. O'Reilly:

Please find attached Licensee Event Report #82-039 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,

" Reactor Trip System Instrumentation," on November 8, 1982.

Should there be any questions, please call us at your convenience.

Very truly yours, M

O.

W.

Dixon, Jr.

CJM:0WD:dwr Attachment cc:

V.

C.

Summer A.

R.

Koon T.

C.

Nichols, Jr.

G.

D. Mof fatt G.

H.

Fischer Site QA

0. W.

Dixon, Jr.

C. L. Ligon (NSRC)

H.

N.

Cyrus G. J.

Braddick H. T. Babb J.

L. Skolds D.

A.

Nauman J.

B. Knotts, Jr.

M.

B.

Whitaker, Jr.

B.

A.

Bursey W.

A.

Williams, Jr.

I&E (Washington)

O.

S.

Bradham Document Management Branch R. B. Clary INPO Records Center

,,$"'"t M. N.

Browne NPCF IG 4

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A Mr. James P.

O'Reilly LER No.82-039 Page Two December 8, 1982 DETAILED DESCRIPTION OF EVENT During the performance of surveillance testing on November 8, 1982 with the Plant in Mode 2, the power supply for Steam Generator A Steam Flow Transmitter (FT-476) was found to be defective.

The inoperable channel was placed in the tripped condition within one (1) hour in accordance with Technical Specification 3.3.1, Action Statement 6.

PROBABLE CONSEQUENCES There were no adverse consequences as the minimum number of channels per loop as identified in Table 3.3-1 for

" Steam /Feedwater Flow Mismatch and Low Steam Generator Water Level" remained operable during repair of the tripped channel.

CAUSE(S) OF THE OCCURRENCE This occurrence is attributed to a component failure on the transmitter power supply card (FQY-476).

IMMEDIATE CORRECTIVE ACTIONS TAKEN The channel was placed in the tripped condition within one (1) hour.

The defective circuit board was replaced, and a channel calibration was performed on all affected components per the appropriate surveillance test procedure with satisfactory results.

The channel was returned to operable status on November 8, 1982.

ACTION TAKEN TO PREVENT RECURRENCE No further action, other than the normal surveillance testing, is planned by the Licensee.