05000395/LER-1982-026, Forwards LER 82-026/03L-0.Detailed Event Analysis Encl

Forwards LER 82-026/03L-0.Detailed Event Analysis Encl

ML20066K705
Person / Time
Site:	Summer
Issue date:	11/19/1982
From:	Dixon O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20066K709	List: 05000395/LER-1982-026, Forwards LER 82-026/03L-0.Detailed Event Analysis Encl 05000395/LER-1982-026-03, /03L-0:on 821019,operator Noticed Frequent Auto Reactor Coolant Makeup to Vol Control Tank of Chemical Vol & Control Sys.Caused by Cracked Safety Injection Filter B Vent Valve.Leak Test Performed W/Results of 12 Gpm
References
NUDOCS 8211290627
Download: ML20066K705 (3)

LER-1982-026, Forwards LER 82-026/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3951982026R00 - NRC Website

text

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4 SOUTH CAROLINA ELECTRIC & GAS COMPANYNfpg g r,,,,N

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COLUMBIA. SOUTH CAROLINA 29218

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'f, O. W. OexON. JR.

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November 19, 1982 46,.5/

Vict P.ESIDENT wucot n on..riou.

Mr. James 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 Operating License No. NPF-12 Thirty Day Written Report LER 82-026

Dear Mr. O'Reilly:

Please find attached Licensee Event Report #82-026 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 (b) of Technical Specification 3.4.6.2,

" Reactor Coolant System Operational Leakage," on October 20, 1982.

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

Very truly yours, O.

W.

ixon, r.

ARK:OWD:dwf Attachment cc:

V.

C. Summer A.

R.

Koon T.

C. Nichols, Jr.

H. Radin G.

H. Fischer Site QA O.

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, vr.

B.

A. Bursey W.

A.

Williams, Jr.

I& E (Washington)

O.

S. Bradham Document Management Branch R.

B.

Clary INPO Records Center l,gy%

M.

N. Browne NPCF gb File

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50$?O88fffg, PDR

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Mr. James P.

O'Reilly LER No.82-026.

j Page Two j

November 19, 1982 DETAILED DESCRIPTION OF EVENT On October 19, 1982, at approximately 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> with the Plant in Mode 3, the Reactor Operator noticed frequent auto reactor makeup i

to the Volume Control Tank of the Chemical Volume and Control i

System (CVCS).

Investigation was initiated to determine-the cause of the frequent makeup.

PROBABLE CONSEQUENCES In the event of a Safety Injection Actuation, the Safety Injection flow would have been decreased slightly.

There were no adverse consequences as the Plant had not achieved initial criticality.

CAUSE(S) 0F THE OCCURRENCE The cause of the occurrence was that XVT-8385 (Seal Injection l

Filter "B" Vent Valvc) was slightly open.

IMMEDIATE CORRECTIVE ACTIONS TAKEN 1

Investigation was initiated to determine the cause of the frequent makeup to the Volume Control Tank of the CVCS.

Testing that was in progress at this time was terminated in order to stabilize the Plant conditions for the performance of a Reactor Coolant System j

(RCS) leak rate ' test.

At 0126 houro on October 20, 1982, Surveillance Test Procedure (STP) 114.002, " Operational Leak Test," was performed.

The results indicated approximately 10 gpm leakage; however, this leak (T v ) was rate was questionable because the RCS temperature A

unstable, and the CVCS flow did not support these resu$ts.

Investigation continued by inspecting pipirg inside the Reactor 1

Building and checking other possible leak sources such as the Pressurizer Power Operated Relief Valves (PORVs).

7-. -

Mr. James P. O'Reilly LER No.82-026 Page Three November 19, 1982 At approximately 0354 hours0.0041 days <br />0.0983 hours <br />5.853175e-4 weeks <br />1.34697e-4 months <br />, STP-114.002 was performed for the second time resulting in a leak rate of 9.4 gpm.

At approximately 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />, inspection of the Auxiliary Building revealed that XVT-8385. was slightly open.

The valve was closed, and STP-114.002 was performed again with a leak rate of.12 gpm.

ACTION TAKEN TO PREVENT RECURRENCE XVT-8385 was closed which becught the RCS leakage into Technical Specification 3.4.6.2 limit.

The licensee plans no further action as this event appears to be an isolated case.