05000395/LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl

Forwards LER 82-017/03L-0.Detailed Event Analysis Encl

ML20066C754
Person / Time
Site:	Summer
Issue date:	11/05/1982
From:	Dixon O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20066C756	List: 05000395/LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl 05000395/LER-1982-017-03, /03L-0:on 821006,controlled Leakage Exceeded Tech Specs During Surveillance Test Procedure.Caused by Improperly Set Needle Valves Located in Reactor Coolant Pump Seal Injection Line.Valves Positioned Correctly
References
NUDOCS 8211100337
Download: ML20066C754 (2)

LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3951982017R00 - NRC Website

text

'

SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OPPsCE 764

'iNJ. [-]j.,.

COLuus A. south CAROLINA 29218 '.

O. W. DixON. JR.

VICE PRESIDENT November 5, gg p g. 59 NUCLEAR OPERATIONS 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 82-017

Dear Mr. O'Reilly:

Please find attached Licensee Event Report #82-017 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(e),

" Reactor Coolant System Operational Leakage," on October 6,1982.

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

Very truly yours, j

0. W.

Dixon, r.

ARK:0WD:dwf Attachment cc:

V.

C.

Summer A. R. Koon T.

C.

Nichols, Jr.

H. Radin 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 NPCF M. N.

Browne File OFFICgL COPh.

[h 8211100337 821105 PDR ADOCK 05000395 S

PDR

Mr. James P.

O'Reilly LER No.82-017 Page Two November 5, 1982 DETAILED DESCRIPTION OF EVENT

)

On October 6, 1982, with the Plant in Mode 3, Surveillance Test Procedure (STP) 114.001, " Operational Leakage to Reactor Coolant Pump Seals," was performed.

The results indicated that a controlled leakage of 36 gpm existed.

This is in excess of the 33 gpm criteria as required by Technical Specification 3.4.6.2(e).

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

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

CAUSE(S) OF THE OCCURRENCE The cause of the occurrence was that the " needle valves" (8369 A,

B, C), which are located in each Reactor Coolant Pump Seal Injection Line, were not properly set for flow.

This surveillance test was being performed for the first time as part of the plant startup following initial fuel loading.

IMMEDIATE CORRECTIVE ACTION TAKEN l

l Immediate corrective action was taken to position the Reactor Coolant Pump Seal Injection " needle valves" such tnat controlled leakage was less than the Technical Specification limit of 33 gpm.

This action was completed within the four hour requirement of Technical Specification 3.4.6.2 Action Statement (b).

l l

ACTION TAKEN TO PREVENT RECURRENCE The subject valves 8369 A, B,

C.

have been locked into position.

e.

l