05000395/LER-1982-042, Forwards LER 82-042/03L-0.Detailed Event Analysis Encl

Forwards LER 82-042/03L-0.Detailed Event Analysis Encl

ML20070E514
Person / Time
Site:	Summer
Issue date:	12/10/1982
From:	Dixon O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20070E518	List: 05000395/LER-1982-042, Forwards LER 82-042/03L-0.Detailed Event Analysis Encl 05000395/LER-1982-042-03, /03L-0:on 821110,RCS Temp Average Decreased When Control Rods Inserted.Caused by Simultaneous Rod Insertion & Main Steam Dumping.Control Rods Withdrawn & Steam Dump Isolated to Recover Temp Average
References
NUDOCS 8212170287
Download: ML20070E514 (2)

LER-1982-042, Forwards LER 82-042/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3951982042R00 - NRC Website

text

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SOUTH CAROLINA ELECTRIC & GAS COMPANY post oppica 7e4 COLuualA. SOUTH CAROLINA 29219

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o.w.oixON JR.

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vice pnas osur

. h, December 10, 1982

.-o sucta. on..mm.

on Mr. James P. O'Reilly, Director 7,

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U.S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street, N.W.

cP, Atlanta, Georgia 30303

SUBJECT:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Thirty Day Written Report LER 82-042

Dear Mr. O'Reilly:

Please find attached Licensee Event Report #82-042 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 the Action Statement of Technical Specification 3.1.1.4,

" Reactivity Control Systems, Minimum Temperature for Criticality," on November 10, 1982.

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

Ve ry truly yours, h

j

0. W.

ixon, Jr.

HCF:0WD:dwr Attachment cc:

V.

C.

Summer A.

R.

Koon T.

C. Nichols, Jr.

G.

D. Moffatt G.

H.

Fischer Site QA 0.

W.

Dixon, J r.

C. L. Ligon (NSRC)

H. N. Cyrus G. J. Braddick H. T.

Babb J. L.

Skolds D.

A.

Nauman J.

B. Knot ts, J r.

M.

B. Whitaker, Jr.

B.

A. Bursey W.

A.

Williams, J r.

I&E (Washington)

O.

S.

Bradham Document Management Branch R.

B.

Clary INPO Records Center M. N. Browne NPCF File 8212170287 821210 t gyfL'3AL DR ADOCK 05000395 [g_

PDR ggy

g Mr. James P. O'Reilly LER.No.82-042 Page Two December 10, 1982 DETAILED DESCRIPTION OF EVENT On November 10, 1982, with _the Plant in Mode 2, control rods were being inserted to shut down the reactor for a training startup.

As the rod insertion began, Reactor Coolant System (RCS) TA decreased to 547 F.

RCS T vg isrequiredtobegreaterthaNgor A

equal to 551 F per -Technical Specification 3.1.1.4.

PROBABLE CONSEQUENCES There were no adverse consequences as the Technical Specification l

Action Statement was complied with by restoring T vg to greater A

j than 551 F within 15 minutes.

I CAUSE(S) 0F THE OCCURRENCE The cause of this event is attributed to cperator error due to the fact that separate operational events occurred simultaneously, which resulted in a decrease in T vg*

Specifically, as the i

A control rods were being inserted for a reactor shutdown, steam.

was released via a main steam line Power Operated Relief Valve.

Operations were in process to place the Power Operated Relief decreaaed Valves in the automatic pressure control mode.

TAvg to approximately 547 F.

IMMEDIATE CORRECTIVE ACTIONS TAKEN l

Immediate corrective action was taken by the operator to terminate rod insertion and steam dump.

Control rod withdrawal was then l

initiated to increase reactor power in order to recover T vg to A

I greater than 551 F.

During the transient, TAvg decreased to approximately 547 F and was less than 551 F for less than eight (8) minutes.

l ACTION TAKEN TO PREVENT RECURRENCE This event, which occurred as a result of separate simultaneous plant operations, can be viewed as a learning experience for operations shift personnel.

Therefore, in order to prevent recurrence, the details of this occurrence will be reviewed with the operating shift personnel.

This will be accomplished prior to December 24, 1982.