05000395/LER-1982-021, Forwards LER 82-021/03L-0.Detailed Event Analysis Encl

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Forwards LER 82-021/03L-0.Detailed Event Analysis Encl
ML20066F045
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 11/10/1982
From: Dixon O
SOUTH CAROLINA ELECTRIC & GAS CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20066F046 List:
References
NUDOCS 8211170425
Download: ML20066F045 (2)


LER-1982-021, Forwards LER 82-021/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
3951982021R00 - NRC Website

text

_ _ _

j SOUTH CAROLINA ELECTRIC St GAS COMPANY

,OST OFPICs 764 N

COLupelA, SOUTH CAROuNA 29218 T[")

O. W. OtxoN, JR.

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vaca PassioaNT nucta*. o,..anO~.

November 10, 1982 ff cg vq f)

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Mr. James P. O'Reilly, Director op.

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 82-021

Dear Mr. O'Reilly:

Please f.'nd attached Licensee Event Report #82-021 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 (a) of Technical Specification 3 7.1.1,

" Turbine Cycle, Safety Valves," on October 11, 1982.

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

Very truly yours, d

if

$r O. W.

ixon, r.

ARK:0WD:dwr 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, J r.

I&E (Washington)

O.

S. Bradham Document Management Branch R.

B.

Clary NPCF M. N.

Browne File optqcol 00PYk 8211170425 821110 DR ADOCK 050003 g

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Mr; James P. O'Reilly LER No.82-021 Page Two November 10, 1982 DETAILED DESCRIPTION OF EVENT On October 11, 1982, with the Plant operating in Mode 3, surveillance testing was. being performed on the _ Steam Line Code Safety Valves.

As Safety Valve 2806P (located on Steam Line "C")

was being tested, it was discovered that the valve would not lift at'its proper-setpoint.

Af ter several attempts of adjusting the lif t setpoint and applying pressure, the valve fully opened.

Apparently the valve was initially: stuck shut and subsequently opened after being freed:from the-stuck condition. - The resulting transient ' on the Plant was terminated when the valve reset at a Steam Line' pressure or approximately 940 psig.

PROBABLE CONSEQUENCES There are no adverse consequences as the Technical Specification Action Statement was adhered to as discussed below.

Also, the Plant had not yet achieved initial criticality.

CAUSE(S) OF THE OCCURRENCE The cause of the occurrence was that the safety valve inadvertantly lifted after being freed from a stuck closed position.

IMMEDIATE CORRECTIVE ACTIONS TAKEN Immediate corrective action was taken to reset the Power Range Neutron Flux High Trip Setpoint to 87% as addressed in Technical Specificatio r 3.7.1.1, Action Statement (a).

This was accomplished within the four (4) hour requirement of the Technical Specification.

ACTION TAKEN TO PREVENT RECURRENCE Safety Valve 2806P was reset and subsequently retested per Surveillance Test Procedure 401.002.

It was returned to OPERABLE status on October 12, 1982.