05000395/LER-1982-016, Forwards Revised LER 82-016/03L-1.Detailed Event Analysis Encl

Forwards Revised LER 82-016/03L-1.Detailed Event Analysis Encl

ML20064F453
Person / Time
Site:	Summer
Issue date:	12/30/1982
From:	Dixon O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20064F458	List: 05000395/LER-1982-016, Forwards Revised LER 82-016/03L-1.Detailed Event Analysis Encl
References
NUDOCS 8301060360
Download: ML20064F453 (2)

LER-2082-016, Forwards Revised LER 82-016/03L-1.Detailed Event Analysis Encl

Event date:
Report date:
3952082016R00 - NRC Website

text

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SOUTH CAROLINA ELECTRIC & gas COMPANY post orries ve4 Coi.VMBIA. SOUTH CAROUNA 29218

~ O. W. OmON. Jm. LJ -

Vice PnesiosNT Nucuan Openario,es December 30, 1982 3= 'i .z us ~ ..

Mr. James P. O'Reilly, Director 21 .

CD U.S. Nuclear Regulatory Commission **

Region II, Suite 3100 101 Marietta Street, N.W. 'j, Atlanta, Georgia 30303

SUBJECT:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Thirty Day Written Report LER 82-016, Rev. 1 (Interim Report)

Dear Mr. O'Reilly:

Please find attached Licensee Event Report #82-016, Rev.1, 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 16 of Technical Specification 3 3.2,

" Engineered Safety Feature Actuation System Instrumentation," on October 3, 19, 28, and December 2, 1982. The attached report addresses the latest of these incidents. A final report will be submitted at a later date pending the resolution of thece events.

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

Very truly yours, Ah ,

O. W. Dixon, Jr.

CJM:0WD:dwr Attachment cc: V. C. Summer A. R. Koon T. C. Nichols, Jr. G. D. Moffatt 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. Knot ts, 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 M. N. Browne NPCF 8301060360 821230 DR ADOCK 05000 fhb LD

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.; r Mr. James P. O'Reilly 3, /j LER.No.82-016, Rev. 1 Page Two ,

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Decensber 30, 1982 >

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DETAILED DESCRIPTION OF EVENT

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3 On December 2, 1982, with the Plant in Mode 2, the Main Control Boar $

Pressure Indicator-(PI-950) for Reactor Building Pressure failed low.- .

The channel was subsequently declared inoperable and'placed in the tripped condition within one (1) hour in accordance with TechnicalD Specification 3.3.2, Table 3.3-3 [ Functional Units 2.c and 3.b.(2)31',

Action Statement 16. Surveillance Test Procedure-(STP) 303.001,'

" Reactor Building Pressure Instrument Operational Test," was performed with satisfactory results approximately two (2) hours after; failure, and the channel was returned to operable statusu The failure had apparently cleared when the channel was placedain the tripped ^ -

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condition. 3 Additional f ailures of a similar nature occurred, to thisf irstrumen-tation channel on October 3, 19, and 28-(Reference'.LER's182-040 and 82-016, Rev. 0). Investigation performed by the Licensee during/the period of time from October 28 to November 8 indicated that the cause of the failures was due to an intermittent power. supply card (PQY-950) which was subsequently replaced under Maintenance Work, Requests 4884 and 5001. This repair appears to be inadequate cince an additional failure occurred on December 2, 1982.

PROBABLE CONSEQUENCES t There were no adverse consequences during any of the events as three (3) channels of Reactor Building Pressure Indication remained operable at all times.

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CAUSE(S) OF THE OCCURRENCE .

The cause of the occurrence is still under investigation by the Licensee.

IMMEDIATE CORRECTIVE ACTIONS TAKEN The inoperable channel was placed in the tripped condition within one (1) hour in accordance.with Technical Specification'3.3.2, Action ~

Statement 16. Surveillance Test' Procedure (STP) '303.001 was performed with satisfactory results approximately two (2) hours after, failure, "

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l and the channel was returned to operable status. 4 ,

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ACTION TAKEN TO PREVENT RECURRENCE .'

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Repairs will be effected by the Licensee upon identification of the f intermittent component. Technicians have been instructed to isolate

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(9 the failure prior to placing the channel'in the tripped condition on the next occurrence. ,;

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