ML20046B404

LER 93-004-00:on 930629,identified Noncompliance W/Srs of TS 4.3.2.1,Table 3.3-3.8.b.Caused by Personnel Error.Retest Sucessfully Performed & Personnel Involved Have Taken Part in Discussion of Importance of Review process.W/930728 Ltr

ML20046B404
Person / Time
Site:	Summer
Issue date:	07/28/1993
From:	Proper J, Skolds J SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-004, LER-93-4, RC-93-0208, RC-93-208, NUDOCS 9308040164
Download: ML20046B404 (4)

Text

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10CFR50.73 South Carolina Electr6c & Gas Company John L. Skolds

. 5 P.O Box 88 Vice President Nuclear Operations

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July 28, 1993 Refer to: RC-93-0208 Document Control Desk ,

U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:

Subject:

VIRGIL C. SUHMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 LER 93-004 Attached is Licensee Event Report No.93-004 for the Virgil C. Summer Nuclear Station. This report is submitted pursuant to the requirements of Technical SpecificationSection4.3.2.1, Table 3.3-3.8. band 10CFR50.73(a)(2)(1)(B). j Should there be any questions, please call us at your convenience.

Very truly yours, John L. Skolds JWP/JLS/nkk Attachment c: 0. W. Dixon (w/o attachment) L. J. Montondo R. R. Mahan (w/o attachment) NRC Resident Inspector i R. J. White J. B. Knotts Jr.  :

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\t approximately 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on June 29, 1993, Operations personnel identified a 1oncompliance with the surveille.nce requirements of Technical Specification 4.3.2.1, Table 3.3-3.8.b in that XVG03005B-SP had not been stroked from its associated relay during the

)erformance of STP-125.011 " Integrated Safeguards Test B Train", due the lack of power available to the valve. The personnel involved failed to note this as a test discrepancy.

On June 29, 1993, a retest was successfully performed.

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c.,lC, - .,nn PLANT IDENTIFICATION:

Westinghouse - Pressurized Water Reactor EQUIPMENT IDENTIFICATION:

XVG030058-SP, Secondary Isolation Valve For Reactor Building Spray Sump "B" IDENTIFICATION OF EVENT:

i Personnel error in documenting the test discrepancy.

DISCOVERY DATE: June 29, 1993 at approximately 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />.

REPORT DATE: July 26, 1993 l

This report was initiated by Off-Normal Occurrence report 93-049. -

PREVIOUS SIMILAR EVENTS:

Previous missed surveillances due to personnel error have been reported to the NRC:

LER 91-005, submitted on August 26, 1991 ; LER 92-002, submitted on February 28, 1992; LER 92-005, submitted on June 29, 1992.

CONDITIONS PRIOR TO THE EVENT:

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i DESCRIPTION OF EVENT:

At approximately 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on June 29, 1993, Operations personnel identified a noncompliance with the surveillance requirements of Technical Specification 4.3.2.1,  ;

Table 3.3-3.8.b in that XVG03005B-SP had not been stroked from its associated relay  :

during the performance of STP-125.011 " Integrated Safecuards Test B Train", due the  !

lack of power available to the valve. The personnel involved failed to note this as <t  ;

test discrepancy. On June 29, 1993, a. retest was successfully performed. j i

CAUSE OF EVENT: -j The cause of this event was lack of documenting the test discrepancy by the personnel

, involved.

• ANALYSIS OF EVENT:

Plant safety was not compromised by the missed surveillance. The appropriate procedur e l was performed on June 29, 1993, which confirmed that the valve was always fully  ;

functional and capable of performing its intended safety function.

l IMMEDIATE CORRECTIVE ACTIONS: i A surveillance task sheet was manually initiated and successfully completed on June 29 1993 at approximately 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />. ,

i The personnel involved have taken part in a discussion of the importance of the post- a test review process required and proper documentation of test discrepancies.

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ADDITIONAL CORRECTIVE ACTIONS:

l None '

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