05000423/LER-1992-001, :on 920113,leaking Monitoring Connection Containment Isolation Valves Were Not Locked Closed.Caused by Program failure-procedure Deficiency & Administrative Error.Valves Were Locked Closed

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:on 920113,leaking Monitoring Connection Containment Isolation Valves Were Not Locked Closed.Caused by Program failure-procedure Deficiency & Administrative Error.Valves Were Locked Closed
ML20092F468
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/12/1992
From: Mcnatt T, Scace S
NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-92-001, LER-92-1, MP-92-171, NUDOCS 9202190348
Download: ML20092F468 (4)


LER-1992-001, on 920113,leaking Monitoring Connection Containment Isolation Valves Were Not Locked Closed.Caused by Program failure-procedure Deficiency & Administrative Error.Valves Were Locked Closed
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)

10 CFR 50.73(a)(2)
4231992001R00 - NRC Website

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February 12, 1992 MP-92-171 U.S. Nuclear Regulatory Commission Document Control Dest Washington, D.C.

20555 lteference:

Facility Operatine License No. NI'l:-49 Docket No. 50-423 Licensee Event Report 92-001-00 Gentlemen:

This letter forwards Licensee Event Report 92-001-00 required to be submitted within thirty (30) days pursuant to 10CFR50.73(a)(2)(i) any operation or condition prohibited by the plant's 'lechnical Specification.

Very truly yours.

NORTilEAST NUCLEAR ENERGY COhll'ANY

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/ Stephen E. Sefice LIirector, hlillstone Station SESTfGhl:ljs Attachment: LER 92-001-00 cc:

T. T. h1artin, Region 1 Administrator W. J. Raymond, Senior Resident inspector, hIillstone Unit Nos.1, 2 and 3 V. L. Rooney, NRC Project hlanager, hiillstone Unit No. 3 f ((R8V73S51 rGap 9202190340 920212

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.e l ahrenheit and approximately 40 pua (Niuoren Hoat), m sahe, were identihed winch were nmsmp lockmr devnes. The vahes were found timed but not loc ked as icquited. These sahes aie leakare rootutonny connecuon (LMC) sent sahes uluch are used to test the contauirnent isolouon vahes associated with the RilR cold lep m soon hues.

'Ibe f oot catne of the esent k Program f ailure-procedure dehcieno. adminstrause error. The ustem hneu}w did not inchade the subjet.t sahes arnong those reqmred to be lot hed closed.

As unmediate correstne action the sahes were locked tio<ed and the penetranon sunedlances base been updated to include these sah ts.

A change will be subnourd to update the i SAR ConUunment Penetration Table.

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i on knuary 13,1992, at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> with the plant at 09 power in Mode 5 (Cold shutdownh 93 degrees l'ahlenheit and approximately 40 psia (Nntogen floath a non-hcensed operator (pf:0) performing a salve kneup observed that vahes 3Sil'Yu2b,930,931,937.938, and 9M had no lockmg devices while similarly conhgured salves did.

4 The aforementioned sahes are leakage momtonnp connection (LMC) test valves which are used to perform local haktate iesung of the Residual Heat Removal (RHR) cold leg injection line contamnient isolation vahes. A management renew of the mconshtency concluded that the subject salves are considered cotitainment isolation vahes and should be locked closed to cinure containment integnty.

The teuew aho concluded that the required ution of Technical Specihc.ition 4 A1.1, " primary j

Containment-Containment Integnty? had not been satished since the vahes were not locked closed and i

properly conuolled under the administrative program, As att immediate correctise acuon following the discovery of tins discrepancy, the sahes were locked closed All of the Lh!C vahes were widked-down and compared to the p&lDS. All sahes redeved were found closed but not all in their required locked closed position. Of the 136 vahen idenuhed, 37 were found not locked closed including the six idenuffed, 11.

Causc_ulhtnt The root cause of the event is program failure-procedure dehcienc3, adtnmistrative error. The sptern i

Imeups did not include the identihed LMC vahes among those teamred to be locked clowd.

The LMC sahes were not originally r.lasufied as containnient bolation vidves. The ongmal containment penetradon table in the Techmcal Specihcations did not indude tbne valves. This table was deleted from the Technical Specifications; the FSAR Conounment penetrauon Table, wluch then fornied the basis for maimaining containtnent integray, aho did not include the LMC valves as containmem isolation vah n, As part of the redeu in response to this esent. the LMC salves have been reclassihtd as containment isolation valves.

A thorough invesuration of the position and suncillance seguirements for LMC vahes had never been completed because the LMC sahes had not been identified as containment isolation valvet Consequently the Technical Specihcation suneillance requirements of 4.6.1.1 had neser been applied.

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This esent is bemp reported in accordance with 10CFR50.73(a)(2)(ih as an operauon or condaion prohibited by the Technical Specthcations.

Final Safety Analysis Report Section 6.2.4.1.4

  • Design Requirements for Containment Isolanon llatriers,"

states that containment isolauon valves under " administrative control" are required to be locked closed.

American National Standard ANSI $6.8 " Containment Sptem Leakage Testing Requuements" E

Section 6.2 descnbes these test connections as pan of the containment system barrier under.

administrathe controh Conudering these vahes as containment isolanon vahes n consistent with

'10CFR50 Appendix A Criterion 56

  • primary Containment isolation" which aho allows " administrative control" on valves of this type. The surveillance requirements for containment i olanon vahes are specified m Technical Spectheation Section 4 Al.1. ~This section states that all " penetrations" not capable of being closed by automatic sptenu or operator actions are suneilled every 31 days except those that are locked, scaled or otherwhe secured in the closed position. These,ahn were not locked, and smce they were not suncilled on a 31 day frequency, the Technical Specification was uolated.

There were no signihcant safety consequences due to this event. All of the vahes are 3/4 inch test vahes and were found closed. The LMC valves are either arranged as two vahes in series or a single i

sahe with a threaded cap downstream. These vahes are mdependently venhed closed on a valve hneup during each refueling outage following the LLRT of the contamment solation vahes.

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