05000322/LER-1989-005, :on 890321,results of Local Leak Rate Test of Core Spray Suction Valve a Determined That Leakage,When Combined W/All Type B & C Penetration Leakages,Exceeded Tech Spec Limit.Caused by Normal Valve Degradation

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:on 890321,results of Local Leak Rate Test of Core Spray Suction Valve a Determined That Leakage,When Combined W/All Type B & C Penetration Leakages,Exceeded Tech Spec Limit.Caused by Normal Valve Degradation
ML20055C508
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 05/16/1990
From: Schnaars G
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20055C491 List:
References
LER-89-005, LER-89-5, NUDOCS 9005240096
Download: ML20055C508 (3)


LER-1989-005, on 890321,results of Local Leak Rate Test of Core Spray Suction Valve a Determined That Leakage,When Combined W/All Type B & C Penetration Leakages,Exceeded Tech Spec Limit.Caused by Normal Valve Degradation
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(ii)
3221989005R00 - NRC Website

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1989 at 1430, it was determined by the Maintenance On March 21, of valve section that the results of a Local Leak Rate Test (LLRT)

"A" Suction), showed leakage that, when l

E21*MOV-031A (Core Spray combined with all "B" and "C" penetration leakages exceeded the Tech. Spec limit of 0.6 La.

The plant was in Operational Condition 4 (Cold Shutdown) with the mode switch in Shutdown and all rods inserted in the core.

Subsequent testing identified three additional valves which had excessive leakage.

Maintenance Work Requests (MWRs) were generated to investigate the leakage and to repair the valves as needed.

These valves were repaired and This supplemental report is being retested with acceptable results.

submitted to inform the NRC of the completion of repairs to the four t

valves and also that repair of other valves that fail leak rate testing has been deferred due to the New York State - LILCO Shoreham Settlement Agreement.

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PLANT AND_.SYSIEd IDENTIFICATION General Electric - Boiling Water Reactor En'ergy Industry Identification System (EIIS) codes - are-identified in.the text as [xx].

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a IDENTIFICATION QF THE EVEHI Results of LLRT for check valves showed leakage that, when combined l

with all Type B and C penetration leakage, exceeded the ' lech. Spec limit of 0.6 La.

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. Event Date:

- 3/21/89

, Report Date:

5/16/90 l

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. CONDITIONS PRIOB TQ_IBE EVENT ll

. Operational Condition 4 (Cold Shutdown) l Mode Switch - Shutdown POWER LEVEL - 0 RPV Pressure:

0 pcis RPV Temperature :

105 Degrees F All rods inserted in the core DESCRIPTION CF THE EVENT

.On March 21, 1989 at 1430, it was determined by'the Maintenance section that the results of a Local Leak. Rate Test (LLRT) of valve L

1E21*MOV-031A (Core Spray "A" suction valve), showed leakage that, l

L when combined with all "B" and "C" valve leakages exceeded the Tech..

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Spec. limit of 0.6 La.

The penetration was tested to satisfy Tech.

1 Spec.. requirement 3.6.1.2.b.

Upon identification of the excessive leakage, a Maintenance Work-Request was generated to J.nvestigate the cause and then repair the valve.

Subsequent testing Ldentified

- three additional valves which had excessive leakage. lThey are:

1E11*MOV-040B [BO) (RHR Containment Spray-Valve) 1G11*MOV-249 [WK3 (Drywell Equipment Drains Outboard Isolation Valve)

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we r asuwim CAUSE_QE THE EVEHI-The cause: of.the leakage = f or the valves was nornal valve degradation (excessive valve' disc'to seat leakage).

ANALYSIS OF THE EYEHI This event is reportable per 10CFR50.73(a)(2)(ii) as identified in NUREG 1022,'page 12.-

There is minimal safety significance to this.

svent.

The four valves'are set up in a double valve configuration

.Their adjacent valves _were leak tested satisfactorily and would have

- provided a_means for containment isolation upon an accident signkl.

Had:a-LOCA occurred during 5% power operation with the leakage rate above the-allowable rate, the radiation doses would have been well lbelow the-limits as required by 10CFRiOO and the General Design Criterion 19 of Appendix A of 10CFR50.

gQBREQTIVE ACTIQBS

1.

MWRs were gerierated f or the four valves.

These were repaired andiretested with acceptable results.

2.

A list of valves that fail leak rate testing is being maintained. -Repair of these valves hcs been deferred since all fuel _ bundles have been removed from the Primary Containment due to the New York State - LILCO Shoreham Settlement Agreement and because LILCO has received a temporary exemption from the leak rate testing requirements of'10 CFR 50.54(o) and Appendix J, Sections III.D.1 through III'.D.3.

ADDITIONAL INFORMATION

a..

Manufacturgr_and_mQdel_numhtI_Qf.fai1ed_comDonenta YalYe HQ.

Manufacturer Madel H2 1E21*MOV-031A Anchor Darling Co.

E5836-7-1 l

1E11*MOV-040A Velan Valve Co.

B20-01064B-02WN 1E11*MOV-040B Velan Valve Co.

B20-01064B-0210N 1G11*MOV-249 Velan Valve Co.

10-0054B-02WN b.

LER numbers of Drevious similar tYanta 85-049 87-029 N7.C Form 3ASA (6 89) 6