05000265/LER-1994-008, Informs of Commitments Being Made Re LER 94-008,rev 0

Informs of Commitments Being Made Re LER 94-008,rev 0

ML20092F973
Person / Time
Site:	Quad Cities
Issue date:	05/16/1994
From:	Campbell G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20092F971	List: 05000265/LER-1994-008, Informs of Commitments Being Made Re LER 94-008,rev 0
References
GGC-94-079, GGC-94-79, NUDOCS 9509190063
Download: ML20092F973 (1)

LER-1994-008, Informs of Commitments Being Made Re LER 94-008,rev 0

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ii)
2651994008R00 - NRC Website

text

Commonw::lth Edis:n ATTACHMENT 2 Quad Cites Nuclear Power Statori 22710 206 Avenue North Cordovi mitos 61242 9740 j

Telechene 309/654 2241 GGC-94 079 May 16. 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Quad Cities Nuclear Power Station Docket Number 50-265. OPR-30. Unit Two Enclosed is Licensee Event Report (LER)94-008. Revision 00 for Quad Cities Nuclear Power Plant Station.

This report is submitted in accordance with the requirements of the Code of Federal Regulations. Title 10. Part 50.73(a)(2)(ii)(B).

Any event or condition that resulted in the condition of the nuclear power plant including its principal safety barriers being seriously degraded or that resulted in the nuclear plant being in a condition that was outside the design basis of the plant.

The following commitments are being made by this letter:

e Stroking of the A0 2-220-45 valve will be performed at varying frequencies to ensure the failure does not recur due to inactivity, e

At the next outage of sufficient duration, the valves and valve operators will be disassembled and inspected.

A supplemental re) ort. including ~any additional corrective actions e

determined, will )e submitted upon the completion of the investigation.

If there are any questions or coments concerning this letter, please refer them to Nick Chrissotimos. Regulatory Assurance Administrator at 309-654-2241, ext. 3100.

Respectfully.

COMMONWEALTH EDIS0N QUAD CITIES NUCLEAR POWER STATION

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G. G. Campbell Station Manager GGC/TB/pim Enclosure cc:

J. Schrage

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Quad Cities Unit Two 0l5l0l0l.0l2l6l5 I l of l 0 l 4 Tlee (4)

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ABSTRACT:

l At 0850 on 04/17/94, Unit-2 was in the Run mode at approximately 95% rated core thermal powar. During performance of quarterly Reactor Recirculation System Air Operated Valve i

Testing (QCOS 202-12), the inboard and outboard Reactor Recirculation (RR) sample isolation valves A0 2-220-44 and 45 failed to close. Additional attempts to close both valves were successful.

The valves were declared inoperable due to failure to meet inservice inspection testing (IST) requirements.

The valves A0 2-220-44 and 45 were verified closed and taken out of service at 1000, on 4/17/94.

At 1140 the station made a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ENS phone call under 10CFR50.72(b)(1)(ii), degraded j

condition while operating.

The cause of the event and recommended corrective actions will be determined based on continuing testing and investigation.

Further information will be provided as a supplement to this report.

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i LICENSEE EVENT REPORT (LER11TXT COPmMUATION Form Rev. 2.0 l

FACILRT NAME tU Du. At & NUMat.K (2)

LAR MUhaca (6)

FAGE (3)

Year sequeenal Revsmoe Number Number Quad Cities UnitTwo 0l5lol0l0l2 6l5 9l4 0l0l8 0l0 2 lOFl 0 l 4 j

it.ra Energy Induary idenuncanoo sysum (cam codes are useonced an me was as ai l

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PLANT AND SYSTEM IDENTIFICATION

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General Electric - Boiling Water Reactor - 2511 Wt rated core thermal power.

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EVENT IDENTIFICATION:

Inboard and outboard reactor recirculation sample isolation valves l

A0 2-220-44 and 45 failure to close during quarterly surveillance.

A.

CONDITIONS PRIOR TO EVENT

I Unit: Two Event Date: Aar11 17. 1994 Event' Time:

0850

]

Reactor Mode:

04 Mode Name:

RJN Power Level:

95 l

This report was initiated by Licensee Event Report 265\\94-008.

i RUN (4) - In this position the reactor system pressure is at or above 825 psig, and the reactor protection system is energized, with APRM protection and RBM interlocks j

in service (excluding the 15% high flux scram).

B.

DESCRIPTION OF EVENTS:

At 0850 on 04/17/94. Unit-2 was in the Run mode at approximately 95% of rated core thermal power.

During performance of quarterly Reactor Recirculation System Air Operated Valve Testing (0COS 202-12). the inboard Reactor Recirculation (RR) [AD]

4 sample isolation valve A0 2-220-44 [SHV]. failed to indicate closed (in the control j

room) when attempting to operate the valve.

[

The unit process computer indicated the valve had closed, however, open indication was noted on control panel 902-4. A second atte7t to close the valve was successful, with closed indication from both the process computer and the control panel.

The valve A0 2-220-44 was reopened per procedure.

l At 0853. the RR outboard sample isolation valve A0 2-220-45 was tested per the next step of OCOS 202-12. This valve also indicated closed on the process computer but failed to indicate closed on control panel 902-4.

Further closure attempts were made and on the fourth attempt the valve indicated closed on both the process computer and the control panel.

4 The valve A0 2-220-45 was reopened per procedure.

1 At approximately 0950 the valves were declared inoperable due to failure to meet inservice inspection testing (IST) requirements.

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LER265\\94W8.WPF l

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev. 2.0 FACUJTY NAME 0)

IXXM.I NUMBER (2)

LER NUMBER (6)

PAGEQ)

Year Sequennal Revision Number Number Quad Cities Unit Two 0l5l0l0l0l2 6l5 9l4 0l0l8 0l0 3 lOFl 0 l 4 in.u E crsy indunry saenuncaaon sysiem te:.iu, codes are 2 a.4 in in text as tx.x i The Unit-2 Supervisor generated priority Nuclear Work Requests (NWR) #015877 and

1. 015878 to investigate the event.

l The valves AD 2-220-44 and 45 were closed and taken out of service at 1000, on 4/17/94.

Isolation of the process sample line was verified by direct observation of no flow through the sample line at the sample sink.

4 After review of the event, the SE determined it was reportable at approximately 1045 on 4/17/94.

At 1140 the station made a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ENS phone call to the NRC under 10CFR50.72(b)(1)(ii), degraded condition while operating.

Problem Identification Form (PIF)94-967 was generated by the Operations Department on 4/17/94 to document the valves A0 2-220-44 and 45 failure to close.

C.

CAUSE OF THE EVENT

This event is being reported in accordance with 10CFR50.73(a)(2)(ii). The licensee shall report any serious degradation in the condition of the plant or safety barriers.

The investigation into the cause of the valves A0 2-220-44 and 45 failure to close is still in progress.

D.

SAFETY ANALYSIS

The failure of the valves A0 2-220-44 and 45 to close had no impact on the plant's operating conditions at the time of the event.

There is limited safety significance due to both sample isolation valves failing to close during the first attempt.

Had a Design Basis Accident occurred simultaneously with a break in the RR sample line the event is bound by FSAR analysis 15.6.2..

This section analyzes a scenario involving the reactor coolant pressure boundary and a 1 inch instrument line break outside of primary containment. The sample line isolated by A0 2-220-44 and 45 is a 3/4 inch line.

Failure of valves A0 2-220-44 and 45 did not place the station in an unanalyzed condition.

E.

CORRECTIVE ACTIONS

The imediate corrective actions associated with this event were to declare the valves A0 2-220-44 and 45 inoperable.

The NRC was notified, and priority NWR's were generated to investigate the valves failure to close.

LER265\\94\\008.WPF

i UCENSEE EVENT REPORT n.ER) TEXT CONTINUA 110N Form Rev.2.0 FACI 3.ITY NAME (I)

DOCKET NUMBER (2)

LER NUMBtR (6)

PAGEth Year Sequennal Revismo Number Number Quad Cities Unit Two 0l5l0l0l0l2l6l5 9l4 0l0l8 0l0 4 joFl 0 l 4 6 tal Energy latustry idenaficauon Sysicm (Lils) codes an Wenhed m the trat as (AX)

Recent failures of valve A0 2-220-45 to close were attributed to solenoid valve problems.

The solenoid was replaced as a preventive action under NWR #015878, on 4/21/94. The removed solenoid was bench tested, and disassembled for internal inspection.

No abnormalities were noted in respect to the bench test or internal inspection.

Continuing efforts to determine the cause of the event include investigation and testing of an appropriate stroking schedule for the valves and valve operators, as well as disassem)1y and inspection of the valves.

Stroking of valve A0 2-220-45 will be performed weekly, bi-weekly and then monthly to ensure the failure does not recur due to inactivity. Appropriate corrective actions for both the A0 2-220-44 and 45 valves will be determined based on the results of this testing (NTS# 2651809400801).

At the next outage of sufficient duration, the valves and valve oaerators will be disassembled and inspected. Appropriate corrective actions will Je taken based on the results of the inspections (NTS# 2651809400802).

A supplemental report. including any additional corrective actions determined, will be suamitted upon the completion of the investigation (NTS# 2651809400803).

The RR sample valves provide a primary containment isolation of the RR sampling pathway. With either valve inoperable, one valve must remain closed at all times.

The valve A0 2-220-44 will remain out of service closed until corrective actions for valve A0 2-220-45 can be determined.

F.

PREVIOUS OCCURRENCE:

I l

After review of the Nuclear Tracking System data base, there were no LER's generated in the past three years which involved RR sample isolation valve failure on either unit at Quad Cities Station.

G.

COMPONENT FAILURE DATA

There has not been any specific failed component identified in this event to date.

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LER265\\94\\008.WPF