ML19325C534

LER 89-014-00:on 890910,determined That Combined Leakage Rate from All Penetrations & Valves Exceeded Tech Spec Limit.Root Cause Unknown.No Corrective Action Taken. Supplemental Rept Will Be issued.W/891002 Ltr

ML19325C534
Person / Time
Site:	Quad Cities
Issue date:	10/02/1989
From:	Bax R, Rolfes J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-014-02, LER-89-14-2, RLB-89-215, NUDOCS 8910170014
Download: ML19325C534 (4)

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U. S. Nuclear Regulatory Commission '

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Reference:

-Quad Cities Nuclear Power Station

, r Docket Number 50-254, DPR-29, Unit One  ;

l Enclosed is Liceasee. Event Report (LER)89-014, Revision 00, for Quad' Cities j Nuclear Power. Station.

i This' report is submitted in accordance with the requirements of the Code of u Federal Regulations, Title 10, Part 50.73(a)(2)(1)(0) which states that the ,

licensee shall report _any operation or condition prohibited by.the plant's s

Technical Specifications. >

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- Respectfully, COMONWEALTH EDISON COMPANY

- QUAD CITIES NUCLEAR POWER STATION M gg l R. L. axl l Station Manager RLB/MJBlad

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. Enclosure

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. cc: R. Stols R. Higgins

.INPO Records Center NRC Region III f51>

2312H 'f 8910170014 891002 i' PDR ADOCK 05000254

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LICENSEE EVENT REP 0NT (LER) 7, ,, 7 ,

Facility name (1) Docket number (2) Pana #11

" tittaa unit ana el 11 of of ol 21 El 4 1 ef al3 f Title (4) Escoeding Technical Specification Leaksee Limits for Containment Isolation valves and Itain tinam f aalatian Valvet - cautet ta ha Datarained Event nata fE1 LER ' " -- f 61 amaart Data (7) Other Farilitiet Involved fal Month Day Year Year, Setpuential [ Revision Month Day Year -Facility mamat DockgLNumberftl el El of of of f I

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al's 11 e al e al a oIiI4 oIo 1 Ie of 2 al e of si el el of I I THi$ REP 0ET Is sUSMITTED PUR$uANT TO THE REQUIREMENTS OF 10CFR f thack ana er mera of the followinal fit) 1 20.402(b) __ 20.40$(c) 50.73(a)(2)(iv) .,, 73.71(b)

POWER 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)

LEVEL 20.405(a)(1)(11) _ 50.36(c)(2) 50.73(a)(2)(v11) ___ Other (Specify flo) o!olc 20.405(a)(1)(iii) L 50.73(a)(2)(1) _ 50.73(a)(2)(viii)(A) in Abstract

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Litthift CONTACT FOR THIS,LER f121 Name T[LEPHAMr NLMtR AREA CODE

_.1av kalfen. Technical staff tnainaar. Ext. 21&c 31019 El El 41 -l 21 21 el toMPLETE ONE LINE FOR [ACH toMPON T FAILUAE DEstRIBED IN THIS REPORY (13)

CAUSE SYSTEM COMPcNENT MANUFAC. REPORTABLE CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE TURER TO NPRDS TURER TO NPRDS I I I l 1 l l l l l 1 1 I I I I l l l 1 i / l l l l 1. _ I I SUPPLEMENTAL ttPotf EXPECTED (141 Expected Month I oav l Year Submission r Ivan (If van. ensniate ExPttT[o cinMissroh Daft) l NO Date 0 5) ,, 3 l3;,l,,,

ABSTRACT (Limit to 1400 spaces, i.e, approximately fifteen single-space typewritten lines) (16)

On September 10, 1989, Quad Cities Unit One was shut down for the end of cycle 10 refueling and maintenance outage. At 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br /> while local leak rate testing (LLRT) the Drywell/ Torus purge volume [VB] bounded by A0-1-1601-23, 24, 60, 61, 62, ,

and 63 valves [NH][ISV), it was determined that the measured combined leakage rate I of 522.0 standard cubic feet per hour (SCFH) from all penetrations (PEN) and valves

[V) eFCluding the Main Steam (SB] Isolation Valves (MSIV) (ISV) had exceeded the Technical Specification 3.7.A.2.a.2 limit of 293.75 SCFH (0.6 La).

On September 11, 1989, at 2035 hours0.0236 days <br />0.565 hours <br />0.00336 weeks <br />7.743175e-4 months <br /> while performing LLRT on the Unit One Main Steam Isolation Valves A0 1-203-2A and A0 1-203-2D were found to leak in excess of the Technical Specification (3.7.A.2.a.3) limit of 11.5 SCFH. A0 1-203-2A leaked at a rate of 27.65 SCFH and A0 1-203-2D leaked at 24.19 SCFH.

The-root cause of the excessive leakages will not be known until repairs have been completed and the valves have been retested. No corrective action has been taken at this time. A supplemental report will be issued to document the causes and corrective actions taken to bring the combined leakage and the MSIV leakage below the required limits. This report is being submitted to comply with 10CFR50.73(a)(2)(1)(B).

2253H/06602

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,  : PLANT AND SYSTEM IDENTIFICATION: ,

" General' Electric - Bolling Water Reactor - 2511 MWt rated core thermal power.

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EVENT IDENTIFICATION: Exceeding Technical Specification Leakage Limits for -

Containment Isolation Valves and Penetrations and Main l Steam Isolation Valves - Causes to ba Determined

, A. CONDITIONS PRIOR TO EVENT:  :

Unit:' One Event Date: September 10, 1989 Event Time: 0955 Reactor Mode: 1 Mode Name: SHUTDOWN Power Level: 00% ,

This report was initiated by Deviation Report D-4-1-89-075 and Supplement 1. [

SHUTDOWN Mode (1) - In this position, a reactor scram is inttlated, power to the control rod drives is removed, and the reactor protection trip systems have been deenergized for 10 seconds prior to permissive for manual reset. ,

B. DESCRIPTION OF EVEN1

On September 10, 1989, Unit One was shut down for the end of cycle 10 refueling and -

maintenance outage. On September 10, 1989, at 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br /> while performing local leak rate testing (LLRT), the Drywell/ Torus purge volume (VB) bounded by A0-1-1601-23, 24, 60, 61, 62, and 63 valves (NH][ISV) was found to have a leakage >

rate of.522.0 standard cubic feet per hour (SCFH). During this event, the e Technical Specification (3.7.A.2.a.2) limit of 293.75 SCFH (0.60 La) combined l 1eakage from all valves (NH)[ISV) and penetrations (NH][ PEN) except Main Steam (SB) j 1

Isolation Valves (ISV) (MSIV) was exceeded.

On September 11.-1989, at 2035 hours0.0236 days <br />0.565 hours <br />0.00336 weeks <br />7.743175e-4 months <br /> while performing LLRT on the Unit One MSIVs, A0 1 203-2A was found to have'a leakage rate of 27.65 SCFH and A0 1-203-2D a 1 -leakage rate of 23.04 SCFH. While performing a check of the leakage rate

calculations. l-203-20 was actually determined to leak at 24.19 SCFH. The rate for l .both valves exceeded the Technical Specification (3.7.A.2.a.3) limit of 11.5 SCFH for any one MSIV.

The failure mode for.these and other valves (V) and penetrations to be tested during the' refuel outage is not known at this time, since the testing and repair of these. items is not complete. A supplemental report will be submitted when all valves and penetrations are repaired and tested.

.C.- APPARENT CAUSE OF EVENT: .

L l This report is being submitted to comply with the requirements of 10CFR50.73(1)(2)(1)(B) which states that the licensee shall report any operation or condition prohibited by the plant's Technical Specifications.

L' The cause of the excessive leakage cannot be determined until repairs have been

' completed and the valves have been retested. A supplemental report documenting these repairs and any corrective actions taken will be issued.

22s3H/0660Z

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D. SAFETY ANALYSIS OF EVENT. ,

l The safety consequences of this_ event were minimal-since LLRT is a conservative method for-quantifying containment leakage. The actual leakage under accident

• L conditions would be less than that determined by LLF.T. because some lines would be  !

filled with water rather than air, and some lines would be isolkted by non-primary  !

containment isolation valves [NG)[ISV). Also, where more than one valve is present i

'in a line, as in the case of the MSIVs it is realistic to expect the leakage to be equal to tha lesser leakage of the two valves. However, the maximum pathway  !'

leakage is used for comparison with the Technical Specification requirements, which assume the best valve fails to isolate and the leakage is equal to the greater i leaktge of the two valves. ,

Secondary Containment [JM) and the Standby Gas Treatment [BH] system were operable  !

.to provide additional safety barriers.  :

t E. CORRECTIVE ACTIONS:

No corrective actions have been taken at this time. A supplemental report will be ,

Issued which will document the corrective actions taken to bring the combined leakage and the MSIV leakage below the required limits. 1.

F. PREVIOUS EVENTS: ,

265/88-007 Leak Rate From all Valves and Penetrations Excluding MSIVs on Unit Two in Excess of Technical Specification 1mit (

t 254/87-016 Leak Rate From all Valves and Penetrations Excluding MSIVs on Unit One in Excess of Technical Specification Limit 265/86-014 Leak Rate From all Valves and Penetrations Excluding MSIVs on Unit Two in Excess of Technical Specification Limit 254/86-002 Unit One MSIV in Excess of Allowable Leakage i 265/86-013 Unit Two MSIV in Excess of Allowable Leakage l 265/86-006 Unit Two MSIVs in Excess of Allowable Leakage These are the most recent reported events; other failures have occurred previous to ,

1986.

G. COMPONENT FAILURE DATA:

L Component. failure data is not available at this time since repairs have not been L completed. Failure data will be included in the supplemental report.

l' 22s3H/06602 l

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