ML20012B296

LER 90-003-00:on 900205,determined That Leakage Rate for HPCI Sys Steam Exhaust Check Valve Exceeded Tech Spec Limits.Caused by Excessive Leakage.Check Valve Replaced W/ Mission Check Valve W/Carbon Steel springs.W/900305 Ltr

ML20012B296
Person / Time
Site:	Quad Cities
Issue date:	03/05/1990
From:	Bax R, Rolfes J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-003-02, LER-90-3-2, RLB-90-073, RLB-90-73, NUDOCS 9003140147
Download: ML20012B296 (5)

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,. Quad Cities Nuclear Power Station 22710 206 Avenue North '

l ooreova, Illinois 61242 j Telephone 800/664 2241 l

RLB-90-073 1 I

March 5, 1990 l

i U. S. Nuclear Regulatory Commission l Document Control Desk Hashington, DC 20555 i

Reference:

Quad Cities Nuclear Power Station Docket Number 50-265, DPR-30 Unit Two -

Enclosed is Licensee Event Report (LER)90-003, Revision 00, for Quad Cities l Nuclear Power Station.

This report is submitted in accordance with the requirements of the Code of Federal Regulations. Title 10, Part 50.73(a)(2)(1)(B): The licensee shall ,

report any operation or condition prohibited by the plant's Technical ,

Specification.  :

Respectfully, COMMONWEALTH EDISON COMPANY i QUAD CITIES NUCLEAR POWER STATION i b

R. L. Bax Station Manager RLB/MJB/eb Enclosure cc: R. Stols  ;

R. Higgins INPO Records Center NRC Region III 7/

9003140147 900305 PDR ADOCK 05000263 y S PDC g

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LICENSEE EVENT REPORT (LER) rarm Rev 2.0

'8 Facility name (1) Docket humber (2) Pane ts) ha Citiet unit Two of El el of of 21 61 1 1 of a 4 Title (4)' Exceeding Technical specifi:stion Leakage Limit for Containment Isolation Valves and Penetraliant Due to Excettive Leakane f rom HPCI Steam Exhaust Check Valve Event Date (1) t[R N ar (6) Reoort cate (7) Other Facilitiet involved (R)

Month Day Year Year / secuential /j/j/ Revision Month Day Year Facility Namet Docket Numberft1

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/ Ma r j/// Number of si 01 of of I l

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of 2 of n 910 910 c!oi3 oIo oi3 oft of e of El of of of I I p TH!s REPORT Is SUBMITTED PURSUANT 10 THE REQUIREMENTS OF 10CFR ftheek one or more of the followine) till 1 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)

PDWCR _ 20.405(a)(1)(1) 50.36(c)(1) _ $0.73(a)(2)(v) ,_ 73.71(c)

LEVEL _ 20.405(a)(1)(11) __ 50.36(c)(2) _ $0.73(a)(2)(vii) __ Other (specify flei o!o!O _ 20.405(a)(1)(111) _X 50.73(a)(2)(1) _ 50.73(a)(2)(v111)(A) in Abstract

///////////////////,/////// 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(v111)(B) below and in

//////////////////'/ j

/////// 20.405(a)(1)(v) $0.73(a)(2)(iii) 50.7)(a)(2)(u) Text)

L1t[NSEE CONTAtt FOR THl$ LER (121 Name Jay Rolfes. Technical $taff Engineer. Extension 2160 TELEPHONE NUMBER AREA c00E 3 Io19 61 s1 41 -l 21 21 al COMPLETE ONE LINE FOR EACH COMPO FAILURE DEttRIBED IN THIS REPORT (11) cAU$E SYSTEM COMPONENT MANUFAc. REPORTABLE CAUSE SYSTEM COMPONENT MANUFAt- REPORTABLE TuttR TO NPRDS TURER TO NPRDS

• x al J l 11 Si y M! 31 61 o Y I I l l l 1 I i l I I I I I I I I I I I I

$UPPLEMENTAL REPORT EXPECTED (141 Expected Month l Day l Year Submission X lYet fif vet. complete EXPECTED SUBMISSIDN oATE) l ND (

ol6 l3ll l910 ABSTRACT (Limit to 1400 spaces. i.e. approximately fif teen single-space typewritten lines) (16)

ABSTRACT:

On February 4, 1990, Quad Cities Unit Two was shutdown for the end of cycle 10 refueling and maintenance outage. On February 5,1990, at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, while local leak rate testing (LLRT) the High Pressure Coolant Injection (HPCI) system steam exhaust check valve, it was determined that the measured leakage rate of 528.6 standard cubic feet per hour (SCFH) exceeded the Technical Specification 3.7.A.2.a.2 limit of 293.75 SCFH (0.60La) for all valves and penetrations excluding >

the main steam isolation valves (MSIV).

The apparent cause for exceeding the Technical Specification 0.6 La limit was due to the excessive leakage of the HPCI steam exhaust check valve. Corrective action will include repairing / replacing the valve and initiating a study to determine a replacement valve for this application due to previous problems encountered. A supplemental report will be issued to document the progress of this study, report any additional valves which are found to leak excessively and the actions taken to L bring the combined leakage below the required limit. This report is being p submitted to comply with 10CFR50.73(a)(2)(1)(B).

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, tfftkitt EVtkT ktPORT fttR) Ytri tokTfkuAf f 0N Form Rev 2.0

't FACILITY NAfE (1) DOCKET NUMttR (2) tre kuMatR (6) Pane f31 j//

.s Year ~ /j/j/ sequential Revision  ;

,- j/// Number // g// N'=har th d fitiet Unit Two 0 l E l 0 l 0 1 0 l 21 6l E 010 - 0 l0l1 - 0l0 01 2 0F 014 I TEXT Energy Industry Identification system (t!!s) codes are identified in the text as [Xxl PLANT AND SYSTEM IDENTIFICATION:

L General Electric - Bolling Water Reactor - 2511 MWt rated core thermal power, j EVENT IDENTIFICATION: Exceeding Technical Specification Leakage Limit for Containment  !

Isolation Valves and Penetrations Due to Excessive Leakage from  ;

HPCI Steam Exhaust Check Valve., ,

A. CONDITIONS PRIOR TO EVENT:

Unit: Two Event Date: February 5, 1990 Event Time: 1730 Reactor Mode: 1 Mode Name: Shutdown Power Level: 007.

This report was initiated by Deviation Report D-4-02-90-004 -

Shutdown Mode (1) - In this position, a reactor scram is initiated, 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 EVENT:

On February 4, 1990, Unit Two was shutdown for the end of cycle 10 refueling and maintenance outage. On February 5,1990, at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, while performing local leak rate testing (LLRT) in accordance with QTS 100-18. HPCI Steam Exhaust Local Leak Rate Test (2301-45), the High Pressure Coolant Injection (HPCI)[BJ) steam exhaust check valve (NH)[ISV), CV-2-2301-45, was found to have a leakage of 528.6 standard cubic feet per hour (SCFH). The Technical Specification 3.7.A.2.a.2.  ;

limit of 293.75 SCFH (0.60La) combined leakage from all valves (NH)[ISV) and penetrations [NH][ PEN) except the Main Steam Isolation Valves [ISV)(MSIV) was exceeded.

The failure mode for this valve is not known at'this time since repairs have not been completed. Action Item Record 4-90-5 has been initiated to determine a replacement valve for the application. A supplemental report will be issued to document the progress of this study, to report any additional valves which are '

found to leak excessively and the actions taken to bring the combined leakage below the required limit.

'C. APPARENT CAUSE OF EVENT:

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

The apparent cause of the excessive leakage of the HPCI steam exhaust check valve CV 2-2301-45 cannot be determined until the valve is disassembled and inspected for repair. A supplemental report will be issued to document the results of the valve inspection and any corrective actions taken.

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i LIffkttf EVENT RENikt f t[R) ItXT tokfiktlAffbN Fore Rev 2.0 t FACILITY NAMI (1) DOCKEi NUMBER (2)  !*t kuMatt f6) Pane f31 i

Year p/,/,/

seguential // Revision l

/// u d er ,//p/,/ M *= r w ettias unit Tuo o I s I e I o 1 o 1 21 si s clo - oIe13 . oIe el 3 or 014 ftxt. Energy Industry Identification system ([11s) cooes are identified in the text as [xx) r D. SAFETY ANALYSIS OF EVENT:  ;

i e The safety consequences of this event were minimal since LLRT is a conservative  !

method for quantifying containment leakage. The actual leakage under accident j conditions would be less than the maximum pathway leakage determined by LLRT for  ;

several reasons. For example, when two valves in series are tested by pressurizing i between the two, the combined leakage of the two valves is considered the maximum pathway leakage for that penetration. The true maximum pathway leakage is the greater leakage of either individual valve, which could be significantly less than

'the combined leakge of the two valves. In addition, the minimum pathway leakage, i which is the lesser leakage of two valves in series, is a nere realistic leakage for a given penetration than the maximum pathway leakage. j u  :

l The Standby Gas Treatment (BH] system (SBGT) was available during the event to l provide an additional barrier to prevent an uncontrolled release of radioactive materials in the event of an accident. The excessive air leakage of 2301-45 under <

LLRT conditions did not affect the ability of the HPCI system to perform its ,

intended function.  !

E. CORRECTIVE ACTIONS:

Tht immediate corrective action taken at this time was to initiate Action Item Record 4-90-5 to involve corporate engineering support in determining an alterrate valve for the HPCI steam exhaust system which is more suitable for the application. 1 Due to the leakage performance of the HPCI steam exhaust check valves CV 1(2)-2301-45, several attempts have been made to prevent the recturring failure cf these valves. In May 1985, the Unit Two HPCI steam exhaust check valve was replaced with a Mission check valve modified by Clow Corporation by replacing i carbon steel springs and bearings with stainless steel components. In March 1986, the Unit One check valve was replaced with a valve manufactured by C&S Valve Company with a seat made of a Nordel elastomer which was intended to be superior in i terms of resistance to high temperatures and low pressure steam than the previous valve seat material. The Unit One valve was replaced during the following refueling outage with a Marlin check valve which had an inlaid seat design which tas intended to prevent steam from directly impacting the seat surface.

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Littutti EVENT ktPORT f LtR) ttrf 00kTIMuATION Form tev 2.0 at L[TY NAMC (1) DOCKET NUMBER (2) LER NLMBtR f 61 Paae (3)

L e Year //

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$eguential

/p,/ Revision p/

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^"-d fitiet Linit Teso 0lE l 0 1 0 l 0 l 21 61 E 910 - 0l011 - 010 01 4 0F 014 ftxt Energy Industry Ioentification system (tits) codes are toentified in the text as [xxl F -. PREVIOUS EVENTS:

254/89-014 Exceeding Technical Specification Limits for Containment Isolation Valves and Main Steam Isolation Valves.

265/88-007 Leak Rate From All Valves and Penetrations Excluding MSIV's on Unit Two in Excess of Technical Specification Limit.

254/87-016 Leak Rate From All Valves and Penetrations Excluding MSIV's on Unit One in Excess of Technical Specification Limit.

265/86-014 Leak Rate From All Valves and Penetrations Excluding MSIV's on Unit Two in Excess of Technical Specification Limit.

These are the most recent reported events; other related events have occurred previous to 1986.  ;

i G. COMPONENT FAILURE DATA:

Component failure data is not available at this time, since inspections and repairs of failed components is not complete. Failure data will be included i in a supplemental report.

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