ML20029D657

LER 94-005-00:on 940407,chain Locking Mechanism on CP Suction Isolation Valve,Was Found Broken.Caused by Personnel Error.Corrective Action:New Chain Placed on Valve Handwheel & Chain Locking Mechanism intacted.W/940506 Ltr

ML20029D657
Person / Time
Site:	Beaver Valley
Issue date:	05/06/1994
From:	Freeland L DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-005, LER-94-5, ND3MNO:3568, NUDOCS 9405090195
Download: ML20029D657 (5)

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'Af Telephone (412) 393-6000 Bx4 Shippingport. PA 15077-0004 May 6,1994 ND3MNO:3568 1

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, Licensee No. NPF-73 LER 94-005-00 United States Nuclear Regulatory Commission i Document Control Desk Washington, DC 20555 Gentlemen:

In accordance with Appendix A, Beaver Valley Technical Specifications, the following Licensee Event Report is submitted:

LER 94-005-00,10 CFR 50.73.a.2.i.B, " Improper Locking of Charging Pump Suction Valve."

l 8 f fn L. . Freeland General Manager i I

Nuclear Operations clp Attachment 9405090195 940506 '

{DR ADOCK 05000412 """

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May 6,1994 ND3MNO:3568

- Page 2 cc: Mr. T. T. Martin, Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. G. E. Edison, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 Larry Rossbach, Nuclear Regulatory Commission, BVPS Senior Resident Inspector J. A. Hultz, Ohio Edison 76 S. Main Street Akron, OH 44308 Mark Burns Centerior Energy 6200 Oak Tree Blvd.

Independence, OH 441014661 INPO Records Center 700 Galleria Parkway Atlanta, GA 30339-5957 Mr. Robert Barkanic ,

Department of Environmental Resources l P.O. Box 2063 16th Floor, Fulton Building Harrisburg, PA 17120 Director, Safety Evaluation & Control Virginia Electric & Power Co.

P.O. Box 26666 One James River Plaza Richmond, VA 23261

i U.S. NUCLEAR REOULATORY COMMISSION APPROVED HY OMH NO. 315o4104 (5 92) EXPIRES 5/31/95 ES'MMATED BURDEN PER RESPONSE 1D COMPL,Y WrDiTIIS

. INFORMATION COLLECTION REQUEST 30 0 HR5 FORWMD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN EST1 MATT TO THE IN ORMATION l, AND RFCORDS MANAGEMENT BRANCH (MNBB Tflik t's NUCLEAR 2 1ANDTO (See reverse for required nurnber of digitveharacters for each block) ypyyg{M,MQg*,A,SH]

M AN AGFMFMr AND MUfYWr,WASHINcrrON, DC 20101 FACILTrY NAME(1) DUCKER NUMBER (2) .*AGE (3)

Beaver Valley Power Station Unit 2 05000412 , 1OF3 irru e)

Improper Locking of Charging Pump Suction Vahe EVENT DATE (5) 1.ER NUMHER (6) l REPORT NUMBER (7) OTi!ER FACILITIES INv0LvED '

sEQUEKrlAL REVISION CKET NUMBER MONDI DAY FACILrrYNAME MA MONDI DAY YEAR YEAR NUMBER NUMBER YEAR 05000

'^'YY N AM E DOCKET NUMBLR 04 07 94 94 - 005 - 00 05 06 94 05000 OPERATINO Tills REPORT IS SUlBil'ITED PURSUANT TO Ti!E R.EQUIREMENTS OF 20 CFR R (Check one or nwre)(11)

MODE (9) 1 20.402(b) 20.405(c) 50.73(aX2Xiv) 73.71(b)

POWER 20.4054aylXi) 50.36(cyl) 50.73(ay2Xv) 73.71(c) 11 VEL (10) 100 20.405(a)(lXia) 50.36(cX2) 50.73(aX2 Xvii) OTiiER (spa 4m abanet 20.405(aYIViii)) X $0.73(aX2Xi) 50.73(aK2XviiiXA) 50.73(aX2Xii) 50.73(sX2XviiiXB) t=k= end m Text l 20.405(aXIXiv) 20 405(aXIXv 50.73(aX2Xiii) 50.73(aX2Xx) NRC Fona 3MA) 1.lCENSEE CONTACT FOR Tills 1.ER (12)

TAMg TELEPliONE NUMilER (swiude Area Code)

Irrry R. Freeland, General Manager Nuclear Operathms (412) 643-1258 COMPLETE ONE I INE FOR EACH COMPONENT FAILURE DESCRIBED IN TlflS REPORT (13)

CAUSE si3 TEM COMPONtNT MANUFACTURER REPURIAHLE COMPONEVr MANUF AC"rURLR REPORTABLE TO NPRDS TU NPRDS l A BQ XXXX XXXX N l

SUPPL EMENTAL REPORT EXPECTED (14) EXPECTED MONTil DAY YEAR l

YES X No SUHMISSION

Of yes. complete EXPECTED SUBMISSION DA1T) DATE AllsTRACT (Lunt to 1400 spaces, i e., approximately 15 amgle-spaced typewritten imes) (16)

On April 7,1994, the chain locking mechanism on a Charging Pump Suction Isolation Valve, 2CilS*MOV8130A, was found broken. This valve is one of four series suction valves that can be aligned to provide separate suction flowpaths following a loss of ecolant accident. This valve is normally locked and de-energized in the open position. The chain was found routed through the valve yoke such that when the valve was energized and closed, the chain was stressed and broken. In addition, the valve handwhccl stem was bent. The last valve closure occurred on 10/23/93 in support of a tag-out evolution and it appears that this valve stroke stressed and fractured the chain. Technical Specifications require this valve to either be locked in the open position or verified open by surveillance once every 31 days. A new chain was immediately placed on the valve handwhcci and routed such that valve stroking will not interfere with the chain. All padlocked motor operated valves outside containment were inspected and found to l have the chain locking mechanism routed in the correct manner. There were no safety implications as result of this event. The Charging Pump Suction Isolation Valve,2CilS*MOV8130A, was maintained de-energized in the open position throughout the time period when the locking mechanism was believed to be degraded.

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, NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMH NO.3150-0104 (5 92) EXPIRFS N31/95 ErnMATED BURDEN PER RESPONSE TO COMPLY %Tm 71118 INFORMATION COLLECDON REQUETr: 30 0 HR$ FORWARD LICENSEE EVENT REPORT (LER) cOuuturS REGARDING BURDEN ESUMATER)THE INFORMATION TEXT CONTINUATION AND RECORDS MANAGFMEWT BRANCH (MNBB 7714), U.S. NUCLEAR RECAJLATDRY COMMISSION. WASHINGTON, DC 20553-0001. AND TO THE PAPERWORK REDUCnON PROJECT QlS0-0104),OFTICE OF MAN AGEMENT AND Br_fDGET, WASHINGTON, DC 20101 FACILITlY NAME (1) rXX'K ET NUMBER (2) LER NUMBER (6) PAGE (3)

SEQUENTIAL REVISION Beaver Valley Power Station Unit 2 05000412 YEAR NUMBER NUMBER 94 005 00 2OF3 nxT ut.~ w u na m .m.,awa8tacw mv(17)

DESCRIPTION OF TIIE EVENT On April 7,1994, the chain locking mechanism for a Charging Pump Suction Isolation Valve,2CHS*MOV8130A, was found to be broken. This suction valve is one of four scrics suction valves that can be aligned to provide separate suction flowpaths following a loss of coolant accident. This valve,2CIIS*MOV8130A, is normally locked and de-energized in the open position. The chain was found routed through the valve yoke such that when the valve was energized and closed, the chain was stressed and broken.

Additionally, the valve handwhcci stem was bent. The last valve closure occurred on 10/23/93 in support of a safety tag-out evolution. The valve had been electrically stroked closed from the benchboard prior to the tag-out. It appears that this valve closure performed on 10/23/93, stressed and fractured the chain. Technical Specification surveillance requirement 4.5.2.c.1 requires this valve to be either locked in the open position or verified open by surveillance once every 31 days.. Subsequent to this valve closure, other activities were performed on the valve and valve operator prior to the plant startup. During these activitics, the loose chain ends may have been inappropriately repositioned on a stud bolt on the rear of the motor operator. The repositioning gave the appearance of the chain being unbroken. Subsequent visual and " hands-on" pulling of the chain, performed 11/3/93 through 2n/94, failed to identify this discrepancy. The broken chain was discovered by an NRC inspector on 4D/94, with the valve still in its correct position .

CAUSE OF Tile EVENT The cause for this event was personnel error. The chain locking mechanism was routed through the valve yoke such that when the valve was energized and closed, the chain was stressed and broken. Additionally, the improper repositioning of the broken chain ends, and not reporting the deficiency to the control room, centributed to this event. The surveillance verifications of the locking mechanism also failed to identify the chain failure.

CORRECTIVE ACTIONS The following corrective actions have been take as a result of this event:

1. A new chain was placed on the valve handwhcci and routed such that valve stroking will not interfere with the chain. The valve was verified to be properly locked following installation of the new chain.

2. All padlocked motor opuated valves outside containment were inspected and found to have the chain locking mechanism intact and routed in the correct manner .

3. An investigation was conducted to identify all evolutions involving this valve from the time it was previously unlocked until the event date. All individuals that could be identified were intersiewed to determine when the valve was improperly chained and when or how the chain ends were placed over the stud bolt on the rear of the motor operator. This investigation determined when the valve was improperly chained, but could not identify w hen the repositioning of the broken chain ends occurred.

4. The valve condition was inspected and evaluated to confirm that the stress placed on the valve handwhccl assembly did not affect valve operability.

NRC FORM MA (3-92)

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, NRC f ORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 31504104

($-92) EXP1RES 5/31/95 ESTIMATED BURDFN PER RESPONSE 10 COMPLY %TDITHIS

[NFORMATION COLLECDON REQUEST So 0 HR3 FORWARD LICENSEE E\ RENT REPORT (LER) COMMENTS REGARDING BURDEN ErnMA11510'nlE INFORMA110N TEXT CONTINUATION AND RECORD 5 MANAGEMENT BRANCH (MNBB 7714),U S N1LY' LEAR REGULA1 DRY COMMISSION, WASHINGON, DC 20351-0001, AND TO THE PAPERWORK REDUCTION PROJECT 01WO104), OFTICE OF MANAGEMEVT AND BUDGFT, WASHINGTON, DC 20%3 FACll.!TlY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

SEQUENTIAL REVISION Beaver Valley Power Station Unit 2 05000412 YEAR NUMBER NUMBER 94 005 00 3OF3 TTXT (llenore pace u reqmrol awe addsnonal ecpus ofhRCMe X44 { l 7)

5. This event will be reviewed by Licensed and Non-Licensed Operations and Maintenance personnel to emphasize the need to correctly lock a component and proper verification methods. Proper actions upon discovery of a locking defect such as a broken chain will be stressed.

REPORTABILITY This written report is being submitted in accordance with 10CFR50.73.a.2.i.B, as a condition prohibited by Technical Specifications.

Since the valve was not properly locl<cd, ulve position surveillance was required to be performed once every 31 days. This position surveillance was not performed.

SAFETY IMPLICATIONS There were no safety implications as result of this event. The Charging Pump Suction Isolation Valve,2CIIS*MOV8130A, was maintained de-energized in the open position throughout the time period when the locking mechanism was believed to be degraded.

An evaluation of the elTects of this event concluded that the valve was operable, and that there was no impact on the core damage frequency or the probabilistic risk assessment pertaining to the safety injection system.

PREVIOUS OCCURRENCES A review of plant records for the previous five years determined this to be the first reported occurrence in recent history involving a deficient locking mechanism. I I

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