ML20029D803

LER 94-003-00:on 940404,two Flow Orifices Were Improperly Installed.Caused by Improper Installation of All Accessible Flow Orifices.Personnel Performed Procedure Ost 1.6.4 Correcting Improperly Installed orifices.W/940504 Ltr

ML20029D803
Person / Time
Site:	Beaver Valley
Issue date:	05/04/1994
From:	Freeland L DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-003-01, LER-94-3-1, ND3MNO:3567, NUDOCS 9405100120
Download: ML20029D803 (5)

Text

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"2';;?! "."PA 150774J004 Shippingport May 4,1994 ND3MNO:3567 Beaver Valley Power Station, Unit No.1 Docket No. 50-334, Licensee No. DPR-66 LER 94-003-00 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

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

LER 94-003-00,10 CFR 50.73.a.2.i.B, " Improperly Installed Flow Orifice."

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g L. R. Freeland General Manager Nuclear Operations STC/cip l Attachment l

9405100120 940504 1 gDR ADOCK 0500 4

4 May 4,1994 ND3MNO:3567 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. l Independence, OH 44101-4661 l l

INPO Records Center 700 Galleria Parkway Atlanta, GA 30339-5957 l

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

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

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• NRC FORN1366 U.S. NUCLEAR REGUL.ATORY CONINilSSION APPROVED IlY ONtil NO. 3150-0104 (5-12) ,

EXP1REN 5/31/95 ESTIMATED BURDEN PER RESPONSC TOCOMPLY WnllTills INFORMATION COLLECnON REQUEST 50 0 HRS FORWARD LICENSEE EVENT REPORT (LER) COMuENTs REoARoiNo neRDrN trnuaTr TO THE iNrOkMA110N AND RECORDS MANAGl:MLNT 11RANC}l(MNbB Tfl4 U S NUCLEAR (See revene for required number of digits characters for each block) .

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NAath TE11 PHONE NUNtUER (mdude Area Cedel L. R. Freeland, General Manager Nuclear Operations (412)643-1258

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ABSTRACT (l.irnt to 1400 spaces, i c , approximately 15 single-spaced t)pewntien hnes) (16)

On April 4,1994 at 1330 hrs, two flow orifices used to verify compliance with the Reactor Coolant Pump controlled leakage i Technical Specification limits were found to be improperly installed. Because these orifices are sensitive to flow orientation, the actual flow could be as much as 20 % greater than indicated.

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. At 1729 hrs, a controlled leakage calculation was performed using this 20 % correction factor for the "B" and "C" reactor coolant pumps. Results showed that the controlled leakage was greater than the Technical Specification limit. Flows were adjusted within limits.

A review of the past year's controlled leakage calculations was performed correcting for these orifices being installed backwards. It showed that the controlled leakage technical specification limit had previously been exceeded.

l l Therefore, this event is being reported in accordance with 10CFR50.73a.2.i.B as a condition prohibited by Technical Specifications.

The safety implications of this event were minimal. The basis for the controlled leakage limit is to ensure that safety injection flow will not be less than that assumed in the accident analysis. Engineering analysis shows that minimum required safety injection flow required by the accident analysis would have been available.

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DESCRIPTION OF EVENT

, On April 4,1994 at 1330 hrs, flow elements FE-CII-127 and FE-CH-124 were found installed backwards. These elements measure seal injection flow on the "B" and "C" reactor coolant pumps and are used to determine controlled leakage in accordance with Technical Specification 16 4 2, " Reactor Coolant Sy stem Leakage." Because actual controlled leakage was unknown, Technical Specification 3.6.4.2 action statement was invoked at this time.

At 1710 hrs, the station received verbal notification from Westinghouse Engineering that with these orifices installed backwards actual flow could be as much as 20 % greater than indicated. This correction factor was based on engineering judgement developed through experience of evahtating incorrectly installed orifices at other Westinghouse operating plants for similar applications.

At 1729 hrs, the controlled leakage calculation, Operations Surveillance Test (OST) 1.6.4, was performed using this 20 % correction factor for the "B" and "C" reactor coolant pumps. Results showed that the controlled leakage was greater than the 28 gpm Technical Specification limit. The flows ucrc adjusted within limits and Technical Specification action statement was no longer applicabic.

A review of past controlled leakage calculations was performed correcting for these orifices being installed backwards. The results showed that the controlled leakage technical specification limit of 28 gpm had previously been exceeded.

Therefore, the station had operated in a condition prohibited by Technical Specifications. Further follow-up evaluation by Westinghouse Engineering of similar events supported their initial 20 % correction.

CAUSE OF EVENT A review of past maintenance did not identify any previous work which could have reversed the orifices.

The cause of this event was determined to be improper installation of flow orifices FE-CH-124 and 127. Because these orifices are beveled, they are sensitive to flow path direction.

CORRECTION ACTIONS The following corrective actions have been or will be taken as a result of this event:

1. Operations personnel performed procedure OST 1.6.4, " Measurement of Controlled Leakage" correcting for the improperly  ;

installed orifices and verified compliance with controlled leakage limits by adjusting flow s.

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2. The System Engineers verified proper installation of all accessible flow orifices used to satisfy Technical Specification l Surveillance Requirements and other testing requirements. Inaccessible orifices at current plant conditions will be inspected during Unit i 10R and Unit 2 5R. At present one additional beveled orifice was found incorrectly installed, however Technical Specifications were not affected.

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3. The improperly installed orifices will be corrected during the nc.st refueling outage or entry into mode 5.

REPORTABILITY This report is being submitted in accordance with 10CFR50.73.a.2.i.B because the station operated in a condition prohibited by I Technical Specifications.

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TEXT (!/mcwo gace os roepoured. use addars<malcuynes ofARC f um tut,(l7) l SAFETY IM PLICATIONS The safety implications of this event ucre minimal. The basis for the controlled leakage limit is to ensure that in the event of a i LOCA (Loss of Coolant Accident) safety injection How will not be less than that assumed in the accident analysis. j Engineering has analyzed this event and determined that safety injection now would not be less than minimum required design l i

Dow as a result of this event. l l

l PREVIOllS SIMil AR EVENTS No similar events have been previously reported involving improperly installed Don orifices.

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