ML20046B548

LER 93-012-00:on 930702,discovered That Hydrogen Analyzer Inoperable During Quarterly Performance of Calibration Procedure.Test Personnel Contributed to Cause of Event.Test & Calibration Procedures Will Be revised.W/930730 Ltr

ML20046B548
Person / Time
Site:	Beaver Valley
Issue date:	07/30/1993
From:	Freeland L DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-012, LER-93-12, ND3MNO:3476, NUDOCS 9308050126
Download: ML20046B548 (8)

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Telephone (412) 393 6000 0 x4 Stuppingport, PA 15077-0004 July 30,1993 ND3MNO:3476 Beaver Valley Power Station, Unit No.1 Docket No. 50-334, Licensee No. DPR-66 LER 93-012-00 United States Nuc, w 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 93-012-00,10 CFR 50.73.a.2.i.B, Reactor Startup With A Wide-Range Containment Hydrogen Analyzer Inoperable."

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L. R. Freeland General Manager Nuclear Operations JHK/sl Attachment n3D118 a ,

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. .y July 30,1993 ND3MNO:3476 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. Holtz, Ohio Edison 76 S. Main Street Akron, OH 44308 Larry Beck Centerior Energy 6200 Oak Tree Blvd.

Independence, OH 44101-4661 INPO Records Center 700 Galleria Parkway Atlanta, GA 30339-5957 Mr. Robert Barkanic Department of Environmental Resources 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 W. Hartley Virginia Power Company 5000 Dominion Blvd.

2SW Glenn Allen, VA 23060

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July 30,1993 l ND3MNO:3476  :

Page 3  ;

.I J. M. Riddle f Halliburton NUS i Foster Plaza 7 ,

661 Anderson Drive Pittsburgh, PA 15220 i i

Bill Wegner, Consultant  !

23 Woodlawn Terrace i Fredricksburg, VA 22405 j i

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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 m ea EXPIRES 5/31/95 ETTIMATED BURDEN PE R HE LPONSE TO COMPty veta TH1 LICENSEE EVENT REPORT (LER) 2%E'E*Rr Es % $"$LAI!*O O ,d O*2 ANO RECORDS VANAGEMENT BRANCH (VNSE4 7714h U $. NgCdAq DEGULATORY COMM;ssrON. W A9H;NGTON, Z ;O'if E00Dt, AND TO THE' F AfiFTWORK REDUCTION PROSCT 131% C% Or' ice OF (See reverse for required number of digits / characters for each block) MANAGEMENT AND BUDGET, W ASHINGTON. DC M03 f ACILITV NAME (1) DOCKET NUMBER (2) PAGE (3)

Beaver Valley Power Station Unit 1 05000 334 1 OF Q4 181LE (4)

Reactor StaltUp With A Wide Range Containrnent Hydrogen Analyzer inoperable EVENT DATE (5) LER NUMBER (6i REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8) vwH DAv vFAn YEAR UONTH DAY YEAR A

F ACILirf NAML DOC ETNUVHER

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07 02 93 93 - 012 00 0 7 30 93 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 6: (Check one or moren (11)

MODE (9) 1 20 402(b) 20.405tc) 50.73ta)(2)0v) 73 71(b)

POWER 20 405taH1)b) 50 35(c)(1) 50.73(a)(2)(v) 73 71(c)

LEVEL (10) gog 20 405(a)(1Hu) 50.36(c)(2) 50 73(a)(2)(vn) OTHER 20.405(aH1)Dn) X 50.73;aH2)0) 50 73(a)(2)(vaiHA) # 4 mAb*ad 20 405(aH110v) 50 73(aH2)(h) 50.73(aH2)(viiiHB) (,Id A 20 405ta)(1)(v) 50.73ta)(2)Dr0 50.73(a)(2Hx)

LICENSEE CONTACT FOR THIS LER (12) f4AML IELEPHONt NUYi.!L h pnctuGe Ama Guue; L. R. Freeland. General Manager Nuclear Operations 4 1 2 643- 1258 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) cesE svsTEv ccunom NT MANui AC'UREh

]g CAUEE SYSTEM COMPONENT MANU3 ACTUNER

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J A IK XXXX XXXX N SUPPLEMENTAL REPORT EXPEC1ED (14) EXPECTED "" C^' 4" vts

" SUBMISSION er yn. wve* rxPEC'ED SJfMSSON DA'E) X DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 singie-spaced typewntten lines) (16)

On July 2, 1993, with Unit 1 operating at 100 % power, Hydrogen Analyzer H2A-1HY-101A was discovered to be INOPERABLE. The Hydrogen Analyzer was discovered INOPERABLE during the quarterly performance of Calibration Procedure 1MSP-46.04A-1, " Containment Hydrogen-Monitoring Loop H2-HY101A Calibration", when no sample flow was obtained through the analyzer. Investigation by Instrument and Control Technicians performing the calibration revealed that the flow control valves for Hydrogen Analyzer Flowmeters F2 and F3 were closed. The Technicians opened the flowmeter flow control valves and adjusted the flows to the values obtained on April 8 1993 during the previous calibration. On July 2, 1993, the calibration procedure was successfully completed and the Hydrogen Analyzer was declared OPERABLE. Further investigation revealed that the flowmeter flow control valves were mistakenly closed on April 19, 1993, during restoration from Surveillance Procedure 1BVI 1.46.3 " Wide Range Hydrogen Monitoring System Leak Test". With the discovery of the INOPERABLE Hydrogen Analyzer, it was determined that on June 15, 1993, Unit 1 entered Operational Mode 2 with one Wide-Range Hydrogen Analyzer INOPERABLE, a violation of Technical Specifications. The redundant Wide-Range Hydrogen Analyzer was OFERABLE at the time of the mode change.

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REQUIRED NUMBER OF DIGITS / CHARACTERS ,

FOR EACH BLOCK i

BLOCK NUMBER OF t NUMBER DIGITS / CHARACTERS i 1 UP TO 46 FACIUTY NAME [

DON MBER 5 3 IN ADDITION O 05000 3 VARIES PAGE NUMBER  ;

4 UP TO 76 THLE 5 EVENT DATE 2 PER BLOCK 7 TOTAL

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2 FOR REVISION NUMBER  !

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UP TO 18 - F ACILRY NAME OTHER FACILRES INRWD l 0 TOTAL - DOCKET NUMBER 3 lN ADDITION TO 05000 j 9 1 OPERATING MODE  !

10 3' POWER LEVEL  !

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'1 REQUIREMENTS OF 10 UR CHECK BOX THAT APPLIES P TO 50 FOR NAME I 12 LtCENSEE CONTACT 14 FOR TELEPHONE -;

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Description of Event:

Unit 1 was in Operational Mode 1 at 100% Power. On July 2, 1993 at 0210, during the quarterly performance of Calibration Procedure 1MSP-46.04A-I, " Containment Hydrogen Monitoring Loop H2-HY101A ,

Calibration", no sample flow was obtained on Wide-Range Hydrogen Analyzer H2A-1HY-101A. Investigation by Instrument and Control .

Technicians performing the calibration revealed that the flow control i valves for Hydrogen Analyzer Flowmeters F2 and F3 were closed. The l Nuclear Shift Supervisor was notified of the problem and H2A-1HY-101A was declared INOPERABLE. The Nuclear Shift Supervisor requested the Technicians to verify that the flowmeter flow control valves on the redundant Wide-Range Hydrogen Analyzer, H2A-1HY-101B were in the proper position. At 0320 on July 2, 1993, flowmeter flow control valves for H2A-1HY-101B were verified to be in the proper position and H2A-1HY-101B was considered OPERABLE. The Technicians obtained a copy of 1MSP-46.04A-I, performed on April 8, 1993, and adjusted the flowmeter flow control valves to obtain the previously recorded flowrates. 1MSP-46.04A-I was successfully completed for H2A-1HY-101A at 1510 on July 2, 1993 and the Hydrogen Analyzer was declared OPERABLE.

An investigation following this incident determined that the_ Hydrogen Analyzer Flowmeter Flow Control Valves, F2 and F3 were closed during the Ninth Refueling Outage during restoration from Surveillance Procedure 1BVT 1.46.3, " Wide Range Hydrogen Monitoring System Leak

Test". The procedure instructed the test personnel to fully open the flowmeter flow control valves to ensure that the entire Hydrogen Analyzer System was leak tested. There were no test procedure steps to return the flowmeter flow control valves to their normally throttled position following completion of the test. The test personnel mistook the throttled flow control valves as being initially closed, and therefore closed the flowmeter flow control i valves at the conclusion of the test. IBVT 1.46.3 was also performed t i

on April 19, 1993, for Hydrogen Analyzer H2A-1HY-101B. H2A-1HY-101B was calibrated on June 4, 1993 while Unit 1 was still in Operational -

Mode 5; however, no indication that its flowmeter flow control valves were found in the closed position was reported.

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Cause of the Event:

i Two factors contributed to this event:

1) The test procedure did not include a restoration step (s) for the hydrogen analyzer flowmeter flow control valves. Usually ,

when a valve is in a throttled position, the number of turns required to place that valve in the test position is counted and recorded so that it can be returned to its original position upon completion of the test.

2) The test personnel were not familiar with the operation of the Wide-Range Hydrogen Analyzers and believed that the flowmeter ,

flow control valves would be adjusted during operation to obtain the desired flowrate.

Corrective Actions:

Immediate: The flowmeter flow control valves for the redundant HydrocJen Analyzer H2A-1HY-101B were immediately verifled to be in the proper position. The flowmeter flow control valves for Hydrogen Analyzer H2A-1HY-101A were adjusted to obtain the flowrate ,

recorded in the previously performed calibration procedure.

Long Term: 1) Test procedure, 1BVT 1.46.3 will be revised to maintain positive control of flowmeter flow control valve position throughout the test.

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2) Calibration procedure, IMSP-46.04A-I will be revised to provide the procedure performer with required flowmeter flowrates.

3) Personnel involved with the performance of both ,

the calibration and the testing of the Hydrogen Analyzers were counseled on the importance of procedure compliance and the need to report ,

deficiencies.

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REGU'JTORY COMM'SSION W ASMiNGTON. DC 20555 ODDt, AND TO t TME PAPERWORK REDUCTION PRCUECT (3160 0904), OFFICE C#

MANAGEMENT AND BJ3GET, W8 SHfN3 TON. DC 20S23 F ACIUTY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) g SEQUEM4Au REV@ON NUMBER NUMBER 05000 OF '

Braver Valley Power Station Unit 1 334 93 - 01 2- 00 94 04 TEXT pimoro sosce a ceganea us* ecortions cop es or Nhc Form ass (try l Previous Similar Events:

There have been no previous reportable events similar to this one.

Reportability:

The Unit entered Operational Mode 2 with one Wide-Range Hydrogen t Analyzer INOPERABLE. This event is reportable under 10CFR50.73.a.2.i.B. as a condition prohibited by Technical l Specifications.

l Safety Implications:

The safety implications due to this event are minimal. Hydrogen Analyzer H2A-1HY-101A is one of two hydrogen analyzers. The redundant Hydrogen Analyzer, H2A-1HY-101B was OPERABLE. Hydrogen analyzers are required to detect the buildup of hydrogen in the reactor containment building during major loss of reactor coolant accidents, which have a low probability of occurrence. The hydrogen analyzers are not used during normal plant operation.

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