ML20045G459

LER 93-010-00:on 930614,determined That TS Surveillance on SI Accumulator Samples Missed Due to Draining & Refilling Accumulators Several Times During Outage.Accumulators a & C Immediately sampled.W/930708 Ltr

ML20045G459
Person / Time
Site:	Beaver Valley
Issue date:	07/08/1993
From:	Freeland L DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-010, LER-93-10, ND3MNO:3469, NUDOCS 9307140005
Download: ML20045G459 (8)

Text

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TNephone 14 t?) 3934000 f4urfeir Group Snippingport PA 150N 0004 July 8,1993  ;

ND3MNO:3469 )

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Beaver Valley Power Station, Unit No. I Docket No. 50-334, Licensee No. DPR-66 1 LER 93-010-00 l 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 93-009-00,10 CFR 50.73.a.2.i.B, " Missed Technical Specification l Surveillance on Safety Injection Accumulator Samples."

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. R. reeland General Manager Nuclear Operations DAW /tp Attachment 120014 y 'u r 9307140005 930708 E PDR ADOCK 05000334 i S PDR m@

July 8,1993 ND3MNO:3469' Page 2 -

'l cc: Mr. T. T. Afartin, Regional Administrator i 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, Oli 44101-4661 INPO Records Center 700 Galleria Parkwa-y 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

.- - 'l July 8,1993 ND3MNO:3469 '

l Page 3 J. M. Riddle 1 Halliburton NUS ]

Foster Plaza 7 1 661 Anderson Drive -l Pittsburgh, PA 15220 .l l

Bill Wegner, Consultant 1 23 Woodlawn Terrace  :'

Fredricksburg, VA 22405

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NRCiFORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 g, sa EXPIRES 5/31/95 ESTIMATED BURDE N FLR RESPONSE TO COMPLY W:7 H THis INFORMATION COLLE CTION REQUES1 50 0 MHS F QHWARD LICENSEE EVENT REPORT (LER) COMWNTS RE GARDWG BUWN FSTWTE TO THE iM ORMADON AND HECORDS MANAGEMENT BHANCH (MNBB 7714!, O S. NUCLEAR REGULATORY COMMiS904 W ASMNGTO% DC 20%5 00c1, AND TO THf FAPEnWORK REDUCTION PAGIFCI (3150 0134L OF F ICE OF (Seu reverse for required number of digits / characters for each block) M ANAGl MENT AND 130DGEi. W ASHINGTON, DC N t ActuM NAME pp (T)oCW NUMBER W PAGEp)

Beaver Va!!ey Power Station Unit 1 l 05000 334 1 OF 04 IITLE (4)

Missed Technical Specification Surveillance on Safety injection Accumulator Samples.

EVENT DATE (5) LER NUMBER (6i REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8) uoNrH nu sim vEAn 3

}I[ l[g" MONTH DAY YEAR 0 000  %

r Aouiy Naut Dorfg7 Navatn 06 1 4 93 93 - 010 - 00 07 08 93 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 4: (Check one or more) (11)

MODE (9) 3 20 402(bi 20 405(c) 50 73(an2)ov) 73.71(b)

~ POWER 20 405 fan 1)D) 50 35(c)(1) 50 73(a)(2Hv) 73 71(c)

LEVEL (10) 20 405(aH1)Dil 50.35(c)(2) 50.73(an2)(vii) oTHER O_

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LICENSEE CONTACT FOR THIS LER (12)

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L. R. Freeland, General Manager Nuclear Operations 4 1 2 643-125_8 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) cAvri Or W COMTNP ' MANufACTuHfD CAUH SYS*l M CDVPONE N1 M ANUF ACTURC H D BO XXXX XXXX N SUPPLEMENT AL REPORT EXPECTED (14) EXPECTED MON'" D" *"

vEs SUBMISSION No m gs. nere% exotrto s ov;E:N dam X DATE (15)

ABSTRACi {Linut to 1400 spaces, i e , approoniately 15 single-spaced typewntten lines) (16)

On 6/14/93, Unit One was in Mode 3, Hot Standby, at 547 F and 2235 psig, recovering from the ninth refueling outage. At approximately 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br /> on 6/14/93, a review of sampling requirements, performed by a chemistry department supervisor, determined that the proper boron concentration of the A, B, and C Safety Injection Accumulators had not been verified prior to increasing Reactor Coolant System (RCS) pressure above 1000 psig, as required by Technical Specifications. RCS pressure was increased above 1000 psig on 6/9/93 at 0535 hours0.00619 days <br />0.149 hours <br />8.845899e-4 weeks <br />2.035675e-4 months <br />. Records indicated that the B accumulator was sampled with satisfactory results on 6/9/93 at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />, but the A and C accumulators were not sampled. The chemistry supervisor immediately notified the shift supervisor and directed the Shift chemistry Specialist to sample the A and C accumulators. At 1830 the sample analysis indicated that both the A and C accumulators were within the required range.

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NUMBER DIGITS / CHARACTERS 1 UP TO 46 FACluTY NAME 8 TOTAL DOCKET NUMBER 3 IN ADDITION TO 05000 3 VARIES PAGE NUMBER s

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4 UP TO 76 TITLE 6 TOTAL 5 EVENT DATE 2 PER BLOCK 7 TOTAL 2 FOR YEAR 6 LER NUMBER 3 FOR SEOUENTIAL NUMBER 2 FOR REVISION NUMBER .

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7 REPORT DATE 2 PE BLOCK UP TO 18 - FACILITY NAME 8 OTHER FACILITIES INVOLVED r 8 TOTAL - DOCKET NUMBER 3 IN ADDITION TO 05000 9 1 OPERATING MODE

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' 1 REQUIREMENTS OF 10 CFR CHECK BOX THAT APPLIES UP TO 50 FOR NAME j 12 LICENSEE CONTACT 14 FOR TELEPHONE CAUSE VARIES 2 FOR SYSTEM h 13 4 FOR COMPONENT EACH COMPONENT FAILURE 'i 4 FOR MANUFACTURER NPRDS VARIES CHECK BOX THAT APPUES N A RENT NECTED -

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NRC FORM.366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 S *2r EXPIRES 5/31/95 ES?? MATED BURDEN PER RESPONSE TO COMPLY WTH TH!5

' LICENSEE EVENT REPORT (LER) ZT@siE#$50ffdEE OZ*MRT2 TEXT CONTINUATlON $$u"j*$R" $,*Mls'U!Eo"TE*o$'S/AS"E C E' THE FAPER*ORK REDUCTION PRlNECT (31$>0104). OF FICE OF MANAGEME*U AND BUDGET, WASHINGTON, DC 20503 F ACILITY NAME (1) DOCKET NUMBEH (2) LER NUMBER (6) PAGE (3l YEAR GULhT'4k R& Q**

NUMBE R NUMBER 05000 or Beaver Valley Power Station Unit 1 334 93 - 01 0- 00 02 04 rw vi n. u..c. nu,a ,a. .mn.: m ac im o n Description of Event:

On 6/14/93, Unit One was in Mode 3, Hot Standby, at 547 0 F and 2235 psig, recovering from the ninth refueling outage. At approximately 1740 hours on 6/14/93, a review of sampling requirements, performed by a chemistry department supervisor, determined that the proper boron concentration of the A, B, and C Safety Injection Accumulators had not been verified prior to increasing Reactor Coolant System (RCS) pressure above 1000 psig. Technical Specification 3/4.5.1 requires samples to verify the proper boron concentration at least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of a solution volume increase of greater than or equal to one percent. This is applicable in Modes 1, 2, and 3 (above 1000 psig). Unit One transitioned from Mode 4 to Mode 3 on 6/8/93, and the RCS pressure was increased'above 1000 psig on 6/9/93. Due to other circumstances, Unit One returned to Mode 5 on 6/9/93. On 6/12/93, Unit One again entered Mode 3 and increased the RCS pressure to greater 1000 psig. Records indicated that the B accumulator was sampled with satisfactory results on 6/9/93 at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />, but the A and C accumulators were not sampled. The chemistry supervisor immediately notified the shift supervisor and directed the Shift chemistry Specialist to sample the A and C accumulators. At 1830 the sample analysis indicated that the A and C accumulators were 2092 ppm and 2086 ppm respectively, which is within the required range of 1900 ppm to 2100 ppm Boron.

Cause of The Event Two factors contributed to the missed surveillance:

1) The accumulators had been drained and refilled several times during the outage. The filling took place in Modes where the accumulators were not required to be operable and the surveillance did not apply.

2) The chemistry department controls for ensuring that surveillances are met for mode changes were not sufficiently adequate to prevent this event from occurring.

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NRC FORY 366A f5 92;

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NRC FORM.366A U.S. NUCLEAR REGULATORY COMMISSION' APPROVED BY OMB NO. 3150-0104 52 EXPlRES 5/31/95 -

ESTIMATED BURDEN PER RESPONSE TO COMP,Y i WITH THIS LICENSEE EVENT REPORT (LER) C7J'20EGATfG ERo"#$$.T000 d MIts T CONMMUM AN AE R S MANA EMEMr B'%NOH (VNBa M14L U S. NUCLEAR REGJLATORY COMMlSSION, WASHINGTON, DO 20555 0D01, AND TO THE FAPERWORK REDUCTION P;"11ECT (3150 0104), OFFCE OF MANAGEMEN7 AND BJDGET, WASHINGTON, DC 20503 FACILITY NAME 0) DOCKET NUMBER 12) LER NUMBLR (6) P AGE (3) ygg LEQUENLAL REV@gt.

NUMBER NUMBER U

Beaver Valley Power Station Unit 1 334 93 - 01 0 00 03 04 tex, w n. .c.c.T. <.u e n .sn. eon.. onw m, o n Corrective Actions Immediate: The A and C accumulators were immediately sampled and adequate boron concentration was verified.

Long Term: 1) The Chemistry Department is developing  ;

procedural controls delineating the surveillance requirements to support mode changes.

2) As an additional barrier, the Operations department plant startup procedure will be enhanced to include an explicit verification of accumulator boron concentration prior to progressing to Mode 3.

Previous Similar Events A review of station documents revealed the following sampling surveillance events. Neither of these events occurred during Mode changes:

1) Unit 2 LER 2-90-024 documented an event where the Chemistry department failed to perform a Technical Specification required sample of the Boric Acid Storage tanks.

2) Unit 2 LER 2-92-012 documented an event where the Chemistry department failed to perform a Technical Specification required analysis of dissolved oxygen in the Reactor Coolant' System.

Reportability Increasing RCS pressure above 1000 psig without obtaining the required accumulator samples is a condition prohibited by Technical Specifications 3/4.0.4. As such, this event is reportable under 10CFR50.73.a.2.1.B.

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VC FORM 366A ($ 92)

NRC FORT 4 36(d U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 31F<C104 -

is e EXPIRES $/31/95 ESTIMAND BJRDEN PER RESPONSE TO COh PLY Wm1 THIS INFORMA?CN COLLECTON REQUEST: 60 0 F 43 F ORW ARD UCENSEE EVENT REPORT (LER) COMvf*CS REGARDIN3 BURDEN ES% ATE TO

• HE MOWATON AND RECORD TEXT CONTINUATION Reaut330R,S MANAGEMEN' couM:sS.Oy, BRANOH WAss,NoTON (MNBB 'rt4L oc 2e,33.oco , ANoUTO S , NUCLEA THE PAPE5' WORK REDUCTON PROJECT (315&o104), OFFICE O# ,

MANAGEVENT AND BJDGET, WASH'NGTON DC 20S03 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBt R (6) PAGE (3) yggq bEQUENTA. ALViscre NUMBER NUMBER Beaver Valley Power Station Unit 1 334 93 - 01 0- 00 04 04 TEsihw. .o.c. a ,m?.a ,a. .m- ev.. or we re xsA, s,11 Safety Implications The safety implications due to this event are minimal. Although the required samples were not cbtained prior to increasing RCS pressure above 1000 psig, the accumulators are filled from the Refueling Water Storage Tank, which was always greater than 2000 -

ppm and leus than 2100 ppm (from samples obtained weekly during May and June) . The accumulator requirement is 1900 ppm to 2100 ppm. Also, when samples were obtained, all three accumulators were within the required range.

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l N40 F@M 366A p.97;

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