ML17292A364

LER 96-003-00:on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures revised.W/960712 Ltr

ML17292A364
Person / Time
Site:	Columbia
Issue date:	07/12/1996
From:	Bemis P, Foley C WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GO2-96-138, LER-96-003, LER-96-3, NUDOCS 9607220176
Download: ML17292A364 (8)

Text

CATEGORY 1~

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9607220176 DOC.DATE: 96/07/12 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION FOLEYgC.J. Washington Public Power Supply System BEMIS,P.R. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 96-003-00:on 960615,required surveillance test not performed when required by TS 3.4.1.3.Caused by inadequate procedures. Implementing surveillance procedure a reactor plant startup procedures revised.W/960712 DISTRIBUTION CODE: ZE22T COPIES RECEIVED:LTR j TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:

ltr.

ENCL / SIZE:

E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 PD 1 1 COLBURN,T 1 1 INTERNAL: ACRS 1 1 A~E- D 2 2 AEOD/SPD/RRAB 1

/SR'LE 1 CENTE 1 1 NRR/DE/ECGB 1 1 NRR D EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 .1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN4 FILE 01 1 1 D EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEgJ H 2 2 NOAC MURPHYiG.A 1 1 NOAC POOREgW. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 U

N NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415"2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL , 26

ti WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 July 12, 1996 G02-96-138 PER 296-0495 Docket No. 50-397 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 LICENSEE EVENT REPORT NO. 96-003-00 Transmitted herewith is Licensee Event Report No. 96-003-00 for the WNP-2 Plant. This report is submitted in response to the reporting requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence.

Should you have any questions or desire additional information, please call me or L.C. Fernandez at (509) 377-4147.

Respectfully II" P.<s ice eside t, Nuclear Operations PRB/CJF/lr Enclosure CC: LJ Callan, NRC-RIV KE Perkins, Jr., NRC-RIV, Walnut Creek Field Office NS Reynolds, Winston & Strawn TG Colburn, NRC NRC Sr. Resident Inspector (Mail Drop 927N, 2 Copies)

INPO Records Center - Atlanta, GA DL Williams, BPA (Mail Drop 399) 96072203.76 9607i2 PDR ADQCK 05000397 S PDR ZE:~z/,

UCENSEE EVEN REPORT (LER)

ACILITY NAHE (1) ET NUH6 R ( AGE 3)

Washin ton Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 I OF ITLE (4)

Failure to Comply With Technical Specification Surveillance Requirement Due to Inadequate Procedures EVENT DATE 5 LER NUHBER 6 REPORT DATE 7 OTHER FACILITIES INVOLVED 8 KONTH DAY YEAR YEAR EQUENTIAL EVISION HONTH OAY YEAR FACILITY NAHES NUHB R (5)

UHBER UHBER 50 0 6 1 5 9 6 9 6 0 0 3 0 0 0 7 1 2 50 PERATING HIS REPORT IS SUBHITTEO PURSUANT TO THE REQUIREHENTS OF 10 CFR 5: (Check one or more of the fo lowing) (11 OOE (9) 2 OWER LEVEL 0.402 b) 0.405(C) 0.73 a 2)(iv) 73.71(b)

(10) 0.405(a)(1) I) 0.36(c)(1) 0 '3(a)(2)(v) 73.73(c) 0.405(a)(1) li) 0.36(c)(2) 0.73(a)(2)(vii) THER (Specify in Abstract 0.405(a)(1) ill) 0.73(a)(2)(i) 0.73(a)(2)(vill)(A) elow and in Text, NRC 0.405(a)(1) lv) 0.73(a)(2)(ii) 0.73(a)(2)(vill)(8) orm 366A) 0.405(a)(1)(v) 0.73(a)(2)(ill) 0.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER 12 TELEPHONE NUHBER C.J. Foley, Licensing Engineer REA CODE 0 9 7 7 - 4 3 2 5 COHPLETE OHE LINE FOR EACH C(NPOHENT FAILURE DESCRIBED IK THIS REPORT (13)

CAUSE SYSTEH CQIPONENT HANUFACTURER EPORTABLE CAUSE SYSTEN C(NPONENT HANUFACTURER EPORTABLE 0 NPRDS 0 NPRDS SUPPLEHENTAL REPORT EXPECTED (14) XPECTED SUBHISSION HONTH DAY YEAR ATE (15)

YES (I f es c tete EXPECTED SUBNISSION DATE) KO z o4l At 2024 hours0.0234 days <br />0.562 hours <br />0.00335 weeks <br />7.70132e-4 months <br /> on June 15, 1996, with WNP-2 starting up in Mode 2, a surveillance test required to verify Recirculation System loop fiow balance was initiated beyond the time interval required by Technical Specification 4.4.1.3.

The cause of the event was reactor plant startup and surveillance procedures that were incorrect or omitted relevant information. The surveillance test was completed satisfactorily at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on June 15, 1996, demonstrating that Recirculation System loop fiows were balanced within limits allowed by Technical Specification 3.4.1.3.

The event had 'no safety significance.

Pl n i h At the time of the event, the plant was in Mode 2 with the reactor approximately at the 3% thermal power level. The plant was starting up after completion of the Spring 1996 refueling and maintenance outage.

LICENSEE EVENT REPORT R)

TEXT CONTINUATION ACILlTY NAHE 1) DOCKET NUHBER (2) LER NDHBER (8 AGE (3) ear umber ev. No.

Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 6 03 0 2 F 3 ITLE (4)

Failure to Comply With Technical Specification Surveillance Requirement Due to Inade uate Procedures IhmLoDm:

At approximately 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br /> on June 15, 1996, an operator reviewing logs and completed procedures governing activities being performed as part of restarting the plant after the Spring 1996 outage, determined that a surveillance test had not been performed within the period required by the Technical Specifications.

The surveillance test was required to verify that Reactor Recirculation System [AD] loop flows were balanced within limits allowed by Technical Specification 3.4.1.3, and should have been performed by June 13, 1996. \

n:

The required surveillance test was initiated at 2024 hours0.0234 days <br />0.562 hours <br />0.00335 weeks <br />7.70132e-4 months <br /> on June 15, 1996, completed at 2049 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.796445e-4 months <br />, and approved by the Shift Manager at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />.

E~Q150:

The root cause of this event was reactor plant startup and surveillance procedures that were incorrect or omitted relevant information. The surveillance procedure used to verify Reactor Recirculation (RRC)

System loop flow balance contains three separate parts covering three different surveillance requirements:

jet pump (P) operability, RRC loop fiow balance, and the Average Power Range Monitor fiow channel check. The "Purpose" section of this surveillance procedure included the statement, "This surveillance is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of thermal power exceeding 25% of rated thermal power, in LE Pess th;a or equal to] 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />'fter an idle recirculation loop is returned to operation, and daily thereafter when the reactor is in operational conditions 1 or 2." That is an incorrect statement since it does not reflect the requirement of Technical Specification 3.4.1.3 for daily verification of RRC loop flow balance when in Modes I and 2 regardless of reactor power level. Additionally, the procedure governing reactor plant startup stated that the particular surveillance procedure was required after reaching 25% reactor power, and also did not address the Technical Specification requirement to verify RRC loop flow balance on a daily basis after entering Mode 2. These procedural deficiencies required the operating staff to rely on past experience and acquired knowledge to assure that all Technical Specification requirements were met for the proper conditions. Consequently, the root cause of this event was reactor plant startup and surveillance procedures that were incorrect or omitted relevant information.

r rr The implementing surveillance procedure was changed to clearly identify the purposes and conditions under which it is applicable. Additionally, the procedure governing reactor plant startup has been changed to clearly identify both jet pump operability and Reactor Recirculation System loop fiow balance must be verified per Technical Specifications 3.4.1.2 and 3.4.1.3.

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UCENSEE EVENT REPORT R)

TEXT CONTINUATION ACILITY NAHE (i) 00CKET NUHBER (2) LER NUHBER (8) AGE 3) ear umber ev. No.

Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 6 03 0 3 F 3 1TLE (4)

Failure to Comply With Technical Specification Surveillance Requirement Due to Inade uate Procedures I n The event had no safety significance. As part of the ongoing startup, both Reactor Recirculation System pumps had been started at 15 Hz operation at 2202 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.37861e-4 months <br /> on June 12, 1996, prior to entering Mode 2 at 2227 hours0.0258 days <br />0.619 hours <br />0.00368 weeks <br />8.473735e-4 months <br />. Pursuant to the procedure governing operation of the Reactor Recirculation System, loop flow balance had been verified as part of that evolution. Review of plant records between June 12 and June 15, 1996 demonstrated that Reactor Recirculation System loop fiows were balanced within limits specified by Technical Specification 3.4.1.3 during the entire interval. Therefore, the system was being operated within Technical Specification 3.4.1.2 and 3.4.1.3 requirements in this interval, although the required Technical Specification surveillance test for loop fiow balance verification was not performed until June 15, 1996.

Licensee Event Report 88-033-00 identified an event involving a surveillance test related to the control room ventilation system that had not been performed on a timely basis during plant startup.