ML17279A864

LER 87-031-01:on 871118,condition Prohibited by Plant Tech Specs Not Identified When Performing Weekly Tech Spec Surveillance for Plant Batteries.Caused by Personnel Error. Counseled Individuals involved.W/880225 Ltr

ML17279A864
Person / Time
Site:	Columbia
Issue date:	12/18/1987
From:	Davison W, Powers C WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-031, LER-87-31, NUDOCS 8803080374
Download: ML17279A864 (8)

Text

REGULA INFORMATION D I STR I BUT I 0 STEM<R I DS)ACCESSION NBR: 8803080374 DOC.DATE: 87/12/18 NOTARIZED:

NO FACIL: 50-397 WPPSS Nuclear Progecti Unit 2i Washington Public Poee AUTH.NAME AUTHOR AFFILIATION DAVISONi W.S.Washington Public Poeer Supply System POWERSi C.M.Wash ing ton Pub l i c Power Sup p l g Sg s tern REC IP.NAME RECIPIENT AFFILIATION DOCKET 05000397

SUBJECT:

LER 87-031-01:

on 871118 condition prohibited bg plant Tech Specs not identified chen performing weekly Technical Spec surveillance

%or plant batteries.

Caused bg personnel error.Counseled individuals involved.W/880225 itr.DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ENCL SIZE: TITLE: 50.73 Licensee Event Report<LER)i Incident Rpti etc.NOTES: REC IP IENT ID CODE/NAME PDS LA SAMWORTHi R INTERNAL: ACRS MICHELSON AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DEST/ADS7E4 NRR/DEST/ESB 8D NRR/DEST/MEBPH3 NRR/DEST/PSB8D1 NRR/DEST/SGB 8D NRR/DLPQ/GABiOA NRR/DREP/RAB 10A NR DR IS/SIB9A1 REG F I 02 RES/D RGN5 FILE 01 COPIES LTTR ENCL 1 1 1 1 1 1 1 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1'1 1 1 1 1 1 1 1 REC IP IENT ID CODE/NAME PDS PD ACRS MOELLER AEOD/DSP/NAS AEOD/DSP/TP*B DEDRO NRR/DEBT/CEB8H7 NRR/DEST/I CSB7A NRR/DEST/MTB 9H NRR/DEBT/RSB 8E NRR/DLPG/HFBiOD NRR/DOEA/EAB11E NRR/DREP/RPB 10A NRR/PMAS/I LRB 12 RES TELFORDiJ~RES/DRPS DIR COP I'ES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 EXTERNAL: EGhG GROHi M H ST LOBBY WARD NRC PDR NSIC MAYST G 5 5 1 1 1 1 1 FORD BLDG HOY, A LPDR NSIC HARRIS'1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 46 ENCL 45 I'

NRC Form 355 (9431 LICENSEE EVENT REPORT (LER)V.S.NUCLEAR REOULATORY COMMISSION APPAOVED OMB NO.31504101 EXPIAES: 4/31/BS FACILITY NAME (I)Washin ton Nuclear Plant-Unit 2 PACE 3)DOCKET NUMBER l2)0 5 0 0 0 397 ior0 4'""'" 250 Volt Battery Float Voltage Be ow Tec n>ca peer scat>on Limit-Not Correcte Due to Personnel Error During Battery Surveillance EVENT DATE (5)LER NUMBER (5)REPORT DATE (7)OTHER FACILITIES INVOLVED (SI MONTH OAY YEAR YEAR A r: SSOVSNTIAL rXcS NVMSE R~rN REvrslorc NUMBER MONTH OAY YEAR FACILITY NAMES DOCKET NUMBER(SI 0 5 0 0 0 111 88 7 87 03 I 0 I I 2 18 87 0 5 0 0 0 OPERATINO MODE (Ql POWE R LEYEL 9 3.vkr'Iy+CP~XTIC.

',+gfrn;20A02(bl 20.405(~I (1)I 0 20A05(el(1)

(4)20A05(ell1)(4ll 20A05(e)(1)(lv) 20A05 le I ll I (vl 20A05(e)50M(c)(l)50.35(c)(2)50.73(e)(2)(ll 50.73(e)I 2)(4)50.734)(2)

IIBI LICENSEE CONTACT FOR THIS LER (12I 50.73(e)l2)II el 60.73(e)(2)(v) 50.73(e)(2)(vSI 60.73(el(2) 441)IAI 50.73(el(20vl4)(B) 50.73(e)(2)(e)THIS REPOAT IS SUBMITTED PURSUANT 7 0 THE REQUIREMENTS OF 10 CFR (): ICheck one Or mOre of the IOIIovffnFI (11 73.71(5)73.71(cl OTHER (Specify In Ahrtrect below end In Text, NRC Eorm 36EAI NAME W.S.Davison, Compliance Engineer TELEPHONE NUMBER AREA CODE 50 93 77-250 I COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS AEPOAT (13)X~CAUSE SYSTEM COMPONENT MANVFAC.TURER EPORTABLE r~~.TO NPADS>So@......

Ic r'jy"Rp" CAUSE SYSTEM COMPONENT MANUFAC-TURER EPORTABLE TO NPRDS~AS@LMM SUPPLEMENTAL REPORT EXPECTED (le)EXPECTED SUBMISSION DATE II BI MONTH DAY YEAR YES Ilf yet, conrpiere EXPECTED SIJBhtISSION DATEI NO ABSTRACT ILimit ro ic00 tpecet, I.e., epproelmeteiy fifteen tinpiecpece typewritten tinct)l15)O'LL md&wOQ NO wO+(A mo PlD OA mt'H O 0(.'a ma m On November 18, 1987, a condition prohibited by Plant Technical Specifications was not identified when performing the weekly Technical Specification surveillance for Plant batteries.

The test was completed by Plant electricians as a successful test and given to the Operations'epartment Shift Manager for review and acknowledgement of completion.

It was then reviewed and signed by the Shift Manager at 0531 hours0.00615 days <br />0.148 hours <br />8.779762e-4 weeks <br />2.020455e-4 months <br /> and submitted to the Plant Electrical Maintenance group for review.At 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />, the department cognizant reviewer recognized that the 250 Volt Battery voltage recorded was below the Technical Specification minimum required value.After the Shift Manager was informed of the low voltage condition, the voltage was returned to within allowable limits at 0821 hours0.0095 days <br />0.228 hours <br />0.00136 weeks <br />3.123905e-4 months <br />.The immediate cause was personnel error in that contrary to the approved procedure the electricians did not inform the Operations staff of the discrepancy and signed the test results as being satisfactory.

The root cause was a combination of lack of mental attention and poor work practice.The electricians failed to recognize the low battery voltage and did not perform the procedure steps in the proper order.Corrective actions include the counselling of'individuals involved, providing instruction to Maintenance Department personnel concerning performance of Technical Specification survei llances, placing the LER on the Required Reading List for Operations and Maintenance Departments, adding of this event to the subject list for Operations Requalification Training and Maintenance shop meetings and modification of the Technical Specification Surveillance Testing Program.No significant degradation of 250 Volt Battery capacity occurred.All systems with safety-related isolation valves supplied from the 250 Volt Battery have redundant AC powered valves for isolation.

The Shutdown Cooling System (SDC)functions can be performed by the Alternate Shutdown Cooling Flowpath if SDC is not operable.Additionally, the DC power system at WNP-2 contains two other Class IE 125 Volt DC power supply subsystems, each of which alone is capable of suppIyin(9.

sufficient power to ensure safe shutdown capability.

Consequently, this event had no affect on the health and safety of plant personnel or the public.NRC Form 345 (94)3)

NRC FoIm SddA (94)3)LICENSEE EVENT REPORT (LERI TEXT CONTINUATION V,S.NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO.3150&104 EXPIRES: 8/31/88 FACILITY NAME Ill OOCKET NUMSER (2l LER NVMSER (5)PACE IS)Washington Nuclear Plant-Unit 2 0 s 0 0 o 3 7 TEXT///mom opOOO<</oOM)OOI, oW/do/OOon/I HRC Fom/3//SAS/112)Plant Conditions YEAR NN 8 7 SEOVENTIAL NVMSER 0 3 REVISION NVMIOR 01 02 OF 0 4 a)Power Level-93%b)Plant Hode-1 (Power Operation)

Event Descri tion On November 18, 1987, a condition prohibited by Plant Technical Specifications was not identified when performing the weekly Technical Specification surveillance for Plant batteries.

The test was completed by Plant electricians and given to the Operations Department Shift Hanager for review and acknowledgement of completion.

It was then reviewed and signed by the Shift Hanager at 0531 hours0.00615 days <br />0.148 hours <br />8.779762e-4 weeks <br />2.020455e-4 months <br /> and submitted to the Plant Electrical Haintenance group for review.At 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />, the cognizant Haintenance Department reviewer recognized that the 250 Volt Battery voltage was recorded as being below the Technical Specification minimum required value.After the Shift Hanager was informed of the low voltage condition, the voltage was returned to within allowable limits at 0821 hours0.0095 days <br />0.228 hours <br />0.00136 weeks <br />3.123905e-4 months <br />.The immediate cause of this event was determined to be personne'I error in that two utility electrical technicians failed to recognize the actual plant conditions (i.e., that the 250 Volt Battery was inoperable due to low battery float voltage).Contrary to the approved procedure, the electricians did not inform the Operations staff of any discrepancies and signed the test results as being satisfactory.

The root cause of this event was determined to be a combination of lack of mental attention and poor work practice.The electricians recorded the voltage properly as required by procedure, but failed to recognize the significance of the Technical Specification required battery system parameters.

The low voltage reading of 256.9 volts (minimum voltage is 258 volts)should.have initiated action to-inform the Operations staff on an immediate basis and to signify the test results as unsatisfactory on the cover page of the procedure.

Poor work practice was used when the technicians did not perform the procedure step by step, but instead recorded the data in convenient groups.Subsequently, they then initialed all the procedure steps on that page, as a group, without carefully reading each step individually.

As a result of this method, the Technical Specification acceptance criteria listed in the procedure were overlooked.

Immediate Corrective Action Plant operators returned 250 Volt'Battery voltage to within Technical Specification required limits as soon as the out-of-specification condition was recognized.

NRC FORM SddA)94)3)4 V.S CPO I 985.0 824 538/455 NRC FOIIA 358A 1943)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S, NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO3)50&)04 EXPIRES: 8/31/88 FACILITY NAME 11)OOCKET NUMBER 12)LER NUMBER LE)PAGE IS)Washington Nuclear Plant-Unit 2 TEXT//IIIKvf Spfcf/I/fqv/md, I/ff~HRC FfmI 358AS/11T) o s o o o 3 g 7 YEAR;Py.i 8 7 SEGI/ENTIAL NUM EA 0 3 I REVISION NUMBER 01 03 or-0 4 Further Evaluation and Corrective Action o The Shift Manager accepted the surveillance as complete at 0531 hours0.00615 days <br />0.148 hours <br />8.779762e-4 weeks <br />2.020455e-4 months <br />.The cognizant Maintenance Department reviewer recognized that an error had been made at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> and float voltage was returned to within Technical Specification limits at 0821 hours0.0095 days <br />0.228 hours <br />0.00136 weeks <br />3.123905e-4 months <br />.Therefore, 250 VoIt Battery voltage was below the minimum value and the battery was inoperable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 51 minutes.Since Specification 3.8.2.I.a allows a maximum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore the battery to operable status, this event is reportable per IOCFR50.73(a)(2)(i)(B) in that it was a"condition prohibited by the Plant's Technical Specif ications." o A confirmatory check of battery terminal voltage, individual battery cell electrolyte levels and individual battery cell specific gravities verified the battery to be in an operable status.o The individuals involved with this event have been counselled concerning responsibility for identification of operability sensitive surveillance data and proper procedure performance.

o Maintenance Department personnel will receive instruction on the proper methods of performing Technical Specification surveillances and identification and reporting of discrepancies.

o This LER will be required reading for all Operations and Maintenance Department personnel.

o This LER will be added to the subject lists of items to be discussed during Operations Requalification Training and Maintenance Department shop meetings.o The Technical Specification Surveillance Testing Program will be modified to identify the Shift Manager's test completion signature as the final.review for equipment operability and to specify that any applicable Technical Specification LCO time requirement start at that point.o During the two-year periodic review of Technical Specification Surveillance Procedures, each procedure will be modified as necessary to improve identification of test acceptance criteria by technicians and to improve the capability for timely, thorough review by the Shift Manager.NRC FORM SSSA (983)A U.S GPO 1988 0 824 538/455 NRC Form 3SBA I94/3)LICENSEE EVENT REPORT ILERI TEXT CONTINUATION V.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO 3150&/04 EXPIRESI 8/3I/88 FACILITY NAME III DOCKET NUMBER LTl LEA NUMBER IS SSOUSNTrAL NUMBER ASY/5/ON NUMSSA PAGE ISI Washington Nuclear Plant-Unit 2 TEKT///more f/roof N/f//rkwS r/fo eCkWenel/YRC Arrrr 38SI'5/IITl Safet Si nificance o 5 o o o 3 9 7 8 7 0 3 01 04oF 0 4 A review of the details of this event shows that, although the Class IE 250 Yolt Battery was inoperable per Technical Specifications for 51 minutes longer than allowed, this DC power source contained sufficient power to ensure safe shutdown capability during the entire time period.The 250 Volt DC System supplies power to Reactor Core Isolation Cooling System (RCIC), Reactor Water Cleanup System (RWCU)and the Reactor Heat Removal Shutdown Cooling System (SDC)isolation valves.The RCIC, SDC and RWCU systems each contain a redundant AC powered isolation valve which would function to isolate if the DC powered valve was inoperable.

The RCIC and RWCU systems are not required to function during accident conditions.

The SDC system functions can be performed by the Alternate Shutdown Cooling Flow path if required.Additionally, the DC power system at WNP-2 contains two other Class IE 125 volt DC power supply subsystems each of which alone is capable of supplying sufficient power to ensure safe shutdown capability.

Consequently; this event had no affect on the health and safety of Plant personnel or the public.Similar Events Other events which involved Technical Specification equipment operability problems during surveillance activity are documented on LERs 87-23, 86-05, 85-54, 85-51 and 85-49.EI IS Information Text Reference EI IS Reference 250 Volt Battery 125 Yolt DC Power Supply Systems RCIC System EI EI BN Component BTRY BTRY RWCU CE SDC BO N/IC fOAM 355A 1983)o U.S GPO.'I 988 0 825 538/155 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.o.Box 968~3000 George Washington Way~Richland, Washington 99352 Docket No.50-397 February 25, 1988 Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555

Subject:

NUCLEAR PLANT NO.2 LICENSEE EVENT REPORT NO.87-031-01

Dear Sir:

Transmitted herewi th i s Li censee Event Report No.87-031-01 f or the WNP-2 Plant.This report is, submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence.

Very truly yours, C.H.Powers (H/D 927M)WNP-2 Plant Manager CHP:db

Enclosure:

Licensee Event Report No.87-031-01 cc: Hr.John B.Martin, NRC-Region V Mr.C.J.Bosted, NRC Site (H/D 901A)INPO Records Center-Atlanta, GA Hs.Dottie Sherman, ANI Mr.D.L.Williams, BPA (H/D 399)