ML17284A413

LER 88-019-00:on 880527,control Room Emergency Filtration Sys Actuated on 880520.Caused by Failure to Reset balance- of-plant Relay Cabinet Due to Inadequate Procedure.Trip Condition reset.W/880627 Ltr

ML17284A413
Person / Time
Site:	Columbia
Issue date:	06/27/1988
From:	Arbuckle J, Powers C WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-019, LER-88-19, NUDOCS 8807070064
Download: ML17284A413 (6)

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'C CEIZRATED DI RJBUTION DEMONSTR TJON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8807070064 DOC.DATE: 88/06/27 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION ARBUCKLE,J.D. Washington Public Power Supply System POWERS,C.M. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 88-019-00:on 880527,control room emergency filtration sys actuation during testing due to inadequate procedure.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR NOTES:

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ENCL TITLE: 50.73 Licensee Event Report (LER), Incident Rpl, etc.

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RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 A SAMWORTH, R 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2

~N DR 'S/ IB 9A 1 1 NUDOCS-ABSTRACT 1 1

~REG F 02 1 1 RES TELFORD,Z 1 1 RES/DE/EIB RGN5-: FILE '1 1 1

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RES/DRPS DEPY 1 .1 EXTERNAL: EG&G WILLIAMS,S 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 j

A TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44

NRC Form 368 V.S. NUCLEAR REGULATORY COMMISSION (0 83)

APPROVED OMB NO. 3150410(

EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER)

FACILITY NAME HI DOCKET NUMBER l21 PAGE 3i Washin ton Nuclear Plant - Unit 2 0 5 0 0 0 397 1 OFO 4

""'"'Control Room Emergency F> tr at>on ystem ctuation ur>ng est>ng ue to Inadequate Procedure Personnel Error EVENT DATE (5) LER NUMBER (61 REPORT DATE (71 OTHER FACILITIES INVOLVED IBI MONTH DAY YEAR YEAR o c'r ssar/BNTIAL fr<2 RsvrsroN MONTH OAY YEAR FACI LITY NA M ES DOCKET NUMBER(3)

C?P. NUMBER rynp Nr/MBSR 0 5 0 0 0 052 0 88 88 01 9 0 00 627 8 8 0 5 0 0 0 OPERATING THIS REPORT Is sUBMITTED pURSUANT To THE REGUIREMENTs oF 10 cFR ()r Icntcsr ont or mort of rnt foriowinp/ Ill)

MODE (8) 73.7((B) 5 20.402(BI 20.405(c) 50.73(o l(21(iv)

POWE R 20,405(sill l(0 60.35(c)(ll 50.73(el(2)(v) 73.7((cl LEYEL 0 0 0 20.405 (o) ll I )ii) 50.38(c) (21 50.73(e l(2) (vii) OTHER ISptcify in Aosrrtcr INIOVV end in Ttvr, HRC FOrm 20,405 (~ IllI (iii1 50.7 3( ~ I (2 Hi) 50.73( ~ l(2)(viii)(Al 366AI 20.405( ~ I (1) I I v) 50,73(e) (2) (ii) 50.73( ~ l(21(viiil(81 20.405 I ~ I (1 l(vI 50.73(o l(21(iiil 50.73 (~ I (2)(o I LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE J.D. Arbuckle Com liance En ineer 50 937 7 -21 15 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 MANUFAC. REPORTABLE MANUFAC. REPORTABLE CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT TI/REA TO NPADS Pnvvp()jxTBF@

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SUPPLEMENTAL REPORT EXPECTED (141 MONTH DAY YEAR EXPECTED SUBMISSION DATE (151 YES Irf ytL comprtrt EXPECTED SUBMISSION DATE/ NO ABSTRACT ILimrr ro /400 sotcts, /e., tpprovimtrtiy /if/ten sinprt sotto ryptwrirrtn /inn/ (151 On May 27, 1988 it was determined that a Control Room Emergency Filtration System The inadvertent actuation which occurred on May 20, 1988 was reportable per 10CFR50.73.

start of Control Room Emergency Filtration System Fan WN-FN-54B was the failure of Plant Instrument and Control ( I 8 C ) Technicians to reset the trip logic (due to an inadequate procedure) during the performance of a Reactor Building Exhaust Plenum Radiation Monitor (REA-RIS-609B and D) Response Time Test.

The immediate cause of this event was the failure to reset the Balance of Plant Relay Cabinet (RC-2), Division II, trip circuitry due to an.'inadequate procedure. The root cause of the event is personnel error during the procedure revision and review process.

A previously approved procedure deviation, which added steps to reset a subchannel half-trip condition prior to continuing with the procedure; was not incorporated during the two-year periodic review and revision process for the procedure.

After verification that no actual initiating condition existed, the trip condition was reset and the system was returned to normal lineup. Further corrective actions include

1) adding the requirement to the procedure that the WN trip circuitry be reset, and 2) modifying the Periodic Procedure Revision Form to include verification that deviations have been incorporated.

This event posed no threat to the health and safety of .either the public or Plant personnel.

8807070064 880627 I+~

PDR ADOCK 05000397 8 PDC .((

NRC Form 358

NRC Farm 35SA U.S. NUCLEAR REOULATORY COMMISSION 15431 LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPAOVEO OMB NO, 3)50WIOA EXPIRES: S/31/dd FACILI'TY NAME 111 OOCKET NUMSER 12) LER NUMSER Id) PAOE IS) yg':5 sEovENTIAL ~..z>N IIEvrsIoN NUMaeo .:) N VM e II Washington Nucl ear Pl ant - Uni t 2 p 5 p p p 3 9 7 8 8 019 0 0 0 2 oF 0 4 TExT /5'ore <<ace ir rtpu/rerL u>> a/raoa'M/ P//IC %%drm 3%A 5/ II 7)

Plant Conditions a) Power Level - 0%

b) Plant Mode - 5 (Refueling)

Event Descri tion On May 27, 1988 it was determined that a Control Room Emergency Filtration System actuation which occurred on May 20, 1988 was reportable per 10CFR50.73. The inadvertent start of Control Room Emergency Filtration System Fan WN-FN-54B was the result of a failure to reset the trip logic during the performance of Plant Procedure (PPh1) 7.4.3.2.3.24, "Secondary Containment Isolation on Reactor Building Exhaust Radiation High (Channels B and D) - Response Time Test". The procedure provides instructions for performance of a Response Time Test of Reactor Building Exhaust Plenum Radiation Monitors REA-RIS-609B and REA-RIS-609D to demonstrate time response of the logic within the Secondary Containment Isolation System.

Plant Instrument and Control ( IEC) Technicians had completed the installation of test equipment =for REA-RIS-609B, which caused a half-trip in Balance of Plant Relay Cabinet (RC-2), Division II. However, the procedure did not require personnel to reset this half-trip prior to placing REA-RIS-609D in a test condition. Because the circuitry was not reset, there was a half-trip condition in existence for subchannel B. (To clear the trip conditions for Control Room Ventilation, personnel must reset WN Reset Pushbuttons 3 BX and 3BY.)

As a result, when the I8C Technicians disconnected the sensor input cable to REA-RIS-609D, a second half-trip condition was introduced in RC-2 (subchannel D) which caused a full trip of the WN Start Logic and, by design, WN-FN-54B automatically started. It should be noted that the I8C Technicians performed each step of the process as it was described in the procedure.

The immediate cause of this event was the failure to reset the RC-2 trip circuitry due to an inadequate procedure. The root cause of this event is personnel error during the procedure revision and review process.. A procedure deviation had previously been approved which added steps to reset the subchannel half-trip condition prior to proceeding to the opposite channel. However, this deviation was not incorporated into the current revision during the two-year periodic review and update process. Plant Instrument and Control and Plant Administration personnel collectively failed to ensure that the deviation was incorporated. This event would not have occurred process.

if the deviation had been included during the procedure revision Immediate Corrective Action After verification that no actual initiating condition existed, the trip condition was reset and the Control Room Emergency Filtration System was returned to normal lineup.

Nrlc so/IM 3aaA <<U.S.OPO:1055-0.524 535/Sd5 15431

NRC form 3SSA U.S. NUCLEAR REQULATORY COMMISSION (883)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AffROVED OMB NO. 3(50WIOS EXPIRES: 8/31/88 fACILI'TYNAME (I) DOCKET NUMBER (2) LER NUMBER (5) ~ AQE (3)

SEQUENTIAL ?Ar REVISION YEAR 2'/ NUMSER '3+ NUMBER Washington Nuclear Plant - Unit 2 o s o o o 3 9 7 8 8 01 9 00 030F 0 4 TEXT /4 more Recce IB RR)end, ore aSS(iane/ HRC Form 3//SAY/ ( IT)

Further Evaluation and Corrective Action A. Further Evaluation

l. The event was not considered to be reportable at the time of occurrence because a planned full actuation would have occurred later in the procedure and, therefore, it was considered to be a preplanned sequence and no four-hour or 30 day reports were necessary. However, upon later review (May 27, 1988) it was determined that since the actuation occurred prior to the expected step. in the procedure, the event was subsequently determined to be reportable.

2. Since the time-frame that the deviation was written (1986), the procedure deviation process has been changed such that the affected pages are now removed from the procedure and the marked up pages are integrated in place of those pages. It is possible that the deviation would have been incorporated into the procedure had it been processed under the current program.

B. Further Corrective Action

1. Plant Procedure 7.'4.3.2.3.24 has been deviated to require that the WMA trip circuitry be reset prior to continuing with the procedure.

2. The Periodic Procedure Revision Form will be modified to include verification that an outstanding .procedure deviation has been incorporated.

3. A letter will be issued to appropriate Plant personnel which explains the modification to the Periodic Procedure Revision, Form and the reason for the change.

Safety Si nificance There is no safety significance associated with this event in that there was no actual initiating condition which would have caused the system to actuate, and all equipment operated correctly to place the Control Room Ventilation System in an isolation condition. Accordingly, this event posed no threat to the health and safety of either the public or Plant personnel.

Similar Events84-017, 84-018,85-027, 85-036 and 87-009 NRC SORM SSSA RU 8 OPO 1888<HIES 538/455 (883)

NRC Form SEEA US. NUCLEAR REQULATORY COMMISSION 1883)

LICENSEE EVENT REPORT {LER) TEXT CONTINUATION APPROVED OMS NO. 3150M)04 EXPIRES: 8/31/88 FACILITY NAME Ill DOCKET NUMSER (21 LER NUMSER PEI ~ AOE )3)

YEAR SEQUENTIAL IIEYIEIQN NUM ER NUM E II Washington Nuclear Plant - Unit TEXT /I/moro E/woo /o /or/roko/ Moo ~ H/IC %%dnn 3/ISA 3/ (IT) 2 0 5 0 0 0 3 9 7 8 8 019 00 04'"0 EI IS Information Text Reference EIIS Reference System Component Control Room Emergency Filtration System VH WMA-FN-548 VH Fan REA-RIS-609A VA 45 REA-RIS-6098 VA 45 NRC SQRM EEEA o U.S/SPO:)8884428 838/Edd IS 43)

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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 Docket No. 50-397 June 27, 1988 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO.88-019

Dear Sir:

Transmitted herewith is Licensee Event Report No.88-019 for 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.M. Powers (M/D 927M)

WNP-2 Plant Manager CMP:lg

Enclosure:

Licensee Event Report No.88-019 cc: Mr. John B. Martin, NRC - Region V Mr. C.J . Bosted, NRC Site (M/D 901A)

INPO Records Center - Atlanta, GA Ms. Dottie Sherman, ANI Mr. D.L. Williams, BPA (M/D 399)