ML18005A577

LER 88-021-00:on 880809,automatic Start of Auxiliary Feedwater Pump Occurred While Performing Operational Surveillance Test OST-1826.Caused by Procedural Deficiency. Procedures revised.W/880908 Ltr

ML18005A577
Person / Time
Site:	Harris
Issue date:	09/08/1988
From:	Jerrica Johnson, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-880182-(O), LER-88-021, LER-88-21, NUDOCS 8809140146
Download: ML18005A577 (4)

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REM~RNPA 5.,.Pi~~~~'CCESSION NBR:8809140146 DOC.DATE: 88/09/08 NOTARIZED:

NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH.NAME AUTHOR AFFILIATION JOHNSON,J.R.

Carolina Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION W/8 lt DISTRIBUTION CODE: ZE22D COPIES RECEIVED:LTR I ENCL/SIZE: TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.NOTES:Application for permit renewal filed.05000400

SUBJECT:

LER 88-021-00:on 880809,automatic start of auxiliary feedwater pump.W/880908 ltr.r~RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEYIB INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/NAS AEOD/DSP/TPAB DEDRO NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES TELFORDIJ RES/DSIR/EIB EXTERNAL'G&G WILLIAMS i S H ST LOBBY WARD NRC PDR NSZC MAYSgG COPIES LTTR ENCL 1 1 1 1 1 1 1 1 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 4 4 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD ACRS MOELLER AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/QAB 10 NRR/DREP/RAB 10 NRR DR SIB 9A E 02 R'ES/DS EPY RGN2 FILE 01 FORD BLDG HOY,A LPDR NSIC HARRISiJ COPIES LTTR ENCL 1 1 2 2 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 1 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 46 ENCL 45 NRC Form.'?58 L983)LICENSEE EVENT REPORT (LER)~U.S.NUCLEAR REGULATORY COMMISSION APPAOVED OMB NO.31608(04 EXPIRES: 8/31/88 FACILITY NAME (I)Shearon Harris Nuclear Power Plant Unit 1 DOCKET NUMBER (2)PACE 3I 0 5 0 0 0 4 0 0 1 OF 0""'" Automatic Start of Auxiliary Feedwater Pump while Performing Operational Surveillance Test OST-1826.EVENT DATE (5)LEA NUMBER (6)REPORT DATE (7I OTHER FACILITIES INVOLVED (8)MONTH DAY YEAR YEAR?>I SEQUENTIAL NUMBERÃFrr MONTH NVMBE/I OAY YEAR FACILITY rtAMES DOCKET NUMBEAISI 0 5 0 0 0 0 8 09 8 88 8 0 2 1 00 09 088 8 0 5 0 0 0 OPERATINO MODE (8)POWER LEVEL (10)20.402(tr) 20.405(~)(I)II)20.405(~)(1)(4)20.408(~l(1(((ill 20.405(e l(1 l(lr)20.405(e)(1)(r)20.405(cl 50.38(c)(1)50.38(c)(2)50.73(e)(2)(ll 50.73(e)(2)(8)50.73(el (2)(ill)LICENSEE CONTACT FOR THIS LER (12)50.73(~)(2)(le)50.73(e)l2)(el 60.73(e)I 2)(r8)60,73(el(2)(rill l(A)50,73(e)(2)(rlSHB) 50,73(~l(2)lxl THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 cFR ();(Check one or more of thr foffowino/

(11 73.71(8)73.71(c)OTHER ISprclfy/n Ahttrect hrfow erxf In Trxt,/IIIC Form 36EA/NAME Joseph R.Johnson Senior Specialist

-Regulator Com liance TELEPHONE NUMBER AREA CODE 919362-2083 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCAISED IN THIS REPORT l13)CAUSE SYSTEM COMPONENT MANUFAC.TUREA EPORTABLE TO NPRDS Hhe)IIII rg:.ro: CAUSE SYSTEM COMPONENT MANUFAC TUREA EPOR TABLE lr SUPPLEMENTAL REPOAT EXPECTED (14)YES Ilf yrr, complrtr EXPECTED SI/EMISSIOII DATE/X NO ABSTRACT I(.lmlt to/4/X/tpecrr,/.r., rpproximr rely/i/tron tlnole.toter typrrrrfttrn

/incr/l18)EXPECTED SUBMISSION DATE U6)MONTH DAY YEAR ABSTRACT'n August 9, 1988, at 0334, the plant was shutdown in Mode 5.While performing OST-1826,"ESF Response Time, Train B", which required lifting electrical leads to verify the"B" Train Auxiliary Feedwater Pump operation as a result of a Safety Injection signal, the"B" AFW Pump automatically started as required.However, when the'electrical leads were replaced, the"B" AFW Pump started unexpectedly as a result of both Main Feedwater Pumps being in the tripped condition.

The cause of the event was a procedure deficiency which failed to specify that the MFW Pump control switches be placed in the"STOP" position prior to reconnecting electrical leads.The applicable procedures will be revised to add the needed step.8809f40i46 880908 PDR ADOCK 05000400 8 PNU riw~NRC Form 388 (883)

NRC Form 3SSA 194)3)LICENSEE EVENT REPORT ILER)TEXT CONTINUATION U.S, NUCLEAR REGULATORY COMMISSION APPROVED OMS NO, 3)50-0104 EXPIRES: 8/31/88 PACIUTY NAME II I DOCKET NUMSER 12)LER NUMSER 15)PAGE 13)Shearon Harris Nuclear Power Plant Unit 1 TEXT///more Spece ll r)U/iree/, ece mR/Onne//Y/IC form 3//SASI I\7)DESCRIPTION:

0 5 0 0 0 4 0 0 v EAR,"cgk?8 8 SEGUENTIAL NUMSSR 4*0 2 1 REV lSION NUMSSR 0 0 0 2 OF 0 2 On August 9, 1988, at 0334, the plant was shutdown in Mode 5.The reactor vessel was vented and at approximately 90 degrees Fahrenheit.

Surveillance Test OST-1826,"ESF Response Time, Train"B", was being performed.

OST-1826 required lifting electrical leads'o ensure that the"B" Train Auxiliary Feedwater (AFW)Pump (EIIS:BA)would start as a result of a Safety Injection (SI)signal, but not due to the trip of both Main Feedwater (MFW)Pumps (EIIS:SJ), which occurs as a result of the SI signal.This portion of the test was completed satisfactoril.y', however, when the disconnected electrical leads were placed back in the pretest position, the"B" Train AFW Pump started unexpectedly since both MFW Pumps were tripped.Since both s rstems were in test lineups, no water was introduced inadvertently into the steam generators.

CAUSE: The cause of the event was a procedure deficiency'.

The test procedure failed to instruct the operator to place the"B" MFW Pump control switch in the"STOP" position before reconnecting the electrical leads in the MFW Pump control circuitry.

ANALYSIS OF EVENT: This event is being reported in accordance with 10CFR50.73(a)(2)(iv) as an automatic actuation of an Engineered Safety Feature.There were no safety consequences as a result of this event.The Auxiliary Feedwater System functioned as designed during the test, and proper operation was verified by the Control Operator.No water was actually injected into the steam generators because of the valve lineup required by the test procedure.

OST-1826 is only performed with the unit in Mode 5 or 6;therefore, the event is not possible in other modes.There have been no previous similar events.CORRECTIVE ACTION: Procedures OST-1825"ESF Response Time, Train A" and OST-1826"ESF Response Time, Train B" will be revised to ensure that both MFW Pump control switches are placed in the"STOP" position prior to lifting/reconnecting electrical leads in the MFW/AFW circuitry.

NRC SORM SSSA 194)3)e U.S GPO.'1985 0 524 538/455 CHAL Carolina Power&Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 SE>0;e F88.File Number'SHF/10-13510C Letter Number'HO-880182 (0)U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 88-021-00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.

This report fulfills the requirement for a written report within thirty (30)days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September 1983.Very truly yours,~H~R.A.Watson Vice President Harris Nuclear Project JRJ:dj Enclosure cc.'Dr.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRR)Mr.W'.H.Bradford (NRC-SHNPP)MEM/HO-8801820/1/OSL

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