ML18033A368

LER 88-002-00:on 880811,unplanned RWCU Isolation Occurred. Caused by Personnel Error.Temp Indicating Switch Recalibr & Sys Returned to svc.W/880909 Ltr

ML18033A368
Person / Time
Site:	Browns Ferry
Issue date:	09/09/1988
From:	Randy Baker, Campbell G TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-002-03, LER-88-2-3, NUDOCS 8809150012
Download: ML18033A368 (10)

Text

Ac CELERATZD DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8809150012 DOC.DATE: 88/09/09 NOTARIZED: NO DOCKET g FACIL:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION BAKER,R.L. Tennessee Valley Authority CAMPBELL,G.G. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 88-002-00:on 880811,unplanned RWCU isolation due to personnel error.

W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:

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

S NOTES:1 Copy each to: S. 'Black, J.G.Partlow,S.Richardson 05000296 B.D.Llaw,.F.McCoy.

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL SIMMS,M 1 1 PD 1 1 D GEARS,G 1 -1 INTERNAL ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 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/QAB 10 NRR/DOEA/EAB ll NRR/DLPQ/HFB 10 NRR/DREP/RPB 10 1

1 2

1 1

2 NRR/DREP/RAB 10

~RR~RIS/ IB 9A 1

1 1

1 1

1' NUDOCS-ABSTRACT 1 1 ~RE 02 1 RES TELFORDiJ 1 1 RES/DSIR DEPY 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G WILLIAMS,S 4 4 FORD BLDG HOY g 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 NOTES 5 5 A

D TOTAL NUMBER OF COPIES REQUIRED: LTTR 51 ENCL 50

NUCLEAR AEOULATORY COMMISSION NRC Form 355 (903/ APPROVED OMB NO. 3150-0104 LICENSEE EVENT*REPORT"ILERI'.S. EXPIRESl 5/31/55 DOCKET NUMBER l2) PA E I FACILITY NAME Il) 0 5 0 0 0 ,1 OF BROWNS FERRY UNIT 3 TITLE (4I UNPLANNED. REACTOR WATER CLEANUP ISOLATION DUE TO PERSONNEL ERROR EVENT DATE(5) LER NUMBER LS) REPORT DATE (7) OTHER FACILITIES INVOLVED (SI

'OAY YEAR, YEAR '/@ SEOVENTIAL NVMSEII @ NVMSER MONTH OAY YEAR 'ONTH FACILITYNAMES DOCKET NUMBER(SI 0 5 0 0 0 08'88OP ERAT)NO 88 '0 0 2 0.0 09 I

9 8 8 THIS REPORT IS SUBMITTED PUASVANT T 0 THE REQUIREMENTS OF 10 CFR (): IChech one or more OI the Iollowinp/ (ll 0 5 0 0 0 MODE (9) 20.402(h) 20.405(c) X 50 73( ~ l(2)(lvl  : 73.7)(h)

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(vill)(A) 73.71(c)

~ OWER 20.405( ~ I(II(l) 50.36(c)(II LEYEL0 0 0 '0,405 ( ~ I (1)(llI 50.35(cl(2)'0.73(

60.73(cl(2l(vill OTHER /Soec/ly In Ahttrett Oelow end /n Text. IYRC Form 20.405( ~ l(1) (III) ~ l(2) (II 50.73( ~ ) (2) 366AI 20.405( ~ l(1) (lvl 50.73( ~ ) (2 IIII) 60.73( ~ l(2) (5) 20.405( ~ l(1)(~ ) 50.73( ~ ) (2) ) 50.73( ~ )(2)(x)

LICENSEE CONTACT FOR THIS LER (12),

NAME TELEPHONE NUMBER AREA CODE Richard'. Baker, En ineer, Plant 0 erations Review Staff 20 72 9-2 538 COMPLE'TE ONE LINE FOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANVFAC. EPORTABLE

'CAUSE, SYSTEM COMPONENT SYSTEM COMPONENT TVRER TO NPAOS TVRER cl@+ei%

SUPPLEMENTAL'EPORT EXPECTED (14) MONTH OAY YEAR EXPECTED SUBMISSION DATE I'ISI YES (l/,yet. complete EI(PECTEO SUBMISSION DATE/ NO ASSTRACT /Limit to /400 toecet. I e., eoorox/merely /i/teen t/nple toece tyoewri Iten I/ntn/ (15)

On August ll, 1988, at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, with all, three Browns Ferry units defueled, the temperature indicating switch (TIS) monitoring .the discharge of the 'unit 3 reactor water cleanup (RWCU) nonregenerative heat exchanger initiated an isolation of the RWCU system. Th'is isolation function is an engineered'afety feature (ESF) of the primary containment isolation system. At the time of this. event plant personnel were decontaminating the panel which houses the TIS. During an. investigation of the cause of the event'he instrument mechanics discovered that the setpoint knob, located on the front of the TIS', was turned'rom the original calibrated setpoint of 140 degrees fahrenheit to 52 degrees fahrenheit. This change in the setpoint has been .attributed to inadvertent personnel. error during the decontami.nation process. The TIS was recalibrated to the original setpoint and the RWCU system was returned to service at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />. This i.'s considered an isolated event since no other events of a similar nature have been recorded. All decontamination crews have been reminded to use caution when decontaminating any plant panels due to possibl'e ESF actuati;ons.

Pc 09/500%'2 '00029/I 880909 pDR ADOCK 0 8

NRC Form 355 (9 83)

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0 NRC Form 3ddA U S, NUCLEAR REOULATORY COMMISSION

)043)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVED OMS NO. 3ISOW104 EXPIRES: 8/31/88 FACILITY NAME IIl DOCKET NUMBER (2) LER NUMBER Idl PACE I3)

YEAR r'iM SEQVENT/AL ~%I rrdVISION NVMddrI ~ .or rrVM d/I BROMNS FERRY UNIT 3 o s o o o 2 9 6 88 002 0 002 oFO 3 TEXT ///moro Nrooo */o)/rkorL rr>> //POooo////IC Forrrr 3/)I/A3/ IIT)

Descri tion of Event On August 11, 1988, at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, with all three Browns Ferry units defueled, the unit 3 reactor water cleanup (RMCU) system (EIIS code CE) isolated. This isolation function is an engineered safety feature (ESF) of the primary containment isolation system (EIIS code JM). The RWCU isolation was caused by a reduced trip setpoint on temperature indicating switch (TIS) (EIIS code TIS) 69-11. This TIS is designed to isolate the RWCU system on high temperature of the water downstream of the nonregenerative heat exchanger. Flow control valves (FCV) 69-1 and 69-12 closed and B RWCU pump tripped as designed. FCV 69-2 would have normally closed as designed, but it remained open because its power was removed under a hold order. At the time of this event, plant personnel were decontaminating the panel which houses TIS-69-11. The instrument mechanics checked TIS-69-11 and found the setpoint knob, located on the front of the TZS, was turned from the original calibrated setpoint of 140 degrees fahrenheit to 52 degrees fahrenheit. The instrument was. recalibrated to the original setpoint and the RMCU system was returned to service at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />.

Cause of Event The isolation of the RWCU system was caused by the inadvertent personnel error of accidently turning the TIS setpoint knob during the decontamination process. No member of the decontamination crew was aware that the setpoint on TIS-69-11 had been changed. However, because 'of the physical location of the setpoint control knob, the setpoint could, have accidently been changed by contact with a rag, brush, etc. without the individual realizing it.

Anal sis of Event The RWCU system is designed to provide continuous mechanical filtration and chemical demineralization of reactor water. This system is also designed to isolate upon a .high temperature indication- at the discharge of the RWCU nonregenerative heat exchanger. This system functioned exactly as designed. The isolation- of the RWCU system due to high water temperature downstream of the nonregenerative heat exchanger is a non-safety function to reduce reactor water temperature to acceptable levels for the resin material used in the filter demineralizers. The temporary loss of RWCU had a negligible effect on reactor water .chemistry. The associated technical specification requirements for monitoring water chemistry parameters and the implementing procedures provide early detection for any chemistry problems that could result from the loss of RWCU. If this event had occurred during .power operation, there would have been no effect on plant safety. As stated above, water chemistry monitoring would provide required protection to equipment from any chemical parameter approaching, a technical specification limit.

NIIC FORM Sddk o U.S OPO'.1088 OP82l 538/l SS (043)

i?

NRC Form 3ddA U.S. NUCLEAR REGULATORY COMMISSION (983)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVFD OMS NO. 3150M)04 EXPIRES: 8/31/88 FACILITYNAME DOCKET. NUM8ER (3) LER NUMBER (8) PAGE IS)

YEAR '4, iX'r SEQVENTr*L @(i 4dyrSK)N NVM e4 NVMSE4 "03 (11'ROWNS FERRY UNIT 3 0 5 0 0 0 '2 9 88 0 02 00 03 TEXT //I mOre eeeee le deq/reer/ rree eederden/I HRC FOnrr 3///IA'e/ (17)

Corrective Action During an investigation of the cause of the event the instrument mechanics discovered that the setpoint knob, located on the f'ront of the 'TIS, was turned from the original calibrated setpoint of 140:degrees fahrenheit to 52 degrees fahrenheit. The TIS was reset and, cal'ibrated to the original setpoint of 140 degrees fahrenheit and the RMCV system was returned to service at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />.

This is considered .an isolated event since,no other events .of a similar nature have been recorded.

All decontamination crews have been reminded to use caution when decontaminating any plant panels. due to,possible ESF actuations. 'No further corrective action is planned.

Previous Simil'ar Events None Commitments None NRC FORM Sddo 4 U.S GPO.198~82 d.538/4 55 (9831

iI ik a/

TENNESSEE 'VALLEY AUTHORITY Browns Ferry,.Nuc1ear'Plant Post Office Box 2000 Decatur, Alabama 35602 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Dear Sirt

'TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR. PLANT UNIT 3 DOCKET NO. 50-296 FACILITY OPERATING LICENSE DPR-68 REPORTABLE OCCURRENCE REPORT BFRO-50-296/88002 The enclosed'eport provides details concerning the unplanned reactor water cleanup isolation due to personnel error. This report is submitted in accordance with 10 CFR 50.73 (a)(2),(iv).

Very truly yours, TENNESSEE VALLEY AUTHORITY k jn-~

Guy G. Campbell Plant Manager Browns Ferry Nuclear 'Plant Enclosures cc (Enclosures):

Regional Administration INPO Records Center U.S. Nuclear:Regulatory Commission Suite 1500 Office of Inspection -and Enforcement 1100'ircle 75 'Parkway Region II 'Atlanta, Georgia 30339 101 Marietta Street, Suite 2900

'Atlanta, Georgia 30303 NRC Resident Inspec'tor, Browns Ferry Nuclear Plant

~@gyP An'Equal Opportunity Employer

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