ML17348A498

LER 90-007-00:on 900726,component Cooling Water Pump 4A Automatically Started.Caused by Error Made by Nonlicensed Personnel.Pressure Controller PC-4-611 Recalibrated. W/900810 Ltr

ML17348A498
Person / Time
Site:	Turkey Point
Issue date:	08/10/1990
From:	Harris K, Dawn Powell FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-90-293, LER-90-007-02, LER-90-7-2, NUDOCS 9008150276
Download: ML17348A498 (10)

Text

ACCELERATED DlsfRlBUTlON DEMONSTRATlON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9008150276 DOC.DATE: 90/08/10 NOTARIZED: NO DOCKET g FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION POWELL,D.R. Florida Power 6 Light Co.

HARRIS,K.N. Florida Power It'ight Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 90-007-00:on 900726,automatic start of 4A CCW pump due to low CCW pump discharge header pressure.

W/9 ltr.

DISTRXBUTION CODE: XE22T COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Xncide t Rpt, etc.

NOTES

,RECIPIENT COPXES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 EDISON,G 1 1 XNTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/ DS P/TPAB 1 1 AEOD/ROAB/DS P 2 2 NRR/DET/ECMB 9H l. 1 NRR/DET/EMEB9H3 NRR/DLPQ/LPEB10 1 1 NRR/DLPQ/LHFB11 1 1 1 1 NRR/DOEA/OEAB11 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 B8D1 1 1 NRR/DST/SRXB 8E 1 1 REG L 02 1 1 RES/DSIR/EIB 1 1 FILE 01 1 1 EXTERNAL EGGG BRYCE I J ~ H 3 3 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSXC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32

P.O. ox14000, Juno Beach, FL 33408-0420 APL AUG 1 0 1990 L-90-293 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Unit 4 Docket No. 50-251 Reportable Event: 90-007 Date of Event: July 26, 1990 Automatic Start of the 4A Component Cooling Water (CCW) Pump Due to Low CCW Pump Discharge Header Pressure The attached Licensee Event Report is being provided pursuant to the requirements of 10CFR50.73 as notification of the subject event.

Very truly yours, cV~w Vice President Turkey Point Nuclear Plant KNH/DRP/dwh Attachment cc: Stewart D. Ebneter, Regional Administrator, Region llr USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 9008150276 900810 PDR ADOCK 05000251 PDC an FPL Graup company

NRC Form 355 (943) U.S. NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO. 3(50010e LICENSEE EVENT REPORT (LER) EXPIAES: SISIISS FACILITY NAMK (Il DOCKET NUMSER (2) PA 5 Turkey Point Unit 4 o s o o o2 51>of 04 Automatic Start of t e 4 omponen oo sng a er ump ue o ow ump Dischar e Header Pressure EVEN'7 DATE(5) LEA NUMSEA (5> REPORT DATE It) OTHER FACILITIES INVOLVKD(5)

MONTH OAY YEAR YEAR QIIK NVMSKR NUMsc re MON1'H OAY YEAR FACILITY NAMES DOCKET NVMSEAISI N/A 0 5 0 0 0 726 90 90 0 0 0 0 8 1 0 9 0 0 5 0 0 0 THIS RFPORT IS SUSMI'TTEO PUASUANT T 0 THE REDUIREMENTS Of 10 Cf R $ : IChntr one or more ol rhe Io/Iorwnpl (11 OPERATING MODE (5) 20.402(d) 5 20.405(cl 50,73( ~ II2)(le) 73.71ldl POWER 20.405(el(1)(i) 50.35(c) (1) 50.73(el(2)(e) 73.7((cl LEVEL I10) 20.e05(el(ll(9) 50.35(cl(2) 50.73 (el 1 21(e ill O'THEA ISpeclry in Adrtrect dHow endin TeeL NRC form 20.405(e) (I )(iiil 50.7 3(e I (1) Ill 50.73( ~ ) (2)(riill(AI 3664I 20.405(el(1)(le) 50.73(e l(1) (il) 50,73( ~ l(2) (rlii(ISI 20.405( ~ I I I IN) 50.73(el(2)(llil 50.73( ~ )(2)(el LICENSEE CONTACT FOR THIS LER (11)

NAME TELEPHONE NUMSER AREA CODE David R. Powe11, Licensing Superintendent 30 524 6-65 59 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRISED IN THIS REPORT (13)

MAhlUFAC EPOR1'ASLE MANVFAC FPORTASLK CAUSE SYSTEM COMPONENT CAUSE SYSTKM COMPONEN'T TVRKR TO NPROS >4<~j4HH$4~%> TURER TO NPROS SUPPLEMENTAL AKPORT EXPECTED (ICI MONTH OAY YEAR EXPECTED SV 5 M I SS I ON DATE I'(5I YES IIIyn, compiere EXPECTED SVdMISSION DA TEI AEETRAcT I(,lmlr ro Ic00 rpecn, I A. euuroeimereiy Iiireen rinpre.rpece typewrrtrcn rrnnl IlSl At 1228, on July 26, 1990, with Unit 4 in Mode 5 (Cold Shutdown), the 4A Component Cooling Water (CCW) pump automatically started. Prior to this event, the 4C CCW pump was operating and the 4B CCW heat exchanger was out of service for cleaning. At approximately 1155, the 4B CCW pump was started in preparation for returning the 4B CCW heat: exchanger to service and taking the 4C CCW heat exchanger out of service for cleaning. After swapping the CCW heat exchangers, the 4B CCW pump was stopped. A low CCW pump discharge header pressure condition was sensed by pressure controller PC-4-611 and the 4A CCW pump automatically started within 5 seconds, as designed.

,The cause for this event was cognitive error made by a non-licensed utility person. A contributing factor was inadequate administrative controls. On January 6, 1988, the low pressure setpoint for PC-*-611 was changed from 75.0 psig +/- 1.5 psig to 60.0 psig +/- 1.5 psig. On January 19, 1988, PC-3-611 and PC-4-611 were calibrated to the new setpoint. However, the master instrument calibration data sheets were not revised to reflect the new setpoint or attached to the Plant Work Orders physically changing the instrument setpoints. PC-4-611 has been calibrated to 60 psig +/- 1.5 psig. PC-*-611 instrument calibration data sheets have been revised to reflect a low pressure setpoint of 60.0 psig +/- 1.5 psig.

NRC form 355 (9 5) I

NRC Form 355A (9.83) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILER1 TEXT CONTINUATION APPROVEO OMB NO. 3150WI04 EXPIRESI Bl31l88 FACILITY NAME (I) OOC K ET NUMBER (2)

LER NUMBER (5) PACE (3) seauerr TIAL NUM err $ :>< rrevrerorr

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rruM eR Turkey Point Unit 4 o s o o o 2 1 9 0 007 0 0 0 2OF0 4 TEXT illmoro rpooo io roerrliod, ooo oddi)rcpt>>l HRC %%dnn 355r('4) (17)

DESCRIPTION OF THE EVENT At 1228, on July 26, 1990, with Unit 4 in Mode 5 (Cold Shutdown), the 4A Component Cooling Water (CCW) pump (EIIS:CC, Component:P) automatically started within 5 seconds of pressure controller PC-4-611 (EIIS:CC, Component:PC) sensing a low CCW pump discharge header pressure condition. The 4C CCW pump continued to operate during this event.

Prior to this event, the CCW System was aligned for single pump operation. The 4C CCW pump was operating and the 4B CCW heat exchanger was out of service for cleaning. At approximately 1155, the 4B CCW pump was started in preparation for returning the 4B CCW heat exchanger to service and taking the 4C CCW heat exchanger out of service for cleaning. After swapping the CCW heat exchangers, the 4B CCW pump was stopped. A low CCW pump discharge header pressure condition was sensed by PC-4-611 and the 4A CCW pump automatically started within 5 seconds, as designed.

At 1357, on July 26, 1990, FPL notified the NRC Operations Center of a significant event in accordance with 10CFR50.72(b)(2)(ii) as an automatic actuation of an Engineered Safety Feature (ESF).

CAUSE OF THE EVENT The cause for this event was cognitive error made by a non-licensed utility person. A contributing factor was inadequate administrative controls t:o ensure that revised setpoints were incorporated into instrument calibration data sheets.

On January 6, 1988, the setpoints for PC-*-611 were changed from 75.0 psig +/- 1.5 psig to 60.0 psig +/- 1.5 psig in accordance with Administrative Procedure AP 0140.2, "Changing Setpoints," which required a 10CFR50.59 safety evaluation and subsequent review by the Plant Nuclear Safety Committee (PNSC).

.This setpoint change was deemed necessary to prevent nuisance automatic starts of the standby CCW pump(s) due to flow transients when switching from two pump to one pump operation.

Single pump operation results in CCW pump discharge header pressures close to 75.0 psig.

On January 19, 1988, PC-3-611 and PC-4-611 were recalibrated to 60.0 psig +/- 1.5 psig. Calibration of these pressure controllers was performed under a Plant Work Order (PWO), using the setpoint change package as guidance. The master instrument NRC FORM 355A (94)3)

i ~

E'

NRC FONS 388A U.S. NUCLEAR REOULATORY COMMISSION (943)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVEO OMB NO. 3(50M(04 EXPIRES: 8/31/88 I'ACILITYNAME (1) OOCKET NUMBER (2)

LER NUMBER (8) PACE (3)

SEOVENTIAL X~ NUMBER 'I(> REVISION

.P~g/

NVMSSR Turkey Point Unit 4 o s o o o 25 190 0 0 7 03 oFO 4 TEXT ///mom r/Mrr /r /rrwird, IIrr rdd4'one////IC /rdmI JSSA'r/ (IT) calibration data sheet for PC-*-611 should have been revised to reflect the new low pressure set point and attached to the PWOs at this time. This administrative task was not performed.

During the Unit 4 Cycle 12 refueling outage, PC-4-611 had to be moved due to mechanical interference with the CCW heat exchanger tube bundle replacement. Upon reinstallation, PC 611 was calibrated to 75.0 psig +/- 1.5 psig using the instrument, calibration data sheet as guidance.

Troubleshooting performed on PC-4-611 as a result of this automatic 4A CCW pump start determined that the instrument low pressure alarm setpoint was within specifications. However, a post-work review of the PWO identified that the wrong low pressure setpoint was specified on the instrument calibration data sheet. The as-found setpoint of PC-4-611 was 75.5 psig.

ANALYSIS OF THE EVENT Low CCW pump discharge header pressure is controlled by pressure controller PC-4-611 which is located at the inlet to the 4B CCW heat exchanger. PC-4-611 is provided with a low pressure alarm which is annunciated in the Control Room and is used to start th'e standby CCW pump(s) upon reaching a low CCW pump discharge header pressure setpoint. The Design Basis Document (DBD) for the CCW System states that PC-*-611 does not perform a safety function. Only one CCW pump and two CCW heat exchangers are required to mitigate the consequences of a maximum hypothetical accident (MHA).

The Unit 4 CCW pumps remained operable and the 4C CCW pump continued to operate during this event. Upon automatic starting of the 4A CCW pump, the CCW pump discharge header pressure increased above 75.0 psig.

CORRECTIVE ACTIONS PC-4-611 was recalibrated to 60.0 psig +/- 1.5 psig.

2 ~ PC-3-611 was found to be set at approximately 63.5 psig and was recalibrated to 60.0 psig +/- 1.5 psig.

3 ~ The instrument calibration data sheets for PC-*-611 have been revised to specify a low pressure setpoint. of 60.0 Pslg +/ 1 ' Psigr NRC PORM SSSA (943)

NRC Form 388A U.S. NUCLEAR REGULATORY COMMISSION (943)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3150M)04 EXPIR ES: 8/31/88 FACILITYNAME (I) OOCKET NUMBER (3) LER NUMBER (8) PAGE (3)

SCC1UCNTIAL RcvlsloN YEAR gg NUMBER

>SIC(

NUMSCR Turkey Point Unit 4 o2 51 90 0 0 7 0 0 04 o" 0 4 TEXT ///moro sosco IS ror/virsd, vso sddirions/HRC Form 388IC's/ (IT) 4 Setpoint change documents will be verified against instrument calibration data sheets. Identified discrepant

~

conditions will be evaluated and resolved. This task will be completed by September 28, 1990.

5 ~ Maintenance Instruction (MI) 102-114, "Maintenance Instruction On The Spot Change (MICHANGE) Preparation, Review, and Approval Form," has been revised to include provisions for changing instrument calibration data sheets based on information contained in a Plant Change or Modification (PC/M).

6. An On-The-Spot-Change has been generated to Administrative Procedure O-ADM-701, "Plant Work Order Preparation." This change requires instrument calibration data sheets to be verified and attached to PWOs that involve instrument calibrations or calibration checks.

ADDITIONAL INFORMATION A similar event was reported in LicenseePC-4-611 Event Report (LER) 50-251/90-006. At the time of the event, was believed to be set at 60.0 psig +/- 1.5 psig. FPL believes the CCW pump discharge header pressure would have decreased below 60 psig during the sequence of events described therein. Discovery that PC-4-611 was set at 75.0 psig +/- 1.5 psig does not change the root cause or corrective actions contained in LER 50-251/90-006.

NRC FORM 388A (9831