ML20042F978

LER 89-031-01:on 890828,480-volt Engineered Safeguards Stepdown Transformer a Faulted Causing Decay Heat Train Closed Cycle Cooling Pump a to Deenergize.Caused by Degraded Insulation.Transformer replaced.W/900507 Ltr

ML20042F978
Person / Time
Site:	Crystal River
Issue date:	05/07/1990
From:	Boldt G, Moffatt L FLORIDA POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0590-05, 3F590-5, LER-89-031, LER-89-31, NUDOCS 9005100252
Download: ML20042F978 (8)

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• Power C O R P O R AT tO N h!ay7,1990 3F0590-05 U. S. Nuclear Regulatory Commission I Attention: Document Control Desk Washington, D. C. 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 <!

Operating License No. DPR-72 Licensee Event Report No. 89-031-01

Dear Sir:

1 Enclosed is a supplement to Licensee Event Report (LER)89-031 which was 1 previously submitted in accordance with 10 CFR 50.73. This supplement is being submitted to provide the results of a failure analysis to determine i the cause of the transformer failure and to report on additional  !

corrective action.  !

Should there be any questions, please contact this office.

Sincerely, G. L Boldt Vice President, Nuclear Production WLR: mag l Enclosure xc: Regional Administrator, Region II Senior Resident Inspector 1

l-l 9005100252 900507 .

DR ADocK c500 POST OFFICE BOX 219

• CRYSTAL RIVER, FLORIDA 32629 0219 + (904) 563-2943 l

A Florida Progress Company

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DOCKET NUMSER (2) PAGE (3, F ACILITY NAME ('l CRYSTAL RIVER UNIT 3 015 l 0 l010 l 3 l0 l2 1 lor@g TITLE '4' Failure _of . 'A' 480 volt Engineered Safeguards Transformer Causes Temporary Interruption of Decay Heat Cooling and a Plant Operational MODE Change EVENT DATE IS) LER NUMBER 14) REPORT DATE 17) OTHER F ACILITIES INVOLVED (St N,",) MONTH DAY vlAR F ACILiv V NAuf 5 DOCKE T NUMBER (31 MONTH DAY YEAR YEAR O h"'

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NAMg TE LEPHONE NUMBE R L. W. M0FFATT, NUCLEAR SAFETY SUPERVISOR 9 l0 l4 7 l9 [5 l- l6 l4 8 1 l6 COP *PLETE ONE LINE FOR E ACH COMPONENT F AILURE DESCRISED IN THis REPORT 1131 MA AC REP " L ** C AI' " $

CAUSE SYSTEM COMPONENT CAU$E SY STE V COMPONE NT y O NPR 3 TO N*R X X;F]M j R  ; ; ;

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Crystal River Unit 3 was in MODE 5 (COLD SHUTDOWN) to perform repairs to a Nuclear Services Raw Water . Pump with the B Decay Heat train (DH) removed from service. The A DH train was operating and the Reactor Coolant System was filled and intact with an operable Steam Generator. At 0237 on August 28, 1989, the A 480 Volt Engineered Safeguards (ES) stepdown transformer faulted causing DH Closed Cycle Cooling Pump A (DCP-1A) to de-energize. Loss of DCP-1A removed the cooling for DH train A, rendering this train inoperable. At 0256, DH Train B and its support systems were started. The A and B 480 Volt ES buses were then cross-tied to provide AC power to the A bus. The loss of DH cooling caused an increase in RCS temperature and an inadvertent entry into MODE 4 (HOT SHUTDOWN). The transformer has oeen replaced. The transformer faulted due to insulation degradation caused by aging. During the event, operators attempted to operate the B Train DH suction isolation valve (DHV-40) from the control room. ihis valve failed because the nut securing the linkage between the motor operator and the valve stem had backed off from normal operation. DHV-40 has been repaired and the nut on the linkage has been staked to prevent it from backing off. The redundant valve, DHV-39, will be staked.

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CRYSTAL RIVER UNIT 3 o js jo jo lo l 3;0 g2 8; 9 ._

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0l1 0l2 or 0 j7 sw w u a . .e . .-ac 1 m anm EVENT DESCRIPTION Crystal River Unit 3 (CR-3) was in COLD SHUTDOWN (MODE 5) to perform repairs to the Emergency Duty Nuclear Services Raw Water Pump (RWP-2B) [BS,P]. CR-3 had.

been shutdown at the time of this event for approximately 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />. The repair work required divers to enter the 'B' Raw Water Pit. To safely conduct the repair work it was necessary to remove the 'B' Decay Heat Train from service.

The 'B' Decay Heat Removal train includes the 'B' Decay Heat Raw Water Pump (RWP-3B) [BS,P], the 'B' Decay Heat Closed Cycle Cooling Pump (DCP-1B) [CC,P],

and the 'B' Decay Heat Removal Pump (DHP-1B) [BP,P]. In accordance with Technical Specifications, the 'A' Decay Heat train was cperating and the Reactor Coolant System (RCS) was filled and intact with operable Steam Generators

[AB,SG]. All Reactor Coolant Pumps [AB,P] were off. One train of Main Feed Water (MFW) had been secured to perform maintenance on the 'B' Main Feedwater Booster Pumps [SJ,P]. MFW train 'A' was providing feedwater to the steam generators, while they were alternately being blown down for cleanup. A Reactor Building purge was in progress. By 2045 on August 27, 1989 all diving operations in the 'B' Raw Water Pit had been secured.

At 0237 on August 28,1989, the ' A' 480 Volt Engineered Safeguards (ES) stepdown transformer [ED,XFMR] faulted causing Decay Heat Closed Cycle Cooling Pump A (DCP-1A) to de-energize. Loss of DCP-1A removed the cooling source for Decay Heat train ' A' and DHP-1A, rendering this train inoperable. Power was also interrupted to various plant ventilation systems. The RB Purge was isolated as designed when power was interrupted to the Purge Radiation Monitor vacuum pump

[IL,P]. ES inverters [EE,INVT] swapped to battery power. Reactor Coolant System temperature, as measured at the decay heat cooler outlet, at the time of the fault was approximately 190 degrees F and the RCS pressure was approximately 165 psig. Decay Heat train 'A' was kept operating for a short time and provided forced circulation through the reactor.

Licensed operators quickly identified the cause of the event. Despite a loss of various equipment status lights, the plant condition was rapidly determined from redundant indicators. In accordance with procedures, actions were immediately initiated to assure the steam generators could be used if necessary to remove decay heat until the 'B' Decay Heat Train could be started. These actions included checking which Reactor Coolant Pump start permissives were met, assuring Turbine Bypass Valves [TA,V) were available, and assuring condenser vacuum was available. In parallel, actions were taken to start Decay Heat Train

'B'. This required clearing tags from tagged out equipment, racking in breakers, opening valves, and energizing the pumps. At 0251, while preparing to start Decay Heat Train 'B', the RCS temperature increased above 200 degrees and an entry into HOT SHUTDOWN (MODE 4) was noted. At 0256, Decay Heat Train 'B' and its support systems were started and the 'A' Decay Heat Pump was secured. At 0258, the RCS temperature returned below 200 degrees and the plant reentered COLD SHUTDOWN (MODE V). Operator actions during this event were timely and appropriate. i l

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0l1 0l3 0' 01 7 j tm , , w.. . ., . . ,. ..c w mu ,"m i Once Decay Heat cooling was reestablished, actions were then taken to cross-tie the 'A' and 'B' 480 Volt ES buses to provide AC power to the 'A' bus. At 0322, .

loads were shed from the 'A' 480 Volt ES bus and the bus was checked for electrical faults. When it was verified that the 'A' bus was itself unfaulted, it was connected to the 'B' 480 Volt ES bus. Between 0331 and 0340, loads were placed back on the 'A' 480 Volt ES bus and actions were taken to restore plant equipment which had been affected by the transformer fault.

During the event, operators attempted to operate the "RCS to 'B' Train Decay Heat suction isolation valve" (DHV-40) [BP,lSV) from the control room. Because the linkage between the motor operator and the valve stem was inoperable, the valve had to be opened manually. The delay in opening this valve may have contributed to the time needed to place Decay Heat Train 'B' in service. If the linkage had been operable, then RCS temperature may not have increased as high.

At 0345, CR-3 entered an Unusual Event due to a need for increased awareness of plant conditions. CR 3 then made a one-hour report in accordance with the requirements of 10CFR50.72(a)(i). At 0351 on August 28, 1989, CR-3 exited the Unusual Event.

This event is being reported because it cause:' an entry into a higher mode rhile e@lpment required in that mode was inoperable. This is a violation of Technical Specification 3.0.4 and reportable per InCFR50.73(a)(?)(1)(B).

G!MSI The transfermer faulted due to insulatior degradation caused by aging.

The linkage en PHV-40 failed because *.he nut securing the linkage backed off fre, normal operation. As a ecsult of an verlier failure, a recommendation had been made to mechanically secure the nut on this linkage. The re:ponsible engineer deterr.ined that no additional ccrrective actions were necded since the set screws for the nut had been tightened. However, he failed to notice this action had been performed prior to the failure and that it had been ineffective.

This personnel error appears to be cognitive and is not a procedural violation.

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CRYSTAL RIVER UNIT 3

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0l1 0l4 of 0 l7 im m. muvim EVENT ANLLYSIS This event did not challenge the fuel, the fuel clad or the reactor pressure boundary. The maximum average incore temperature was 210 degrees. This is well  !

witt.in fuel, clad and RCS limits. Adequate shutdown margin and subcooling margin were maintained. Additionally, Steam Generators were available to provide core cooling. If Decay Heat train 'B' had not been started and the ES 480 Volt buses had not been cross-tied, then core cooling would still have been available.

Steam Gonerator cooling typically requires entry into MODE 4 in order to reach an RCS temperature where steam can be produced. To the extent possible, entry into MODE IV under these conditions is a preplanned process.

An engineering evaluation has been performed to determine the effect of operating the ' A' Decay Heat and ' A' Decay Heat Raw Water pumps without cooling. This ,

evaluation determined that no pump degradation had occurred during the short time cooling was not provided.

If this event had occurred during operation, then various ES equipment would have lost motive power, and may have required manual operation. The more critical ES equipment is powered by inverters which will swap to DC power from the station batteries. Sco t~ n e attached Enclosure for a list of loads on the l 480 Volt bus. Most of this equipment fails as is. Other enponents such as the ventilation systems and the sup,Prt pump 3 would have been de-energized.

The battery backed inverters and the redundant 'B' train would then be used to

. assure a safe shutdown to MODE 4 (HOT SHU1E0WN)

@lRICTIVE ACILQfi$

The 'A' 490 Volt ES transforner has been replaced. Florida Power will perform f  :

a check of the 'B' 480 Voit ES transformer. The program to periodically check in? 480 Volt transformers is teing enhan:cd ta include editional electrical '

checke DHV 40 has been repsired and the nut on the linkage has been staked to prevent it from backing oli during operction. The licka;)e nut on redundant alve, DHV-39, will also be staked prior to start-up.

PREVIOUS SIMILAR EVENTS Decay Heat System cooling has been lost on three prior occasions. LER 86 02 describes a loss of Decay Heat cooling due to a diving fatality. LER 86-03 describes a loss of decay heat due to Decay Heat pump motor overload and failure of the Decay Heat suction isolation valve. The other event, LER 88-22, was caused by a change in the Decay Heat isolation valve auto-closure interlock setpoint. There are no prior events of a faulted 480 Volt ES stepdown transformer. In 1986 the Decay Heat suction isolation valve was found to be inoperable when the nut securing the linkage became loose.

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ENCLOSURE 480 VOLT ES BUS 3A LOADS ,

COMPONENT IDENTIFICATION EIIS ID FUNCTION ES MCC 3Al ED SEE BELOW ES MCC 3A2 ED SEE BELOW ES MCC 3A3 ED SEE BELOW ES MCC 3AB ED SEE BELOW DCP-1A CC,P Decay Heat Closed Cycle Cooling Pump A fMHE 1A KM,CHU Control Complex Chiller A ES MCC 3Al ACDP 39 ED,PL 480V Control Complex Lighting Panel ACDP-40 ED,PL 480V Control Complex Lighting Panel ACDP 41 ED,PL 480V Control Complex Lighting Panel ACDP-51 ED,PL Control Complex Distribution Panel ACDP-116 ED,PL Chem Rad Distribution Panel AHF-BA VG, FAN SF Pumps Air Handling Unit A AHF-15A CC, FAN DC Air Handling Unit A AHF 20A VF, FAN Controlled access area Exhaust Fan ,

AHD24A VF, FAN Intermediate Bldg Exhaust Fan A AHF-29A VF, FAN Intermediate Bldg Supply Fan A AHF-44A VF. FAN Sanpling Room Exhaust fan A A!!V-1B EB,lSV RB Par +je Exhaust Isolation AHV-lC BB,ISV RB Purge Supply Isolation BSV-3 BE,lSV BSP-1A Discharge isolation BSV 12 BE,V Sodium Hydroxide to BSP-IA BSV-17 BE,lSV BSP 1A Suction Isulation i BSV-35 BE,V Spare Tank Suction to BSP 1A CAHE-3A SR,0lTR A BWST Heater CFV 11 BP,SHV CFT A Sample Valve CFV-12 BP SMV CFT B Semple Valve CFV-15 BP,VTV CFT B Vent to Waste Gas BP,VIV CFV-16 CFT A Vent to Weste G u DHV-3 BP,V DH Suction frco RCS DHV-5 BP V DHP-1A Discharge to RCS DHV-Il BP,V DHP-1A Discharge to MVP-1A Suction DHV-34 BP,V DHP-1A Suction from BWST DHV 39 BP,V DHP-1A Suction from RCS DHV-42 BP,V DHP-1A Suction from RB Sump DHV-Il0 BP,FCV DHP-1A Flow Control Valve DOV-210 KK,V SW to RW Flush Water D0P-2A KK,P Flush Water Pump A FWV-15 SJ,ISV B MFWP Suction Valve FWV-30 SJ,ISV A Main Block Valve FWV 31 SJ,ISV A Low Load Block Valve HTTR-1A FE,XFMR Heat Tracing Transformer 3-1A HTTR-3A FE,XFMR Heat Tracing Transformer 3-3A 1

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MVV 23 BQ,1NV HPI Injection Valve (normal source)

MVV-24 BQ,INV HPI Injection Valve (normal source)

MUV-25 BQ,1NV HPI Injection Valve (emergency source)

MVV-26 BQ,1NV HPIInjectionValve(emergencysource)

RMP-Al IL,P RMA 1 Vacuum Pump RMP-A2 IL,P RMA 2 Vacuum Pump RMP A7 IL,P RMA-7 Vacuum Pump ,

RMP-A14 IL,0VT RMA-14 480V Outlet SFP-1A DA,P Spent Fuel Pump A ,

VBIT-1A EF,1NVT A Inverter Normal AC Supply VBIT-1C EF,INVT C Inverter Normal AC Supply VBTR-3A ED,XFMR 480V/120V Transformer for VBDP-12 i VBTR-3C ED,XFMR 480V/120V Transformer for VBDP-13  :

ES MCC 3A2 ACDP 5 ED,PL 480V A Diesel Room Distribution Panel .

AHF-1A BK, FAN Reactor Building fan Assembly A AHF-17A VI, FAN Control Complex Normal Supply Fan A VI, FAN Control Complex Emergency Supply Fan A AHF-18A AHF-19A VI, FAN Control Complex Return Ftn A AHF-22A VJ, FAN A Diesel Gen Room Fan A AHF-22B VJ, FAN A Diesel Gen Room Fan B CAV-1 BR,lSV Pressurizer Steam Space Samplo Iso.

CAV-3 BR.ISV Pressurizer Water Space Sample Iso. 1 CAV-4 BR,lSV A DISG SMple Isc, Valve i CAV-5 BR,ISV B OTSG Sample Iso, Velve I CAV-126 BR,ISV RC 3.etdown Sample Iso. Valve l CHP-1A KM,P Chilled Water Supply Fump DFP-1A DE,P A Diesel Gen Feel Transf er Pump DHHE-2A BP.EHlR BWST Heater A >

HTIR 2A FE,XFMR Heat Tracing Transformer 3 2A L HsTR-4A FE.XrMR Heat Tracing Transforcar 3 4A HTTR-5A FE,XFMR Heat 1racir.g Transformer 3-5A 3 MVP-2A BQ,P MUb1A Matn Lubo Oil Pump g, MVP-4A BQ,P MVP-1A Gear Oil Pump MVV 40 CB,ISV Letdown Cooler A Outlet Iso '

MUV-41 CB,lSV Letdown Cooler B Outlet Iso MVV-53 BQ,V MVP Recirculation Valve MUV-258 CB,ISV Bleed-off Iso from RCP-1A MUV-259 CB,lSV Bleed-off Iso from RCP-1B MVV-260 CB ISV Bleed-off Iso from RCP-10 MUV-261 CB,lSV Bleed-off Iso from RCP-ID TBM-1 TA,TGR Turbine-Gen Turning Gear Motor l VBTR-4A ED,XFMR Backup AC Power to VBIT-1A VBTR-4C ED,XFMR Backup AC Power to VBIT-lC l WDV-3 WD,V RB Sump Pumps Discharge Valve

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0l3l1 0 l1 0l7 or 0l7 WDV 60 WD,ISV RCOT Vent Isolation Valve WDV-94 WD,V RCDT Pump Discharge Valve WDV 406 WD,ISV RB Waste Gas Isolation Valve WSP-1 WE.P RB Range Sample Recirculation Pump ES MCC 3A3 AHF-54A VI, FAN EFIC Room Fan A AHP-1A LD, CMP Auto Temp Control Air Compressor A AHP-1B LD. CMP Auto Temp Control Air Compressor B DPBC-1A EJ,BYC A Battery Charger DPBC-lc EJ,BYC C Battery Charger DPBC-lE EJ BYC E Battery Charger EGDG 1A EK,PL EGDG-1A Circuit Breaker Panel Board MUV-73 BQ,V MVP-1A Suction from BWST ,

MVV 505 BQ,iSV MUHE-lc Outlet Isolation Valve ES MCC 3AR AHF-lc BK, FAN RB Fan Assembly C ACDP-14 ED,PL Turbine Bldg Emergency Lighting Panel ACDP-15 ED,PL Aux Bldg Emergency Lighting Panel ACDP-38 ED PL 240/120V Control Compicx Lighting Pn1 CFV-5 BP,lSV A CFT Isolation Valve CFV- F< f>P,lSV B CFT isolation Valve UHV 7 BP,V A DH Discharge Cross-tie i DHV-8 BP,V B DH Discharge Cross-tie DilV-41 BP,lSV Dil Drop line Isolation Valve DHV-91 BP,ISV DH to Pressurizer Spray Iso Valve DWV-160 KK,lSV DW to RB Isolation Valve l MVP 20 BQ.P MVP-1B Main Lube Oil Pump MVP-4B BQ,P MUP-1B Main Gear Oil Pump  :

MUV 18 B0,lSV RCP Sor injection Isolation Valve '

MUV-27 CE,lSV Normal Makeup Isolation Valve ,

RCV-11 AB,lSV PORV Block Valve RCV-13 AB,lSV Pressurizer Spray Valve Isolation Pressurizer Spray Valve RCV-14 AB,V RCV-53 AB,FCV DH to Pressurizer Control Valve l

i

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