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| {{#Wiki_filter:ACCELERATED DOCVMENT DISTKCBUTION SYSTEM REGULAQIY INFORMATION DISTRIBUTI SYSTEM (RIDE)ACCESSION NBR:9307270061 DOC.DATE: 93/07/22 NOTARIZED: | | {{#Wiki_filter:ACCELERATED DOCVMENT DISTKCBUTION SYSTEM REGULAQIY INFORMATION DISTRIBUTI SYSTEM (RIDE) |
| NO FAClLq50-251 Turkey Point Plant, Unit 4, Florida Power and Light C AUTH.::AME AUTHOR AFFILIATION KNORR,J.E. | | ACCESSION NBR:9307270061 DOC.DATE: 93/07/22 NOTARIZED: NO DOCKET FAClLq50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.::AME AUTHOR AFFILIATION KNORR,J.E. Florida Power & Light Co. |
| Florida Power&Light Co.PLUNKETT,T.F. | | PLUNKETT,T.F. Florida Power & Light Co. |
| Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000251 | | RECIP.NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 93-002-00:on 930622,RT occurred due to manual turbine trip.Installed guard preventing inadvertent operation of auxiliary governor trip lever.W/930722 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES RECIPIENT ID CODE/NAME PD2-2 LA RAGHAVANFL INTERNAL: ACNW AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB | | LER 93-002-00:on 930622,RT occurred due to manual turbine trip. Installed guard preventing inadvertent operation of auxiliary governor trip lever.W/930722 ltr. |
| ~DS SPLB REG FIL 02 G FILE 01 EXTERNAL'G&G BRYCE F J~H NRC PDR NSIC POORE,W.COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD AEOD/DOA AEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHYFG.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 2 2 1 1.1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: | | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: |
| PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 0 0 0.Box 029100, Miami, FL, 33102-9100 APL L-93-166 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 JUL 2g]ggg Gentlemen:
| | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| Re: Turkey Point Unit 4 Docket No.50-251 Reportable Event: 93-002-00 Reactor Tri Due to Manual Turbine Tri The attached Licensee Event Report 251/93-002-00 is being provided in accordance with 10 CFR 50.73 (a)(2)(iv).If there are any questions, please contact us.Very truly yours, pgj)>~T.F'.Plunkett Vice President Turkey Point Nuclear TFP/JEK/3k enclosure cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Ross C.Butcher, Senior Resident Inspector, USNRC, Turkey Point Plant~cate 9307270061 930722 PDR*DOCK, 0500025k S PDR on FPL Group company iP C lg LICEN E EVENT REPO (LER)PACILITY NAME (1)TURKEY POINT UNIT 4 TITLE (4)REACTOR TRIP DUE TO MANUAL TURBINE TRIP DOCKET NUMBER (2)PACE (3)05000251 1" 3 EVENT DATE (5)LER NUMBER(6)RPT DATE (7)OTHER PACILITIES INVOLVED (8)MON DAYYR YR SEQ 4 Rt MON DAY PACILITY NAMES DOCKET 4 (S)06 22 93 93'02 00 07 22 93 OPERATING MODE (9)POWER LEVEL (10)33%10 CFR 50.73 a 2 iv LICENSEE CONTACT FOR THIS LER (12)J.E.Knorr, Regulation and Compliance Specialist COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)TELEPHONE NUMBER 305-246-6757 CAU SE SYSTEM TG COMPONENT 94 MANUPACTURER W120 NPRDS7 CAUSE SYSTEM COMPONENT MANUPACTURER NPRDS2 SUPPLEMENTAL REPORT EXPECTED (14)NO Z YES 0'XPECTED SUBMISSION DATE (15)MONTH DAY (1f yes, cmaplete EXPECTED SUBMISSION DATE)ABSTRACT (16)On the morning of June 22, 1993, Turkey Poi.'nt Unit 4 was at 100%power and conducting a turbine trip test on the main turbine in accordance with procedures and procedural requirements. | | NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 RAGHAVANFL 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 |
| At the successful completion of the turbine trip test, the plant operators were unable to relatch the turbine trip.Turkey Point Unit 4 was reduced in power with the intent of taking the turbine off line to trouble shoot and repair, if necessary, the turbine trip latching, mechanism., At 1231 Eastern Daylight Time (EDT), with reactor power having been reduced to approximately 33%power, loss of turbine control oil pressure resulted in a turbine anti-motoring trip followed by a generator lockout.Based on the turbine anti-motoring indication.and the generator lockout, plant operators manually.tripped the turbine.A reactor trip at 1232 EDT resulted from the manual turbine trip.The NRC was notified in accordance with 10 CFR 50.72 (b)(2)(ii)June 22I 1993(at 1315 EDT.Extensive investigations of probable cause for the turbine anti-motoring trip and generator lockout were completed. | | ~DS SPLB 1 1 NRR/DSSA/SRXB 1 1 REG FIL 02 1 1 RES/DSIR/EIB .1 1 G FILE 01 1 1 EXTERNAL 'G&G BRYCE F J H ~ 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHYFG.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL"RIDS" RECIPIENTS: |
| The investigations concluded that the cause was an inadvertent operation of the auxiliary governor.trip lever by personnel restoring the turbine controls to normal after the turbine trip test.The unrelated inability to relatch the turbine trips was caused by incorrect clearances in the overspeed trip block between the trip relay and the relay bushing, and between the relay cup valve and the relay cover plate.These clearances were corrected and Unit 4 was returned to service on June 26, 1993. | | PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| 0 L II ,l LICENSEE VENT REPORT (LER)TEXT CONTINUATION r FACILITY NAME DOCKET NUMBER LER NUMBE PAGE NO.TURKEY POINT UNIT 4 05000251 93-002-00 2 QF 3 I.DESCRIPTION OF THE EVENT On the morning of June 22, 1993, Turkey Point Unit 4 was at 100%power and conducting a turbine trip test on the main turbine in accordance with operations surveillance procedure 4-0SP-200.3, Secondary Plant Periodic Tests.At the successful completion of the'urbine trip test, the plant operators were unable to relatch the turbine trip.Turkey Point Unit 4 was reduced in power with the intent of taking the turbine off line to trouble shoot and repair, if necessary, the turbine latching mechanism. | | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 |
| Prior to the load reduction, discussions were held with operations personnel to alert them of actions to be taken (such as initiating manual trips)if any unexpected events were to occur during the load reduction. | | |
| Direct communications were established between the turbine front standard and the control room for use during the load reduction. | | 0 0 |
| At 1231 Eastern Daylight Time (EDT), with reactor power reduced to approximately 33%power, loss of turbine control oil pressure resulted in a turbine anti-motoring trip followed by a generator lockout.Based on the turbine anti-motoring indication and the generator lockout, plant operators manually tripped the turbine.A reactor trip at 1232 EDT resulted from the manual turbine trip.An Event Response Team was established to investigate the root cause of the trip.II.CAUSE OF THE EVENT The release of the turbine trip test lever by the operator after receipt of the turbine anti-motoring trip indication resulted in the manual turbine trip and the subsequent reactor trip.After extensive troubleshooting of the turbine trip block, the overspeed trip block and the control oil system, no mechanical reason for the turbine valve closure could be found.The investigation results led to the conclusion that the cause of the original turbine anti-motor signal was the inadvertent tripping of the auxiliary governor trip lever.While holding the lever on the overspeed trip block in the test position during the power reduction, the operator, who was wearing a heavy fire coat for personnel protection, may have caught the coat on the auxiliary governor trip lever causing the turbine anti-motoring indication. | | : 0. Box 029100, Miami, FL, 33102-9100 APL L-93-166 10 CFR 50.73 JUL 2g]ggg U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| A contributing cause to the turbine tri;p/reactor trip was the inability to relatch the turbine trip.After troubleshooting and testing the overspeed trip block and turbine trip block, a dimensional setup error in the overspeed trip relay plunger was discovered. | | Re: Turkey Point Unit 4 Docket No. 50-251 Reportable Event: 93-002-00 Reactor Tri Due to Manual Turbine Tri The attached Licensee Event Report 251/93-002-00 is being provided in accordance with 10 CFR 50.73 (a) (2) (iv) . |
| The inability to relatch the turbine trips was caused by incorrect clearances in the overspeed trip block between the trip relay and the relay, bushing, and between the relay cup valve and the relay cover plate.The dimension between the relay cup valve end surface and the relay plunger shoulder must be identical to the dimension between the end plate and the lip on the relay bushing.If these dimensions are inexact, the pressure in the oil system will not permit relatching the turbine trip.III.ANALYSIS OF THE EVENT During the testing of the turbine trips, the test lever allows the testing to proceed without a turbine trip occurring. | | If there are any questions, please contact us. |
| If the test=lever Ib A' | | Very truly yours, |
| ~~LICENSEE gjPNT REPORT (LER)TEXT~ONT INUAT ION'FACILITY NAME DOCKET'NUMBER LER NUMBER PAGE NO.TURKEY POINT UNIT 4 05000251 93-002-00 3 QF 3 had been returned to its normal operation position without relatching the turbine trip, an actual turbine trip would have occurred.When the turbine anti-motoring signal occurred, the test lever was released and a turbine trip and, subsequently, a reactor trip occurred.The anti-motoring signal apparently occurred when the auxiliary governor trip lever was inadvertently actuated and control oil pressure was lost.All systems responded as designed to the trip signal.A turbine trip is an event analyzed in the Turkey Point Units 3 and 4 Updated Final Safety Analysis Report (UFSAR).The UFSAR discusses the expected plant response to a complete loss of generator load.The UFSAR analysis assumes a complete loss of load without a subsequent reactor trip and shows the adequacy of the pressure relieving devices and that no core damage results.In this event a reactor trip occurred as designed.Therefore, the.UFSAR analysis bounds the turbine trip and reactor trip which occurred in this case.This event was reported in accordance with 10 CFR 50.73 (a)(2)(iv), due to an actuation of the Reactor Protection System.IV.CORRECTIVE ACTIONS 1.A guard preventing the inadvertent operation of the auxiliary governor trip lever was installed. | | >~ |
| 2.The critical dimensions on the relay plunger of the overspeed trip relay were restored and the relay was tested successfully. | | pgj)Plunkett T. F'. |
| Unit 4 was returned to service on June 26, 1993.V.ADDITIONAL INFORMATION No other events of this type are known to have occurred at Turkey Point.The overspeed trip device manufacture and model details are as follows: Westinghouse Electric Corporation.Overspeed Trip Valve Print No.676J811 System and component identification described in this report: SYSTEM OR COMPONENT EIIS CODE IEEE 803a/83 Main Turbine Turbine Trip Block Overspeed Trip Block Reheat Valves Intercept Valves Generator Breakers TA TG TG SB TA EL TRB 94 94 FCV FCV BKR | | Vice President Turkey Point Nuclear TFP/JEK/3k enclosure cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Ross C. Butcher, Senior Resident Inspector, USNRC, Turkey cate Plant Point 9307270061 PDR |
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| | 930722 |
| | *DOCK, 0500025k PDR iP S |
| | on FPL Group company |
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| | LICEN E EVENT REPO (LER) |
| | DOCKET NUMBER (2) PACE (3) |
| | PACILITY NAME (1) |
| | TURKEY POINT UNIT 4 05000251 1 " 3 TITLE (4) REACTOR TRIP DUE TO MANUAL TURBINE TRIP EVENT DATE (5) LER NUMBER(6) RPT DATE (7) OTHER PACILITIES INVOLVED (8) |
| | MON DAY YR YR SEQ 4 Rt MON DAY PACILITY NAMES DOCKET 4 (S) 06 22 93 93'02 00 07 22 93 OPERATING MODE (9) 10 CFR 50.73 a 2 iv POWER LEVEL (10) 33% |
| | LICENSEE CONTACT FOR THIS LER (12) |
| | J. E. Knorr, Regulation and Compliance Specialist TELEPHONE NUMBER 305-246-6757 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | CAU SYSTEM COMPONENT MANUPACTURER NPRDS7 CAUSE SYSTEM MANUPACTURER NPRDS2 COMPONENT SE TG 94 W120 SUPPLEMENTAL REPORT EXPECTED (14) NO Z YES 0'XPECTED SUBMISSION DATE (15) |
| | MONTH DAY (1f yes, cmaplete EXPECTED SUBMISSION DATE) |
| | ABSTRACT (16) |
| | On the morning of June 22, 1993, Turkey Poi.'nt Unit 4 was at 100% power and conducting a turbine trip test on the main turbine in accordance with procedures and procedural requirements. At the successful completion of the turbine trip test, the plant operators were unable to relatch the turbine trip. Turkey Point Unit was reduced in power with the intent of taking the turbine off line to 4 |
| | trouble shoot and repair, if necessary, the turbine trip latching, mechanism., |
| | At 1231 Eastern Daylight Time (EDT), with reactor power having been reduced to approximately 33% power, loss of turbine control oil pressure resulted in a turbine anti-motoring trip followed by a generator lockout. Based on the turbine anti-motoring indication .and the generator lockout, plant operators manually .tripped the turbine. A reactor trip at 1232 EDT resulted from the manual turbine trip. The NRC was notified in accordance with 10 CFR 50.72 (b) (2) (ii) June 22I 1993( at 1315 EDT. |
| | Extensive investigations of probable cause for the turbine anti-motoring trip and generator lockout were completed. The investigations concluded that the cause was an inadvertent operation of the auxiliary governor .trip lever by personnel restoring the turbine controls to normal after the turbine trip test. The unrelated inability to relatch the turbine trips was caused by incorrect clearances in the overspeed trip block between the trip relay and the relay bushing, and between the relay cup valve and the relay cover plate. These clearances were corrected and Unit 4 was returned to service on June 26, 1993. |
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| | LICENSEE VENT REPORT (LER) TEXT CONTINUATION r |
| | FACILITY NAME DOCKET NUMBER LER NUMBE PAGE NO. |
| | TURKEY POINT UNIT 4 05000251 93-002-00 2 QF 3 I. DESCRIPTION OF THE EVENT On the morning of June 22, 1993, Turkey Point Unit 4 was at 100% power and conducting a turbine trip test on the main turbine in accordance with operations surveillance procedure 4-0SP-200.3, Secondary Plant Periodic Tests. At the successful completion of the'urbine trip test, the plant operators were unable to relatch the turbine trip. Turkey Point Unit 4 was reduced in power with the intent of taking the turbine off line to trouble shoot and repair, if necessary, the turbine latching mechanism. Prior to the load reduction, discussions were held with operations personnel to alert them of actions to be taken (such as initiating manual trips) if any unexpected events were to occur during the load reduction. Direct communications were established between the turbine front standard and the control room for use during the load reduction. At 1231 Eastern Daylight Time (EDT), with reactor power reduced to approximately 33% power, loss of turbine control oil pressure resulted in a turbine anti-motoring trip followed by a generator lockout. Based on the turbine anti-motoring indication and the generator lockout, plant operators manually tripped the turbine. A reactor trip at 1232 EDT resulted from the manual turbine trip. An Event Response Team was established to investigate the root cause of the trip. |
| | II. CAUSE OF THE EVENT The release of the turbine trip test lever by the operator after receipt of the turbine anti-motoring trip indication resulted in the manual turbine trip and the subsequent reactor trip. After extensive troubleshooting of the turbine trip block, the overspeed trip block and the control oil system, no mechanical reason for the turbine valve closure could be found. The investigation results led to the conclusion that the cause of the original turbine anti-motor signal was the inadvertent tripping of the auxiliary governor trip lever. While holding the lever on the overspeed trip block in the test position during the power reduction, the operator, who was wearing a heavy fire coat for personnel protection, may have caught the coat on the auxiliary governor trip lever causing the turbine anti-motoring indication. |
| | A contributing cause to the turbine tri;p/reactor trip was the inability to relatch the turbine trip. After troubleshooting and testing the overspeed trip block and turbine trip block, a dimensional setup error in the overspeed trip relay plunger was discovered. The inability to relatch the turbine trips was caused by incorrect clearances in the overspeed trip block between the trip relay and the relay, bushing, and between the relay cup valve and the relay cover plate. The dimension between the relay cup valve end surface and the relay plunger shoulder must be identical to the dimension between the end plate and the lip on the relay bushing. If these dimensions are inexact, the pressure in the oil system will not permit relatching the turbine trip. |
| | III. ANALYSIS OF THE EVENT During the testing of the turbine trips, the test lever allows the testing to proceed without a turbine trip occurring. If the test =lever |
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| | LICENSEE gjPNT REPORT (LER) TEXT~ONTINUATION' FACILITY NAME DOCKET 'NUMBER LER NUMBER PAGE NO. |
| | TURKEY POINT UNIT 4 05000251 93-002-00 3 QF 3 had been returned to its normal operation position without relatching the turbine trip, an actual turbine trip would have occurred. When the turbine anti-motoring signal occurred, the test lever was released and a turbine trip and, subsequently, a reactor trip occurred. The anti-motoring signal apparently occurred when the auxiliary governor trip lever was inadvertently actuated and control oil pressure was lost. |
| | All systems responded as designed to the trip signal. |
| | A turbine trip is an event analyzed in the Turkey Point Units 3 and 4 Updated Final Safety Analysis Report (UFSAR). The UFSAR discusses the expected plant response to a complete loss of generator load. The UFSAR analysis assumes a complete loss of load without a subsequent reactor trip and shows the adequacy of theevent pressure relieving devices and that a reactor trip occurred as no core damage results. In this designed. Therefore, the .UFSAR analysis bounds the turbine trip and reactor trip which occurred in this case. |
| | This event was reported in accordance with 10 CFR 50.73 (a) (2) (iv), due to an actuation of the Reactor Protection System. |
| | IV. CORRECTIVE ACTIONS |
| | : 1. A guard preventing the inadvertent operation of the auxiliary governor trip lever was installed. |
| | : 2. The critical dimensions on the relay plunger of the overspeed trip relay were restored and the relay was tested successfully. Unit 4 was returned to service on June 26, 1993. |
| | V. ADDITIONAL INFORMATION No other events of this type are known to have occurred at Turkey Point. |
| | The overspeed trip device manufacture and model details are as follows: |
| | Westinghouse Electric Corporation |
| | .Overspeed Trip Valve Print No. 676J811 System and component identification described in this report: |
| | SYSTEM OR COMPONENT EIIS CODE IEEE 803a/83 Main Turbine TA TRB Turbine Trip Block TG 94 Overspeed Trip Block TG 94 Reheat Valves SB FCV Intercept Valves TA FCV Generator Breakers EL BKR |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6121997-08-29029 August 1997 LER 97-007-00:on 970730,automatic Reactor Trip Occurred. Caused by Closure of B Main Steam Isolation Valve.Failed W Relay & Equivalent Relays Were replaced.W/970829 Ltr ML17354A6081997-08-18018 August 1997 LER 97-006-00:on 970722,manual Reactor Trip Occurred Due to Failed Rod Control Power Supplies.Replaced Twelve Power Supplies in Rod Control Logic & Power cabinets.W/970818 Ltr ML17354A5801997-07-14014 July 1997 LER 97-005-00:on 970618,RCP Oil Collection Sys Was Found Outside Design Basis.Caused Because Design Did Not Consider Component Parts to Be Potential Leakage Sources.Entire RCP Oil Collection Sys Was reviewed.W/970714 Ltr ML17354A5141997-05-22022 May 1997 LER 97-002-00:on 970423,automatic Reactor Tripped.Caused by Actuation of Turbine Overspeed Protection Circuit. Administrative Procedures Governing Inadequate Work Controls Will Be Revised to Capture Lessons learned.W/970522 Ltr ML17354A5061997-05-0909 May 1997 LER 97-003-00:on 970410,mode Changed W/O Meeting Requirements of TS 3.0.4 Due to Inadequate Procedural Guidance.Night Order Was Issued to Inform Personnel That S/G Blowdown Keylock Switches Were Left in drain.W/970509 Ltr ML17354A5051997-05-0909 May 1997 LER 97-004-00:on 970411,auxiliary Feedwater Automatic Start Upon Trip of All Main Feedwater Pumps,Occurred.Caused by Mispositioned Valve Closing.Valves Listed as Inappropriately Positioned Were repositioned.W/970509 Ltr ML17354A4781997-04-25025 April 1997 LER 97-001-00:on 970327,ECCS Recirculation Loop Leakage Was Found to Be in Condition Outside Design Basis Due to Gasket Movement During Installation During Spring 1966 Reassembly. Gasket Replaced & Pump tested.W/970425 Ltr ML17354A4581997-03-28028 March 1997 LER 97-002-00:on 970303,manual Reactor Trip Following Rod Control Urgent Failure Alarm Occurred.Caused by Phase Failure Detection on Stationary a Circuits of 2BD Rod Control Cabinet.Air Conditioning replaced.W/970328 Ltr ML17354A4511997-03-26026 March 1997 LER 97-001-00:on 970118,missed Surveillance on CR Position Verification Occurred Due to Inoperable Rod Deviation Monitor.Faulty Circuit Common Connection Was Corrected & Rdm Operability Was restored.W/970326 Ltr ML17354A4061997-02-0303 February 1997 LER 96-004-03:on 970107,identified Three Instances of Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Surveillance Procedures Revised ML17354A3771996-12-27027 December 1996 LER 96-012-00:on 961204,determined Containment Average Temp Being Determined Based on Only Two Temp Elements Instead of Three as Required by Tss.Caused by Log Only Requiring One Entry.Log revised.W/961227 Ltr ML17354A3261996-11-0606 November 1996 LER 96-011-00:on 961009,potential for Overpressurizing Post Accident Containment Vent Filter Housings Occurred.Caused by Improper Change Mgt.Monitoring Sys Operating Procedures revised.W/961106 Ltr ML17354A3071996-10-22022 October 1996 LER 96-010-00:on 960924,manual Reactor Shutdown Occurred. Caused by Failed Rod Control Sys Regulation Card in 2AC Power cabinet.2AC Power Cabinet DC Power Supplies,Cabling & Connectors checked.W/961022 Ltr ML17353A8711996-08-27027 August 1996 LER 96-009-00:on 960729,failed to Reflect Heavy Load Design Info in Procedural Controls.Caused by Failure to Incorporate 1982 Procedure Changes.Suspended Lifting of Heavy Loads & Took Turbine Bldg Crane OOS.W/960827 Ltr ML17353A7411996-06-18018 June 1996 LER 96-008-00:on 960521,surveillance Method for Testing Emergency Diesel Generators (EDG) Determined Inadequate. Caused by Personnel Error.All Four EDGs Rapid Start Tested & EDG Surveillance Procedures modified.W/960618 Ltr ML17353A7401996-06-18018 June 1996 LER 96-004-02:on 960524,identified Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Entered Tech Spec Statements,Tested Required Instruments Functions & Revised Plant procedure.W/960618 Ltr ML17353A6901996-05-13013 May 1996 LER 96-004-01:on 960220,identified Potential Tech Spec non-compliance Associated W/Surveillance Testing of AFW Actuation Circuitry on Sg.Caused by Inadequate Surveillance Procedures.Procedures revised.W/960513 Ltr ML17353A6741996-05-0606 May 1996 LER 96-001-00:on 960409,manual Rt Occurred Due to Turbine Governer Control Oil Perturbation.Disassembled & Inspected Governor Valve for Cleanliness & Corrosion products.W/960506 Ltr ML17353A6651996-04-29029 April 1996 LER 96-007-00:on 960329,inadvertent ESF Actuation Occurred During Refueling Outage Due to Cognitive Personnel Error. Personnel Involved Counseled & Integrated Safeguards Test Procedures Being revised.W/960429 Ltr ML17353A6601996-04-25025 April 1996 LER 96-006-00:on 960327,manual Rt Occurred Due to 3C Transformer Lockout & Loss of 3B SG Mfp.Replaced SAM Timer Relay in 3AC16.W/960425 Ltr ML17353A6491996-04-23023 April 1996 LER 96-005-00:on 960326,certain Safety Injection Accumulator Filled Evolutions Resulted in cross-tied Configuration.C/A: Night Order Written & Operations Procedure 3/4-OP-064 revised.W/960423 Ltr ML17353A6051996-03-18018 March 1996 LER 96-003-00:on 960222,two Arpi Inoperable & TS 3.0.3 Entered.Proposed License Amend Submitted to Revise Allowed Misalignment from +/-12 Steps to =/-18 Steps Between Arpi & Dpi at Less than 90% power.W/960318 Ltr ML17353A6041996-03-18018 March 1996 LER 96-004-00:on 960220,surveillance Testing of AFW Actuation Circuitry Was Inadequate.Caused by Inadequate Surveillance Procedures.Tested Untested Portions of Actuation Logic for AFW Automatic Start signal.W/960318 Ltr ML17353A5861996-03-0606 March 1996 LER 96-002-00:on 960209,automatic Turbine Trip/Rt Occurred Due to High SG Level.Caused by Personnel Error.Replaced Both Hinge Pins on B Sgfp Discharge Check valve.W/960306 Ltr ML17353A5761996-03-0101 March 1996 LER 96-001-00:on 960131,intake CWS Flow Rates Found W/ Potential to Be Less than Required by Design Basis.Caused by Influx of Aquatic Grass & Algae Onto Basket Strainers of Icw Flow Path.Mechanically Cleaned strainers.W/960301 Ltr ML17353A4451995-11-0909 November 1995 LER 95-007-00:on 951017,manual Rt Occurred Following Drop of Four Control Rods.Caused by Water Intrusion Into Rod Control Power Cabinet 2BD.Inspected Control Power Cabinet 2BD for Other Water damage.W/951109 Ltr ML17353A4241995-10-12012 October 1995 LER 95-006-00:on 950913,analysis Showed That CCW Exchangers Susceptible to Damage Due to flow-induced Vibration.Ccw Sys Has Been Flow Balanced to Closer tolerances.W/951012 Ltr ML17353A3601995-09-13013 September 1995 LER 95-005-00:on 950818,containment Pressure Testing Procedure Resulted in Inhibiting Both Trains of Containment Pressure from Initiated Esf.Revised Procedure to Require Testing of Each Train separately.W/950913 Ltr ML17353A2951995-07-17017 July 1995 LER 94-005-02:on 941103,both Units Outside Design Basis Due to Design Defect in Safeguards Bus Sequencer Test Logic. Resumed Monthly Manual Testing of Sequencer ML17352B1581995-05-0505 May 1995 LER 95-004-00:on 950407,unit Being Shutdown to Investigate Recurring non-urgent Failure Alarms from Redundant Rod Control Power Supplies.Reactor Manually Tripped.All Four PS-3 Power Supplies replaced.W/950505 Ltr ML17352B1181995-04-0707 April 1995 LER 95-003-00:on 950309,intake Cooling Water Flow Rate Through CCW Heat Exchangers Fell Below Assumed Design Basis. Caused by an Influx of Aquatic Grass & Algae Onto Basket Strainers.Strainers cleaned.W/950407 Ltr ML17352B0701995-03-13013 March 1995 LER 95-002-00:on 950215,inadequate Definition of Loops Filled Resulted in Units in Condition Prohibited by Ts. Issued TS Position Statement to Define Term Loops Filled as Used in TS 6.4.1.1.4.W/950313 Ltr ML17352B0321995-02-0909 February 1995 LER 94-005-01:on 941103,design Defect Found in Safeguards Bus Sequencer Test Logic,Placing Facility Outside Design Basis.Design Mods to Eliminate Software Logic Problems Will Be Implemented During Next Refueling outages.W/950209 Ltr ML17352B0101995-01-20020 January 1995 LER 94-006-00:on 941226,C Main Feedwater Control Valve Failed Closed,Causing Reactor & Turbine Trips.Caused by Loose Screw Terminal Connection.I/P Transducers Replaced W/ New Model W/Different Design Wire connection.W/950120 Ltr ML17352A9511994-12-13013 December 1994 LER 94-006-00:on 941130,Unit 4 Tripped Automatically.Caused by Failure of Flexible Link Connection Between Main Generator B Phase Bus & Associated Isolated Phase Bus Bar. All Bolts on Flexible Link checked.W/941213 Ltr ML17352A8871994-11-10010 November 1994 LER 94-005-00:on 941103,design Defect in Safeguards Bus Sequencer Test Logic Places Both Units Outside Design Basis. Caused by 3A Sequencer Failed to Respond as Expected to Opposite Unit SI signal.W/941110 Ltr ML17352A8851994-11-10010 November 1994 LER 94-004-00:on 941103,Unit 3 Outside Design Basis Due to Two of Three Required Safety Injection Pumps Inoperable. Control Switches for 3A & 3B Safety Injection Pumps Immediately Returned to automatic.W/941110 Ltr ML17352A8421994-10-21021 October 1994 LER 94-004-00:on 940923,Unit 4 Tripped Automatically from Rated Power.Caused by Faulty Regulator Transistor.Faulty Backup Power Supply Replaced & Maint History for Power Supplies reviewed.W/941021 Ltr ML17352A8431994-10-20020 October 1994 LER 94-005-00:on 940924,Unit 4 Manually Tripped.Caused by Manual Actuation.Light Bulb & Socket replaced.W/941020 Ltr ML17352B1671994-08-16016 August 1994 LER 94-003-00:on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced 1999-07-20
[Table view] Category:RO)
MONTHYEARML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6121997-08-29029 August 1997 LER 97-007-00:on 970730,automatic Reactor Trip Occurred. Caused by Closure of B Main Steam Isolation Valve.Failed W Relay & Equivalent Relays Were replaced.W/970829 Ltr ML17354A6081997-08-18018 August 1997 LER 97-006-00:on 970722,manual Reactor Trip Occurred Due to Failed Rod Control Power Supplies.Replaced Twelve Power Supplies in Rod Control Logic & Power cabinets.W/970818 Ltr ML17354A5801997-07-14014 July 1997 LER 97-005-00:on 970618,RCP Oil Collection Sys Was Found Outside Design Basis.Caused Because Design Did Not Consider Component Parts to Be Potential Leakage Sources.Entire RCP Oil Collection Sys Was reviewed.W/970714 Ltr ML17354A5141997-05-22022 May 1997 LER 97-002-00:on 970423,automatic Reactor Tripped.Caused by Actuation of Turbine Overspeed Protection Circuit. Administrative Procedures Governing Inadequate Work Controls Will Be Revised to Capture Lessons learned.W/970522 Ltr ML17354A5061997-05-0909 May 1997 LER 97-003-00:on 970410,mode Changed W/O Meeting Requirements of TS 3.0.4 Due to Inadequate Procedural Guidance.Night Order Was Issued to Inform Personnel That S/G Blowdown Keylock Switches Were Left in drain.W/970509 Ltr ML17354A5051997-05-0909 May 1997 LER 97-004-00:on 970411,auxiliary Feedwater Automatic Start Upon Trip of All Main Feedwater Pumps,Occurred.Caused by Mispositioned Valve Closing.Valves Listed as Inappropriately Positioned Were repositioned.W/970509 Ltr ML17354A4781997-04-25025 April 1997 LER 97-001-00:on 970327,ECCS Recirculation Loop Leakage Was Found to Be in Condition Outside Design Basis Due to Gasket Movement During Installation During Spring 1966 Reassembly. Gasket Replaced & Pump tested.W/970425 Ltr ML17354A4581997-03-28028 March 1997 LER 97-002-00:on 970303,manual Reactor Trip Following Rod Control Urgent Failure Alarm Occurred.Caused by Phase Failure Detection on Stationary a Circuits of 2BD Rod Control Cabinet.Air Conditioning replaced.W/970328 Ltr ML17354A4511997-03-26026 March 1997 LER 97-001-00:on 970118,missed Surveillance on CR Position Verification Occurred Due to Inoperable Rod Deviation Monitor.Faulty Circuit Common Connection Was Corrected & Rdm Operability Was restored.W/970326 Ltr ML17354A4061997-02-0303 February 1997 LER 96-004-03:on 970107,identified Three Instances of Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Surveillance Procedures Revised ML17354A3771996-12-27027 December 1996 LER 96-012-00:on 961204,determined Containment Average Temp Being Determined Based on Only Two Temp Elements Instead of Three as Required by Tss.Caused by Log Only Requiring One Entry.Log revised.W/961227 Ltr ML17354A3261996-11-0606 November 1996 LER 96-011-00:on 961009,potential for Overpressurizing Post Accident Containment Vent Filter Housings Occurred.Caused by Improper Change Mgt.Monitoring Sys Operating Procedures revised.W/961106 Ltr ML17354A3071996-10-22022 October 1996 LER 96-010-00:on 960924,manual Reactor Shutdown Occurred. Caused by Failed Rod Control Sys Regulation Card in 2AC Power cabinet.2AC Power Cabinet DC Power Supplies,Cabling & Connectors checked.W/961022 Ltr ML17353A8711996-08-27027 August 1996 LER 96-009-00:on 960729,failed to Reflect Heavy Load Design Info in Procedural Controls.Caused by Failure to Incorporate 1982 Procedure Changes.Suspended Lifting of Heavy Loads & Took Turbine Bldg Crane OOS.W/960827 Ltr ML17353A7411996-06-18018 June 1996 LER 96-008-00:on 960521,surveillance Method for Testing Emergency Diesel Generators (EDG) Determined Inadequate. Caused by Personnel Error.All Four EDGs Rapid Start Tested & EDG Surveillance Procedures modified.W/960618 Ltr ML17353A7401996-06-18018 June 1996 LER 96-004-02:on 960524,identified Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Entered Tech Spec Statements,Tested Required Instruments Functions & Revised Plant procedure.W/960618 Ltr ML17353A6901996-05-13013 May 1996 LER 96-004-01:on 960220,identified Potential Tech Spec non-compliance Associated W/Surveillance Testing of AFW Actuation Circuitry on Sg.Caused by Inadequate Surveillance Procedures.Procedures revised.W/960513 Ltr ML17353A6741996-05-0606 May 1996 LER 96-001-00:on 960409,manual Rt Occurred Due to Turbine Governer Control Oil Perturbation.Disassembled & Inspected Governor Valve for Cleanliness & Corrosion products.W/960506 Ltr ML17353A6651996-04-29029 April 1996 LER 96-007-00:on 960329,inadvertent ESF Actuation Occurred During Refueling Outage Due to Cognitive Personnel Error. Personnel Involved Counseled & Integrated Safeguards Test Procedures Being revised.W/960429 Ltr ML17353A6601996-04-25025 April 1996 LER 96-006-00:on 960327,manual Rt Occurred Due to 3C Transformer Lockout & Loss of 3B SG Mfp.Replaced SAM Timer Relay in 3AC16.W/960425 Ltr ML17353A6491996-04-23023 April 1996 LER 96-005-00:on 960326,certain Safety Injection Accumulator Filled Evolutions Resulted in cross-tied Configuration.C/A: Night Order Written & Operations Procedure 3/4-OP-064 revised.W/960423 Ltr ML17353A6051996-03-18018 March 1996 LER 96-003-00:on 960222,two Arpi Inoperable & TS 3.0.3 Entered.Proposed License Amend Submitted to Revise Allowed Misalignment from +/-12 Steps to =/-18 Steps Between Arpi & Dpi at Less than 90% power.W/960318 Ltr ML17353A6041996-03-18018 March 1996 LER 96-004-00:on 960220,surveillance Testing of AFW Actuation Circuitry Was Inadequate.Caused by Inadequate Surveillance Procedures.Tested Untested Portions of Actuation Logic for AFW Automatic Start signal.W/960318 Ltr ML17353A5861996-03-0606 March 1996 LER 96-002-00:on 960209,automatic Turbine Trip/Rt Occurred Due to High SG Level.Caused by Personnel Error.Replaced Both Hinge Pins on B Sgfp Discharge Check valve.W/960306 Ltr ML17353A5761996-03-0101 March 1996 LER 96-001-00:on 960131,intake CWS Flow Rates Found W/ Potential to Be Less than Required by Design Basis.Caused by Influx of Aquatic Grass & Algae Onto Basket Strainers of Icw Flow Path.Mechanically Cleaned strainers.W/960301 Ltr ML17353A4451995-11-0909 November 1995 LER 95-007-00:on 951017,manual Rt Occurred Following Drop of Four Control Rods.Caused by Water Intrusion Into Rod Control Power Cabinet 2BD.Inspected Control Power Cabinet 2BD for Other Water damage.W/951109 Ltr ML17353A4241995-10-12012 October 1995 LER 95-006-00:on 950913,analysis Showed That CCW Exchangers Susceptible to Damage Due to flow-induced Vibration.Ccw Sys Has Been Flow Balanced to Closer tolerances.W/951012 Ltr ML17353A3601995-09-13013 September 1995 LER 95-005-00:on 950818,containment Pressure Testing Procedure Resulted in Inhibiting Both Trains of Containment Pressure from Initiated Esf.Revised Procedure to Require Testing of Each Train separately.W/950913 Ltr ML17353A2951995-07-17017 July 1995 LER 94-005-02:on 941103,both Units Outside Design Basis Due to Design Defect in Safeguards Bus Sequencer Test Logic. Resumed Monthly Manual Testing of Sequencer ML17352B1581995-05-0505 May 1995 LER 95-004-00:on 950407,unit Being Shutdown to Investigate Recurring non-urgent Failure Alarms from Redundant Rod Control Power Supplies.Reactor Manually Tripped.All Four PS-3 Power Supplies replaced.W/950505 Ltr ML17352B1181995-04-0707 April 1995 LER 95-003-00:on 950309,intake Cooling Water Flow Rate Through CCW Heat Exchangers Fell Below Assumed Design Basis. Caused by an Influx of Aquatic Grass & Algae Onto Basket Strainers.Strainers cleaned.W/950407 Ltr ML17352B0701995-03-13013 March 1995 LER 95-002-00:on 950215,inadequate Definition of Loops Filled Resulted in Units in Condition Prohibited by Ts. Issued TS Position Statement to Define Term Loops Filled as Used in TS 6.4.1.1.4.W/950313 Ltr ML17352B0321995-02-0909 February 1995 LER 94-005-01:on 941103,design Defect Found in Safeguards Bus Sequencer Test Logic,Placing Facility Outside Design Basis.Design Mods to Eliminate Software Logic Problems Will Be Implemented During Next Refueling outages.W/950209 Ltr ML17352B0101995-01-20020 January 1995 LER 94-006-00:on 941226,C Main Feedwater Control Valve Failed Closed,Causing Reactor & Turbine Trips.Caused by Loose Screw Terminal Connection.I/P Transducers Replaced W/ New Model W/Different Design Wire connection.W/950120 Ltr ML17352A9511994-12-13013 December 1994 LER 94-006-00:on 941130,Unit 4 Tripped Automatically.Caused by Failure of Flexible Link Connection Between Main Generator B Phase Bus & Associated Isolated Phase Bus Bar. All Bolts on Flexible Link checked.W/941213 Ltr ML17352A8871994-11-10010 November 1994 LER 94-005-00:on 941103,design Defect in Safeguards Bus Sequencer Test Logic Places Both Units Outside Design Basis. Caused by 3A Sequencer Failed to Respond as Expected to Opposite Unit SI signal.W/941110 Ltr ML17352A8851994-11-10010 November 1994 LER 94-004-00:on 941103,Unit 3 Outside Design Basis Due to Two of Three Required Safety Injection Pumps Inoperable. Control Switches for 3A & 3B Safety Injection Pumps Immediately Returned to automatic.W/941110 Ltr ML17352A8421994-10-21021 October 1994 LER 94-004-00:on 940923,Unit 4 Tripped Automatically from Rated Power.Caused by Faulty Regulator Transistor.Faulty Backup Power Supply Replaced & Maint History for Power Supplies reviewed.W/941021 Ltr ML17352A8431994-10-20020 October 1994 LER 94-005-00:on 940924,Unit 4 Manually Tripped.Caused by Manual Actuation.Light Bulb & Socket replaced.W/941020 Ltr ML17352B1671994-08-16016 August 1994 LER 94-003-00:on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced 1999-07-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML17355A4471999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Turkey Point,Units 3 & 4.With 991008 Ltr ML17355A4121999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Turkey Point,Units 3 & 4.With 990909 Ltr ML17355A3981999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Turkey Point,Units 3 & 4.With 990809 Ltr ML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17355A3841999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Turkey Point,Units 3 & 4.With 990713 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17355A3611999-06-30030 June 1999 Refueling Outage ISI Rept. ML17355A3511999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Turkey Point,Units 3 & 4.With 990609 Ltr ML17355A3331999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Turkey Point,Units 3 & 4.With 990511 Ltr ML20217B9871999-04-0808 April 1999 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408 ML17355A2881999-04-0505 April 1999 COLR for Turkey Point Unit 4 Cycle 18. ML17355A2911999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Turkey Point,Units 3 & 4.With 990414 Ltr ML17355A2551999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Turkey Point Nuclear Power Plant,Units 3 & 4.With 990315 Ltr ML17355A2261999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Turkey Point,Units 3 & 4.With 990211 Ltr ML17355A2201999-01-20020 January 1999 Refueling Outage ISI Rept. ML17355A1911998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Turkey Point,Units 3 & 4.With 990112 Ltr ML18008A0461998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Turkey Point,Units 3 & 4.With 981209 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1891998-11-0909 November 1998 Simulatory Certification Update 2. ML17354B1901998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Turkey Point,Units 3 & 4.With 981112 Ltr ML17354B1591998-10-23023 October 1998 COLR for Turkey Point Unit 3 Cycle 17. ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B1311998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Turkey Point Unit 3 & 4.With 981012 Ltr ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML17354B0981998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Turkey Points,Units 3 & 4.With 980915 Ltr ML17354B0771998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Turkey Point,Units 3 & 4.W/980810 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354B0241998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Turkey Point,Units 3 & 4.W/980709 Ltr ML17354B0171998-06-29029 June 1998 Rev 1 to PTN-FPER-97-013, Evaluation of Turbine Lube Oil Fire. ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML17354A9711998-05-31031 May 1998 Monthly Operating Repts for Turkey Point,Units 3 & 4. W/980611 Ltr ML17354A9231998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Turkey Point,Units 3 & 4.W/980511 Ltr ML17354A8821998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Turkey Point,Units 3 & 4.W/980409 Ltr ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354B0001998-03-18018 March 1998 Florida Power & Light Topical Quality Asurance Rept, Dtd June 1998 ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A8311998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Turkey Point,Units 3 & 4.W/980311 Ltr ML17354A7871998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Turkey Point,Units 3 & 4.W/980209 Ltr ML17354A7581997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Turkey Point,Unit 3 & 4.W/980112 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A7381997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Turkey Point,Units 3 & 4.W/971215 Ltr ML17354A7211997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Turkey Point,Units 3 & 4.W/971114 Ltr ML17354A7491997-10-13013 October 1997 SG Insp Rept. ML17354A8851997-10-13013 October 1997 FPL Units 3 & 4 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 960408-971013. ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6791997-10-0606 October 1997 COLR Unit 4 Cycle 17, for Turkey Point ML17354A6811997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Turkey Point,Units 3 & 4.W/971009 Ltr 1999-09-30
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ACCELERATED DOCVMENT DISTKCBUTION SYSTEM REGULAQIY INFORMATION DISTRIBUTI SYSTEM (RIDE)
ACCESSION NBR:9307270061 DOC.DATE: 93/07/22 NOTARIZED: NO DOCKET FAClLq50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.::AME AUTHOR AFFILIATION KNORR,J.E. Florida Power & Light Co.
PLUNKETT,T.F. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 93-002-00:on 930622,RT occurred due to manual turbine trip. Installed guard preventing inadvertent operation of auxiliary governor trip lever.W/930722 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
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- 0. Box 029100, Miami, FL, 33102-9100 APL L-93-166 10 CFR 50.73 JUL 2g]ggg 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: 93-002-00 Reactor Tri Due to Manual Turbine Tri The attached Licensee Event Report 251/93-002-00 is being provided in accordance with 10 CFR 50.73 (a) (2) (iv) .
If there are any questions, please contact us.
Very truly yours,
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pgj)Plunkett T. F'.
Vice President Turkey Point Nuclear TFP/JEK/3k enclosure cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Ross C. Butcher, Senior Resident Inspector, USNRC, Turkey cate Plant Point 9307270061 PDR
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930722
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LICEN E EVENT REPO (LER)
DOCKET NUMBER (2) PACE (3)
PACILITY NAME (1)
TURKEY POINT UNIT 4 05000251 1 " 3 TITLE (4) REACTOR TRIP DUE TO MANUAL TURBINE TRIP EVENT DATE (5) LER NUMBER(6) RPT DATE (7) OTHER PACILITIES INVOLVED (8)
MON DAY YR YR SEQ 4 Rt MON DAY PACILITY NAMES DOCKET 4 (S) 06 22 93 93'02 00 07 22 93 OPERATING MODE (9) 10 CFR 50.73 a 2 iv POWER LEVEL (10) 33%
LICENSEE CONTACT FOR THIS LER (12)
J. E. Knorr, Regulation and Compliance Specialist TELEPHONE NUMBER 305-246-6757 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAU SYSTEM COMPONENT MANUPACTURER NPRDS7 CAUSE SYSTEM MANUPACTURER NPRDS2 COMPONENT SE TG 94 W120 SUPPLEMENTAL REPORT EXPECTED (14) NO Z YES 0'XPECTED SUBMISSION DATE (15)
MONTH DAY (1f yes, cmaplete EXPECTED SUBMISSION DATE)
ABSTRACT (16)
On the morning of June 22, 1993, Turkey Poi.'nt Unit 4 was at 100% power and conducting a turbine trip test on the main turbine in accordance with procedures and procedural requirements. At the successful completion of the turbine trip test, the plant operators were unable to relatch the turbine trip. Turkey Point Unit was reduced in power with the intent of taking the turbine off line to 4
trouble shoot and repair, if necessary, the turbine trip latching, mechanism.,
At 1231 Eastern Daylight Time (EDT), with reactor power having been reduced to approximately 33% power, loss of turbine control oil pressure resulted in a turbine anti-motoring trip followed by a generator lockout. Based on the turbine anti-motoring indication .and the generator lockout, plant operators manually .tripped the turbine. A reactor trip at 1232 EDT resulted from the manual turbine trip. The NRC was notified in accordance with 10 CFR 50.72 (b) (2) (ii) June 22I 1993( at 1315 EDT.
Extensive investigations of probable cause for the turbine anti-motoring trip and generator lockout were completed. The investigations concluded that the cause was an inadvertent operation of the auxiliary governor .trip lever by personnel restoring the turbine controls to normal after the turbine trip test. The unrelated inability to relatch the turbine trips was caused by incorrect clearances in the overspeed trip block between the trip relay and the relay bushing, and between the relay cup valve and the relay cover plate. These clearances were corrected and Unit 4 was returned to service on June 26, 1993.
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LICENSEE VENT REPORT (LER) TEXT CONTINUATION r
FACILITY NAME DOCKET NUMBER LER NUMBE PAGE NO.
TURKEY POINT UNIT 4 05000251 93-002-00 2 QF 3 I. DESCRIPTION OF THE EVENT On the morning of June 22, 1993, Turkey Point Unit 4 was at 100% power and conducting a turbine trip test on the main turbine in accordance with operations surveillance procedure 4-0SP-200.3, Secondary Plant Periodic Tests. At the successful completion of the'urbine trip test, the plant operators were unable to relatch the turbine trip. Turkey Point Unit 4 was reduced in power with the intent of taking the turbine off line to trouble shoot and repair, if necessary, the turbine latching mechanism. Prior to the load reduction, discussions were held with operations personnel to alert them of actions to be taken (such as initiating manual trips) if any unexpected events were to occur during the load reduction. Direct communications were established between the turbine front standard and the control room for use during the load reduction. At 1231 Eastern Daylight Time (EDT), with reactor power reduced to approximately 33% power, loss of turbine control oil pressure resulted in a turbine anti-motoring trip followed by a generator lockout. Based on the turbine anti-motoring indication and the generator lockout, plant operators manually tripped the turbine. A reactor trip at 1232 EDT resulted from the manual turbine trip. An Event Response Team was established to investigate the root cause of the trip.
II. CAUSE OF THE EVENT The release of the turbine trip test lever by the operator after receipt of the turbine anti-motoring trip indication resulted in the manual turbine trip and the subsequent reactor trip. After extensive troubleshooting of the turbine trip block, the overspeed trip block and the control oil system, no mechanical reason for the turbine valve closure could be found. The investigation results led to the conclusion that the cause of the original turbine anti-motor signal was the inadvertent tripping of the auxiliary governor trip lever. While holding the lever on the overspeed trip block in the test position during the power reduction, the operator, who was wearing a heavy fire coat for personnel protection, may have caught the coat on the auxiliary governor trip lever causing the turbine anti-motoring indication.
A contributing cause to the turbine tri;p/reactor trip was the inability to relatch the turbine trip. After troubleshooting and testing the overspeed trip block and turbine trip block, a dimensional setup error in the overspeed trip relay plunger was discovered. The inability to relatch the turbine trips was caused by incorrect clearances in the overspeed trip block between the trip relay and the relay, bushing, and between the relay cup valve and the relay cover plate. The dimension between the relay cup valve end surface and the relay plunger shoulder must be identical to the dimension between the end plate and the lip on the relay bushing. If these dimensions are inexact, the pressure in the oil system will not permit relatching the turbine trip.
III. ANALYSIS OF THE EVENT During the testing of the turbine trips, the test lever allows the testing to proceed without a turbine trip occurring. If the test =lever
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LICENSEE gjPNT REPORT (LER) TEXT~ONTINUATION' FACILITY NAME DOCKET 'NUMBER LER NUMBER PAGE NO.
TURKEY POINT UNIT 4 05000251 93-002-00 3 QF 3 had been returned to its normal operation position without relatching the turbine trip, an actual turbine trip would have occurred. When the turbine anti-motoring signal occurred, the test lever was released and a turbine trip and, subsequently, a reactor trip occurred. The anti-motoring signal apparently occurred when the auxiliary governor trip lever was inadvertently actuated and control oil pressure was lost.
All systems responded as designed to the trip signal.
A turbine trip is an event analyzed in the Turkey Point Units 3 and 4 Updated Final Safety Analysis Report (UFSAR). The UFSAR discusses the expected plant response to a complete loss of generator load. The UFSAR analysis assumes a complete loss of load without a subsequent reactor trip and shows the adequacy of theevent pressure relieving devices and that a reactor trip occurred as no core damage results. In this designed. Therefore, the .UFSAR analysis bounds the turbine trip and reactor trip which occurred in this case.
This event was reported in accordance with 10 CFR 50.73 (a) (2) (iv), due to an actuation of the Reactor Protection System.
IV. CORRECTIVE ACTIONS
- 1. A guard preventing the inadvertent operation of the auxiliary governor trip lever was installed.
- 2. The critical dimensions on the relay plunger of the overspeed trip relay were restored and the relay was tested successfully. Unit 4 was returned to service on June 26, 1993.
V. ADDITIONAL INFORMATION No other events of this type are known to have occurred at Turkey Point.
The overspeed trip device manufacture and model details are as follows:
Westinghouse Electric Corporation
.Overspeed Trip Valve Print No. 676J811 System and component identification described in this report:
SYSTEM OR COMPONENT EIIS CODE IEEE 803a/83 Main Turbine TA TRB Turbine Trip Block TG 94 Overspeed Trip Block TG 94 Reheat Valves SB FCV Intercept Valves TA FCV Generator Breakers EL BKR
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