Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045F6631993-06-25025 June 1993 LER 93-014-00 on 930529,logic Sys Functional Testing Was Incomplete Due to Test Procedure Deficiencies.Temporary Procedure Changes made.W/930625 Ltr ML20043B9831990-05-23023 May 1990 LER 90-016-00:on 900424,automatic Isolation Signal Closed Suction Valves from Reactor Water Recirculation Sys.On 900425,suction Valves Closed & RHR Pump Tripped.Caused by Chattering Pressure Switch.Switches replaced.W/900523 Ltr ML20012C5161990-03-0909 March 1990 LER 90-004-00:on 900207,isolation of RCIC Sys Occurred, Resulting in Initiation of 7-day Limiting Condition of Operation.Caused by Failure of Master Trip Unit.Subj Unit replaced.W/900309 Ltr ML20011E1431990-01-29029 January 1990 LER 89-020-01:on 891105,reactor Scram Initiated by High APRM Neutron Flux from Pressure Transient from Turbine Control Valve Closure.Caused by Void Collapse in Core Moderator. Computer Programming Changed Re Transient data.W/900129 Ltr ML20006C1571990-01-26026 January 1990 LER 89-026-00:on 891105,reactor Scram from Full Power Occurred Due to Problems W/Turbine electro-hydraulic Control Sys.On 891220,contractor Notified Util That Valves Tested Did Not Actuate within Setpoint as required.W/900126 Ltr ML20005E8541990-01-0202 January 1990 LER 89-025-00:on 891130,isolation Signal Closed Outboard Isolation Valves on Steam Supply Line to HPCI Sys,Rendering HPCI Sys Inoperable & Initiating 7-day Limiting Condition for Operation.Caused by Excess steam.W/900102 Ltr ML19332F0471989-11-30030 November 1989 LER 89-021-00:on 891031,circuit Breaker for RCIC Inboard Injection Valve to Feedwater Sys Tripped During Required Valve Testing.Caused by Fault in Motor Winding Insulation. New Motor installed.W/891130 Ltr ML19332E6241989-11-30030 November 1989 LER 89-019-00:on 891031 & 891103,HPCI Sys Declared Inoperable Due to Electrical Ground in Speed Control Circuit.Caused by Buildup of Conductive Corrosion Products. Connector Cleaned & Sys Returned to svc.W/891130 Ltr ML19325F2791989-11-13013 November 1989 LER 89-007-01:on 890509,surveillance of Fire Barrier Penetrations,Per Tech Spec 4.12.F Not Conducted within Allowed Time Period.Caused by Misinterpretation of Fire Protection Ref Manual.Fire Watch established.W/891113 Ltr ML19327C1351989-11-0707 November 1989 LER 89-015-01:on 890918,two Remote Manually Operated Diaphragm Air Operated Isolation Valves Failed Closing Time Acceptance Criteria.Caused by Buildup of Iron Oxide Sludge. Valves Disassembled & Cleaned ML19327B9821989-11-0606 November 1989 LER 89-018-00:on 891008,HPCI High Steam Flow Signal Closed Isolation Valves for Outboard Steam Supply & Steam Line Warning.Caused by Air in Sensing Sys Leading to Unstable Oscillation.Pressure Sensor Vented & calibr.W/891106 Ltr ML19324B1151989-10-23023 October 1989 LER 88-008-01:during 1988 Refuel Outage,One Primary Containment Penetration Exceeded Tech Spec 4.7.A.2.b Limit When Subjected to Local Leak Rate Testing.Leakage Attributed to Wear.Valves replaced.W/891023 Ltr ML19327B1521989-10-20020 October 1989 LER 89-017-00:on 890920,ESFAS Initiated Group II Primary Containment Isolation Signal Triggering RHR & LPCI Sys Isolations.Caused by Cognitive Human Error in Not Finding Isolation Signal.Fuse Replaced & Sys restarted.W/891020 Ltr ML19327B1501989-10-18018 October 1989 LER 89-016-00:on 890918,scram Signal Automatically Initiated During Transfer of Power Supply for Reactor Protection Sys. Caused by Lack of Caution Statement in Procedure.Procedure Revised to Add Time Caution for Bus transfers.W/891018 Ltr ML19327B1331989-10-18018 October 1989 LER 89-015-00:on 890918,two of Nine Remote Manually Operated Diaphragm Air Operated Containment Isolation Valves Failed Acceptance Criteria for Closing Time.Caused by Buildup & Hardening of Iron Oxide Sludge.Valves cleaned.W/891018 Ltr ML20052E2811982-04-30030 April 1982 LER 82-017/03L-0:on 820402,MSIV 10% Closure Position Switches on Two Valves Did Not Trip When Tested.Caused by Mechanical Drift of Valve Position Switch Operating Cams. Adjustment Made ML20052C2511982-04-20020 April 1982 LER 82-005/01X-1:on 820315,during Normal Operation, Containment Oxygen Concentration Exceeded 4% Limit for Approx 6-h.Caused by Personnel Error.Startup Checkoff List Revised ML20049H6181982-02-23023 February 1982 LER 82-001/01T-0:on 820210,Tech Spec Setpoint for HPCI Turbine Steam Line High Flow Appeared High.Caused by Failure to Discover Error in Setpoint Calculation During Administrative Review of Startup Test Program ML20039B6171981-12-14014 December 1981 LER 81-079/03L-0:on 811116,sample of Standby Gas Treatment Charcoal Was Less than 99% Efficient in Removing Methyl Iodide.Apparently Caused by Age of Charcoal.Charcoal Replaced ML20049A8301981-09-24024 September 1981 LER 81-069/03L-0:on 810828 & 29,during Operation in Degraded Mode,Drywell Particulate Monitoring or Gaseous Monitoring Made Inoperable to Permit Corrective Maint.Caused by Need to Replace Sample Pumps Because of Age ML20039E2581981-07-0707 July 1981 LER 81-051/03L-0:on 810608,leakage from Solidified Radwaste Container Noted During Shipment Preparation.Caused by Pinhole Leak in Liner Apparently Due to Dumping During Handling.New Liner Prepared & Area Decontaminated ML19352A8851981-05-29029 May 1981 LER 81-039/03L-0:on 810429,during Normal Operation,Trouble Shooting of Indicator Lamp Problem for Containment Spray Valves 10-MOV-26A & 31A Revealed Limit Switch Rotor Failure. Cause Unknown.Rotors Replaced.Evaluation Ongoing ML19347F4881981-05-12012 May 1981 LER 81-034/03L-0:on 810414,direct Indication of Drywell/ Torus Differential Pressure Not Available W/Containment Penetration Instrument Isolated.Caused by Computer Out of Svc Due to Dirty Printed Circuit Board Contacts ML19345G7921981-04-15015 April 1981 LER 81-024/03L-0:on 810323,drywell Equipment Drain Sump Pump B Lost Suction & Could Not Effect Sump Pump Out.Cause Unknown.Amend to Tech Spec Submitted ML19350B9921981-03-19019 March 1981 LER 81-021/03L-0:on 810219,core Spray Pipe Break Switch 14-DPIS-43A Found Set Above Tech Spec Limit.Caused by Instrument Drift.Surveillance Increased to Daily,Guide Valve Changed to More Conservative Set Point & Training Conducted ML19352A1611981-03-0606 March 1981 LER 81-018/03L-0:on 810209,steam Line High Flow Switches 02-DPIS-116A & 116B Were Found Outside Tech Spec.Probably Caused by Instrument Drift.Switches Calibr ML20003C3381981-02-24024 February 1981 LER 81-017/03L-0:on 810207,average Power Range Monitors a & E Downscale Trips Found Set at Less than 2.5/125,in Violation of Tech Spec 3.1-1.Possibly Caused by Instrument Drift.Downscale Trips Adjusted ML19351F8871981-02-16016 February 1981 LER 81-009/03L-0:on 810115,during Normal Operation, Administrative Review Noted Fire Hose Gasket Insp & Rerack Not Completed as Required by Tech Specs.Caused by Personnel Error.Improper Data Sheets Not Used After May 1980 ML20003B7161981-02-16016 February 1981 LER 81-010/03L-0:on 810117,HPCI Sys Started But Failed to Automatically Operate at Rated Speed.Caused by Sys Controller.Operator Increased Speed & Discharge Pressure. Controller Replaced ML20003B0061981-02-0404 February 1981 LER 81-001/01T-0:on 810121,problems Re IE Bulletin 80-25 Found in safety-relief Valve Solenoids.Probably Caused by Solenoid Valve Vendor Inadequacy.Eleven Solenoid Pairs Disassembled,Inspected & Cleaned ML19351F0841980-12-17017 December 1980 LER 80-090/03L-0:on 801130,MSIV 29-A0V-80A 90% Open Limit Switch Did Not Reset When Valve Was Fully Opened.Cause Undetermined.Fuses for Follower Relay Pulled to Keep Channel Tripped While Being Repaired ML19351F0831980-12-17017 December 1980 LER 80-089/03L-0:on 801126,reactor Core Isolation Cooling Steam Line Low Pressure Switch 13-PS-87B Found Set Outside Tech Spec Limits.Caused by Instrument Drift.Switch Adjusted & Surveillance Frequency Increased ML19345C5341980-12-0202 December 1980 LER 80-082/03L-0:on 801102,solenoid Pilot Valve 16-1-SOV-101 B,Associated W/Containment Isolation Valve 16-1-AOV-101B, Failed Causing AOV to Fail.Caused by Worn Plunger & Dirt in Valve.Parts Cleaned & Replaced ML19345A8761980-11-21021 November 1980 LER 80-081/03L-0:on 801023,carbon Dioxide Sys Associated W/North Cable Run Room Would Not Actuate from Heat Detectors or Local Push Button.Caused by Wiring Changes Due to Mods Resulting in Wire Physically Preventing Proper Operation ML19339B2091980-11-0303 November 1980 LER 80-078/03L-0:on 801005,drywell Equipment Drain Sump Integrator (20-FQ-530) & Flow Recorder (20-FR-528) Were Found Inoperable.Cause Not Stated.Flow Transmitter Replaced. No Problem Found W/Integrator or Recorder ML19332B0181980-09-12012 September 1980 LER 80-073/03L-0:on 800815 During Surveillance,Offgas Radiation Monitor B Found Out of Calibr.Caused by Instrument Drift & Detector Aging.Adjusted & Restored Monitor to Operable Status 3 Days After Discovery ML19331D4061980-08-29029 August 1980 LER 80-067/03L-0:on 800805,while Conducting Instrument Surveillance Check,Steam Line Low Pressure Switches Found Set Higher than 100 Psig Limit.Caused by Instrument Drift. Instruments Calibr & Returned to Svc ML19331D4111980-08-29029 August 1980 LER 80-068/03L-0:on 800806,during Normal Cold Shutdown, Conducting Instrument Surveillance F-ISP-15,drywell Drain Sump Pump Flow Transmitter Found Out of Tolerance.Caused by Instrument Drift.Instrument Recalibr ML19331D4171980-08-29029 August 1980 LER 80-069/03L-0:on 800807,during Normal Shutdown,While Conducting Surveillance Test F-ST-22A,auto Depressurization Sys Timer Found Set Below Limit.Caused by Setpoint Drift. Timer Adjusted & Returned to Svc ML19331D6501980-08-28028 August 1980 LER 80-066/03L-0:on 800805,during Normal Shutdown,Conducting Surveillance Procedure F-ISP-8,core Spray Sys Pipe Break Detection Switches 14-DPIS-43A & 43B Found Set Greater than Limit.Caused by Instrument Drift.Instruments Recalibr ML19331D6401980-08-27027 August 1980 LER 80-065/03T-0:on 800814,during Normal Operations,While Inerting Primary Containment,Standby Gas Treatment Sys A&B Found Inoperable.Caused by Blocked Drain Line Allowing Water to Accumulate in Line Until Fans Could Not Discharge ML19331C8501980-08-14014 August 1980 LER 80-063/03L-0:on 800717,during Normal Shutdown, Surveillance Revealed That Average Power Range Monitor E Indicated 48 When Required to Read Between 49 & 51.Caused by Instrument Drift.Monitor Recalibr ML19331C4731980-08-12012 August 1980 LER 80-061/03L-0:on 800714,during Shutdown,Functional Test of Hydraulic Snubbers Revealed Two Snubbers Which Failed Lockup & bleed-rate Values.Caused by Normal Wear.Snubbers Were Replaced ML19327A2621980-07-30030 July 1980 LER 80-060/03L-0:on 800710,while Conducting Surveillance Per Tech Spec Table 4.2-6,Item 6,torus Water Level Instrument Did Not Properly Indicate Actual Level.Caused by Air in Level Transmitter &/Or Sensing Lines.Air Vented ML19330A6131980-07-22022 July 1980 LER 80-057/03L-0:on 800628,during Normal Shutdown,One Cell in Each 24 Volt Battery for Diesel Fire Pump Failed to Meet Min Specific Gravity Requirements of Surveillance Test. Caused by Charger Being Out of Svc During Surveillance ML19330A5861980-07-22022 July 1980 LER 80-058/03L-0:on 800628,during Normal Shutdown Operations,Functional Tests of Average Power Range Monitor Instruments Found Not Conducted Per Tech Specs.Caused by Manual Scheduling of Computer Outage ML19330A5271980-07-22022 July 1980 LER 80-059/03L-0:on 800703,during Normal Shutdown Surveillance,Level Switches & Pressure Indicator Showed 128 Instruments Out of Calibr or Not Properly Operating.Caused by Instrument Drift.Instruments Recalibr.Two Replaced ML19320C0661980-07-10010 July 1980 LER 80-056/03L-0:on 800610,during Normal Shutdown & Surveillance Testing,Emergency Diesel Generator C Tripped on High Circulating Current.Caused by Dirty or Defective Contact on Voltage Regulator Droop Switch ML19320B5131980-07-0707 July 1980 Updated LER 80-046/03X-1:on 800430,surveillance Testing Revealed Shutdown Cooling Permissive Switches Set in Excess of 75 Psig Limit.Caused by Procedural Error.Instruments Recalibr & Returned to Svc ML19329G3041980-07-0707 July 1980 LER 80-055/03L-0:on 800607,surveillance Revealed Intermediate Range Monitor,A Indicating 120 When Reading of 125 Was Required.Caused by Instrument Drift.Adjustment & Calibr Restored Instrument to Operable Status 1993-06-25
[Table view] Category:RO)
MONTHYEARML20045F6631993-06-25025 June 1993 LER 93-014-00 on 930529,logic Sys Functional Testing Was Incomplete Due to Test Procedure Deficiencies.Temporary Procedure Changes made.W/930625 Ltr ML20043B9831990-05-23023 May 1990 LER 90-016-00:on 900424,automatic Isolation Signal Closed Suction Valves from Reactor Water Recirculation Sys.On 900425,suction Valves Closed & RHR Pump Tripped.Caused by Chattering Pressure Switch.Switches replaced.W/900523 Ltr ML20012C5161990-03-0909 March 1990 LER 90-004-00:on 900207,isolation of RCIC Sys Occurred, Resulting in Initiation of 7-day Limiting Condition of Operation.Caused by Failure of Master Trip Unit.Subj Unit replaced.W/900309 Ltr ML20011E1431990-01-29029 January 1990 LER 89-020-01:on 891105,reactor Scram Initiated by High APRM Neutron Flux from Pressure Transient from Turbine Control Valve Closure.Caused by Void Collapse in Core Moderator. Computer Programming Changed Re Transient data.W/900129 Ltr ML20006C1571990-01-26026 January 1990 LER 89-026-00:on 891105,reactor Scram from Full Power Occurred Due to Problems W/Turbine electro-hydraulic Control Sys.On 891220,contractor Notified Util That Valves Tested Did Not Actuate within Setpoint as required.W/900126 Ltr ML20005E8541990-01-0202 January 1990 LER 89-025-00:on 891130,isolation Signal Closed Outboard Isolation Valves on Steam Supply Line to HPCI Sys,Rendering HPCI Sys Inoperable & Initiating 7-day Limiting Condition for Operation.Caused by Excess steam.W/900102 Ltr ML19332F0471989-11-30030 November 1989 LER 89-021-00:on 891031,circuit Breaker for RCIC Inboard Injection Valve to Feedwater Sys Tripped During Required Valve Testing.Caused by Fault in Motor Winding Insulation. New Motor installed.W/891130 Ltr ML19332E6241989-11-30030 November 1989 LER 89-019-00:on 891031 & 891103,HPCI Sys Declared Inoperable Due to Electrical Ground in Speed Control Circuit.Caused by Buildup of Conductive Corrosion Products. Connector Cleaned & Sys Returned to svc.W/891130 Ltr ML19325F2791989-11-13013 November 1989 LER 89-007-01:on 890509,surveillance of Fire Barrier Penetrations,Per Tech Spec 4.12.F Not Conducted within Allowed Time Period.Caused by Misinterpretation of Fire Protection Ref Manual.Fire Watch established.W/891113 Ltr ML19327C1351989-11-0707 November 1989 LER 89-015-01:on 890918,two Remote Manually Operated Diaphragm Air Operated Isolation Valves Failed Closing Time Acceptance Criteria.Caused by Buildup of Iron Oxide Sludge. Valves Disassembled & Cleaned ML19327B9821989-11-0606 November 1989 LER 89-018-00:on 891008,HPCI High Steam Flow Signal Closed Isolation Valves for Outboard Steam Supply & Steam Line Warning.Caused by Air in Sensing Sys Leading to Unstable Oscillation.Pressure Sensor Vented & calibr.W/891106 Ltr ML19324B1151989-10-23023 October 1989 LER 88-008-01:during 1988 Refuel Outage,One Primary Containment Penetration Exceeded Tech Spec 4.7.A.2.b Limit When Subjected to Local Leak Rate Testing.Leakage Attributed to Wear.Valves replaced.W/891023 Ltr ML19327B1521989-10-20020 October 1989 LER 89-017-00:on 890920,ESFAS Initiated Group II Primary Containment Isolation Signal Triggering RHR & LPCI Sys Isolations.Caused by Cognitive Human Error in Not Finding Isolation Signal.Fuse Replaced & Sys restarted.W/891020 Ltr ML19327B1501989-10-18018 October 1989 LER 89-016-00:on 890918,scram Signal Automatically Initiated During Transfer of Power Supply for Reactor Protection Sys. Caused by Lack of Caution Statement in Procedure.Procedure Revised to Add Time Caution for Bus transfers.W/891018 Ltr ML19327B1331989-10-18018 October 1989 LER 89-015-00:on 890918,two of Nine Remote Manually Operated Diaphragm Air Operated Containment Isolation Valves Failed Acceptance Criteria for Closing Time.Caused by Buildup & Hardening of Iron Oxide Sludge.Valves cleaned.W/891018 Ltr ML20052E2811982-04-30030 April 1982 LER 82-017/03L-0:on 820402,MSIV 10% Closure Position Switches on Two Valves Did Not Trip When Tested.Caused by Mechanical Drift of Valve Position Switch Operating Cams. Adjustment Made ML20052C2511982-04-20020 April 1982 LER 82-005/01X-1:on 820315,during Normal Operation, Containment Oxygen Concentration Exceeded 4% Limit for Approx 6-h.Caused by Personnel Error.Startup Checkoff List Revised ML20049H6181982-02-23023 February 1982 LER 82-001/01T-0:on 820210,Tech Spec Setpoint for HPCI Turbine Steam Line High Flow Appeared High.Caused by Failure to Discover Error in Setpoint Calculation During Administrative Review of Startup Test Program ML20039B6171981-12-14014 December 1981 LER 81-079/03L-0:on 811116,sample of Standby Gas Treatment Charcoal Was Less than 99% Efficient in Removing Methyl Iodide.Apparently Caused by Age of Charcoal.Charcoal Replaced ML20049A8301981-09-24024 September 1981 LER 81-069/03L-0:on 810828 & 29,during Operation in Degraded Mode,Drywell Particulate Monitoring or Gaseous Monitoring Made Inoperable to Permit Corrective Maint.Caused by Need to Replace Sample Pumps Because of Age ML20039E2581981-07-0707 July 1981 LER 81-051/03L-0:on 810608,leakage from Solidified Radwaste Container Noted During Shipment Preparation.Caused by Pinhole Leak in Liner Apparently Due to Dumping During Handling.New Liner Prepared & Area Decontaminated ML19352A8851981-05-29029 May 1981 LER 81-039/03L-0:on 810429,during Normal Operation,Trouble Shooting of Indicator Lamp Problem for Containment Spray Valves 10-MOV-26A & 31A Revealed Limit Switch Rotor Failure. Cause Unknown.Rotors Replaced.Evaluation Ongoing ML19347F4881981-05-12012 May 1981 LER 81-034/03L-0:on 810414,direct Indication of Drywell/ Torus Differential Pressure Not Available W/Containment Penetration Instrument Isolated.Caused by Computer Out of Svc Due to Dirty Printed Circuit Board Contacts ML19345G7921981-04-15015 April 1981 LER 81-024/03L-0:on 810323,drywell Equipment Drain Sump Pump B Lost Suction & Could Not Effect Sump Pump Out.Cause Unknown.Amend to Tech Spec Submitted ML19350B9921981-03-19019 March 1981 LER 81-021/03L-0:on 810219,core Spray Pipe Break Switch 14-DPIS-43A Found Set Above Tech Spec Limit.Caused by Instrument Drift.Surveillance Increased to Daily,Guide Valve Changed to More Conservative Set Point & Training Conducted ML19352A1611981-03-0606 March 1981 LER 81-018/03L-0:on 810209,steam Line High Flow Switches 02-DPIS-116A & 116B Were Found Outside Tech Spec.Probably Caused by Instrument Drift.Switches Calibr ML20003C3381981-02-24024 February 1981 LER 81-017/03L-0:on 810207,average Power Range Monitors a & E Downscale Trips Found Set at Less than 2.5/125,in Violation of Tech Spec 3.1-1.Possibly Caused by Instrument Drift.Downscale Trips Adjusted ML19351F8871981-02-16016 February 1981 LER 81-009/03L-0:on 810115,during Normal Operation, Administrative Review Noted Fire Hose Gasket Insp & Rerack Not Completed as Required by Tech Specs.Caused by Personnel Error.Improper Data Sheets Not Used After May 1980 ML20003B7161981-02-16016 February 1981 LER 81-010/03L-0:on 810117,HPCI Sys Started But Failed to Automatically Operate at Rated Speed.Caused by Sys Controller.Operator Increased Speed & Discharge Pressure. Controller Replaced ML20003B0061981-02-0404 February 1981 LER 81-001/01T-0:on 810121,problems Re IE Bulletin 80-25 Found in safety-relief Valve Solenoids.Probably Caused by Solenoid Valve Vendor Inadequacy.Eleven Solenoid Pairs Disassembled,Inspected & Cleaned ML19351F0841980-12-17017 December 1980 LER 80-090/03L-0:on 801130,MSIV 29-A0V-80A 90% Open Limit Switch Did Not Reset When Valve Was Fully Opened.Cause Undetermined.Fuses for Follower Relay Pulled to Keep Channel Tripped While Being Repaired ML19351F0831980-12-17017 December 1980 LER 80-089/03L-0:on 801126,reactor Core Isolation Cooling Steam Line Low Pressure Switch 13-PS-87B Found Set Outside Tech Spec Limits.Caused by Instrument Drift.Switch Adjusted & Surveillance Frequency Increased ML19345C5341980-12-0202 December 1980 LER 80-082/03L-0:on 801102,solenoid Pilot Valve 16-1-SOV-101 B,Associated W/Containment Isolation Valve 16-1-AOV-101B, Failed Causing AOV to Fail.Caused by Worn Plunger & Dirt in Valve.Parts Cleaned & Replaced ML19345A8761980-11-21021 November 1980 LER 80-081/03L-0:on 801023,carbon Dioxide Sys Associated W/North Cable Run Room Would Not Actuate from Heat Detectors or Local Push Button.Caused by Wiring Changes Due to Mods Resulting in Wire Physically Preventing Proper Operation ML19339B2091980-11-0303 November 1980 LER 80-078/03L-0:on 801005,drywell Equipment Drain Sump Integrator (20-FQ-530) & Flow Recorder (20-FR-528) Were Found Inoperable.Cause Not Stated.Flow Transmitter Replaced. No Problem Found W/Integrator or Recorder ML19332B0181980-09-12012 September 1980 LER 80-073/03L-0:on 800815 During Surveillance,Offgas Radiation Monitor B Found Out of Calibr.Caused by Instrument Drift & Detector Aging.Adjusted & Restored Monitor to Operable Status 3 Days After Discovery ML19331D4061980-08-29029 August 1980 LER 80-067/03L-0:on 800805,while Conducting Instrument Surveillance Check,Steam Line Low Pressure Switches Found Set Higher than 100 Psig Limit.Caused by Instrument Drift. Instruments Calibr & Returned to Svc ML19331D4111980-08-29029 August 1980 LER 80-068/03L-0:on 800806,during Normal Cold Shutdown, Conducting Instrument Surveillance F-ISP-15,drywell Drain Sump Pump Flow Transmitter Found Out of Tolerance.Caused by Instrument Drift.Instrument Recalibr ML19331D4171980-08-29029 August 1980 LER 80-069/03L-0:on 800807,during Normal Shutdown,While Conducting Surveillance Test F-ST-22A,auto Depressurization Sys Timer Found Set Below Limit.Caused by Setpoint Drift. Timer Adjusted & Returned to Svc ML19331D6501980-08-28028 August 1980 LER 80-066/03L-0:on 800805,during Normal Shutdown,Conducting Surveillance Procedure F-ISP-8,core Spray Sys Pipe Break Detection Switches 14-DPIS-43A & 43B Found Set Greater than Limit.Caused by Instrument Drift.Instruments Recalibr ML19331D6401980-08-27027 August 1980 LER 80-065/03T-0:on 800814,during Normal Operations,While Inerting Primary Containment,Standby Gas Treatment Sys A&B Found Inoperable.Caused by Blocked Drain Line Allowing Water to Accumulate in Line Until Fans Could Not Discharge ML19331C8501980-08-14014 August 1980 LER 80-063/03L-0:on 800717,during Normal Shutdown, Surveillance Revealed That Average Power Range Monitor E Indicated 48 When Required to Read Between 49 & 51.Caused by Instrument Drift.Monitor Recalibr ML19331C4731980-08-12012 August 1980 LER 80-061/03L-0:on 800714,during Shutdown,Functional Test of Hydraulic Snubbers Revealed Two Snubbers Which Failed Lockup & bleed-rate Values.Caused by Normal Wear.Snubbers Were Replaced ML19327A2621980-07-30030 July 1980 LER 80-060/03L-0:on 800710,while Conducting Surveillance Per Tech Spec Table 4.2-6,Item 6,torus Water Level Instrument Did Not Properly Indicate Actual Level.Caused by Air in Level Transmitter &/Or Sensing Lines.Air Vented ML19330A6131980-07-22022 July 1980 LER 80-057/03L-0:on 800628,during Normal Shutdown,One Cell in Each 24 Volt Battery for Diesel Fire Pump Failed to Meet Min Specific Gravity Requirements of Surveillance Test. Caused by Charger Being Out of Svc During Surveillance ML19330A5861980-07-22022 July 1980 LER 80-058/03L-0:on 800628,during Normal Shutdown Operations,Functional Tests of Average Power Range Monitor Instruments Found Not Conducted Per Tech Specs.Caused by Manual Scheduling of Computer Outage ML19330A5271980-07-22022 July 1980 LER 80-059/03L-0:on 800703,during Normal Shutdown Surveillance,Level Switches & Pressure Indicator Showed 128 Instruments Out of Calibr or Not Properly Operating.Caused by Instrument Drift.Instruments Recalibr.Two Replaced ML19320C0661980-07-10010 July 1980 LER 80-056/03L-0:on 800610,during Normal Shutdown & Surveillance Testing,Emergency Diesel Generator C Tripped on High Circulating Current.Caused by Dirty or Defective Contact on Voltage Regulator Droop Switch ML19320B5131980-07-0707 July 1980 Updated LER 80-046/03X-1:on 800430,surveillance Testing Revealed Shutdown Cooling Permissive Switches Set in Excess of 75 Psig Limit.Caused by Procedural Error.Instruments Recalibr & Returned to Svc ML19329G3041980-07-0707 July 1980 LER 80-055/03L-0:on 800607,surveillance Revealed Intermediate Range Monitor,A Indicating 120 When Reading of 125 Was Required.Caused by Instrument Drift.Adjustment & Calibr Restored Instrument to Operable Status 1993-06-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000333/LER-1999-008-01, :on 990910,HPCI Sys Was Declared Inoperable Due to Apparent Failure of Master Trip Unit (MTU) within HPCI Sys Automatice Isolation Logic.Subject MTU Was Replaced & HPCI Sys Was Returned to Operable Status.With1999-10-12012 October 1999
- on 990910,HPCI Sys Was Declared Inoperable Due to Apparent Failure of Master Trip Unit (MTU) within HPCI Sys Automatice Isolation Logic.Subject MTU Was Replaced & HPCI Sys Was Returned to Operable Status.With
ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data JAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With ML20212E9761999-09-21021 September 1999 Safety Evaluation Supporting Amend 255 to License DPR-59 05000333/LER-1998-015, :on 981211,identified Logic Sys Functional Test Inadequacies.Caused by Personnel error.Re-review of Surveillance Testing for EDG Sys to Ensure TS Surveillance Tests Adequate,Scheduled to Be Completed by Jan 15, 20001999-09-0808 September 1999
- on 981211,identified Logic Sys Functional Test Inadequacies.Caused by Personnel error.Re-review of Surveillance Testing for EDG Sys to Ensure TS Surveillance Tests Adequate,Scheduled to Be Completed by Jan 15, 2000
05000333/LER-1999-007-01, :on 990809,both a & B Division of CS Pump Start Interlock Relays Exceeded Values Required by Ts.Caused by Inappropriate as-left Calibr Tolerance for Time Delay Relays.Relays Were Immediately Recalibr.With1999-09-0808 September 1999
- on 990809,both a & B Division of CS Pump Start Interlock Relays Exceeded Values Required by Ts.Caused by Inappropriate as-left Calibr Tolerance for Time Delay Relays.Relays Were Immediately Recalibr.With
JAFP-99-0261, Monthly Operating Rept for Aug 1999 for Jafnpp.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Jafnpp.With JAFP-99-0236, Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with ML20210J0061999-07-30030 July 1999 Safety Evaluation Supporting Amend 253 to License DPR-59 ML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) 05000333/LER-1999-006-01, :on 990609,LCPI Mode of RHR Sys Was Inoperable. Caused by Loss of Automatic Startup Capability of RHR Pumps. Repaired Defective Fuse Contact & Conducted Equipment Failure Evaluation.With1999-07-0808 July 1999
- on 990609,LCPI Mode of RHR Sys Was Inoperable. Caused by Loss of Automatic Startup Capability of RHR Pumps. Repaired Defective Fuse Contact & Conducted Equipment Failure Evaluation.With
05000333/LER-1999-005-01, :on 990506,missed Surveillance Test Was Noted. Caused by Inoperable Containment Hydrogen/Oxygen Analyzer. Counseled Personnel Involved & Revised Procedures.With1999-07-0707 July 1999
- on 990506,missed Surveillance Test Was Noted. Caused by Inoperable Containment Hydrogen/Oxygen Analyzer. Counseled Personnel Involved & Revised Procedures.With
ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept JAFP-99-0211, Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With 05000333/LER-1999-004-01, :on 990403,two Electrical Leads in 09-30 Panel in Relay Room Were Found Unlanded.Caused by Inattention to Detail & Inadequate Process to Ensure Complete Protective Tag.Performed Extent of Condition Walkdowns.With1999-06-17017 June 1999
- on 990403,two Electrical Leads in 09-30 Panel in Relay Room Were Found Unlanded.Caused by Inattention to Detail & Inadequate Process to Ensure Complete Protective Tag.Performed Extent of Condition Walkdowns.With
JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with1999-06-0202 June 1999 Annual Summary of Changes,Tests & Experiments for 1997/1998. with JAFP-99-0181, Monthly Operating Rept for May 1999 for Jafnpp.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Jafnpp.With 05000333/LER-1999-002, :on 990113,discovered That Suppression Chamber RB Vacuum Breaker Isolation Valve Differential Pressure Switches Were Out of Tolerance Due to Incorrect Assumption in Calculation.Calibr Pressure Switches.With1999-05-13013 May 1999
- on 990113,discovered That Suppression Chamber RB Vacuum Breaker Isolation Valve Differential Pressure Switches Were Out of Tolerance Due to Incorrect Assumption in Calculation.Calibr Pressure Switches.With
JAFP-99-0166, Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With ML20205N4041999-04-12012 April 1999 Safety Evaluation Supporting Amend 252 to License DPR-59 JAFP-99-0142, Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With 05000333/LER-1998-015, :on 981211,logic Sys Functional Test Inadequacies Were Noted.Caused by Personnel Error.Revised ST-9P, Functional Test of Breakers 10514 & 10516 EDG Logic Auxiliary Stationary Contact. with1999-03-0808 March 1999
- on 981211,logic Sys Functional Test Inadequacies Were Noted.Caused by Personnel Error.Revised ST-9P, Functional Test of Breakers 10514 & 10516 EDG Logic Auxiliary Stationary Contact. with
JAFP-99-0092, Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20206U4851999-02-0808 February 1999 Safety Evaluation Supporting Amend 251 to License DPR-59 ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20199G9041999-01-12012 January 1999 Safety Evaluation Supporting Amend 250 to License DPR-59 JAFP-99-0011, Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With 05000333/LER-1998-013, :on 981117,containment Leakage Rate Exceeds Authorized Limits,Was Determined.Caused by Valve Sealing Failure.Failed Valves Repaired & Retested Satisfactorily Prior to Plant Startup1998-12-17017 December 1998
- on 981117,containment Leakage Rate Exceeds Authorized Limits,Was Determined.Caused by Valve Sealing Failure.Failed Valves Repaired & Retested Satisfactorily Prior to Plant Startup
05000333/LER-1998-014, :on 981117,trip of RPS Power Supply & ESF Actuation Occurred.Caused by Relay Failure.Relay Was Replaced & Motor Was Restarted Satisfactorily.With1998-12-15015 December 1998
- on 981117,trip of RPS Power Supply & ESF Actuation Occurred.Caused by Relay Failure.Relay Was Replaced & Motor Was Restarted Satisfactorily.With
ML20198B5171998-12-11011 December 1998 Safety Evaluation Supporting Amend 248 to License DPR-59 05000333/LER-1998-012, :on 981104,failure to Meet Primary Containment Leakage Rate Testing Program Requirements Was Noted.Caused by Deficient Test Procedures.Leak Rate Test Procedures Were Revised & Testing Was Completed.With1998-12-0404 December 1998
- on 981104,failure to Meet Primary Containment Leakage Rate Testing Program Requirements Was Noted.Caused by Deficient Test Procedures.Leak Rate Test Procedures Were Revised & Testing Was Completed.With
ML20198F9991998-12-0404 December 1998 Assessment of Licensing Basis for Use of Containment Overpressure Credit for Net Positive Suction Head Analyses Power Authority of State of New York,James a Fitzpatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196J6201998-12-0101 December 1998 Safety Evaluation Supporting Amend 247 to License DPR-59 JAFP-98-0396, Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20196G0181998-11-25025 November 1998 Safety Evaluation Supporting Amend 246 to License DPR-59 ML20195J7521998-11-18018 November 1998 Rev 7 to Jaf Colr ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20197G6221998-11-0606 November 1998 Non-proprietary Rev 7 to HI-971661, Licensing Rept for Reracking of Ja FitzPatrick Sfp ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting JAFP-98-0360, Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20155C2821998-10-30030 October 1998 Non-proprietary Rev 0 to GENE-187-30-1598 Np, CRD Bolting Flaw Evaluation for Ja FitzPatrick Nuclear Power Plant 05000333/LER-1998-011, :on 980929,failure to Meet Drywell Continuous Atmosphere Monitoring Sys TS Surveillance Test Requirements Were Noted.Caused by Deficient Tp.Declared Both Channels of CAM Sys Inoperable.With1998-10-27027 October 1998
- on 980929,failure to Meet Drywell Continuous Atmosphere Monitoring Sys TS Surveillance Test Requirements Were Noted.Caused by Deficient Tp.Declared Both Channels of CAM Sys Inoperable.With
ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 JAFP-98-0322, Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With 1999-09-08
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