05000010/LER-1997-001-06, :on 970210,120 Volt Circuit Breaker Supplying Alternate Iodine & Particulate Sampling Sys Tripped.Caused by Mgt Deficiency.Disconnected Auxiliary Loads,Restricted Use of Outlets & Verified Continued Sys Operation1997-03-12012 March 1997
- on 970210,120 Volt Circuit Breaker Supplying Alternate Iodine & Particulate Sampling Sys Tripped.Caused by Mgt Deficiency.Disconnected Auxiliary Loads,Restricted Use of Outlets & Verified Continued Sys Operation
05000237/LER-1990-007-09, :on 900802,unplanned Primary Containment Group V Isolation Occurred.Cause Not Identified.Relay Circuitry & Sys Parameters Investigated Prior to Resetting Isolation Signal & Visual Observation Made1990-08-28028 August 1990
- on 900802,unplanned Primary Containment Group V Isolation Occurred.Cause Not Identified.Relay Circuitry & Sys Parameters Investigated Prior to Resetting Isolation Signal & Visual Observation Made
05000237/LER-1989-032, :on 891210,as-left Type B & C Local Leak Rate Test Data Exceeded Tech Spec Limit of 488.452 Std Cubic Ft/H.Caused by Degradation of Telephone & Electrical Conduit Penetration Seal.Conduit Cut & Capped1989-12-29029 December 1989
- on 891210,as-left Type B & C Local Leak Rate Test Data Exceeded Tech Spec Limit of 488.452 Std Cubic Ft/H.Caused by Degradation of Telephone & Electrical Conduit Penetration Seal.Conduit Cut & Capped
05000237/LER-1989-001-05, :on 890121,unanticipated Reactor Scram & Group II Primary Containment Isolation Occurred Due to Loss of Reactor Protection Sys Motor Generator Sets.Caused by Procedural Deficiency.Procedure Reviewed1989-02-21021 February 1989
- on 890121,unanticipated Reactor Scram & Group II Primary Containment Isolation Occurred Due to Loss of Reactor Protection Sys Motor Generator Sets.Caused by Procedural Deficiency.Procedure Reviewed
05000249/LER-1984-019-02, :on 841024,determined That Two Flow Makeup Boxes Used for Local Leak Rate Testing Out of Calibr & Should Have Been Added to as-found Type B & C Leakage Rate. Caused by Improper Calibr Due to Box Design1987-08-0303 August 1987
- on 841024,determined That Two Flow Makeup Boxes Used for Local Leak Rate Testing Out of Calibr & Should Have Been Added to as-found Type B & C Leakage Rate. Caused by Improper Calibr Due to Box Design
05000237/LER-1987-006-02, :on 870228,during Refueling,Reactor Scram & Group II Isolation Occurred.Caused by Trip at Bus 28 of Main Feed Breaker of Motor Control Ctr (MCC) 28-2.Reactor Protection Sys Bus 2B Transferred to MCC 25-21987-03-30030 March 1987
- on 870228,during Refueling,Reactor Scram & Group II Isolation Occurred.Caused by Trip at Bus 28 of Main Feed Breaker of Motor Control Ctr (MCC) 28-2.Reactor Protection Sys Bus 2B Transferred to MCC 25-2
05000237/LER-1987-007-02, :on 870227,drywell Structural Steel Radial Beam Discovered Outside Design Requirements.Caused by Reinstallation Deficiency.Beam Repair Completed on 870314, Per Engineering Change Notice D875-091987-03-25025 March 1987
- on 870227,drywell Structural Steel Radial Beam Discovered Outside Design Requirements.Caused by Reinstallation Deficiency.Beam Repair Completed on 870314, Per Engineering Change Notice D875-09
05000249/LER-1987-002-09, :on 870225,while Unit Operating at 87% Power, HPCI Sys Discovered Inoperable.Caused by Oil Pressure Regulation Valve Failure.Similar Event Occurred on 870313. Limits of PS4 Reset to 60 Psig Increasing1987-03-25025 March 1987
- on 870225,while Unit Operating at 87% Power, HPCI Sys Discovered Inoperable.Caused by Oil Pressure Regulation Valve Failure.Similar Event Occurred on 870313. Limits of PS4 Reset to 60 Psig Increasing
05000249/LER-1987-003-06, :on 870227,shutdown Cooling HX Outlet Temp Found Greater than 212 F.Caused by Operator Failure to Adequately Monitor Reactor Water Temp on Proper Instrumentation.Water Temp Reduced1987-03-24024 March 1987
- on 870227,shutdown Cooling HX Outlet Temp Found Greater than 212 F.Caused by Operator Failure to Adequately Monitor Reactor Water Temp on Proper Instrumentation.Water Temp Reduced
05000237/LER-1987-005-02, :on 870218,w/unit Shut Down for Refueling Outage,Snubbers 1301,1302 & 1303 Failed to Activate or Bleed within Allowable Ranges.Caused by Upgraded Test Acceptance Criteria.Two Mechanical Snubbers Installed1987-03-21021 March 1987
- on 870218,w/unit Shut Down for Refueling Outage,Snubbers 1301,1302 & 1303 Failed to Activate or Bleed within Allowable Ranges.Caused by Upgraded Test Acceptance Criteria.Two Mechanical Snubbers Installed
05000249/LER-1987-001-09, :on 870209,hourly Fire Insp for East End of Unit 2/3 Cable Tunnel Not Established Immediately Per Tech Spec 3.12.C.1.Caused by Operating Personnel Error.Hourly Fire Watch Immediately Established1987-03-0303 March 1987
- on 870209,hourly Fire Insp for East End of Unit 2/3 Cable Tunnel Not Established Immediately Per Tech Spec 3.12.C.1.Caused by Operating Personnel Error.Hourly Fire Watch Immediately Established
05000237/LER-1987-003-01, :on 870108,found Primary Containment Drywell Structural Steel Not Meeting FSAR Design Requirements.Caused by Inadequate Confirmation of Original Const & as-built Configuration.Repair Program Developed1987-02-0606 February 1987
- on 870108,found Primary Containment Drywell Structural Steel Not Meeting FSAR Design Requirements.Caused by Inadequate Confirmation of Original Const & as-built Configuration.Repair Program Developed
05000237/LER-1987-003, :on 870108,primary Containment Drywell Structural Steel Did Not Meet FSAR Design Requirements Due to Inadequate Connections Between Radial & Tangential Beams. Caused by Inadequate Confirmation of Const1987-02-0606 February 1987
- on 870108,primary Containment Drywell Structural Steel Did Not Meet FSAR Design Requirements Due to Inadequate Connections Between Radial & Tangential Beams. Caused by Inadequate Confirmation of Const
05000249/LER-1986-026-03, :on 860911,drywell Oxygen Content Exceeded 4% for Greater than 24 H W/Mode Switch in Run.Caused by Personnel Error.Operating Procedures DOP-1600-5 & DOP 1600-6 Revised & Guidance Under Development1987-02-0505 February 1987
- on 860911,drywell Oxygen Content Exceeded 4% for Greater than 24 H W/Mode Switch in Run.Caused by Personnel Error.Operating Procedures DOP-1600-5 & DOP 1600-6 Revised & Guidance Under Development
05000237/LER-1987-004-01, :on 870108,primary Containment Type B & C Local Leak Rate Test Limit Exceeded Due to Excessive Leakage Through Isolation Valve.Valve Will Be Repaired & Retested Per Dts 1600-1 When Cause Determined1987-01-29029 January 1987
- on 870108,primary Containment Type B & C Local Leak Rate Test Limit Exceeded Due to Excessive Leakage Through Isolation Valve.Valve Will Be Repaired & Retested Per Dts 1600-1 When Cause Determined
05000237/LER-1987-002-02, :on 870105,radwaste Off Stream Liquid Effluent Monitor Isolated During Radwaste Discharge.Caused by Operator Failure to Verify Proper Valve Alignment & Sample Flow.Foreman Relieved of Duties1987-01-27027 January 1987
- on 870105,radwaste Off Stream Liquid Effluent Monitor Isolated During Radwaste Discharge.Caused by Operator Failure to Verify Proper Valve Alignment & Sample Flow.Foreman Relieved of Duties
05000237/LER-1987-001-01, :on 870102 & 0121,ultrasonic Testing Revealed Through Wall Indications on Pipe Welds PD5-D20 & 8-12.Caused by Igscc.Engineering Evaluation on Indications Performed1987-01-23023 January 1987
- on 870102 & 0121,ultrasonic Testing Revealed Through Wall Indications on Pipe Welds PD5-D20 & 8-12.Caused by Igscc.Engineering Evaluation on Indications Performed
05000249/LER-1986-022-06, :on 861222,one of Two Fuel Pool Floor Radiation Monitors on Side of Refuel Floor of Reactor Bldg Spuriously Spiked Causing Automatic Start of Standby Gas Treatment Sys. Caused by Failed Radiation Monitor1987-01-0909 January 1987
- on 861222,one of Two Fuel Pool Floor Radiation Monitors on Side of Refuel Floor of Reactor Bldg Spuriously Spiked Causing Automatic Start of Standby Gas Treatment Sys. Caused by Failed Radiation Monitor
05000237/LER-1986-029-04, :on 861213,standby Liquid Control Relief Valve a Found to Open at 1,510 Psi.Caused by Setpoint Drift. Relief Valve Setpoint Adjusted & Retested1987-01-0808 January 1987
- on 861213,standby Liquid Control Relief Valve a Found to Open at 1,510 Psi.Caused by Setpoint Drift. Relief Valve Setpoint Adjusted & Retested
05000237/LER-1986-030-04, :on 861214,MSIV 2-203-2B Leaked in Excess of Tech Spec 3.7.A.2.b Limit.Caused by Packing Leak on 2-203-2B Valve.Valve Repacked & Local Leak Test Successfully Performed1987-01-0606 January 1987
- on 861214,MSIV 2-203-2B Leaked in Excess of Tech Spec 3.7.A.2.b Limit.Caused by Packing Leak on 2-203-2B Valve.Valve Repacked & Local Leak Test Successfully Performed
05000249/LER-1986-025-05, :on 861211,reactor Scram Occurred During Cycle of Main Stop Valve (EIIS Code Ts).Caused by Closure of Three Main Stop Valves.Switch Replaced & Test Circuitry Operated as Required1987-01-0505 January 1987
- on 861211,reactor Scram Occurred During Cycle of Main Stop Valve (EIIS Code Ts).Caused by Closure of Three Main Stop Valves.Switch Replaced & Test Circuitry Operated as Required
05000237/LER-1986-028-04, :on 861208,Tech Specs for HPCI Area Temp Switches Exceeded.Caused by Instrument Setpoint Drift. Switches Recalibr to Trip Point Setting1986-12-31031 December 1986
- on 861208,Tech Specs for HPCI Area Temp Switches Exceeded.Caused by Instrument Setpoint Drift. Switches Recalibr to Trip Point Setting
05000237/LER-1986-027-04, :on 861130,during Surveillance 4400-1, Containment Cooling Svc Water Vault Floor Drain Level Switch 2-4941-8 Failed.Caused by Loss of Spring Tension Due to Normal Wear.Switch Repaired1986-12-30030 December 1986
- on 861130,during Surveillance 4400-1, Containment Cooling Svc Water Vault Floor Drain Level Switch 2-4941-8 Failed.Caused by Loss of Spring Tension Due to Normal Wear.Switch Repaired
05000237/LER-1986-026-02, :on 861129,primary Containment Deinerted More than 24 H Prior to Shutdown.Caused by Personnel Error.Shift Supervisors Notified & Shutdown Procedures Changed Re Deinerting Time Restriction1986-12-29029 December 1986
- on 861129,primary Containment Deinerted More than 24 H Prior to Shutdown.Caused by Personnel Error.Shift Supervisors Notified & Shutdown Procedures Changed Re Deinerting Time Restriction
05000237/LER-1986-009, :on 860401,seismic Evaluation of Control Room Panels for Mounting of Future Instrumentation Revealed Missing Mount Bolts.Caused by Initial Installation Deficiency.Bolts & Track Welds Installed1986-12-29029 December 1986
- on 860401,seismic Evaluation of Control Room Panels for Mounting of Future Instrumentation Revealed Missing Mount Bolts.Caused by Initial Installation Deficiency.Bolts & Track Welds Installed
05000249/LER-1986-023-05, :on 861201,Tech Spec Requirements for Reactor Coolant Sample Radioactivity Analysis Exceeded.Sample Not Analyzed Due to Miscommunication Between Radiation Chemistry Technician & Spectrometry Room Personnel1986-12-24024 December 1986
- on 861201,Tech Spec Requirements for Reactor Coolant Sample Radioactivity Analysis Exceeded.Sample Not Analyzed Due to Miscommunication Between Radiation Chemistry Technician & Spectrometry Room Personnel
05000249/LER-1986-024-05, :on 861205,unit Shutdown Commenced Due to Qualification Deficiency of Environmentally Qualified Cable Splices in Drywell Penetrations.Caused by Excessive Leakage Current.Qualified Tape Used to Repair Splices1986-12-22022 December 1986
- on 861205,unit Shutdown Commenced Due to Qualification Deficiency of Environmentally Qualified Cable Splices in Drywell Penetrations.Caused by Excessive Leakage Current.Qualified Tape Used to Repair Splices
05000237/LER-1986-025-04, :on 861122,grab Sample Not Connected to Chimney Effluent Sample Point.Caused by Personnel Error.Technician Involved Admonished.Comprehensive Training Planned for All Technicians to Review Tech Spec1986-12-18018 December 1986
- on 861122,grab Sample Not Connected to Chimney Effluent Sample Point.Caused by Personnel Error.Technician Involved Admonished.Comprehensive Training Planned for All Technicians to Review Tech Spec
05000237/LER-1986-024-04, :on 861117,main Chimney Separate Particulate Iodine & Noble Gas Sampler (Sping) Experienced Loss of Flow Condition.Caused by Water in Filters of Sping.Work Request D59639 Initiated1986-12-16016 December 1986
- on 861117,main Chimney Separate Particulate Iodine & Noble Gas Sampler (Sping) Experienced Loss of Flow Condition.Caused by Water in Filters of Sping.Work Request D59639 Initiated
05000249/LER-1986-020-05, :on 861113,isolation Condenser Containment Isolation Signal Received in Control Room.Cause Undetermined.Engineering Contacted,Test Instrumentation Installed & Analysis in Progress1986-12-12012 December 1986
- on 861113,isolation Condenser Containment Isolation Signal Received in Control Room.Cause Undetermined.Engineering Contacted,Test Instrumentation Installed & Analysis in Progress
05000249/LER-1986-019-06, :on 861113,scram Occurred Due to Two Simultaneous,Unrelated half-scrams.First half-scram Caused by Personnel Error.Second half-scram Caused by Dirty Connection in Circuit.Connection Cleaned1986-12-12012 December 1986
- on 861113,scram Occurred Due to Two Simultaneous,Unrelated half-scrams.First half-scram Caused by Personnel Error.Second half-scram Caused by Dirty Connection in Circuit.Connection Cleaned
05000249/LER-1986-021-06, :on 861110,w/unit in Run Mode,Reactor Scram Occurred Due to Loss of Control Air to Msivs.Caused by Mechanic Inadvertently Removing Power Lead.Mechanic Reprimanded & Tailgate Conducted1986-12-0909 December 1986
- on 861110,w/unit in Run Mode,Reactor Scram Occurred Due to Loss of Control Air to Msivs.Caused by Mechanic Inadvertently Removing Power Lead.Mechanic Reprimanded & Tailgate Conducted
05000249/LER-1986-018-06, :on 861014,Group V (Isolation Condenser) Containment Isolation Signal Received.Corrective Actions Will Be Considered When Cause Determined1986-11-13013 November 1986
- on 861014,Group V (Isolation Condenser) Containment Isolation Signal Received.Corrective Actions Will Be Considered When Cause Determined
05000249/LER-1986-012-02, :on 860902,reactor Manually Scrammed Due to Excessive Number of Accumulator Alarms Received Due to CRD Pump Trip.Caused by Failed Charging Water Isolation Valve 3-305-113.Valve Repaired & Scram Testing Procedure Revised1986-11-10010 November 1986
- on 860902,reactor Manually Scrammed Due to Excessive Number of Accumulator Alarms Received Due to CRD Pump Trip.Caused by Failed Charging Water Isolation Valve 3-305-113.Valve Repaired & Scram Testing Procedure Revised
05000249/LER-1986-017-07, :on 861014,Group I Isolated & Subsequent Reactor Scram Occurred.Caused When Contractor Inadvertently Jarred Msivs.Personnel Counseled1986-11-0303 November 1986
- on 861014,Group I Isolated & Subsequent Reactor Scram Occurred.Caused When Contractor Inadvertently Jarred Msivs.Personnel Counseled
05000249/LER-1986-016, :on 860927,full Reactor Scram Initiating Signal Received While Reversing Main Condenser Circulating Water Flow.Caused by Component Failure.Operability Restored. Valve Motors & Setscrews Inspected.Gears Safety Wired1986-10-27027 October 1986
- on 860927,full Reactor Scram Initiating Signal Received While Reversing Main Condenser Circulating Water Flow.Caused by Component Failure.Operability Restored. Valve Motors & Setscrews Inspected.Gears Safety Wired
05000249/LER-1986-016-07, :on 860927,full Reactor Scram Initiating Signal Received While Reversing Main Condenser Circulating Water Flow.Caused by Component Failure When Setscrews Holding Pinion Gear Vibrated Loose.Setscrew Tightened1986-10-21021 October 1986
- on 860927,full Reactor Scram Initiating Signal Received While Reversing Main Condenser Circulating Water Flow.Caused by Component Failure When Setscrews Holding Pinion Gear Vibrated Loose.Setscrew Tightened
05000237/LER-1986-022-01, :on 860901,fire Main Valve Position Not Verified on Schedule.Caused by Oversight by Operations Dept Personnel.Importance of Completing Surveillances as Scheduled Emphasized1986-10-0909 October 1986
- on 860901,fire Main Valve Position Not Verified on Schedule.Caused by Oversight by Operations Dept Personnel.Importance of Completing Surveillances as Scheduled Emphasized
05000237/LER-1986-023-04, :on 860920,reactor Bldg Ventilation Sys Isolated & Standby Gas Treatment Sys Initiated.Caused by Power Supply 2-1705-7B Failure Due to Defective Dial Component.Power Supply Replaced1986-10-0808 October 1986
- on 860920,reactor Bldg Ventilation Sys Isolated & Standby Gas Treatment Sys Initiated.Caused by Power Supply 2-1705-7B Failure Due to Defective Dial Component.Power Supply Replaced
05000249/LER-1986-015-07, :on 860924,determined That Quarterly Storage Battery Surveillance Not Performed During Required Interval. Caused by Personnel Error.Procedures Revised.Personnel Counseled1986-10-0707 October 1986
- on 860924,determined That Quarterly Storage Battery Surveillance Not Performed During Required Interval. Caused by Personnel Error.Procedures Revised.Personnel Counseled
05000237/LER-1986-022-04, :on 860918,fire Main Valve Position Not Verified Per Tech Spec 4.12.B.1.A.Caused by Personnel Oversight.Event Discussed During Monthly Shift Engineer Meeting1986-09-30030 September 1986
- on 860918,fire Main Valve Position Not Verified Per Tech Spec 4.12.B.1.A.Caused by Personnel Oversight.Event Discussed During Monthly Shift Engineer Meeting
05000249/LER-1986-012-07, :on 860902,reactor Manually Scrammed Due to Large Number of Accumulator Alarms.Caused by Trip of CRD Pump 3B on Low Suction Pressure.Backup Pump Out of Svc for Repair.Procedure Dts 300-1 Changed1986-09-30030 September 1986
- on 860902,reactor Manually Scrammed Due to Large Number of Accumulator Alarms.Caused by Trip of CRD Pump 3B on Low Suction Pressure.Backup Pump Out of Svc for Repair.Procedure Dts 300-1 Changed
05000249/LER-1986-013-07, :on 860827,unit Shutdown Due to Exceeding Limiting Conditions for Operations for Eccs.Caused by Failure of Valve 3-1402-4B.Valve Repaired.All ECCS Valve Operability Surveillances Will Be Performed1986-09-25025 September 1986
- on 860827,unit Shutdown Due to Exceeding Limiting Conditions for Operations for Eccs.Caused by Failure of Valve 3-1402-4B.Valve Repaired.All ECCS Valve Operability Surveillances Will Be Performed
05000249/LER-1986-014-07, :on 860826,during Operating Surveillance 2300-6, Monthly HPCI Sys Pump Test for Inservice Test Program, HPCI Gland Seal Leak Off Drain Failed to Adequately Drain HPCI Condenser Hotwell1986-09-24024 September 1986
- on 860826,during Operating Surveillance 2300-6, Monthly HPCI Sys Pump Test for Inservice Test Program, HPCI Gland Seal Leak Off Drain Failed to Adequately Drain HPCI Condenser Hotwell
05000237/LER-1986-020-03, :on 860827,small Bore Torus Attached Piping Supports Violated Allowable Limits Specified in NUREG-0661. Caused by Design Error.Pipe Supports Will Be Modified1986-09-24024 September 1986
- on 860827,small Bore Torus Attached Piping Supports Violated Allowable Limits Specified in NUREG-0661. Caused by Design Error.Pipe Supports Will Be Modified
05000237/LER-1986-021-04, :on 860828,Unit 2/3 Main Chimney Continuous Particulate & Iodine Sample Not Collected Per Tech Spec 3.2 (Table 3.2.5).Caused by Procedural Inadequacy.New Procedure Will Be Written1986-09-23023 September 1986
- on 860828,Unit 2/3 Main Chimney Continuous Particulate & Iodine Sample Not Collected Per Tech Spec 3.2 (Table 3.2.5).Caused by Procedural Inadequacy.New Procedure Will Be Written
05000249/LER-1986-011-07, :on 860817,fuse Blew During Voltage Reading of Open Position Indicating Limit Switch for Air Operated Valve Tripping Reactor Bldg Ventilation,Drywell Purge Fans & Sump Pumps.Caused by Personnel Error1986-09-16016 September 1986
- on 860817,fuse Blew During Voltage Reading of Open Position Indicating Limit Switch for Air Operated Valve Tripping Reactor Bldg Ventilation,Drywell Purge Fans & Sump Pumps.Caused by Personnel Error
05000237/LER-1986-019-04, :on 860811,while Reactor Operating at 91%,main Turbine Tripped on +55 Inches Reactor Water Level Which Resulted in Full Reactor Scram.Caused by Failure of Feedwater Regulating Valve a to Close1986-09-0909 September 1986
- on 860811,while Reactor Operating at 91%,main Turbine Tripped on +55 Inches Reactor Water Level Which Resulted in Full Reactor Scram.Caused by Failure of Feedwater Regulating Valve a to Close
05000237/LER-1986-015-05, :on 860805,reactor Bldg Ventilation Particulate Sampler Filter Found Broken When Radiation Chemistry Technician (RCT) Attempted to Remove Filter for Counting. Caused by Improper Installation by RCT1986-08-29029 August 1986
- on 860805,reactor Bldg Ventilation Particulate Sampler Filter Found Broken When Radiation Chemistry Technician (RCT) Attempted to Remove Filter for Counting. Caused by Improper Installation by RCT
05000249/LER-1986-010-08, :on 860713,auto Blowdown Sys I Tripped During Instrument Surveillance Logic Test.Caused by Instrument Setpoint Drift.Relays Recalibr1986-08-11011 August 1986
- on 860713,auto Blowdown Sys I Tripped During Instrument Surveillance Logic Test.Caused by Instrument Setpoint Drift.Relays Recalibr