05000309/LER-1997-009, :on 970519,identified Scenario That Could Be More Limiting than Design Basis High Energy Line Break in Turbine Bldg.Caused by Insufficient Detail in Documentation. Replaced Identified Components1997-06-18018 June 1997
- on 970519,identified Scenario That Could Be More Limiting than Design Basis High Energy Line Break in Turbine Bldg.Caused by Insufficient Detail in Documentation. Replaced Identified Components
05000309/LER-1997-010, :on 970509,discovered Defective Tubes in Steam Generators.Caused by Primary & Secondary Water Stress Corrosion,Pitting & Intergranular Attack.Examined Dented Egg Crate Supports & Plugged Detected Cracks1997-06-0909 June 1997
- on 970509,discovered Defective Tubes in Steam Generators.Caused by Primary & Secondary Water Stress Corrosion,Pitting & Intergranular Attack.Examined Dented Egg Crate Supports & Plugged Detected Cracks
05000309/LER-1997-008, :on 970411,IST Deficiencies That Affected Operability Were Discovered.Valves Were Not Considered Part of IST Program.Operability Determination & Initial Engineering Evaluations Performed1997-05-0909 May 1997
- on 970411,IST Deficiencies That Affected Operability Were Discovered.Valves Were Not Considered Part of IST Program.Operability Determination & Initial Engineering Evaluations Performed
05000309/LER-1997-007, :on 970313,no RPT on Site for Greater than Two Hours as Qualified Individual Left Site Due to Illness. Performed Root Cause Evaluation & Reviewed Previous Work Schedules Since 9701011997-04-14014 April 1997
- on 970313,no RPT on Site for Greater than Two Hours as Qualified Individual Left Site Due to Illness. Performed Root Cause Evaluation & Reviewed Previous Work Schedules Since 970101
05000309/LER-1996-043, :on 961227,GL 96-01 Identified Surveillance Issues Discovered.Evaluated All GL 96-01 Issues & Resolved &/Or Tested Prior to Plant Restart1997-04-0303 April 1997
- on 961227,GL 96-01 Identified Surveillance Issues Discovered.Evaluated All GL 96-01 Issues & Resolved &/Or Tested Prior to Plant Restart
05000309/LER-1997-006, :on 970226,propane Tank Improperly Stored Near Pump House Noted.Caused by Personnel Error Due to Lack of Training.Propane Tank Emptied1997-03-28028 March 1997
- on 970226,propane Tank Improperly Stored Near Pump House Noted.Caused by Personnel Error Due to Lack of Training.Propane Tank Emptied
05000309/LER-1997-005, :on 970218,potential Freezing Conditions in Circulating Water Pump House Occurred.Caused by Loss of Offsite Power.Heater Thermostats Have Been Set to Maintain Temperature in Cwph Above 60 F1997-03-20020 March 1997
- on 970218,potential Freezing Conditions in Circulating Water Pump House Occurred.Caused by Loss of Offsite Power.Heater Thermostats Have Been Set to Maintain Temperature in Cwph Above 60 F
05000309/LER-1997-004, :on 970122,discovered Containment Primary Component Cooling Piping Design Inadequacy Due to Lack of Thermal Relief Valves.Installed Relief Valve Protection.W/1997-02-24024 February 1997
- on 970122,discovered Containment Primary Component Cooling Piping Design Inadequacy Due to Lack of Thermal Relief Valves.Installed Relief Valve Protection.W/
05000309/LER-1997-003, :on 970117,leaking Fuel Pins Identified in Westinghouse Fuel.Caused by grid-pin Fretting at mid- Assembly Fuel Spacer Grids.Replaced All Installed Westinghouse Fuel Assemblies1997-02-18018 February 1997
- on 970117,leaking Fuel Pins Identified in Westinghouse Fuel.Caused by grid-pin Fretting at mid- Assembly Fuel Spacer Grids.Replaced All Installed Westinghouse Fuel Assemblies
05000309/LER-1997-002, :on 970110,PCC/SCC Vacuum Relief Valve Testing Occurred.Cause Not Determined.Valves Are Currently in Process of Being Replaced by New Vacuum Breaker Valves.New Valves Will Be Included in IST Program1997-02-10010 February 1997
- on 970110,PCC/SCC Vacuum Relief Valve Testing Occurred.Cause Not Determined.Valves Are Currently in Process of Being Replaced by New Vacuum Breaker Valves.New Valves Will Be Included in IST Program
05000309/LER-1996-042, :on 961219,discovered Lack of Thermal Relief Valves for Several Heat Exchangers.Caused by Subject Valves Not Being in Original Design of Plant.Implemented Administrative Controls1997-01-18018 January 1997
- on 961219,discovered Lack of Thermal Relief Valves for Several Heat Exchangers.Caused by Subject Valves Not Being in Original Design of Plant.Implemented Administrative Controls
05000309/LER-1996-041, :on 961213,pressurizer Pressure Instruments PT-102X,Y Calibrated Beyond Designed Range Affecting SMM & Pits Input.Caused by Inadequate Incertainty Calculation. Transmitters Replaced1997-01-13013 January 1997
- on 961213,pressurizer Pressure Instruments PT-102X,Y Calibrated Beyond Designed Range Affecting SMM & Pits Input.Caused by Inadequate Incertainty Calculation. Transmitters Replaced
05000309/LER-1996-040, :on 961208,inadequate Surveillance Procedure for Reactor Trip Breaker Actuation Identified.Surveillance Procedures 3-6.2.2.11 & 3-6.2.2.10 Revised for One Time Test1997-01-0707 January 1997
- on 961208,inadequate Surveillance Procedure for Reactor Trip Breaker Actuation Identified.Surveillance Procedures 3-6.2.2.11 & 3-6.2.2.10 Revised for One Time Test
05000309/LER-1996-039, :on 961207,both Diesel Generators Were Declared Inoperable & TS Remedial Action 3.12.A Entered.Caused by Oversight in Original Surveillance Procedure Development. Surveillance Procedures Modified1997-01-0606 January 1997
- on 961207,both Diesel Generators Were Declared Inoperable & TS Remedial Action 3.12.A Entered.Caused by Oversight in Original Surveillance Procedure Development. Surveillance Procedures Modified
05000309/LER-1996-038, :on 961205,discovered Cable Separation.Caused Indeterminate.Corrected Wiring Deficiencies Associated W/ Reactor Trip Breakers & Manual Trip Buttons1997-01-0606 January 1997
- on 961205,discovered Cable Separation.Caused Indeterminate.Corrected Wiring Deficiencies Associated W/ Reactor Trip Breakers & Manual Trip Buttons
05000309/LER-1996-037, :on 961114,leaking P-29C Gland Cooling Check Valve Was Observed.Caused by Sticking Check Valve in Gland Cooling Water Supply Line to Pump.Affected Check Valves Have Been Replaced1996-12-16016 December 1996
- on 961114,leaking P-29C Gland Cooling Check Valve Was Observed.Caused by Sticking Check Valve in Gland Cooling Water Supply Line to Pump.Affected Check Valves Have Been Replaced
05000309/LER-1996-036, :on 961031,fans Stopped in Order to Allow Filters to Be Aligned in Bypass Mode Using Procedure.Caused by Note Alerting Operations Personnel.Painting Activities in Spray Bldg Stopped1996-11-26026 November 1996
- on 961031,fans Stopped in Order to Allow Filters to Be Aligned in Bypass Mode Using Procedure.Caused by Note Alerting Operations Personnel.Painting Activities in Spray Bldg Stopped
05000309/LER-1996-034, :on 961025,inadequate Cable Separation for Post Accident Hydrogen Monitors Occurred.Caused by Less than Adequate Control of Cable Separation.Bendix Cable 1IT354 Was Disabled by Lifting Leads at Both Ends1996-11-25025 November 1996
- on 961025,inadequate Cable Separation for Post Accident Hydrogen Monitors Occurred.Caused by Less than Adequate Control of Cable Separation.Bendix Cable 1IT354 Was Disabled by Lifting Leads at Both Ends
05000309/LER-1996-035, :on 961018,requirement for Post Accident Iodine Sampling Inadvertently Removed from Procedure.Caused by Inadequate Control of Licensing Commitment.Procedure 9-304-1 Was Corrected1996-11-18018 November 1996
- on 961018,requirement for Post Accident Iodine Sampling Inadvertently Removed from Procedure.Caused by Inadequate Control of Licensing Commitment.Procedure 9-304-1 Was Corrected
05000309/LER-1996-032, :on 961016,NNS Load Connected to 1E Power Source Without an Isolation Device Identified.Cause Unknown. TV-4001 Part of Circuit Isolated by Opening Slide Links in Mcb & Controlling Slide Links W/Tag Order1996-11-15015 November 1996
- on 961016,NNS Load Connected to 1E Power Source Without an Isolation Device Identified.Cause Unknown. TV-4001 Part of Circuit Isolated by Opening Slide Links in Mcb & Controlling Slide Links W/Tag Order
05000309/LER-1996-031, :on 961009,plant Trip During Reactor Protection Sys Surveillance Occurred.Cause Has Not Been Determined.Ac Logic Matrix Components Were Undergoing Testing at Time of Trip Were Replaced1996-11-0808 November 1996
- on 961009,plant Trip During Reactor Protection Sys Surveillance Occurred.Cause Has Not Been Determined.Ac Logic Matrix Components Were Undergoing Testing at Time of Trip Were Replaced
05000309/LER-1996-030, :on 960926,identified Incorrect Acceptance Criteria Specified for Containment Ventilation/Purge Sys Filter Surveillances.Caused by Cognitive Error.Specified Required Acceptance Criteria1996-10-25025 October 1996
- on 960926,identified Incorrect Acceptance Criteria Specified for Containment Ventilation/Purge Sys Filter Surveillances.Caused by Cognitive Error.Specified Required Acceptance Criteria
05000309/LER-1996-026, :on 960724,discovered EQ of Cables/Connectors Inside CTMT May Not Meet Requirements for Submergence During Dba.Caused by Cognitive Errors on Part of Engineering Personnel.Eq Items Declared Inoperable1996-10-16016 October 1996
- on 960724,discovered EQ of Cables/Connectors Inside CTMT May Not Meet Requirements for Submergence During Dba.Caused by Cognitive Errors on Part of Engineering Personnel.Eq Items Declared Inoperable
05000309/LER-1993-023, :on 931202,found Pcc/Scc Outside Design Basis Due to Continuous Venting Through Nns Piping.No Corrective Actions Listed at This Time1994-01-0303 January 1994
- on 931202,found Pcc/Scc Outside Design Basis Due to Continuous Venting Through Nns Piping.No Corrective Actions Listed at This Time
05000309/LER-1993-022, :on 931110,both Trains of Control Room Ventilation Declared Inoperable Due to Preventative Maint. Consequences of Event,Which Occurs Semiannually,Is Minimal Since Loss of Trains Less than 1 H1993-12-10010 December 1993
- on 931110,both Trains of Control Room Ventilation Declared Inoperable Due to Preventative Maint. Consequences of Event,Which Occurs Semiannually,Is Minimal Since Loss of Trains Less than 1 H
05000309/LER-1993-021, :on 931104,CEA Position Deviation Alarms Disabled.Rod Position Sensing Sys Cards Removed for Troubleshooting During Refueling Outage on 931001.Cards Reinserted & Alarm Functions Restored1993-12-0404 December 1993
- on 931104,CEA Position Deviation Alarms Disabled.Rod Position Sensing Sys Cards Removed for Troubleshooting During Refueling Outage on 931001.Cards Reinserted & Alarm Functions Restored
05000309/LER-1993-020, :on 931012,deviation from TS Requirements for Entry Into Power Operation Condition 7 Noted.Caused by Failure to Recognize Plant Procedure as Stated.Procedures Revised1993-11-15015 November 1993
- on 931012,deviation from TS Requirements for Entry Into Power Operation Condition 7 Noted.Caused by Failure to Recognize Plant Procedure as Stated.Procedures Revised
05000309/LER-1993-019, :on 930928,determined That One of Four Available Swps Did Not Deliver Sufficient Flow Capacity to Meet Design Basis.Cause of Pump Degradation Will Be Determined from Overhauled Results1993-10-28028 October 1993
- on 930928,determined That One of Four Available Swps Did Not Deliver Sufficient Flow Capacity to Meet Design Basis.Cause of Pump Degradation Will Be Determined from Overhauled Results
05000309/LER-1993-018, :on 930903,discovered Seven Defective Tubes in Number 3 Sg.Caused by General Corrosion Due to Contaminants & Stresses.All Defective Tubes Plugged During 1993 Refueling Outage1993-10-0303 October 1993
- on 930903,discovered Seven Defective Tubes in Number 3 Sg.Caused by General Corrosion Due to Contaminants & Stresses.All Defective Tubes Plugged During 1993 Refueling Outage
05000309/LER-1993-017, :on 930815,discovered EDG Sensing Relay Wiring Discrepancy Due to Plants Original Design.Implemented Mod to Design1993-09-20020 September 1993
- on 930815,discovered EDG Sensing Relay Wiring Discrepancy Due to Plants Original Design.Implemented Mod to Design
05000309/LER-1993-016, :on 930804,multiple 480 Volt Breaker Trips Occurred Due to RMS-9 Device Not Being Actuated.Installed RMS-9 Devices in All AK-25 Breakers1993-09-0606 September 1993
- on 930804,multiple 480 Volt Breaker Trips Occurred Due to RMS-9 Device Not Being Actuated.Installed RMS-9 Devices in All AK-25 Breakers
05000309/LER-1993-014, :on 930701,inoperable ECCS During Pump Recirculation Valve Stroke Test Due to Failure of Original TS License Submittal & Current Regulatory Positions. Changed Frequency of Valve Test1993-08-0101 August 1993
- on 930701,inoperable ECCS During Pump Recirculation Valve Stroke Test Due to Failure of Original TS License Submittal & Current Regulatory Positions. Changed Frequency of Valve Test
05000309/LER-1993-013, :on 930618,incorrect Compensatory Action Taken for Inoperable Fire Hose Station.Caused by Personnel Error. Fire Hose Rerouted to Operable Station1993-07-18018 July 1993
- on 930618,incorrect Compensatory Action Taken for Inoperable Fire Hose Station.Caused by Personnel Error. Fire Hose Rerouted to Operable Station
05000309/LER-1993-015, :on 930716,ECCS Valves Found Unlocked.Caused by Result of Design Final Phase of Comprehensive Review Detailing ECCS Design Requirements for Proper Alignment. Valves Locked & Controlling Procedures Revised1993-07-16016 July 1993
- on 930716,ECCS Valves Found Unlocked.Caused by Result of Design Final Phase of Comprehensive Review Detailing ECCS Design Requirements for Proper Alignment. Valves Locked & Controlling Procedures Revised
05000309/LER-1993-012, :on 930527,both Trains of CR Ventilation Declared Inoperable as Result of Preventative Maint.Event Occurs Quarterly & Consequence Minimal Since Loss of Both Trains Short Duration (Less than 1 H)1993-06-27027 June 1993
- on 930527,both Trains of CR Ventilation Declared Inoperable as Result of Preventative Maint.Event Occurs Quarterly & Consequence Minimal Since Loss of Both Trains Short Duration (Less than 1 H)
05000309/LER-1993-011, :on 930525,integrity of Inner Door of Containment Hatch Compromised.On 930526,hatch Outer Door Opened for Maint on Inner Door & TS 3.0.A.2 Entered.Caused by Failure of O-ring to Seal Uniformly & Lubricant Buildup1993-06-26026 June 1993
- on 930525,integrity of Inner Door of Containment Hatch Compromised.On 930526,hatch Outer Door Opened for Maint on Inner Door & TS 3.0.A.2 Entered.Caused by Failure of O-ring to Seal Uniformly & Lubricant Buildup
05000309/LER-1993-008, :on 930415,ECCS Valves Found Unlocked.Caused by Oversight in Procedure Controls Due to Misunderstanding of Lube Water Supply Requirements for Svc Water Pump Operability.Controlling Procedures Revised1993-05-17017 May 1993
- on 930415,ECCS Valves Found Unlocked.Caused by Oversight in Procedure Controls Due to Misunderstanding of Lube Water Supply Requirements for Svc Water Pump Operability.Controlling Procedures Revised
05000309/LER-1993-009, :on 921116,review of Rept Determined That ECCS Temporarily Disabled During Valve Stroke Testing.On 921202, Determined That Valves SIA-M-53 & SIA-M-54 Inoperable.Valve Stroke Testing Frequency Changed to Quarterly1993-05-0808 May 1993
- on 921116,review of Rept Determined That ECCS Temporarily Disabled During Valve Stroke Testing.On 921202, Determined That Valves SIA-M-53 & SIA-M-54 Inoperable.Valve Stroke Testing Frequency Changed to Quarterly
05000309/LER-1993-010, :on 930408,determined That Surveillance Testing of ECCS Subcomponents Causes Inoperable ECCS Subsys.Caused by Failure of Original TS License Submittal to Recognize Impact of Testing ECCS Subcomponents1993-05-0606 May 1993
- on 930408,determined That Surveillance Testing of ECCS Subcomponents Causes Inoperable ECCS Subsys.Caused by Failure of Original TS License Submittal to Recognize Impact of Testing ECCS Subcomponents
05000309/LER-1993-007, :on 930315,determined That Automatic Diverse Scram Sys Had Been Inoperable Since 930314.Caused by Transient within Innsdacs.Inputs Were re-enabled & Diverse Scram Sys Returned to Operable Status1993-04-13013 April 1993
- on 930315,determined That Automatic Diverse Scram Sys Had Been Inoperable Since 930314.Caused by Transient within Innsdacs.Inputs Were re-enabled & Diverse Scram Sys Returned to Operable Status
05000309/LER-1993-006, :on 930222,defective Cutoff Switch Actuator (Paddle) Detected on Reactor Trip Circuit Breaker 10.Faulty Switch on Breaker Replaced & Trip Breaker Tested Successfully1993-04-0909 April 1993
- on 930222,defective Cutoff Switch Actuator (Paddle) Detected on Reactor Trip Circuit Breaker 10.Faulty Switch on Breaker Replaced & Trip Breaker Tested Successfully
05000309/LER-1993-004, :on 930308,upper Level Spray Pump Bldg Fire Door Became Inoperable Due to Personnel Error.Heating Ventilation Unit HV-7 Returned to Svc.Precautions Will Be Placed in Ventilation Procedures1993-04-0707 April 1993
- on 930308,upper Level Spray Pump Bldg Fire Door Became Inoperable Due to Personnel Error.Heating Ventilation Unit HV-7 Returned to Svc.Precautions Will Be Placed in Ventilation Procedures
05000309/LER-1993-005, :on 930308,NRC Inspector Notified CR That Five Manual Valves Necessary to Assure Emergency & Auxiliary Feedwater Flow to Sgs.Caused by Procedural Deficiency.Valves Locked & Controlling Procedure Revised1993-04-0505 April 1993
- on 930308,NRC Inspector Notified CR That Five Manual Valves Necessary to Assure Emergency & Auxiliary Feedwater Flow to Sgs.Caused by Procedural Deficiency.Valves Locked & Controlling Procedure Revised
05000309/LER-1993-003, :on 930211,two Dc Solenoid Pilot Valves Exceeded Environ Qualification Svc Life & Declared Inoperable.Caused by Misidentification of Solenoids.Valves Replaced & EQ Program Updated1993-03-12012 March 1993
- on 930211,two Dc Solenoid Pilot Valves Exceeded Environ Qualification Svc Life & Declared Inoperable.Caused by Misidentification of Solenoids.Valves Replaced & EQ Program Updated
05000309/LER-1993-002, :on 930121,control Room Ventilation Trains Declared Inoperable Due to Preventive Maint.Consequences of Event Which Will Occurred Quarterly,Minimal Since Loss of Trains Short Duration (Less than 1 H)1993-02-19019 February 1993
- on 930121,control Room Ventilation Trains Declared Inoperable Due to Preventive Maint.Consequences of Event Which Will Occurred Quarterly,Minimal Since Loss of Trains Short Duration (Less than 1 H)
05000309/LER-1993-001, :on 921202,determined That,For Brief Period of Time,Both Trains of ECCS LPSI & Containment Spray Subsystems Inoperable.Caused by Erroneous Original TS License Submittal.Valve Stroke Test Frequency Changed1993-01-21021 January 1993
- on 921202,determined That,For Brief Period of Time,Both Trains of ECCS LPSI & Containment Spray Subsystems Inoperable.Caused by Erroneous Original TS License Submittal.Valve Stroke Test Frequency Changed
05000309/LER-1992-012, :on 921116,temporary Disabling of ECCS Occurred.Caused by Failure of Original TS License Submittal to Allow for Surveillance Testing of minimum-flow Recirculation Valves.Valve Stroke Changed1992-12-21021 December 1992
- on 921116,temporary Disabling of ECCS Occurred.Caused by Failure of Original TS License Submittal to Allow for Surveillance Testing of minimum-flow Recirculation Valves.Valve Stroke Changed
05000309/LER-1992-013, :on 920314,discovered through-wall Erosion of Some Feed Ring J-tubes & Moisture Separator Cans.Caused by single-phase erosion-corrosion of J-tubes & Separator Cans. Operating Ph Increased & Sheets Inspected1992-12-21021 December 1992
- on 920314,discovered through-wall Erosion of Some Feed Ring J-tubes & Moisture Separator Cans.Caused by single-phase erosion-corrosion of J-tubes & Separator Cans. Operating Ph Increased & Sheets Inspected
05000309/LER-1991-004, :on 910220,determined That Wiring Separation Discrepancy Existed in Emergency Feedwater Pump Control Circuit & One Train Declared Inoperable.Caused by Lack of Physical Separation.Wiring Rearranged1991-03-22022 March 1991
- on 910220,determined That Wiring Separation Discrepancy Existed in Emergency Feedwater Pump Control Circuit & One Train Declared Inoperable.Caused by Lack of Physical Separation.Wiring Rearranged
05000309/LER-1991-002, :on 910130,loading of Emergency Diesel Generators Found Not to Reflect Expected Kvar Loads During Monthly Test.Generators Tested at Max Kva Load W/Acceptable Results1991-03-0606 March 1991
- on 910130,loading of Emergency Diesel Generators Found Not to Reflect Expected Kvar Loads During Monthly Test.Generators Tested at Max Kva Load W/Acceptable Results