05000305/LER-1998-003, :on 980203,RCS Low Flow Trip Logic Were Identified as Not Been Tested IAW Tss.Caused by Personnel Error.Testing Was Conducted IAW Requirements of Section 4 of TS1998-03-0505 March 1998
- on 980203,RCS Low Flow Trip Logic Were Identified as Not Been Tested IAW Tss.Caused by Personnel Error.Testing Was Conducted IAW Requirements of Section 4 of TS
05000305/LER-1996-007, :on 961023,identified Design Deficiency in Containment Isolation Function.Caused by Oversight During Plant Design.Implemented Administrative Controls to Preclude Subject Condition Prior to Plant start-up1996-11-22022 November 1996
- on 961023,identified Design Deficiency in Containment Isolation Function.Caused by Oversight During Plant Design.Implemented Administrative Controls to Preclude Subject Condition Prior to Plant start-up
05000305/LER-1995-003, :on 950516,failed to Adequately Assess Consequences During Recovery from Switch Misposition Resulted in Turbine/Rt.Reminded Nco of Importance of Self Checking1995-06-14014 June 1995
- on 950516,failed to Adequately Assess Consequences During Recovery from Switch Misposition Resulted in Turbine/Rt.Reminded Nco of Importance of Self Checking
05000305/LER-1990-005, :on 900404,intergranular Attack & IGSCC Results in Both Steam Generators a & B Being Categorized as C-3.All Defective Tubes Plugged & Sludge Lancing & Crevice Flushing Conducted1990-05-0404 May 1990
- on 900404,intergranular Attack & IGSCC Results in Both Steam Generators a & B Being Categorized as C-3.All Defective Tubes Plugged & Sludge Lancing & Crevice Flushing Conducted
05000305/LER-1989-009, :on 890401,during Repositioning of Ventilation Dampers,Jumper Inadvertently Detached from Terminal Block Contact,Causing Damper Actuation.Caused by Procedural Inadequacies.Weidmuller Blocks Installed1989-05-0101 May 1989
- on 890401,during Repositioning of Ventilation Dampers,Jumper Inadvertently Detached from Terminal Block Contact,Causing Damper Actuation.Caused by Procedural Inadequacies.Weidmuller Blocks Installed
05000305/LER-1989-006, :on 890315,audit Identified Failure to Implement Tech Spec Re Testing of Fan Coil Emergency Discharge Dampers & Backfit Dampers.Caused by Procedural Inadequacy.Procedure Updated1989-04-14014 April 1989
- on 890315,audit Identified Failure to Implement Tech Spec Re Testing of Fan Coil Emergency Discharge Dampers & Backfit Dampers.Caused by Procedural Inadequacy.Procedure Updated
05000305/LER-1989-005, :on 890310,insp of Diesel Generator Start Up Air Sys Finds Deficiencies That Could Render Both Diesel Generators Inoperable Due to Inadequate Design.Cause Unknown.Generic Implications Will Be Examined1989-04-10010 April 1989
- on 890310,insp of Diesel Generator Start Up Air Sys Finds Deficiencies That Could Render Both Diesel Generators Inoperable Due to Inadequate Design.Cause Unknown.Generic Implications Will Be Examined
05000305/LER-1987-002, :on 870224,reactor Tripped When Source Range Nuclear Flux Detectors 1 & 2 Erroneously Reached Nominal Reactor Trip Setpoint of 1.0E05 Counts/S.Caused by Seepage of Borated Refueling Water Into Instrument1987-03-26026 March 1987
- on 870224,reactor Tripped When Source Range Nuclear Flux Detectors 1 & 2 Erroneously Reached Nominal Reactor Trip Setpoint of 1.0E05 Counts/S.Caused by Seepage of Borated Refueling Water Into Instrument
05000305/LER-1987-001, :on 870223 & 24,series of High Radiation Alarms Received in Control Room.Caused by Primary to Secondary Leak in Steam Generator 1A.Results of Eddy Current Testing Will Be Submitted1987-03-25025 March 1987
- on 870223 & 24,series of High Radiation Alarms Received in Control Room.Caused by Primary to Secondary Leak in Steam Generator 1A.Results of Eddy Current Testing Will Be Submitted
05000305/LER-1985-015, :on 850617,Fluor Engineers,Inc Notified Util of Inadequate Documentation to Support Seismic Qualification of Diesel Generator Differential Relays.Relays Replaced W/Ge Seismically Qualified Relays on 870120 & 211987-03-0606 March 1987
- on 850617,Fluor Engineers,Inc Notified Util of Inadequate Documentation to Support Seismic Qualification of Diesel Generator Differential Relays.Relays Replaced W/Ge Seismically Qualified Relays on 870120 & 21
05000305/LER-1986-015, :on 861229,svc Water Inlet Valve for Radiation Monitor R-16 Found Closed.Caused by Personnel Error.Sight Flow Meter Cleaned & Operating Procedure Used to Perform Flushing Process Reviewed1987-01-28028 January 1987
- on 861229,svc Water Inlet Valve for Radiation Monitor R-16 Found Closed.Caused by Personnel Error.Sight Flow Meter Cleaned & Operating Procedure Used to Perform Flushing Process Reviewed
05000305/LER-1986-014, :on 861202,during Full Power,Boric Acid Transfer Pumps Inoperable.Caused by Burned Off Section of Heat Tape Around Pump Casing.Insulation on Pump Replaced & Extended to Cover Mechanical Seal & Casing1986-12-31031 December 1986
- on 861202,during Full Power,Boric Acid Transfer Pumps Inoperable.Caused by Burned Off Section of Heat Tape Around Pump Casing.Insulation on Pump Replaced & Extended to Cover Mechanical Seal & Casing
05000305/LER-1986-013, :on 861030,gate to Waste Metering Tank Room, Posted as High Contamination & Radiation Hazard Area, Discovered Unlocked & Open.Caused by Personnel Error.Survey of Area Performed & Procedures Revised1986-11-26026 November 1986
- on 861030,gate to Waste Metering Tank Room, Posted as High Contamination & Radiation Hazard Area, Discovered Unlocked & Open.Caused by Personnel Error.Survey of Area Performed & Procedures Revised
05000305/LER-1986-012, :on 860926,auxiliary Bldg Vent Stack Radiation Monitor Indications Elevated Due to Radioactive Ar-41 Gas & on 861006,zone Special Ventilation Sys Automatically Started on High Radiation Signal Due to Low Setpoints1986-10-24024 October 1986
- on 860926,auxiliary Bldg Vent Stack Radiation Monitor Indications Elevated Due to Radioactive Ar-41 Gas & on 861006,zone Special Ventilation Sys Automatically Started on High Radiation Signal Due to Low Setpoints
05000305/LER-1984-006, :on 840416,containment Isolation Valves Found W/Excessive Leakage Rates Due to Degraded Seal Ring Gaskets. Repairs Performed on Inboard Valves & Design Change Implemented to Relocate Valves1986-09-23023 September 1986
- on 840416,containment Isolation Valves Found W/Excessive Leakage Rates Due to Degraded Seal Ring Gaskets. Repairs Performed on Inboard Valves & Design Change Implemented to Relocate Valves
05000305/LER-1986-011, :on 860811,during Performance of Monthly Fire Pump Flow Test,Both Fire Pumps Simultaneously Out of Svc for Approx 10 S.Caused by Personnel Failure to Follow Procedure.Personnel Counseled1986-09-10010 September 1986
- on 860811,during Performance of Monthly Fire Pump Flow Test,Both Fire Pumps Simultaneously Out of Svc for Approx 10 S.Caused by Personnel Failure to Follow Procedure.Personnel Counseled
05000305/LER-1986-010, :on 860801,ESF Actuation Occurred Due to Electrical Jumper Shorting to Ground.Caused by Low Profile Design of Connecting Screws on Terminal Strip.Banana Jacks Added Where Jumpers Used1986-08-28028 August 1986
- on 860801,ESF Actuation Occurred Due to Electrical Jumper Shorting to Ground.Caused by Low Profile Design of Connecting Screws on Terminal Strip.Banana Jacks Added Where Jumpers Used
05000305/LER-1986-008, :on 860513,reactor/turbine Trip Occurred During Performance of Surveillance Procedure on power-range Nuclear Instrumentation.Caused by Personnel Error.Labeling of Instrumentation Upgraded1986-06-12012 June 1986
- on 860513,reactor/turbine Trip Occurred During Performance of Surveillance Procedure on power-range Nuclear Instrumentation.Caused by Personnel Error.Labeling of Instrumentation Upgraded
05000305/LER-1986-007, :on 860424,reactor Tripped Due to Low Steam Generator Level Coincident W/Steam & Feedwater Flow Mismatch.Caused by Defective Main Feedwater Control Valve. Valve Stroked & Cycled Until Operable1986-05-23023 May 1986
- on 860424,reactor Tripped Due to Low Steam Generator Level Coincident W/Steam & Feedwater Flow Mismatch.Caused by Defective Main Feedwater Control Valve. Valve Stroked & Cycled Until Operable
05000305/LER-1986-006, :on 860420,turbine Trip & Reactor Trip Occurred.Caused by Main Feedwater Control Valve Sticking. Valve Inspected,Adjusted & Cycled to Verify Operability Prior to Restart1986-05-20020 May 1986
- on 860420,turbine Trip & Reactor Trip Occurred.Caused by Main Feedwater Control Valve Sticking. Valve Inspected,Adjusted & Cycled to Verify Operability Prior to Restart
05000305/LER-1986-005, :on 860417,reactor Trip Occurred During Performance of Work Request on Intermediate-Range Nuclear Channel N35.Caused by Premature Removal of Control Power Fuse1986-05-16016 May 1986
- on 860417,reactor Trip Occurred During Performance of Work Request on Intermediate-Range Nuclear Channel N35.Caused by Premature Removal of Control Power Fuse
05000305/LER-1986-004, :on 860401,nonspring-assisted Fire Dampers Mechanically Bound in Intermediate Position.Caused by Not Testing Dampers.Testing of Dampers Continuing & Damper Design Changes Initiated1986-05-14014 May 1986
- on 860401,nonspring-assisted Fire Dampers Mechanically Bound in Intermediate Position.Caused by Not Testing Dampers.Testing of Dampers Continuing & Damper Design Changes Initiated
05000305/LER-1986-003, :on 860326,potential Problem Found w/long-term Reliability of Both Backup Emergency Ac Diesel Generators. Caused by Numerous Fast Starts of Diesel Generator W/O Full Main Lube Oil Pressure1986-04-25025 April 1986
- on 860326,potential Problem Found w/long-term Reliability of Both Backup Emergency Ac Diesel Generators. Caused by Numerous Fast Starts of Diesel Generator W/O Full Main Lube Oil Pressure
05000000/LER-1986-005-03, Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points1986-04-25025 April 1986
Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points
05000305/LER-1986-002, :on 860318,local Leak Rate Test Results Exceeded Tech Spec Limit.Caused by Degraded Component Performance at Three Penetrations.Valves Lapped,Repacked & Satisfactorily Retested1986-04-17017 April 1986
- on 860318,local Leak Rate Test Results Exceeded Tech Spec Limit.Caused by Degraded Component Performance at Three Penetrations.Valves Lapped,Repacked & Satisfactorily Retested
05000305/LER-1986-001, :on 860211,review of Retest Requirements Re Solenoid Valve Replacement Revealed Valve Timing Test Not Performed During 1985.Caused by Erroneous Deletion from Procedures.Test Performed1986-03-13013 March 1986
- on 860211,review of Retest Requirements Re Solenoid Valve Replacement Revealed Valve Timing Test Not Performed During 1985.Caused by Erroneous Deletion from Procedures.Test Performed
05000305/LER-1985-023, :on 851212,loss of Power to Instrument Bus I Occurred.Caused by Failure of Constant Voltage Transformer. Constant Voltage Transformer Replaced & Instrument Bus Returned to Normal Power Supply1986-01-10010 January 1986
- on 851212,loss of Power to Instrument Bus I Occurred.Caused by Failure of Constant Voltage Transformer. Constant Voltage Transformer Replaced & Instrument Bus Returned to Normal Power Supply
05000305/LER-1985-022, :on 851203,discovered That Surveillance Procedure Sp 48-046,conducted on 851127,performed Outside of Required Time Interval.Caused by Calibr of Nuclear Instrumentation Due to 851113 Trip1986-01-0202 January 1986
- on 851203,discovered That Surveillance Procedure Sp 48-046,conducted on 851127,performed Outside of Required Time Interval.Caused by Calibr of Nuclear Instrumentation Due to 851113 Trip
05000305/LER-1985-021, :on 851114,high Flux Shutdown Bistable Trip Value Recorded in Place of High Flux Level Trip Setpoint on Both Source Range Channels.Caused by Personnel Error. Individuals Counseled on Procedure Performance1985-12-26026 December 1985
- on 851114,high Flux Shutdown Bistable Trip Value Recorded in Place of High Flux Level Trip Setpoint on Both Source Range Channels.Caused by Personnel Error. Individuals Counseled on Procedure Performance
05000305/LER-1985-020, :on 851113,failure of Train a Main Feedwater Control Valve Caused lo-lo Water Level in Steam Generator 1A & Reactor Trip.Caused by Two of Four Cap Screws Holding Valve Actuator to Yoke Shearing1985-12-13013 December 1985
- on 851113,failure of Train a Main Feedwater Control Valve Caused lo-lo Water Level in Steam Generator 1A & Reactor Trip.Caused by Two of Four Cap Screws Holding Valve Actuator to Yoke Shearing
05000305/LER-1985-019, :on 851107,at 100% Power,Test of Undervoltage Trip Attachment Conducted for Each Reactor Trip Breaker to Verify Existence of 20 Oz of Force Margin,Per IE Bulletin 85-002.Two Breakers Failed1985-12-0606 December 1985
- on 851107,at 100% Power,Test of Undervoltage Trip Attachment Conducted for Each Reactor Trip Breaker to Verify Existence of 20 Oz of Force Margin,Per IE Bulletin 85-002.Two Breakers Failed
05000305/LER-1985-018, :on 850820,discovered That Fire Hose Insp Required by Tech Spec 4.15.2 Performed Outside Required 18-month (Plus or Minus 25%) Time Interval.Caused by Mgt Oversight When Procedure Modified1985-09-19019 September 1985
- on 850820,discovered That Fire Hose Insp Required by Tech Spec 4.15.2 Performed Outside Required 18-month (Plus or Minus 25%) Time Interval.Caused by Mgt Oversight When Procedure Modified
05000305/LER-1985-017, :on 850808,reactor Tripped Manually to Isolate Ruptured Excess Steam Vent Line.Caused by Carbon Steel Piping Erosion.Ruptured Vent Lines Replaced.Program Implemented to Examine Steam Line Piping1985-09-0606 September 1985
- on 850808,reactor Tripped Manually to Isolate Ruptured Excess Steam Vent Line.Caused by Carbon Steel Piping Erosion.Ruptured Vent Lines Replaced.Program Implemented to Examine Steam Line Piping
05000305/LER-1985-016, :on 850725,control Operator Observed That Position Indication for Containment Isolation Valves & Steam Exclusion Dampers Changed Position.Caused by Power Interruption & Loss of Sys Redundancy1985-08-26026 August 1985
- on 850725,control Operator Observed That Position Indication for Containment Isolation Valves & Steam Exclusion Dampers Changed Position.Caused by Power Interruption & Loss of Sys Redundancy
05000305/LER-1985-015, :on 850617,Fluor Engineers Notified Util That Seismic Qualification of Emergency Diesel Generator Differential Relays Could Not Be Conclusively Determined. Resolution Under Review1985-07-17017 July 1985
- on 850617,Fluor Engineers Notified Util That Seismic Qualification of Emergency Diesel Generator Differential Relays Could Not Be Conclusively Determined. Resolution Under Review
05000305/LER-1985-014, :on 850615,concrete Block Preventing Access to Spent Resin Storage Tank Room Found Removed.Caused by Design Change & Maint Work on Tank.Requirements for Securing High Radiation Areas Discussed1985-07-15015 July 1985
- on 850615,concrete Block Preventing Access to Spent Resin Storage Tank Room Found Removed.Caused by Design Change & Maint Work on Tank.Requirements for Securing High Radiation Areas Discussed
05000305/LER-1985-013, :on 850404 & 0505,heat Tracing Circuit on Suction Line to Containment Hydrogen Analyzer 1A Discovered Inoperable.Caused by Failed Amphenol Connector.Spare Parts Ordered & Failed Connector Bypassed1985-06-12012 June 1985
- on 850404 & 0505,heat Tracing Circuit on Suction Line to Containment Hydrogen Analyzer 1A Discovered Inoperable.Caused by Failed Amphenol Connector.Spare Parts Ordered & Failed Connector Bypassed
05000305/LER-1985-012, :on 850410,reactor Tripped.Caused by Differences in Ground Potential Between Ni & Test Equipment. Purchase of New Portable Picoammeter Being Considered1985-05-10010 May 1985
- on 850410,reactor Tripped.Caused by Differences in Ground Potential Between Ni & Test Equipment. Purchase of New Portable Picoammeter Being Considered
05000305/LER-1985-011, :on 850407,auxiliary Bldg Special Ventilation Sys Actuated from Steam Exclusion Signal.Caused by Steam Issuing Through Blown Rupture Disk on Boric Acid Evaporator Condenser.Ventilation Sys Reset1985-05-0707 May 1985
- on 850407,auxiliary Bldg Special Ventilation Sys Actuated from Steam Exclusion Signal.Caused by Steam Issuing Through Blown Rupture Disk on Boric Acid Evaporator Condenser.Ventilation Sys Reset
05000305/LER-1985-010, :on 850405,reactor Trip Occurred Due to Steam Flow Greater than Feed Flow Signal Coincident W/Lo Steam Generator Level Signal.Caused by One Feed Flow & One Steam Low Transmitter Out of Calibr1985-05-0303 May 1985
- on 850405,reactor Trip Occurred Due to Steam Flow Greater than Feed Flow Signal Coincident W/Lo Steam Generator Level Signal.Caused by One Feed Flow & One Steam Low Transmitter Out of Calibr
05000305/LER-1984-018, :on 840928,investigation of Fan Coil Units W/Less than Design Air Flow Revealed Svc Water Side of Cooling Coils Partially Plugged W/Silt.Caused by Equipment Deficiencies.Fan Coil Units Cleaned1985-04-17017 April 1985
- on 840928,investigation of Fan Coil Units W/Less than Design Air Flow Revealed Svc Water Side of Cooling Coils Partially Plugged W/Silt.Caused by Equipment Deficiencies.Fan Coil Units Cleaned
05000305/LER-1985-007, :on 850225,w/red Pressurizer Channel Tripped & White Channel Calibr,Safety Injection Signal Occurred. Caused by Technician Requesting Wrong Channel Be Tripped. Surveillance Procedure Revised1985-03-27027 March 1985
- on 850225,w/red Pressurizer Channel Tripped & White Channel Calibr,Safety Injection Signal Occurred. Caused by Technician Requesting Wrong Channel Be Tripped. Surveillance Procedure Revised
05000305/LER-1985-008, :on 850225,alarm 47001-34 for Condenser Low Vacuum Turbine Trip,Cleared & Alarmed Again & Both Diesel Generators Started.Caused by Maint to Turbine Trip Mechanism.Start Signal Will Be Removed1985-03-27027 March 1985
- on 850225,alarm 47001-34 for Condenser Low Vacuum Turbine Trip,Cleared & Alarmed Again & Both Diesel Generators Started.Caused by Maint to Turbine Trip Mechanism.Start Signal Will Be Removed
05000305/LER-1985-006, :on 850220,steam Generator Tube Found Incorrectly Plugged.Possibly Caused by Mismarked Tube Sheet. Template Marked to Identify Tubes to Be Plugged1985-03-15015 March 1985
- on 850220,steam Generator Tube Found Incorrectly Plugged.Possibly Caused by Mismarked Tube Sheet. Template Marked to Identify Tubes to Be Plugged
05000305/LER-1985-004, :on 850210,control Room Operator Noticed Reactor Coolant Pump 1B Running.Caused by Grounded Condition in Actuation Circuitry Due to Water Accumulation in Pressure Switch.Hardware Mod Being Evaluated1985-03-13013 March 1985
- on 850210,control Room Operator Noticed Reactor Coolant Pump 1B Running.Caused by Grounded Condition in Actuation Circuitry Due to Water Accumulation in Pressure Switch.Hardware Mod Being Evaluated
05000305/LER-1985-005, :on 850211,exhaust Fan 1A of Auxiliary Bldg Special Ventilation Sys Found Running.Caused by Burnt Out Coil in Solenoid Valve Controlling Air to Zone SV Exhaust Filter 1A Inlet Damper.Valve Replaced1985-03-13013 March 1985
- on 850211,exhaust Fan 1A of Auxiliary Bldg Special Ventilation Sys Found Running.Caused by Burnt Out Coil in Solenoid Valve Controlling Air to Zone SV Exhaust Filter 1A Inlet Damper.Valve Replaced
05000305/LER-1985-003, :on 850208,reactor Tripped.Caused by Decrease in Steam Generator Vol to Low Level Alarm Setpoints. Corrective Action Being Investigated1985-03-0808 March 1985
- on 850208,reactor Tripped.Caused by Decrease in Steam Generator Vol to Low Level Alarm Setpoints. Corrective Action Being Investigated
05000305/LER-1985-002, :on 850125,seismic Analysis for nonsafety- Related Piping Section of Containment Integrated Leak Rate Test Penetration Could Not Be Located.Design Change Will Be Completed During 1985 Refueling Shutdown1985-02-24024 February 1985
- on 850125,seismic Analysis for nonsafety- Related Piping Section of Containment Integrated Leak Rate Test Penetration Could Not Be Located.Design Change Will Be Completed During 1985 Refueling Shutdown
05000305/LER-1985-001, :on 850122,inadvertent Actuation of Internal Containment Spray Sys 1B Occurred,Discharging Approx 2,500 Gallons Borated Water Into Containment Bldg.Operator Secured Sys & Reset Containment Spray1985-02-21021 February 1985
- on 850122,inadvertent Actuation of Internal Containment Spray Sys 1B Occurred,Discharging Approx 2,500 Gallons Borated Water Into Containment Bldg.Operator Secured Sys & Reset Containment Spray
05000305/LER-1984-021, :on 841218,boric Acid Tank Selector Switch Misaligned.Caused by Personnel Error.Switch Returned to Proper Position.Meeting Conducted on Job Attentiveness1985-01-17017 January 1985
- on 841218,boric Acid Tank Selector Switch Misaligned.Caused by Personnel Error.Switch Returned to Proper Position.Meeting Conducted on Job Attentiveness