Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029E4701994-05-12012 May 1994 LER 94-001-00:on 940412,discovered That Total Pressure Offset Constant in Error.Caused by Technician Error. Procedure Will Be Revised to Prevent recurrence.W/940512 Ltr ML20029D7761994-05-0404 May 1994 LER 94-002-00:on 940303,noble Gas Monitor in R-35 Did Not Respond When source-checked During Surveillance.Caused by Component Failure.Corrective Actions:Monitor Repaired & Returned to svc.W/940504 Ltr ML20046C7791993-08-0505 August 1993 LER 93-009-00:on 930715,receipt of Annunciator Charging Pump 12 Overload Trip Observed by CR Operators,Resulting in Unplanned Closure of Containment Isolation Valve.Standby Charging Pump Started Immediately ML20046A9151993-07-26026 July 1993 LER 93-007-01:on 930413,discovered That Valves Required to Mitigate Consequences of Accident Not Included in Section XI ISI & Testing Program.On 930624,identified Six Addl Valve Inappropriately Ommitted from Subj Program.Valves Included ML20046A8931993-07-23023 July 1993 LER 93-008-00:on 930624,observed That Valve CV-31740, Instrument Air to Unit 1 Containment Closed Due to Failure of Coil in Solenoid Operated Pilot Valve.Valve Reopened Locally to Restore Instrument air.W/930723 Ltr ML20044D2241993-05-13013 May 1993 LER 93-007-00:on 930413,discovered That Certain Feedwater Valves,Required to Mitigate Consequences of Accident,Not Included in ASME Section XI ISI & Test Program.Caused by Failure to Interpret Requirements.Valves Tested ML20044D2181993-05-13013 May 1993 LER 93-002-00:on 930403,containment Isolation Valve Which Controls Reactor Makeup Water to Containment Exceeded Max Time for Closure.On 930413,lockwire & Safety Tag Removed. Caused by Communication Errors.Safety Tag Process Reviewed ML20024G7001991-04-22022 April 1991 LER 91-002-00:on 910323,auto-start of Control Room Special Ventilation Sys Occurred.Caused by Spike on Newly Installed Radiation Monitor.Wiring Changed to Provide Time Delay Feature for Remaining Four modules.W/910422 Ltr ML20043B6041990-05-24024 May 1990 LER 90-004-00:on 900424,discovered That Surveillance Test SP1042, Resistance Temp Detector Bypass Flow Meter Functional Test Not Performed within Required Time Period. Caused by Personnel Error.Test performed.W/900524 Ltr ML20043E3761990-05-18018 May 1990 LER 90-007-00:on 900517,discovered That Several Relays Deenergized & Automatic Start & Loading of Diesel Generator D1 Initiated.Caused by Inadequate Design.Mod Initiated to Install Test points.W/900608 Ltr ML20042F5681990-05-0404 May 1990 LER 89-021-01:on 891212,chlorine Monitors on One Train of Control Room Ventilation Inoperable for More than 11 H. Caused by Personnel Error.Operating Procedure for Chlorine Monitoring Sys Issued & Training provided.W/900504 Ltr ML20006A9721990-01-22022 January 1990 LER 89-004-00:on 891221,unit Tripped & Reactor Coolant Pumps Lost Power.Caused by Faulty Voltage Regulation of One CRD Mechanism motor-generator Set.Regulator for Set Replaced & Tested.On 891226,identical Trip occurred.W/900122 Ltr ML20005G3731990-01-11011 January 1990 LER 89-021-00:on 891211,computer Alarmed Indicating Malfunction of Chlorine Monitors 121 & 122 & Leaving Control Room Ventilation Sys Inoperable for More than 11 H.Caused by Personnel Error.Monitor 122 Returned to normal.W/900111 Ltr ML19351A4681989-12-11011 December 1989 LER 89-020-00:on 891108,17,20,23,1201 & 08,automatic Isolation of Control Room Supply & Exhaust Occurred.Caused by Malfunctions of Chlorine Gas Detectors.Addl Monitors Installed & Actuation Logic modified.W/891211 Ltr ML20005D7071989-11-30030 November 1989 LER 89-018-01:on 891024,25,31 & 1112,control Room Received High Radiation Alarm Which Initiated Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Radiation Monitor Spikes.Monitor Modules replaced.W/891130 Ltr ML19332C6171989-11-22022 November 1989 LER 89-018-00:on 891024,25 & 1112,control Room Received Train a High Radiation Alarm,Initiating Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Spike of Radiation Monitor.Monitor replaced.W/891122 Ltr ML19332C6241989-11-22022 November 1989 LER 89-003-00:on 891023,measured Leakage Rate Exceeded Tech Specs Limit While Performing Surveillance Test Sp 2136. Caused by Wear of Grafoil Packing Due to High Frequency of Door Usage.Test Procedures modified.W/891122 Ltr ML19332C7001989-11-20020 November 1989 LER 89-019-00:on 891025,Train a of Auxiliary Bldg Special Ventilation Sys Started Automatically When Power Mistakenly Turned Off.Caused by Personnel Error.Involved Personnel Counseled.Clarifying Revs Made to procedure.W/891121 Ltr ML19325D4901989-10-16016 October 1989 LER 89-017-00:on 890914,discovered That Present Position of Transfer Switch for Power Supplying Control & Protection Relays for Diesel Generator Does Not Meet Requirements of App R.Caused by Inadequate procedures.W/891016 Ltr ML19325C7491989-10-10010 October 1989 LER 89-016-00:on 890908,control Room Received Train B High Radiation Alarm,Which Initiated Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Spike on Radiation Monitor 2R-30.Monitor Upgrade Being pursued.W/891010 Ltr ML19325C1991989-10-0505 October 1989 LER 89-015-00:on 890905 & 23,special Ventilation Sys of Control Rooms 122 & 121 Actuated Automatically.Caused by False High Chlorine Signal & Broken Chlorine Sensitive Paper Tape,Respectively.Detectors repaired.W/891005 Ltr ML19325C1981989-10-0505 October 1989 LER 89-014-00:on 890905,operations Personnel Recalled That SP1093.1 Performed Two Wks Previously Instead of SP1093.2. Caused by Personnel Error in Selecting Incorrect Procedure. Proper Notifications Made & SP1093.2 performed.W/891005 Ltr ML20050A8331982-03-24024 March 1982 LER 82-004/03L-0:on 820226,maint Workman Accidentally Bumped Overspeed Trip Mechanism on Auxiliary Feedwater Pump, Tripping Valve & Making Pump Inoperable.Caused by Personnel Error.Valve Operator Reset ML20042A5101982-03-12012 March 1982 LER 82-003/03L-0:on 820209,during Annual Visual Insp,One Steam Exclusion Control Damper Found Inoperable.Caused by Failure of Drive Gear in Pacific Air Products Damper Model R-35-FS.Gear Replaced ML20040A5671982-01-15015 January 1982 LER 81-030/03L-0:on 811210,degraded Voltage Relay 27A1/B25 Found W/Voltage Setpoint Outside Allowable Band.Causes Being Considered Are Last Calibr Error & Unfamiliarity W/Time Delay Relay Characteristics ML20039E5521981-12-30030 December 1981 LER 81-031/01T-0:on 811216,during Transfer of Spent Fuel in Preparation for Reracking of Pool 2,spent Fuel Assembly Top Nozzle Separated,Causing Assembly to Tip Toward Edge of Pool.Cause Unknown.Fuel Handling Operations Suspended ML20039C2681981-12-16016 December 1981 LER 81-027/03L-0:on 811116,discovered That Pre,Absolute & Charcoal Filter Test Not Done on 11 Shield Bldg Ventilation Sys Replacement on 811112.Caused by Procedural Inadequacies & Poor Communications ML20004D5131981-06-0505 June 1981 LER 81-006/03L-0:on 810507,charging Pump 121 Drive Unit Failed.Caused by Bearing Failure in Varidrive Unit.Damaged Parts Replaced ML20003H9831981-05-0505 May 1981 LER 81-004/03L-0:on 810406,during testing,turbine-driven Auxiliary Feedwater Pump 22 Failed to Come Up to Rated Speed.Caused by Low Governor Setting.Governor Adjusted to Proper Speed ML20003F4861981-04-14014 April 1981 LER 81-003/03L-0:on 810316,during Surveillance Test,Steam Exclusion Damper Actuation Setpoint Exceeded Limit.Caused by Foxboro Model 63U-CC-OHDR-F 6 Bistable Drift.Instrument Recalibr & Tested Satisfactorily ML19350B5241981-03-13013 March 1981 LER 81-002/01T-0:on 810301,during Eddy Current Exam of Steam Generator Tubes,Tubes Found Degraded & Defective.Caused by Corrosion &/Or Fretting.Defective Tubes Plugged ML19345F6211981-02-10010 February 1981 LER 81-001/03L-0:on 810112,while Performing Mod Work,Workman Accidentally Bumped Overspeed Trip Mechanism of Auxiliary Feedwater Pump,Tripping Valve & Making Pump Inoperable. Caused by Personnel Error.Valve Operator Reset ML19341A6711981-01-21021 January 1981 LER 80-038/03L-0:on 801222,during Surveillance Test,One Steam Exclusion Actuation Bistable Tripped Above Tech Spec Limit.Caused by Drift of Foxboro Model 63U-CC-OHDR-F Bistable.Bistable Reinspected & Calibr ML19343B1871980-12-0303 December 1980 Supplemental LER 80-025:on 800904,during Mounting Bolt Insp, Three Defective Vascomax 250 Cvm Bolts Were Discovered in Steam Generator 22.Caused by Stress Corrosion Cracking.New Bolts Were Installed & Tensioned to 50 Ft Lb ML19345B1201980-11-21021 November 1980 LER 80-034/03L-0:on 801031,auxiliary Bldg Special Vent Exhaust Fan 122 Tripped.Caused by Actuation of Thermal Overload Protective Device.Device Replaced ML19339C6181980-11-12012 November 1980 LER 80-032/03L-0:on 801013,during Refueling,Circulating Water Intake Bay Was Drained.Caused by Inoperable Priming Exhauster & Cooling Water Pump 21.Piping Mods Are Being Considered to Allow Maint W/O Effecting Operation ML19339B1991980-10-31031 October 1980 LER 80-028/03L-0:on 801003,previously Acknowledged Annunciator Indicating Fan Coil Unit 24 Was Noticed in Local Control.Caused by Personnel Error.Switch Returned to Remote & Personnel Cautioned to Exercise Care ML19339B2051980-10-31031 October 1980 LER 80-029/03L-0:on 801004,inverter 23 Failed,Leaving Panel 213 de-energized.Caused by Failure of Sola Constant Voltage Transformer.Panel Transferred & Transformer Replaced ML19338F5501980-10-15015 October 1980 LER 80-026/03L-0:on 800916,while Performing Fire Protection Mod Work in Auxiliary Feedwater Pump 22,workman Accidentally Bumped Overspeed Trip Mechanism,Tripping Valve & Making Pump Inoperable for 15 Minutes.Caused by Personnel Error ML19338F5141980-10-13013 October 1980 Updated LER 80-10/03L Dtd 801008,has Been Cancelled ML19347B6351980-10-0808 October 1980 Updated LER 80-010/03L-1:on 800311,containment Vacuum Breaker Isolation Valve 11 Opened at 0.57 Psi Rather than 0.5 Psi.Caused by Drift in Differential Pressure Switch. Setpoint Adjusted & Satisfactorily Tested ML19347B6461980-10-0808 October 1980 Updated LER 80-024/03L-0:on 800829,failed to Perform Inservice Insp of Safety Injection Nozzle to Shell Weld of Both Reactor Vessels.Caused by Unavailability of Test Equipment.Tech Spec & ASME Code Revisions Requested ML19347A9431980-09-25025 September 1980 Updated LER 80-025/01T-1:on 800904,ultrasonic Examination of Steam Generator Support Bolts Revealed That Most Had Crack Indications.Preliminary Cause Suggests Environmentally Assisted Cracking ML19338D7881980-09-19019 September 1980 LER 80-023/03L-0:on 800820,during Review of Surveillance Program Annual test,SP1185 for Control Room Special Ventilation Flow Verification Found Omitted for 1978-1980. Caused by Personnel Error.Personnel Will Review Rept ML19338D7781980-09-18018 September 1980 LER 80-025/01T-0:on 800904,during Refueling Shutdown, Ultrasonic Exam of Steam Generator Support Bolts Revealed Crack Indications.Unit 2 Also Inspected.Caused by Environ Assisted Cracking.All Unit 1 Bolts Will Be Replaced ML19337A2611980-09-0505 September 1980 LER 80-024/03L-0:on 800829,failure to Perform Inservice Insp of Safety Nozzle to Shell Weld of Both Reactor Vessels Was Noted.Cause Due to Equipment Unavailablilty.Rescheduling Requested for 1983 & 1984 Outages ML19338C9351980-09-0202 September 1980 LER 80-022/03L-0:on 800805,during Surveillance test,fan-coil Unit Dome Damper 23 Could Not Be Positioned Properly.Caused by Leaking Air Supply Line to Damper Actuator.Air Supply Line Replaced ML19344A8011980-08-15015 August 1980 LER 80-021/03L-0:on 800718,w/unit at Cold Shutdown for Steam Generator Maint & Insp,Replacement of Inverter 13 Revealed Lack of Seismic Analysis for Mounting Inverter.Caused by Personnel Error ML19330B4661980-07-29029 July 1980 LER 80-020/01T-0:on 800715,during Severe Electrical Storm Several Breakers Operated.Main Generator Was Separated from Grid & Reactor & Reactor Coolant Pumps Tripped.Caused by Electrical Storm.Next Day Conditions Returned to Normal ML19330A8721980-07-24024 July 1980 LER 80-019/03L-0:on 800630,two Power Range High Power Trip Setpoints Were Over Tech Spec Limit.Caused by Personnel Error.Rept Reviewed & Technicians Cautioned 1994-05-04
[Table view] Category:RO)
MONTHYEARML20029E4701994-05-12012 May 1994 LER 94-001-00:on 940412,discovered That Total Pressure Offset Constant in Error.Caused by Technician Error. Procedure Will Be Revised to Prevent recurrence.W/940512 Ltr ML20029D7761994-05-0404 May 1994 LER 94-002-00:on 940303,noble Gas Monitor in R-35 Did Not Respond When source-checked During Surveillance.Caused by Component Failure.Corrective Actions:Monitor Repaired & Returned to svc.W/940504 Ltr ML20046C7791993-08-0505 August 1993 LER 93-009-00:on 930715,receipt of Annunciator Charging Pump 12 Overload Trip Observed by CR Operators,Resulting in Unplanned Closure of Containment Isolation Valve.Standby Charging Pump Started Immediately ML20046A9151993-07-26026 July 1993 LER 93-007-01:on 930413,discovered That Valves Required to Mitigate Consequences of Accident Not Included in Section XI ISI & Testing Program.On 930624,identified Six Addl Valve Inappropriately Ommitted from Subj Program.Valves Included ML20046A8931993-07-23023 July 1993 LER 93-008-00:on 930624,observed That Valve CV-31740, Instrument Air to Unit 1 Containment Closed Due to Failure of Coil in Solenoid Operated Pilot Valve.Valve Reopened Locally to Restore Instrument air.W/930723 Ltr ML20044D2241993-05-13013 May 1993 LER 93-007-00:on 930413,discovered That Certain Feedwater Valves,Required to Mitigate Consequences of Accident,Not Included in ASME Section XI ISI & Test Program.Caused by Failure to Interpret Requirements.Valves Tested ML20044D2181993-05-13013 May 1993 LER 93-002-00:on 930403,containment Isolation Valve Which Controls Reactor Makeup Water to Containment Exceeded Max Time for Closure.On 930413,lockwire & Safety Tag Removed. Caused by Communication Errors.Safety Tag Process Reviewed ML20024G7001991-04-22022 April 1991 LER 91-002-00:on 910323,auto-start of Control Room Special Ventilation Sys Occurred.Caused by Spike on Newly Installed Radiation Monitor.Wiring Changed to Provide Time Delay Feature for Remaining Four modules.W/910422 Ltr ML20043B6041990-05-24024 May 1990 LER 90-004-00:on 900424,discovered That Surveillance Test SP1042, Resistance Temp Detector Bypass Flow Meter Functional Test Not Performed within Required Time Period. Caused by Personnel Error.Test performed.W/900524 Ltr ML20043E3761990-05-18018 May 1990 LER 90-007-00:on 900517,discovered That Several Relays Deenergized & Automatic Start & Loading of Diesel Generator D1 Initiated.Caused by Inadequate Design.Mod Initiated to Install Test points.W/900608 Ltr ML20042F5681990-05-0404 May 1990 LER 89-021-01:on 891212,chlorine Monitors on One Train of Control Room Ventilation Inoperable for More than 11 H. Caused by Personnel Error.Operating Procedure for Chlorine Monitoring Sys Issued & Training provided.W/900504 Ltr ML20006A9721990-01-22022 January 1990 LER 89-004-00:on 891221,unit Tripped & Reactor Coolant Pumps Lost Power.Caused by Faulty Voltage Regulation of One CRD Mechanism motor-generator Set.Regulator for Set Replaced & Tested.On 891226,identical Trip occurred.W/900122 Ltr ML20005G3731990-01-11011 January 1990 LER 89-021-00:on 891211,computer Alarmed Indicating Malfunction of Chlorine Monitors 121 & 122 & Leaving Control Room Ventilation Sys Inoperable for More than 11 H.Caused by Personnel Error.Monitor 122 Returned to normal.W/900111 Ltr ML19351A4681989-12-11011 December 1989 LER 89-020-00:on 891108,17,20,23,1201 & 08,automatic Isolation of Control Room Supply & Exhaust Occurred.Caused by Malfunctions of Chlorine Gas Detectors.Addl Monitors Installed & Actuation Logic modified.W/891211 Ltr ML20005D7071989-11-30030 November 1989 LER 89-018-01:on 891024,25,31 & 1112,control Room Received High Radiation Alarm Which Initiated Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Radiation Monitor Spikes.Monitor Modules replaced.W/891130 Ltr ML19332C6171989-11-22022 November 1989 LER 89-018-00:on 891024,25 & 1112,control Room Received Train a High Radiation Alarm,Initiating Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Spike of Radiation Monitor.Monitor replaced.W/891122 Ltr ML19332C6241989-11-22022 November 1989 LER 89-003-00:on 891023,measured Leakage Rate Exceeded Tech Specs Limit While Performing Surveillance Test Sp 2136. Caused by Wear of Grafoil Packing Due to High Frequency of Door Usage.Test Procedures modified.W/891122 Ltr ML19332C7001989-11-20020 November 1989 LER 89-019-00:on 891025,Train a of Auxiliary Bldg Special Ventilation Sys Started Automatically When Power Mistakenly Turned Off.Caused by Personnel Error.Involved Personnel Counseled.Clarifying Revs Made to procedure.W/891121 Ltr ML19325D4901989-10-16016 October 1989 LER 89-017-00:on 890914,discovered That Present Position of Transfer Switch for Power Supplying Control & Protection Relays for Diesel Generator Does Not Meet Requirements of App R.Caused by Inadequate procedures.W/891016 Ltr ML19325C7491989-10-10010 October 1989 LER 89-016-00:on 890908,control Room Received Train B High Radiation Alarm,Which Initiated Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Spike on Radiation Monitor 2R-30.Monitor Upgrade Being pursued.W/891010 Ltr ML19325C1991989-10-0505 October 1989 LER 89-015-00:on 890905 & 23,special Ventilation Sys of Control Rooms 122 & 121 Actuated Automatically.Caused by False High Chlorine Signal & Broken Chlorine Sensitive Paper Tape,Respectively.Detectors repaired.W/891005 Ltr ML19325C1981989-10-0505 October 1989 LER 89-014-00:on 890905,operations Personnel Recalled That SP1093.1 Performed Two Wks Previously Instead of SP1093.2. Caused by Personnel Error in Selecting Incorrect Procedure. Proper Notifications Made & SP1093.2 performed.W/891005 Ltr ML20050A8331982-03-24024 March 1982 LER 82-004/03L-0:on 820226,maint Workman Accidentally Bumped Overspeed Trip Mechanism on Auxiliary Feedwater Pump, Tripping Valve & Making Pump Inoperable.Caused by Personnel Error.Valve Operator Reset ML20042A5101982-03-12012 March 1982 LER 82-003/03L-0:on 820209,during Annual Visual Insp,One Steam Exclusion Control Damper Found Inoperable.Caused by Failure of Drive Gear in Pacific Air Products Damper Model R-35-FS.Gear Replaced ML20040A5671982-01-15015 January 1982 LER 81-030/03L-0:on 811210,degraded Voltage Relay 27A1/B25 Found W/Voltage Setpoint Outside Allowable Band.Causes Being Considered Are Last Calibr Error & Unfamiliarity W/Time Delay Relay Characteristics ML20039E5521981-12-30030 December 1981 LER 81-031/01T-0:on 811216,during Transfer of Spent Fuel in Preparation for Reracking of Pool 2,spent Fuel Assembly Top Nozzle Separated,Causing Assembly to Tip Toward Edge of Pool.Cause Unknown.Fuel Handling Operations Suspended ML20039C2681981-12-16016 December 1981 LER 81-027/03L-0:on 811116,discovered That Pre,Absolute & Charcoal Filter Test Not Done on 11 Shield Bldg Ventilation Sys Replacement on 811112.Caused by Procedural Inadequacies & Poor Communications ML20004D5131981-06-0505 June 1981 LER 81-006/03L-0:on 810507,charging Pump 121 Drive Unit Failed.Caused by Bearing Failure in Varidrive Unit.Damaged Parts Replaced ML20003H9831981-05-0505 May 1981 LER 81-004/03L-0:on 810406,during testing,turbine-driven Auxiliary Feedwater Pump 22 Failed to Come Up to Rated Speed.Caused by Low Governor Setting.Governor Adjusted to Proper Speed ML20003F4861981-04-14014 April 1981 LER 81-003/03L-0:on 810316,during Surveillance Test,Steam Exclusion Damper Actuation Setpoint Exceeded Limit.Caused by Foxboro Model 63U-CC-OHDR-F 6 Bistable Drift.Instrument Recalibr & Tested Satisfactorily ML19350B5241981-03-13013 March 1981 LER 81-002/01T-0:on 810301,during Eddy Current Exam of Steam Generator Tubes,Tubes Found Degraded & Defective.Caused by Corrosion &/Or Fretting.Defective Tubes Plugged ML19345F6211981-02-10010 February 1981 LER 81-001/03L-0:on 810112,while Performing Mod Work,Workman Accidentally Bumped Overspeed Trip Mechanism of Auxiliary Feedwater Pump,Tripping Valve & Making Pump Inoperable. Caused by Personnel Error.Valve Operator Reset ML19341A6711981-01-21021 January 1981 LER 80-038/03L-0:on 801222,during Surveillance Test,One Steam Exclusion Actuation Bistable Tripped Above Tech Spec Limit.Caused by Drift of Foxboro Model 63U-CC-OHDR-F Bistable.Bistable Reinspected & Calibr ML19343B1871980-12-0303 December 1980 Supplemental LER 80-025:on 800904,during Mounting Bolt Insp, Three Defective Vascomax 250 Cvm Bolts Were Discovered in Steam Generator 22.Caused by Stress Corrosion Cracking.New Bolts Were Installed & Tensioned to 50 Ft Lb ML19345B1201980-11-21021 November 1980 LER 80-034/03L-0:on 801031,auxiliary Bldg Special Vent Exhaust Fan 122 Tripped.Caused by Actuation of Thermal Overload Protective Device.Device Replaced ML19339C6181980-11-12012 November 1980 LER 80-032/03L-0:on 801013,during Refueling,Circulating Water Intake Bay Was Drained.Caused by Inoperable Priming Exhauster & Cooling Water Pump 21.Piping Mods Are Being Considered to Allow Maint W/O Effecting Operation ML19339B1991980-10-31031 October 1980 LER 80-028/03L-0:on 801003,previously Acknowledged Annunciator Indicating Fan Coil Unit 24 Was Noticed in Local Control.Caused by Personnel Error.Switch Returned to Remote & Personnel Cautioned to Exercise Care ML19339B2051980-10-31031 October 1980 LER 80-029/03L-0:on 801004,inverter 23 Failed,Leaving Panel 213 de-energized.Caused by Failure of Sola Constant Voltage Transformer.Panel Transferred & Transformer Replaced ML19338F5501980-10-15015 October 1980 LER 80-026/03L-0:on 800916,while Performing Fire Protection Mod Work in Auxiliary Feedwater Pump 22,workman Accidentally Bumped Overspeed Trip Mechanism,Tripping Valve & Making Pump Inoperable for 15 Minutes.Caused by Personnel Error ML19338F5141980-10-13013 October 1980 Updated LER 80-10/03L Dtd 801008,has Been Cancelled ML19347B6351980-10-0808 October 1980 Updated LER 80-010/03L-1:on 800311,containment Vacuum Breaker Isolation Valve 11 Opened at 0.57 Psi Rather than 0.5 Psi.Caused by Drift in Differential Pressure Switch. Setpoint Adjusted & Satisfactorily Tested ML19347B6461980-10-0808 October 1980 Updated LER 80-024/03L-0:on 800829,failed to Perform Inservice Insp of Safety Injection Nozzle to Shell Weld of Both Reactor Vessels.Caused by Unavailability of Test Equipment.Tech Spec & ASME Code Revisions Requested ML19347A9431980-09-25025 September 1980 Updated LER 80-025/01T-1:on 800904,ultrasonic Examination of Steam Generator Support Bolts Revealed That Most Had Crack Indications.Preliminary Cause Suggests Environmentally Assisted Cracking ML19338D7881980-09-19019 September 1980 LER 80-023/03L-0:on 800820,during Review of Surveillance Program Annual test,SP1185 for Control Room Special Ventilation Flow Verification Found Omitted for 1978-1980. Caused by Personnel Error.Personnel Will Review Rept ML19338D7781980-09-18018 September 1980 LER 80-025/01T-0:on 800904,during Refueling Shutdown, Ultrasonic Exam of Steam Generator Support Bolts Revealed Crack Indications.Unit 2 Also Inspected.Caused by Environ Assisted Cracking.All Unit 1 Bolts Will Be Replaced ML19337A2611980-09-0505 September 1980 LER 80-024/03L-0:on 800829,failure to Perform Inservice Insp of Safety Nozzle to Shell Weld of Both Reactor Vessels Was Noted.Cause Due to Equipment Unavailablilty.Rescheduling Requested for 1983 & 1984 Outages ML19338C9351980-09-0202 September 1980 LER 80-022/03L-0:on 800805,during Surveillance test,fan-coil Unit Dome Damper 23 Could Not Be Positioned Properly.Caused by Leaking Air Supply Line to Damper Actuator.Air Supply Line Replaced ML19344A8011980-08-15015 August 1980 LER 80-021/03L-0:on 800718,w/unit at Cold Shutdown for Steam Generator Maint & Insp,Replacement of Inverter 13 Revealed Lack of Seismic Analysis for Mounting Inverter.Caused by Personnel Error ML19330B4661980-07-29029 July 1980 LER 80-020/01T-0:on 800715,during Severe Electrical Storm Several Breakers Operated.Main Generator Was Separated from Grid & Reactor & Reactor Coolant Pumps Tripped.Caused by Electrical Storm.Next Day Conditions Returned to Normal ML19330A8721980-07-24024 July 1980 LER 80-019/03L-0:on 800630,two Power Range High Power Trip Setpoints Were Over Tech Spec Limit.Caused by Personnel Error.Rept Reviewed & Technicians Cautioned 1994-05-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G4461999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pingp.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211J2851999-08-26026 August 1999 Safety Evaluation Supporting Amends 146 & 137 to Licenses DPR-42 & DPR-60,respectively ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept 05000282/LER-1999-007-01, :on 990625,loss of CR Special Ventilation Function Was Noted.Caused by Broken Door Latch Pins on CR Chiller Door.Ts Amend Request to Establish Allowed OOS Time Was Submitted1999-07-23023 July 1999
- on 990625,loss of CR Special Ventilation Function Was Noted.Caused by Broken Door Latch Pins on CR Chiller Door.Ts Amend Request to Establish Allowed OOS Time Was Submitted
ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196F4081999-06-23023 June 1999 Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units ML20195G5181999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20196L2501999-05-13013 May 1999 Rev 0 to PINGP Unit 1 COLR Cycle 20 05000282/LER-1999-005-01, :on 990508,containment Inservice Purge Sys Was Not Isolated During Heavy Load Movement Over Fuel.Caused by Missing Procedure Step in D58.1.6.PINGP 1224 Was Initiated to Communicate Event & Forestall Repeating Event1999-05-0808 May 1999
- on 990508,containment Inservice Purge Sys Was Not Isolated During Heavy Load Movement Over Fuel.Caused by Missing Procedure Step in D58.1.6.PINGP 1224 Was Initiated to Communicate Event & Forestall Repeating Event
ML20206L6191999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with ML20205N1081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with ML20205B3351999-03-17017 March 1999 Safety Evaluation Supporting Amends 143 & 134 to Licenses DPR-42 & DPR-60,respectively ML20205Q5101999-03-15015 March 1999 Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229 05000306/LER-1999-001-01, :on 990206,TS Required Reactor Protection Logic Test Was Missed.Caused by Personnel Error.Sd Banks Were Inserted at 0544,RT Breakers Were Opened & Test Was Performed.With1999-03-0808 March 1999
- on 990206,TS Required Reactor Protection Logic Test Was Missed.Caused by Personnel Error.Sd Banks Were Inserted at 0544,RT Breakers Were Opened & Test Was Performed.With
ML20207J6951999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant ML20202J7711999-02-0404 February 1999 Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept ML20207L2811999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2 ML20202G3761999-01-31031 January 1999 Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units ML20202J1731999-01-22022 January 1999 Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety 05000306/LER-1998-006-01, :on 981219,unplanned Actuation of ESF Equipment During Performance of Sp.Caused by Personnel Error.Control Room Took Prompt Action & Returned Plant to Proper Status & Second pre-job Briefing for SP-2126 Was Conducted1999-01-18018 January 1999
- on 981219,unplanned Actuation of ESF Equipment During Performance of Sp.Caused by Personnel Error.Control Room Took Prompt Action & Returned Plant to Proper Status & Second pre-job Briefing for SP-2126 Was Conducted
ML20206P7861998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198J6441998-12-17017 December 1998 Rev 0 to PINGP COLR Unit 2-Cycle 19 05000306/LER-1998-005-02, :on 981109,RT from 22% Power During Planned SD Operation Was Noted.Caused by Tt.Fw Heater Drain Level Control Was Thoroughly Inspected & Calibrated.With1998-12-0909 December 1998
- on 981109,RT from 22% Power During Planned SD Operation Was Noted.Caused by Tt.Fw Heater Drain Level Control Was Thoroughly Inspected & Calibrated.With
ML20198L2211998-12-0707 December 1998 Safety Evaluation Supporting Amends 141 & 132 to Licenses DPR-42 & DPR-60,respectively ML20206N2731998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With 05000282/LER-1998-016, :on 981029,negative Flux Rate RT Occurred Upon CR Insertion After Failure of CRD Cable.Caused by Internal Short Circuit Developing in CRDM Patch Cables at Reactor Head Connector.Replaced CRDM Patch Cables.With1998-11-24024 November 1998
- on 981029,negative Flux Rate RT Occurred Upon CR Insertion After Failure of CRD Cable.Caused by Internal Short Circuit Developing in CRDM Patch Cables at Reactor Head Connector.Replaced CRDM Patch Cables.With
ML20196D7341998-11-20020 November 1998 Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi ML20195D3821998-11-0404 November 1998 Safety Evaluation Supporting Amends 140 & 131 to Licenses DPR-42 & DPR-60,respectively ML20155K6301998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20195D3761998-10-30030 October 1998 Safety Evaluation Supporting Amends 139 & 130 to Licenses DPR-42 & DPR-60 05000306/LER-1998-004-01, :on 980910,shield Building Integrity Was Breached.Caused by Inadequate TS Change.Revised Affected Procedures.With1998-10-0505 October 1998
- on 980910,shield Building Integrity Was Breached.Caused by Inadequate TS Change.Revised Affected Procedures.With
ML20198R8061998-09-30030 September 1998 Rev 1 to NSPLMI-96001, Prairie Island Nuclear Generating Plant Ipeee ML20202J7991998-09-30030 September 1998 Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept ML20154H4061998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With ML20198P0571998-09-0303 September 1998 Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator ML20153B0761998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With 05000282/LER-1998-009-01, :on 980731,noted That Recent Testing of RCS Vent Paths Had Not Been Performed in Literal Compliance with Wording of TS 4.18.1.Caused by Misunderstanding of Wording in TS Section 4.18.Will Modify Surveillance Procedures1998-08-27027 August 1998
- on 980731,noted That Recent Testing of RCS Vent Paths Had Not Been Performed in Literal Compliance with Wording of TS 4.18.1.Caused by Misunderstanding of Wording in TS Section 4.18.Will Modify Surveillance Procedures
ML20237D6491998-08-13013 August 1998 Safety Evaluation Supporting Amends 137 & 128 to Licenses DPR-42 & DPR-60,respectively ML20237A3961998-08-11011 August 1998 Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 1999-09-30
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