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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000461/LER-1999-010-01, Inoperability of Div 2 EDG Caused by Fuel Leaking Into Lube Oil, Cancelled1999-10-0707 October 1999 Inoperability of Div 2 EDG Caused by Fuel Leaking Into Lube Oil, Cancelled 05000461/LER-1998-020, :on 980609,inadequate Flow Balancing of Shutdown Water Sys Resulted in Less than Required Flow to Water Sys Loads.Caused by Inadequate Initial Design.New SX Min Flow Path for Div I & II SX Pumps Has Been Established1999-09-14014 September 1999
- on 980609,inadequate Flow Balancing of Shutdown Water Sys Resulted in Less than Required Flow to Water Sys Loads.Caused by Inadequate Initial Design.New SX Min Flow Path for Div I & II SX Pumps Has Been Established
05000461/LER-1996-010, :on 960906,plant Shutdown Occurred Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit.Procedures Will Be Revised, Failed Seal Will Be Replaced & Seal Design Will Be Improved1999-09-13013 September 1999
- on 960906,plant Shutdown Occurred Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit.Procedures Will Be Revised, Failed Seal Will Be Replaced & Seal Design Will Be Improved
05000461/LER-1999-011, :on 990816,improper Restoration of a APRM Caused Monitor to Not Meet Seismic Qualification Requirements.Caused by Lack of Knowledge.Page Latches for Other APRMs Were Inspected & No Anomolies Were Found1999-09-10010 September 1999
- on 990816,improper Restoration of a APRM Caused Monitor to Not Meet Seismic Qualification Requirements.Caused by Lack of Knowledge.Page Latches for Other APRMs Were Inspected & No Anomolies Were Found
05000461/LER-1999-010, :on 990809,declared Div 2 EDG Inoperable Due to Fuel Leaking Into Lube Oil.Replaced Fuel Return Line from Engine Number 12 Cylinder on Div 2 Edg.With1999-09-0808 September 1999
- on 990809,declared Div 2 EDG Inoperable Due to Fuel Leaking Into Lube Oil.Replaced Fuel Return Line from Engine Number 12 Cylinder on Div 2 Edg.With
05000461/LER-1999-009, :on 990617,failure to Satisfy Secondary Containment Bypass Leakage Rate TS Was Noted.Caused by Failure to Properly Classify Containment Penetrations. Procedures Revised.With1999-07-15015 July 1999
- on 990617,failure to Satisfy Secondary Containment Bypass Leakage Rate TS Was Noted.Caused by Failure to Properly Classify Containment Penetrations. Procedures Revised.With
05000461/LER-1999-006, :on 990419,values Used for Containment & Drywell Free Vols Found to Be Smaller than Originally Analyzed Due to Inadequate Calculation Control During Initial Plant Const.With 9905517 Ltr1999-05-17017 May 1999
- on 990419,values Used for Containment & Drywell Free Vols Found to Be Smaller than Originally Analyzed Due to Inadequate Calculation Control During Initial Plant Const.With 9905517 Ltr
05000461/LER-1998-014-01, Design Failure Analysis for FW Piping Does Not Match Fatigue Analysis for FW Nozzles Resulting in Condition Outside of Design Basis for Plant, Has Been Cancelled1999-05-13013 May 1999 Design Failure Analysis for FW Piping Does Not Match Fatigue Analysis for FW Nozzles Resulting in Condition Outside of Design Basis for Plant, Has Been Cancelled 05000461/LER-1998-030-01, Insufficient Suppression Pool Makeup Volume to Meet Design Basis Suppression Pool Level Requirements Following LOCA, Has Been Cancelled1999-04-19019 April 1999 Insufficient Suppression Pool Makeup Volume to Meet Design Basis Suppression Pool Level Requirements Following LOCA, Has Been Cancelled 05000461/LER-1999-004, :on 990126,plant Was Operating Outside Design Basis.Caused Because Design for CR Operator Dose Calculation Did Not Consider Single Failure of CR Ventilation Sys. Revised CR Operator Dose Calculation.With1999-02-25025 February 1999
- on 990126,plant Was Operating Outside Design Basis.Caused Because Design for CR Operator Dose Calculation Did Not Consider Single Failure of CR Ventilation Sys. Revised CR Operator Dose Calculation.With
05000461/LER-1999-002, :on 990106,loss of Offsite Power to SR Electrical Buses Was Noted.Caused by Offsite Fault on in Service Offsite Electrical Supply Line.Repairs Were Made to Faulted Line & Leaning Support Structure.With1999-02-0404 February 1999
- on 990106,loss of Offsite Power to SR Electrical Buses Was Noted.Caused by Offsite Fault on in Service Offsite Electrical Supply Line.Repairs Were Made to Faulted Line & Leaning Support Structure.With
05000461/LER-1998-036, :on 981018,loss of Shutdown Cooling Was Noted. Caused by Personnel Opening Incorrect Electrical Cubicle Door.Learning Opportunities Re Incorrect Cubicle Door Were Communicated to Personnel & Training Will Be Improved1998-11-17017 November 1998
- on 981018,loss of Shutdown Cooling Was Noted. Caused by Personnel Opening Incorrect Electrical Cubicle Door.Learning Opportunities Re Incorrect Cubicle Door Were Communicated to Personnel & Training Will Be Improved
05000461/LER-1998-020, :on 980609,discovered Flow Gauge in Main CR to Be Reading Greater than Instrument Range.Cause Indeterminate.Will Incorporate Event Info Into Operator Training Program & Verified Calibr of Flow Instrumentation1998-07-0808 July 1998
- on 980609,discovered Flow Gauge in Main CR to Be Reading Greater than Instrument Range.Cause Indeterminate.Will Incorporate Event Info Into Operator Training Program & Verified Calibr of Flow Instrumentation
05000461/LER-1996-015, :on 961026,unplanned Esfa of Eight Ci Valves Was Noted.Caused by Lack of Attention to Detail.Placed Description of Event in Operations Night Orders So Operations Personnel Would Be Aware of Details of Event1998-06-24024 June 1998
- on 961026,unplanned Esfa of Eight Ci Valves Was Noted.Caused by Lack of Attention to Detail.Placed Description of Event in Operations Night Orders So Operations Personnel Would Be Aware of Details of Event
05000461/LER-1998-017, :on 980402,inadequate Implementation of SR Was Noted.Caused by Misinterpretation of TS SR 3.8.6.2 & Table 3.8.6-1.Revised Procedure for Performing Battery Cell Specific Gravity Checks1998-05-0404 May 1998
- on 980402,inadequate Implementation of SR Was Noted.Caused by Misinterpretation of TS SR 3.8.6.2 & Table 3.8.6-1.Revised Procedure for Performing Battery Cell Specific Gravity Checks
05000461/LER-1998-014, :on 980325,design Fatigue Analysis for FW Piping Does Not Match Fatigue Analysis for FW Nozzles, Resulting in Condition,Outside Design Basis of Plant Occurred.Cause & Corrective Action,Not Yet Been Determined1998-04-20020 April 1998
- on 980325,design Fatigue Analysis for FW Piping Does Not Match Fatigue Analysis for FW Nozzles, Resulting in Condition,Outside Design Basis of Plant Occurred.Cause & Corrective Action,Not Yet Been Determined
05000461/LER-1998-010, :on 971217,Divs 1 & 2 H & Oxygen Analyzers Were Declared Inoperable Due to Inadequate Commercial Grade Dedication of safety-related Replacement Parts by Supplier. Evaluated Installed Parts for Acceptability1998-04-10010 April 1998
- on 971217,Divs 1 & 2 H & Oxygen Analyzers Were Declared Inoperable Due to Inadequate Commercial Grade Dedication of safety-related Replacement Parts by Supplier. Evaluated Installed Parts for Acceptability
05000461/LER-1998-011, :on 980312,CR Ventilation Sys Was Declared Inoperable Due to Broken/Missing Conduit Hold Down Restraints on VC Chiller Skids.Caused by Personnel Walking on Equipment.Generated Work Requests1998-04-0909 April 1998
- on 980312,CR Ventilation Sys Was Declared Inoperable Due to Broken/Missing Conduit Hold Down Restraints on VC Chiller Skids.Caused by Personnel Walking on Equipment.Generated Work Requests
05000461/LER-1998-008-01, :on 930213,Division I Hydrogen & Oxygen Analyzer Incapable of Meeting Design Basis Were Noted Due to an Excessive Vibration Condition on Air Compressor.Caused by Personnel Error.Div 1 H202 Air Condition Will Be Corrected1998-04-0808 April 1998
- on 930213,Division I Hydrogen & Oxygen Analyzer Incapable of Meeting Design Basis Were Noted Due to an Excessive Vibration Condition on Air Compressor.Caused by Personnel Error.Div 1 H202 Air Condition Will Be Corrected
05000461/LER-1997-034, :on 860929,incorrect Cable Resistance & Brake Horsepower Data Used in Design of Divs 1 & 2 EDG Vent Fans Resulted in Design of Fan Motors Being Outside Design Basis of Plant.Will Revise Electrical Calculation1998-04-0303 April 1998
- on 860929,incorrect Cable Resistance & Brake Horsepower Data Used in Design of Divs 1 & 2 EDG Vent Fans Resulted in Design of Fan Motors Being Outside Design Basis of Plant.Will Revise Electrical Calculation
05000461/LER-1997-023-01, Inadequate Work Instructions Leads to Potential Over-Greasing of Motor Bearings Causing Potential Failure of Various Motors Has Been Canceled1998-03-31031 March 1998 Inadequate Work Instructions Leads to Potential Over-Greasing of Motor Bearings Causing Potential Failure of Various Motors Has Been Canceled 05000461/LER-1998-007, :on 980322,inadequate Engineering Evaluation Leads to Installation of Temporary Mod on DC Electrical Power Sys,Was Determined.Caused by Misjudgement & Misassumptions.Improvements Made to 10CFR50.59 SE Process1998-03-30030 March 1998
- on 980322,inadequate Engineering Evaluation Leads to Installation of Temporary Mod on DC Electrical Power Sys,Was Determined.Caused by Misjudgement & Misassumptions.Improvements Made to 10CFR50.59 SE Process
05000461/LER-1998-005, :on 980130,failure to Verify Closed PCIVs as Required by TS SR Was Noted.Caused by Personnel Error.Will Revised Procedure 1001.05, Authorities & Responsibilities for ROs for Safe Operation & Shutdown1998-03-30030 March 1998
- on 980130,failure to Verify Closed PCIVs as Required by TS SR Was Noted.Caused by Personnel Error.Will Revised Procedure 1001.05, Authorities & Responsibilities for ROs for Safe Operation & Shutdown
05000461/LER-1997-035, :on 860929,division 1 & 2 Battery Chargers Were Incapable of Supplying Full Rated Voltage.Caused by Failure to Include Battery Charger Minimum Voltage Requirement. Adjusted Transformer Tap Settings on Battery Chargers1998-03-19019 March 1998
- on 860929,division 1 & 2 Battery Chargers Were Incapable of Supplying Full Rated Voltage.Caused by Failure to Include Battery Charger Minimum Voltage Requirement. Adjusted Transformer Tap Settings on Battery Chargers
05000461/LER-1998-009, :on 980203,failure to Account for Design Basis Sys Pressures & Voltages for EDG Air Start Sys Was Noted. Caused by Failure of Design Engineer.Changed Spring Size in Solenoid Valve for Division III EDG Air Start Sys1998-03-0404 March 1998
- on 980203,failure to Account for Design Basis Sys Pressures & Voltages for EDG Air Start Sys Was Noted. Caused by Failure of Design Engineer.Changed Spring Size in Solenoid Valve for Division III EDG Air Start Sys
05000461/LER-1998-005, :on 980130,failure to Verify Closed PCIV as Required by TS SRs Noted.Cause for Event Under Investigation & Will Be Provided in Rev to Ler.Procedures Will Be Revised1998-03-0202 March 1998
- on 980130,failure to Verify Closed PCIV as Required by TS SRs Noted.Cause for Event Under Investigation & Will Be Provided in Rev to Ler.Procedures Will Be Revised
05000461/LER-1998-004, :on 980127,division 2 Nuclear Sys Protection Sys Inverter Was Not IAW Plant Design Basis Due to Various Deficiences.Caused by Incorrect Guidance.Corrective Action Has Not Been Identified1998-02-26026 February 1998
- on 980127,division 2 Nuclear Sys Protection Sys Inverter Was Not IAW Plant Design Basis Due to Various Deficiences.Caused by Incorrect Guidance.Corrective Action Has Not Been Identified
05000461/LER-1997-035, :on 860929,noted That Divisions 1 & 2 Battery Chargers Were Incapable of Supplying Full Rated Voltage & Current Flow at Degraded Voltage Trip.Cause Evaluation for Event Has Not Been Completed.Battery Charger Modified1998-01-16016 January 1998
- on 860929,noted That Divisions 1 & 2 Battery Chargers Were Incapable of Supplying Full Rated Voltage & Current Flow at Degraded Voltage Trip.Cause Evaluation for Event Has Not Been Completed.Battery Charger Modified
05000461/LER-1997-034, :on 860929,incorrect Cable Resistance & Brake Horsepower Data Used in Design of Divisions 1 & 2 EDG Vent Fans Results in Design of Fan Motors Being Outside Design Basis.Cause Under Investigation1998-01-16016 January 1998
- on 860929,incorrect Cable Resistance & Brake Horsepower Data Used in Design of Divisions 1 & 2 EDG Vent Fans Results in Design of Fan Motors Being Outside Design Basis.Cause Under Investigation
05000461/LER-1997-024, :on 970830,failure to Comply W/Ts Action Statement to Immediately Restore AC Power Sources Was Determined.Caused by Inadequate Interpretation of TS Action. Licensing Providing Staff Guidance1997-10-29029 October 1997
- on 970830,failure to Comply W/Ts Action Statement to Immediately Restore AC Power Sources Was Determined.Caused by Inadequate Interpretation of TS Action. Licensing Providing Staff Guidance
05000461/LER-1997-025, :on 971002,design Deficiency Resulted in Plant Being Outside Design Basis for Fire in Main CR Potentially Damaging Valves Required in Safe Shutdown of Plant.Cause Could Not Be Determined.Will Analyze MOV Control Circuits1997-10-28028 October 1997
- on 971002,design Deficiency Resulted in Plant Being Outside Design Basis for Fire in Main CR Potentially Damaging Valves Required in Safe Shutdown of Plant.Cause Could Not Be Determined.Will Analyze MOV Control Circuits
05000461/LER-1997-012, :on 970411,discovered That Failure to Correct for Instrument Error During Performance of SGTS Sps Lead to Invalid Surveillance Results.Caused by Lack of Sys Ownership & Procedural Guidance.Sps Reperformed1997-10-27027 October 1997
- on 970411,discovered That Failure to Correct for Instrument Error During Performance of SGTS Sps Lead to Invalid Surveillance Results.Caused by Lack of Sys Ownership & Procedural Guidance.Sps Reperformed
05000461/LER-1997-002, :on 970121,failure to Complete TS 3.8.2 LCO Required Action B.4 Was Noted.Caused by Personnel Error. Training Was Provided to Appropriate Operations Dept Personnel on Event.Revised CPS Procedure 9080.011997-08-28028 August 1997
- on 970121,failure to Complete TS 3.8.2 LCO Required Action B.4 Was Noted.Caused by Personnel Error. Training Was Provided to Appropriate Operations Dept Personnel on Event.Revised CPS Procedure 9080.01
05000461/LER-1997-005, :on 860929,eighteen Containment Penetrations Susceptible to Thermally Induced over-pressurization Were Identified.Caused by Lack of Guidance.Drained Penetrations Not Required post-LOCA1997-08-28028 August 1997
- on 860929,eighteen Containment Penetrations Susceptible to Thermally Induced over-pressurization Were Identified.Caused by Lack of Guidance.Drained Penetrations Not Required post-LOCA
05000461/LER-1997-010, :on 920408,incorrect Voltage in Procedure for Verification of off-site Power Sources Resulted in Ts.Caused by Personnel Error Re Failure to Adequately Review Operability Requirements.Procedure Revised1997-08-28028 August 1997
- on 920408,incorrect Voltage in Procedure for Verification of off-site Power Sources Resulted in Ts.Caused by Personnel Error Re Failure to Adequately Review Operability Requirements.Procedure Revised
05000461/LER-1997-003, :on 970128,failed to Recongnize Impact of Disconnecting Div 1 IRM Cable While Div 2 IRM Cable Was Disconnected Resulted in 2 Out of 4 RPS Actuation Being Satisfied.Caused by Personnel Error.Counseled Personnel1997-07-0101 July 1997
- on 970128,failed to Recongnize Impact of Disconnecting Div 1 IRM Cable While Div 2 IRM Cable Was Disconnected Resulted in 2 Out of 4 RPS Actuation Being Satisfied.Caused by Personnel Error.Counseled Personnel
05000461/LER-1997-013, :on 970508,failure to Adequately Verify That No Trips Existed During Surveillance Test Resulted in Inadvertent Actuation of Sgts.Caused by Personnel Error. Procedure CPS 9532.61 Was Revised1997-06-0404 June 1997
- on 970508,failure to Adequately Verify That No Trips Existed During Surveillance Test Resulted in Inadvertent Actuation of Sgts.Caused by Personnel Error. Procedure CPS 9532.61 Was Revised
05000461/LER-1997-012, :on 860929,failure to Correct Instrument Error During Performance Standby Gas Treatment Sys Surveillance Procedures.Cause of Event Still Under Investigation. Applicable Surveillance Procedures Reperformed1997-05-0808 May 1997
- on 860929,failure to Correct Instrument Error During Performance Standby Gas Treatment Sys Surveillance Procedures.Cause of Event Still Under Investigation. Applicable Surveillance Procedures Reperformed
05000461/LER-1997-010, :on 970408,discovered Incorrect Voltage in Procedure for Verification of off-site Power Sources.Caused by Personnel Error Re Failure to Adequately Review Operability Requirements.Procedures Revised1997-05-0808 May 1997
- on 970408,discovered Incorrect Voltage in Procedure for Verification of off-site Power Sources.Caused by Personnel Error Re Failure to Adequately Review Operability Requirements.Procedures Revised
05000461/LER-1997-011, :on 860929,failed to Verify Breaker Closed at seven-day Frequency Required by TS Due to Omission of Breaker from Surveillance Procedure.Caused by Inadequate Procedures.Revised Procedures1997-05-0808 May 1997
- on 860929,failed to Verify Breaker Closed at seven-day Frequency Required by TS Due to Omission of Breaker from Surveillance Procedure.Caused by Inadequate Procedures.Revised Procedures
05000461/LER-1997-009, :on 970326,surveillance Procedure Does Not Adequately Consider Accuracy of Installed Instrumentation in Meeting TS Requirements for Reactor Core Isolation Cooling Pump.Cause & Corrective Actions Not Determined1997-04-22022 April 1997
- on 970326,surveillance Procedure Does Not Adequately Consider Accuracy of Installed Instrumentation in Meeting TS Requirements for Reactor Core Isolation Cooling Pump.Cause & Corrective Actions Not Determined
05000461/LER-1997-008, :on 920408,determined That DG Undervoltage Relays Inoperable Due to Inadequate Process to Review Operability Requirements of Plant Equipment as Defined in Ts.Amend Requested to Change TS1997-04-22022 April 1997
- on 920408,determined That DG Undervoltage Relays Inoperable Due to Inadequate Process to Review Operability Requirements of Plant Equipment as Defined in Ts.Amend Requested to Change TS
05000461/LER-1997-007, :on 970227,lack of Procedural Guidelines for Maintaining Seismic Qualification Resulted in Division 3 Switchgear Outside Design Basis.Revised CPS Procedures.W/1997-03-27027 March 1997
- on 970227,lack of Procedural Guidelines for Maintaining Seismic Qualification Resulted in Division 3 Switchgear Outside Design Basis.Revised CPS Procedures.W/
05000461/LER-1997-005, :on 860929,seventeen Containment Penetrations Susceptible to Thermally Induced over-pressurization Identified.Cause Unknown.Penetrations Not Required for post- LOCA Drained1997-03-13013 March 1997
- on 860929,seventeen Containment Penetrations Susceptible to Thermally Induced over-pressurization Identified.Cause Unknown.Penetrations Not Required for post- LOCA Drained
05000461/LER-1997-004, :on 970204,failed to Properly Implement TS SR 3.6.5.3.3 Due to Inadequate Procedure.Revised Surveillance Procedure to Verify Valves Closed1997-03-0606 March 1997
- on 970204,failed to Properly Implement TS SR 3.6.5.3.3 Due to Inadequate Procedure.Revised Surveillance Procedure to Verify Valves Closed
05000461/LER-1996-012, :on 910316,failed to Demonstrate Operability of Offsite Power Sources within One Hr During Surveillance While Div 3 EDG Governor Speed Droop Control Set to 50% Due to Inadequate Procedures.Revised Procedures1997-02-18018 February 1997
- on 910316,failed to Demonstrate Operability of Offsite Power Sources within One Hr During Surveillance While Div 3 EDG Governor Speed Droop Control Set to 50% Due to Inadequate Procedures.Revised Procedures
05000461/LER-1997-002, :on 970121,failed to Complete TS 3.8.2 LCO Required Action B.4 for Div I Edg.Cause & Corrective Action Under Investigation.Suppl Rept Expected on 9704171997-02-18018 February 1997
- on 970121,failed to Complete TS 3.8.2 LCO Required Action B.4 for Div I Edg.Cause & Corrective Action Under Investigation.Suppl Rept Expected on 970417
05000461/LER-1997-001, :on 970103,nuclear Fuel Supplier Failed to Analyze Turbine Pressure Regulator Downscale Failure Event in off-rated Condition Per 10CFR21.21.Caused by Error in Nuclear Fuel Supplier.Mcpr Will Be Implemented1997-01-28028 January 1997
- on 970103,nuclear Fuel Supplier Failed to Analyze Turbine Pressure Regulator Downscale Failure Event in off-rated Condition Per 10CFR21.21.Caused by Error in Nuclear Fuel Supplier.Mcpr Will Be Implemented
05000461/LER-1996-020, :on 961223,failure of CR Drive Hydraulic Control Unit Air Line Occurred Due to Overtightening Fitting During Maintenance to Correct Air Leak.Broken Air Line Was Replaced in Accordance with Mwr D616691997-01-20020 January 1997
- on 961223,failure of CR Drive Hydraulic Control Unit Air Line Occurred Due to Overtightening Fitting During Maintenance to Correct Air Leak.Broken Air Line Was Replaced in Accordance with Mwr D61669
05000461/LER-1996-018, :on 961014,incorrect Torque Value for Control Rod Drive Hydraulic Control Units Was Specified by Supplier. Caused by Lack of Attention to Detail.All Hold Down Bolts on CRD HCUs Were Replaced1996-12-17017 December 1996
- on 961014,incorrect Torque Value for Control Rod Drive Hydraulic Control Units Was Specified by Supplier. Caused by Lack of Attention to Detail.All Hold Down Bolts on CRD HCUs Were Replaced
1999-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000461/LER-1999-010-01, Inoperability of Div 2 EDG Caused by Fuel Leaking Into Lube Oil, Cancelled1999-10-0707 October 1999 Inoperability of Div 2 EDG Caused by Fuel Leaking Into Lube Oil, Cancelled U-603277, Monthly Operating Rept for Sept 1999 for Clinton Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Clinton Power Station,Unit 1.With 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 05000461/LER-1998-020, :on 980609,inadequate Flow Balancing of Shutdown Water Sys Resulted in Less than Required Flow to Water Sys Loads.Caused by Inadequate Initial Design.New SX Min Flow Path for Div I & II SX Pumps Has Been Established1999-09-14014 September 1999
- on 980609,inadequate Flow Balancing of Shutdown Water Sys Resulted in Less than Required Flow to Water Sys Loads.Caused by Inadequate Initial Design.New SX Min Flow Path for Div I & II SX Pumps Has Been Established
05000461/LER-1996-010, :on 960906,plant Shutdown Occurred Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit.Procedures Will Be Revised, Failed Seal Will Be Replaced & Seal Design Will Be Improved1999-09-13013 September 1999
- on 960906,plant Shutdown Occurred Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit.Procedures Will Be Revised, Failed Seal Will Be Replaced & Seal Design Will Be Improved
05000461/LER-1999-011, :on 990816,improper Restoration of a APRM Caused Monitor to Not Meet Seismic Qualification Requirements.Caused by Lack of Knowledge.Page Latches for Other APRMs Were Inspected & No Anomolies Were Found1999-09-10010 September 1999
- on 990816,improper Restoration of a APRM Caused Monitor to Not Meet Seismic Qualification Requirements.Caused by Lack of Knowledge.Page Latches for Other APRMs Were Inspected & No Anomolies Were Found
05000461/LER-1999-010, :on 990809,declared Div 2 EDG Inoperable Due to Fuel Leaking Into Lube Oil.Replaced Fuel Return Line from Engine Number 12 Cylinder on Div 2 Edg.With1999-09-0808 September 1999
- on 990809,declared Div 2 EDG Inoperable Due to Fuel Leaking Into Lube Oil.Replaced Fuel Return Line from Engine Number 12 Cylinder on Div 2 Edg.With
U-603267, Monthly Operating Rept for Aug 1999 for Clinton Power Station,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Clinton Power Station,Unit 1.With U-603245, Monthly Operating Rept for Jul 1999 for CPS Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for Jul 1999 for CPS Unit 1.With ML20211C9621999-07-26026 July 1999 ISI Summary Rept 05000461/LER-1999-009, :on 990617,failure to Satisfy Secondary Containment Bypass Leakage Rate TS Was Noted.Caused by Failure to Properly Classify Containment Penetrations. Procedures Revised.With1999-07-15015 July 1999
- on 990617,failure to Satisfy Secondary Containment Bypass Leakage Rate TS Was Noted.Caused by Failure to Properly Classify Containment Penetrations. Procedures Revised.With
U-603232, Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted1999-07-0909 July 1999 Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted U-603233, Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With U-603222, Monthly Operating Rept for May 1999 for Clinton Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Clinton Power Station.With 05000461/LER-1999-006, :on 990419,values Used for Containment & Drywell Free Vols Found to Be Smaller than Originally Analyzed Due to Inadequate Calculation Control During Initial Plant Const.With 9905517 Ltr1999-05-17017 May 1999
- on 990419,values Used for Containment & Drywell Free Vols Found to Be Smaller than Originally Analyzed Due to Inadequate Calculation Control During Initial Plant Const.With 9905517 Ltr
05000461/LER-1998-014-01, Design Failure Analysis for FW Piping Does Not Match Fatigue Analysis for FW Nozzles Resulting in Condition Outside of Design Basis for Plant, Has Been Cancelled1999-05-13013 May 1999 Design Failure Analysis for FW Piping Does Not Match Fatigue Analysis for FW Nozzles Resulting in Condition Outside of Design Basis for Plant, Has Been Cancelled ML20210K8391999-05-11011 May 1999 British Energy Annual Rept & Accounts 1998-99 ML20206H1231999-05-0505 May 1999 Illinois Power Co CPS Main CR Simulator Certification Rept U-603210, Monthly Operating Rept for Apr 1999 for Cps,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Cps,Unit 1.With U-603204, Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR211999-04-30030 April 1999 Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR21 05000461/LER-1998-030-01, Insufficient Suppression Pool Makeup Volume to Meet Design Basis Suppression Pool Level Requirements Following LOCA, Has Been Cancelled1999-04-19019 April 1999 Insufficient Suppression Pool Makeup Volume to Meet Design Basis Suppression Pool Level Requirements Following LOCA, Has Been Cancelled U-603192, Monthly Operating Rept for Mar 1999 for Clinton Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Clinton Power Station,Unit 1.With ML20205D3861999-03-26026 March 1999 Safety Evaluation Supporting Amend 122 to License NPF-62 U-603182, Part 21 Rept Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier, Trentec.Condition Rept 1-99-01-136 Was Initiated to Track Investigation & Resolution of Issue1999-03-12012 March 1999 Part 21 Rept Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier, Trentec.Condition Rept 1-99-01-136 Was Initiated to Track Investigation & Resolution of Issue ML20207H0201999-03-0808 March 1999 Safety Evaluation Supporting Amend 121 to License NPF-62 U-603176, Monthly Operating Rept for Feb 1999 for Clinton Power Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Clinton Power Station,Unit 1.With 05000461/LER-1999-004, :on 990126,plant Was Operating Outside Design Basis.Caused Because Design for CR Operator Dose Calculation Did Not Consider Single Failure of CR Ventilation Sys. Revised CR Operator Dose Calculation.With1999-02-25025 February 1999
- on 990126,plant Was Operating Outside Design Basis.Caused Because Design for CR Operator Dose Calculation Did Not Consider Single Failure of CR Ventilation Sys. Revised CR Operator Dose Calculation.With
ML20207F2031999-02-10010 February 1999 Rev 1 to CPS COLR for Reload 6 Cycle 7 05000461/LER-1999-002, :on 990106,loss of Offsite Power to SR Electrical Buses Was Noted.Caused by Offsite Fault on in Service Offsite Electrical Supply Line.Repairs Were Made to Faulted Line & Leaning Support Structure.With1999-02-0404 February 1999
- on 990106,loss of Offsite Power to SR Electrical Buses Was Noted.Caused by Offsite Fault on in Service Offsite Electrical Supply Line.Repairs Were Made to Faulted Line & Leaning Support Structure.With
ML20202J0181999-02-0303 February 1999 SER Accepting Changes in Quality Assurance Program,Which Continues to Meet Requirements of App B to 10CFR50 ML20199L3581999-01-20020 January 1999 Safety Evaluation Supporting Amend 120 to License NPF-62 ML20199L3871999-01-20020 January 1999 Safety Evaluation Supporting Amend 119 to License NPF-62 U-603223, Illinova Corp 1998 Annual Rept. with1998-12-31031 December 1998 Illinova Corp 1998 Annual Rept. with U-603144, Monthly Operating Rept for Dec 1998 for Clinton Power Station,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Clinton Power Station,Unit 1.With ML20198D8601998-12-14014 December 1998 Safety Evaluation Supporting Amend 118 to License NPF-62 U-603115, Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps in Supplying SR Parts to Npps.Issue Is Not Reportable Under 10CFR21. Dedication Process Did Not Affect Ability of Components1998-12-0404 December 1998 Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps in Supplying SR Parts to Npps.Issue Is Not Reportable Under 10CFR21. Dedication Process Did Not Affect Ability of Components U-603124, Monthly Operating Rept for Nov 1998 for Clinton Power Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Clinton Power Station,Unit 1.With U-603114, Part 21 Rept 21-98-049 Re W Dhp Circuit Breaker Refurbished by Nuclear Logistics,Inc Which Failed to Operate.Caused by Trip Latch out-of-adjustment & Incorrectly Sized Ratchet Lever Assembly Bushing.Breakers Were Returned to Vendor1998-11-25025 November 1998 Part 21 Rept 21-98-049 Re W Dhp Circuit Breaker Refurbished by Nuclear Logistics,Inc Which Failed to Operate.Caused by Trip Latch out-of-adjustment & Incorrectly Sized Ratchet Lever Assembly Bushing.Breakers Were Returned to Vendor 05000461/LER-1998-036, :on 981018,loss of Shutdown Cooling Was Noted. Caused by Personnel Opening Incorrect Electrical Cubicle Door.Learning Opportunities Re Incorrect Cubicle Door Were Communicated to Personnel & Training Will Be Improved1998-11-17017 November 1998
- on 981018,loss of Shutdown Cooling Was Noted. Caused by Personnel Opening Incorrect Electrical Cubicle Door.Learning Opportunities Re Incorrect Cubicle Door Were Communicated to Personnel & Training Will Be Improved
U-603103, Monthly Operating Rept for Oct 1998 for Clinton Power Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Clinton Power Station,Unit 1.With U-603101, Special Rept:On 980918,discovered That Triaxial Seismic Accelerometers Had Not Been Properly Calibrated.Caused by Inadequate Calibration Procedure.Calibration to Be Performed off-site1998-10-28028 October 1998 Special Rept:On 980918,discovered That Triaxial Seismic Accelerometers Had Not Been Properly Calibrated.Caused by Inadequate Calibration Procedure.Calibration to Be Performed off-site ML20154J0001998-10-0909 October 1998 Safety Evaluation Supporting Amend 117 to License NPF-62 ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves ML20154B6351998-10-0101 October 1998 Safety Evaluation Supporting Amend 116 to License NPF-62 U-603091, Monthly Operating Rept for Sept 1998 for Clinton Power Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Clinton Power Station,Unit 1.With ML20153F9871998-09-17017 September 1998 Safety Evaluation Accepting 980225 Proposed Rev 26 to Illinois Power Nuclear Program Qam ML20151U1391998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Clinton Power Station,Unit 1 ML20237E3991998-08-27027 August 1998 SER Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode, for Clinton Power Station ML20237D7041998-08-13013 August 1998 Safety Evaluation Supporting Amend 115 to License NPF-62 ML20237A1521998-08-0707 August 1998 SER Re Mgt Services Agreement at Clinton Power Station. Approval Under 10CFR50.80 Not Required 1999-09-08
[Table view] |
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Ithnc!s Power Company Canton Power Station P.O. Box 678 Chnton. IL 61127 Tal 217 935-0226 Fu 217 935-4632 J. Stephen Perry Senior Vice President ELLINf9lS u-602253 POWER US-940 2 - 14 )LP 2C.220 JSP-071-94 February 14, 1994 Docket No. 50-461 10CFR50.73 Document Control Desk Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Clinton Power Station - Unit 1 Licenlee Event Report No 94-001-00
Dear Sir:
Enclosed is Licensee Event Repart No. 94-001-00: Unexpf.cted Automatic Isolation of Reactor Core Isolation Cooling System during Channel Calibration Surveillance Due to Lifling wrong Thermocouple Lead. This report is being submitted in accordance with the requirements of 10CFR50.73.
l Sincerely yours, j
i
'. Perry
-)
Senior Vice Pr.ident l
RSF/csm Enclosure cc:
NRC Clinton Licensing Project Manager NRC Resident Oflice, V-690 Regional Administrator, Region 111,'USNRC lilinois Department of Nuclear Safety INPO Records Center
.220011
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940228013s 940214
{DR ADOCK 05000461 PDR
N3c FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5-92)
EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS
, LICENSEE EVENT REPORT (LER)
INFORMATION COLLECTION REQUEST:
50.0 HRS.
(ORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB (See reverse for required nunber of digits /chara *--- ror ech block)
W GTON, DC 20 55 0001, ND 0 THE APER k
REDUCTION PROJECT (3150 0104),
OfflCE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
I FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3) i C%nton Pnwer Statinn 05000461 1OF4 TITLE (4) Unexpected Automatic Isolation of Reactor Core Isolation Cooling System during Channel Calibration Surveillance Due to Lif ting Wrong Thermocouple Lead EVENT DATE (5)
LER NUMBER (6)
_RJPORT DATE (7)
OTHER F AClllTIES INVOLVED (8)
MONTH DAY VEAR YEAR SEQUENTIAL REVISI' ' MONTH DAY YEAR TACILITY NAME DOCKET NUMBER NUMBER NUM6U None 05000 01 15 94 94 001 00 02 14 94 F ACILIM NAME DOGET NUMBER None 05000 OPE RAT ING THIS REP _QRT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR H (Check one or more) ell)
MODE (9) 1 20.402(b) 20.405(c) y 50.73(a)(2)(iv) 73.71(b)
POWER 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v)
- 73. 71(c )
LEVEL (10) 100 20.405(a)(1)(ii) 50.36(c)(2)
- 50. 73(a)(2)( vi i )
OTHER
~
20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(vi i i )( A)
(specify in Abstract 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) below and in Text, 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
NRC Forrn 366A)
LICENSEE CONT ACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (include Area Code)
K. R. Foster, Plant Maintenance Specialist (217) 935-8881, Extension 3577 i
COMPL1TE ONE LINE FOR E ACH COMPONENT F AIf.URE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSlEM COMPONENT MANUFACTURER REPORTABLE
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS i
i SUPPLEMENT AL REPORT EXPECTED (14)
EXPECIED MONTH DAY YEAR YES y
NO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE).
DATE (15)
ABSTRACT (limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
With the plant at 100 percent reactor pressure, Control and Instrumentation Maintenance (C&I) technicians were performing a channel calibration surveillance on a Reactor Water Cleanup System heat exchanger room area temperature channel. The technicians reviewed the drawing to verify the correct field thermocouple termination to be lined, but then inadvertently lined a lead from a difTerent terminal, placing the Reactor Core Isolation Cooling (RCIC) system equipment room ambient temperature channel in a tripped condition. As a result, a RCIC steam supply containment isolation valve automatically closed and the RCIC pump turbine tripped from the standby q
mode. The RCIC system was restored within sixteen minutes. The cause of this event is personnel error. The technicians performed inadequate double verification and self-checking in locating and lining the field thermocouple lead. Unusual characteristics of the work area contributed to the cause of this event. Corrective actions include the technicians understanding their error, installing improved labeling and using maxi-grabbers to identify and mark leads to be lined.
4 l
1 hRC FORM 366 (5-92) l
NRC f0RM 366A U.S. NUCLEAR REGLLATORY COMMISSICD APPROVED BY OMB NO. 3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATloN COLLECTION REQUEST:
50.0 HRS.
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FORWARD COMMENTS REGARDING BURDEN ESilMATE TO THE INFORMATION AND RECPRDS MANAGEMENT BRANCH (MNBB 7714),
U.S.
NUCLEAR REGULATORY COMMISSION,
WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104),
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FAC!LITY NAME (1)
DOCKET NUMBE R (2) trR NUMBfR f61 PAGE (3) 05000461 YEAR SEQUENTIAL REvlSION 2 OF 4 NUMBER NUMBER Clinton Power Station 94 001 00 TEXT (if more space is required, use adattional copies of NRC Form 366A) (17)
DESCRIPTION OF EVENT
On January 15,1994, the plant was in Mode 1 (POWER OPERATION) at about 100 percent reactor [RCT]
power. Control and Instrumentation (C&I) Maintenance technicians were preparing to perform a channel calibration surveillance on Reactor Water Cleanup (RWCU) system [CE] heat exchanger [HX] room area temperature channel IE31-N620B [TS). The channel calibration is performed in accordance with sulveillance procedure CPS 9432.17, "RWCU Equipment Area Temp E31-N620A(B), E31-N621 A(B,E,F), E31-N622A(B),
E31-N626A(B) Channel Calibration "
At about 0840, the C&I technicians started the calibration. The surveillance procedure requires technicians to lin field thermocouple leads from terminal strip TB001, terminal 10, in panel [PL] 1H13-P714B to allow a simulated thermocouple input into the channel As directed by the surveillance procedure, the RWCU isolation function was placed in the bypass mode to prevent an RWCU system isolation during the channel calibration.
Prior to lining the leads, the technicians noted that the label identifying terminal numbers was missing from the terminal strip Recalling that corrective action from a previous error in lifting leads requires them to verify termin numbering using the wiring diagram anytime terminal numbering is unclear, the technicians left the area to consult the drawings. Before leaving, the technicians noted that the lead to be lifted was on the bottom terminal stri (TB001). Ilowe 'er, upon returning from reviewing the drawing, the technicians mistakenly located terminal 10 on the bottom row of screws but on the top terminal strip, TB003. As required by tne suiveillance procedure, two technicians verified the terminal location (double verification) for the lead to be lilled.
At about 0858 hours0.00993 days <br />0.238 hours <br />0.00142 weeks <br />3.26469e-4 months <br />, the technicians lifled the lead from the wrong terminal strip, TB003, terminal 10, which is located directly above terminal strip TB001, terminal 10 (the correct terminal).
Lifing the wrong lead placed Reactor Core Isolation Cooling (RCIC) system [BN] equipment room ambient temperature channel lE31-N602B in a tripped condition and completed the one-out-of-two trip logic for actuatin containment isolation valves in Group 5 (RCIC). As a result, Residual Heat Removal [BO] and RCIC steam supply inboard (Division 2) containment isolation valve [ISV] lE51-F063 automatically closed and caused the RCIC pump [P] turbine [TRB] to trip off from the standby mode.
Operators immediately recognized the unexpected automatic closure of valve IE51-F063 and directed the C&l echnicians to re-land the lifled lead and stop the channel calibration. Operators declared the RCIC system t
inoperable and entered the action of Technical Specification 3.7 3, " Reactor Core Isolation Cooling System." T ction allows continued plant operation while the RCIC system is inoperable, provided the High Pressure Core a
Spray (HPCS) system [BG) is operable. It requires the RCIC system to be restored to operable status within fourteen days or a plant shutdown must be initiated. The HPCS system was operable during this event.__
~U.S. NUCLEAa REGUL ATC37 b!SSION APPQOUED BV OMB NO. 3150-0104 EXPIRES 5/31/95 ES?tMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:
50.0 HRS.
'LICENBEE EVENT REPORT (LER)
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE TEXT CONTINUATION INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714),
U.S.
NUCLEAR REGULATORY COMMIS$10N, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104),
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1)
DOCKET NUMBER (2)
LER WUMBER f61 PAGE (3) 05000461 YEAR SEQUENTIAL REVISION 3 OF 4 NUMBER NUMBER Clinton Power Station 94 001 00 P
TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
At about 0901 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.428305e-4 months <br />, operators confirmed that the appropriate containment isolation valves closed by completing oft-normal procedure checklist CPS 4001.02C001, " Automatic Isolation Checklist."
By 0914 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.47777e-4 months <br />, the RCIC isolation trip signals were reset, isolation valve IE51-F063 was reopened, the RCIC system was restored to the standby mode, and the action of Technical Specification 3.7.3 was exited.
Condition Report (CR) 1-94-01-030 was initiated to track a root cause analysis and corrective action determination for the event.
No automatic or manually initiated safety system responses were necessary to place the plant in a safe and stable condition. No other equipment or components were inoperable at the start of this event to the extent that their inoperable condition contributed to this event.
CAUSE OF EVENT
The cause of this event is personnel error by the C&I technicians performing the channel calibration. The technicians properly reviewed the wiring diagram to identify the correct terminal when its location was in question.
Ilowever, the technicians performed inadequate dc.able verification and self-checking in locating the correct terminal in the field and as a result lifled the wrong lead, located on the terminal strip directly above the correct terminal.
Contnbuting to the cause of this event is the difficulty of performing surveillances in Leak Detection (LD) system [UJ panels due to congestion and obstructed terminals and labeling.
CORRECTIVE ACTION
The technicians responsible for causing this event fully understand the errors they made.
To decrease the potential for lifling the wrong leads, labels that are more visible have been installed on all thermocouple terminal strips in Main Control Room panels that have wires lifled during surveillance testing. In addition, all C&I technicians will be given orange maxi-grabbers for attaching to wires prior to lifting the leads.
The grabbers will be used to identify the wires to be lifled and will enhance visibility of the wires and ensure that momentary distractions will not cause the technician to lose track of the terminal being worked. Using the grabbers will also facilitate double verification of the lead to be lifled by allowing a technician to exit the panel so a second technician can enter the panel and verify the lead to be lifted.
NRC FORD 366A U.S. NUCLEAR QEGULATC3Y COMMISSION APPROVED B7 OMB NO. 3150-0104 f 2).
EXP!RES $/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THl$
INFORMATION COLLECTION REQUEST:
50.0 HRS.
' LICENSEE EVENT REPORT (LER)
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE TEXT CONTINUATION INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714),
U.S.
NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104),
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3) 05000461 YEAR SEQUEN11AL REVISION 4 OF 4 NUMBER NUMBrR Clinton Power Station 94 001 00 TEXT (if more space is required, use additional copies of NRC Form 366A) (17)
ANALYSIS OF EVENT
This event is reportable under the provisions of 10CFR50.73(a)(2)(iv) due to the unplanned automatic closure of containment isolation valve iE51-F063, an engineered safety features actuation.
Assessment of the safety consequences and implications of this event indicates that this event was not nuclear safety significant. The RCIC system responded to the RCIC equipment room high ambient temperature signal as designed by isolating the system. The RCIC system was in the standby mode at the time of this event. The HPCS system, the alternate means of providing reactor core cooling under high reactor vessel pressure conditions, was available and operable at the time of this event.
During this event, the RCIC system was inoperable from about 0858 hours0.00993 days <br />0.238 hours <br />0.00142 weeks <br />3.26469e-4 months <br /> until about 0914 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.47777e-4 months <br /> on January 15, 1994.
ADDITIONAL INFORMATION
No equipment or components failed during this event.
t A review of CPS LER history identified two events having similar circumstances. LER 87-016 discussed an unexpected automatic RCIC system isolation caused by personnel error in lifling the wrong lead. The specific cause of L.ER 87-016 was the failure to use available terminal block designation numbers when identifying the lead i
to be lifted Corrective actions included ensuring the involved personnel understood their mistake and briefmg others on lessons learned The corrective actions taken for LER 94-001 enhance the actions taken for LER 87-016.
LER 89-036 discussed an unexpected automatic RCIC system isolation caused by personnel error in failing to perform work at eye level and connecting a millivolt source to the wrong terminal. Corrective actions included ensuring that involved personnel understood their mistake; briefmg others on using ladders / stools so work is at eye level; applying difTerent color tape strips to terminal boards to enhance recognition of boards; revising procedures j
to reduce frequency of entering termination cabinets; and revising procedures to require installation of the millivolt cource in a deenergized state. The leads lifted in the event discussed in LER 94-001 were at eye level.
Corrective action for Condition Report 1-93-08-020 required labeling of terminals in the LD system panels.
Following the occurrence of LER 94-001, Illinois Power identified that this corrective action had not been completed in a timely manner. Therefore, CR 1-94-01-035 was initiated to track a root cause analysis and corrective action for this deficiency.
For further information regarding this event, contact K. R. Foster, Plant Maintenance Specialist, at (217) 935-8881, extension 3577.
hRC FORM 366A (5-92)
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05000461/LER-1994-001, :on 940115,unexpected Automatic Isolation of RCIC Sys Occurred During Channel Calibr Surveillance Due to Lifting Wrong Thermocouple Lead.Labels That Are More Visible Installed to Thermocouple Terminal Strips |
- on 940115,unexpected Automatic Isolation of RCIC Sys Occurred During Channel Calibr Surveillance Due to Lifting Wrong Thermocouple Lead.Labels That Are More Visible Installed to Thermocouple Terminal Strips
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | 05000461/LER-1994-002, :on 940201,MSIV Leakage Control Sys Dilution Air Flow Transmitter Making Transmitter Inoperable.Caused by Personnel Error.Instrument Valves for Transmitter 1E32-NO59 Labled & All Labling for Valves Enhanced |
- on 940201,MSIV Leakage Control Sys Dilution Air Flow Transmitter Making Transmitter Inoperable.Caused by Personnel Error.Instrument Valves for Transmitter 1E32-NO59 Labled & All Labling for Valves Enhanced
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000461/LER-1994-003, :on 940415,reactor Thermal Power Level Exceeded 100 Percent of Rate Thermal Power Due to Unexpected Reactor Recirculation System Flow Control Transient.Corrective Action:Replaced Solenoid & Controller Module |
- on 940415,reactor Thermal Power Level Exceeded 100 Percent of Rate Thermal Power Due to Unexpected Reactor Recirculation System Flow Control Transient.Corrective Action:Replaced Solenoid & Controller Module
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000461/LER-1994-004, :on 940413,during Lass Absence,No SRO Was in MCR & Requirements of TS 6.2.2.b Not Met.Caused by Untimely Action by Lass.Corrective Action:Counseling Lass & Discussing Event W/Senior Reactor Operators |
- on 940413,during Lass Absence,No SRO Was in MCR & Requirements of TS 6.2.2.b Not Met.Caused by Untimely Action by Lass.Corrective Action:Counseling Lass & Discussing Event W/Senior Reactor Operators
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | 05000461/LER-1994-005, :on 940408,while Reviewing Calculations,Concern Was Raised About Setpoints for Undervoltage Relay.Caused by Initial Design Error.Operator Has Received Training on second-level Undervoltage Scheme |
- on 940408,while Reviewing Calculations,Concern Was Raised About Setpoints for Undervoltage Relay.Caused by Initial Design Error.Operator Has Received Training on second-level Undervoltage Scheme
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000461/LER-1994-006, :on 940607,emergency DG Was Not Loaded to at Least 3869 Kw as Required by TS During Tests.Caused by Personnel Error.Replaced Optical Isolator Power Supply & Calibrated Optical Isolator Loop |
- on 940607,emergency DG Was Not Loaded to at Least 3869 Kw as Required by TS During Tests.Caused by Personnel Error.Replaced Optical Isolator Power Supply & Calibrated Optical Isolator Loop
| | 05000461/LER-1994-007, :on 940808,identified That Section 8.3 of Surveillance Test CPS 9031.14 Not Completed Prior to Entry Into Startup Mode Due to Inattention to Detail.Section 8.3 of Surveillance Test CPS 9031.14 Completed |
- on 940808,identified That Section 8.3 of Surveillance Test CPS 9031.14 Not Completed Prior to Entry Into Startup Mode Due to Inattention to Detail.Section 8.3 of Surveillance Test CPS 9031.14 Completed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000461/LER-1994-008, :on 940417,identified That Reactor Recirculation Pump Discharge Valves Outside Seismic Design Bases Due to Loose Yoke Connections.Cause Unknown.Loctite Applied to Threads of Studs/Nuts |
- on 940417,identified That Reactor Recirculation Pump Discharge Valves Outside Seismic Design Bases Due to Loose Yoke Connections.Cause Unknown.Loctite Applied to Threads of Studs/Nuts
| | 05000461/LER-1994-009, :on 941220,operator Failed to Initiate Operability of Offsite Ac Power Sources within One H After Declaring Div 3 EDG Inoperable Due to Oversight.Event Reviewed & Findings Discussed |
- on 941220,operator Failed to Initiate Operability of Offsite Ac Power Sources within One H After Declaring Div 3 EDG Inoperable Due to Oversight.Event Reviewed & Findings Discussed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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