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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000255/LER-1998-011, :on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With1999-09-0202 September 1999
- on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With
05000255/LER-1999-002, :on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With1999-08-20020 August 1999
- on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With
05000255/LER-1999-001, :on 990310,noted Failure to Perform TS Surveillance Channel Check of Auxiliary Feedwater Flow Indication.Caused by Misinterpretation of Definition of Channel Check.Implementing Procedure Has Been Revised1999-04-0909 April 1999
- on 990310,noted Failure to Perform TS Surveillance Channel Check of Auxiliary Feedwater Flow Indication.Caused by Misinterpretation of Definition of Channel Check.Implementing Procedure Has Been Revised
05000255/LER-1998-014, :on 981227,control Rod Drive Seal Housing Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking. Faulted Control Rod drive-2 Seal Housing Was Replaced1999-01-26026 January 1999
- on 981227,control Rod Drive Seal Housing Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking. Faulted Control Rod drive-2 Seal Housing Was Replaced
05000255/LER-1998-013, :on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With1999-01-20020 January 1999
- on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With
05000255/LER-1998-012, :on 981215,discovered That MSIVs Were Slightly Open Based on Local Stem Position.Caused by High Packing Friction Introduced by Packing Replacement During 1998 Rfo. Completed Actions to Assure MSIVs Will Fully Close1999-01-14014 January 1999
- on 981215,discovered That MSIVs Were Slightly Open Based on Local Stem Position.Caused by High Packing Friction Introduced by Packing Replacement During 1998 Rfo. Completed Actions to Assure MSIVs Will Fully Close
05000255/LER-1997-011, :on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced1998-10-29029 October 1998
- on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
05000255/LER-1998-010, :on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested1998-08-18018 August 1998
- on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
05000255/LER-1998-009, :on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of PCS Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired1998-06-30030 June 1998
- on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of PCS Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
05000255/LER-1998-008, :on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures1998-06-0909 June 1998
- on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures
05000255/LER-1998-007, :on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge1998-05-13013 May 1998
- on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge
05000255/LER-1997-013, :on 971110,determined Check Valves in Min Flow Recirculation Piping from Discharge of Each HPSI Pump Were Not Periodically Tested to Confirm Closure Capability.Caused by Inadequate Understanding.Database Revised1998-04-15015 April 1998
- on 971110,determined Check Valves in Min Flow Recirculation Piping from Discharge of Each HPSI Pump Were Not Periodically Tested to Confirm Closure Capability.Caused by Inadequate Understanding.Database Revised
05000255/LER-1998-006, :on 980305,personnel Determined That Operating Procedures Lacked Specific Guidance.Caused by Inadequate Procedures.Alarm Response Procedure 7 Was Revised1998-04-0606 April 1998
- on 980305,personnel Determined That Operating Procedures Lacked Specific Guidance.Caused by Inadequate Procedures.Alarm Response Procedure 7 Was Revised
05000255/LER-1998-005, :on 980217,actuation of Containment Isolation Occurred.Caused by Inadvertent Containment High Radiation Signal.Plant Status Evaluated & Equipment Lineups Restored1998-03-25025 March 1998
- on 980217,actuation of Containment Isolation Occurred.Caused by Inadvertent Containment High Radiation Signal.Plant Status Evaluated & Equipment Lineups Restored
05000255/LER-1998-004, :on 980216,notified Security That Escorted Visitor Had Inserted Her Keycard Into Exiting Turnstile Card Reader Upside Down.Caused by Primarily to Card Reader bleed- Through.Initiated Quarterly Surveillance to Verify Card1998-03-17017 March 1998
- on 980216,notified Security That Escorted Visitor Had Inserted Her Keycard Into Exiting Turnstile Card Reader Upside Down.Caused by Primarily to Card Reader bleed- Through.Initiated Quarterly Surveillance to Verify Card
05000255/LER-1998-003, :on 980113,watertight Door Were Found Improperly Latched.Cause Has Not Been Determined.Door 59 Was Verified Closed & Was Properly Latched1998-02-11011 February 1998
- on 980113,watertight Door Were Found Improperly Latched.Cause Has Not Been Determined.Door 59 Was Verified Closed & Was Properly Latched
05000255/LER-1998-002, :on 980112,potential Challenge to Channel Separation Was Noted.Caused by Inadequate of Temporary Mod. Specific Controls for Future Temporary Configuration Alterations Have Been Incorporated Into Plant Procedures1998-02-10010 February 1998
- on 980112,potential Challenge to Channel Separation Was Noted.Caused by Inadequate of Temporary Mod. Specific Controls for Future Temporary Configuration Alterations Have Been Incorporated Into Plant Procedures
05000255/LER-1998-001, :on 980101,large Leak of CCW During Power Operation Was Noted.Caused by Failure of Flanged Joint Rubber Gasket.Ccw Sys Was Refilled,Vented & Chemistry Restored to Normal1998-02-0202 February 1998
- on 980101,large Leak of CCW During Power Operation Was Noted.Caused by Failure of Flanged Joint Rubber Gasket.Ccw Sys Was Refilled,Vented & Chemistry Restored to Normal
05000255/LER-1997-012, :on 971017,deenergized Control Rods While in Power Operation.Caused by Failure of Individual Barriers to Prevent Inadequate Performance.Post Maint Testing Was Performed.Pages 5,6 & 7 of Incoming Submittal Not Included1998-01-26026 January 1998
- on 971017,deenergized Control Rods While in Power Operation.Caused by Failure of Individual Barriers to Prevent Inadequate Performance.Post Maint Testing Was Performed.Pages 5,6 & 7 of Incoming Submittal Not Included
05000255/LER-1997-013, :on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability1997-12-0909 December 1997
- on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability
05000255/LER-1997-010, :on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation1997-10-30030 October 1997
- on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation
05000255/LER-1997-009, :on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure1997-10-23023 October 1997
- on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure
05000255/LER-1997-008, :on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed1997-10-10010 October 1997
- on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed
05000255/LER-1997-007, :on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts1997-09-24024 September 1997
- on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts
05000255/LER-1996-013, :on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested1997-06-0303 June 1997
- on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested
05000255/LER-1997-006, :on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities1997-05-12012 May 1997
- on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities
05000255/LER-1997-004, :on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS1997-03-24024 March 1997
- on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS
05000255/LER-1997-005, :on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired1997-03-21021 March 1997
- on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired
05000255/LER-1997-003-01, :on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be Verified1997-03-21021 March 1997
- on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be Verified
05000255/LER-1997-002-01, :on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared Operable1997-02-21021 February 1997
- on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared Operable
05000255/LER-1997-001-01, :on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator Repaired1997-02-0505 February 1997
- on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator Repaired
05000255/LER-1996-014, :on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment1996-12-23023 December 1996
- on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment
05000255/LER-1996-002-01, :on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg1996-10-0404 October 1996
- on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg
05000255/LER-1996-012, :on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling Completed1996-09-0909 September 1996
- on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling Completed
05000255/LER-1996-011, :on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments1996-08-29029 August 1996
- on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments
05000255/LER-1996-005, :on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced1996-08-20020 August 1996
- on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced
05000255/LER-1996-010, :on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected1996-08-16016 August 1996
- on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected
05000255/LER-1996-009, :on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis Document1996-08-12012 August 1996
- on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis Document
05000255/LER-1996-006, On 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit1996-08-0202 August 1996 On 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit 05000255/LER-1996-003, :on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board1996-08-0101 August 1996
- on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board
05000255/LER-1996-008, :on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test Procedures1996-06-12012 June 1996
- on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test Procedures
05000255/LER-1995-001, :on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced Microprocessor1996-05-0101 May 1996
- on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced Microprocessor
05000255/LER-1996-007, :on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting Modified1996-04-22022 April 1996
- on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting Modified
05000255/LER-1994-012, :on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD1996-02-19019 February 1996
- on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD
05000255/LER-1996-004, :on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts1996-02-19019 February 1996
- on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts
05000255/LER-1996-001, :on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS1996-01-31031 January 1996
- on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS
05000255/LER-1995-016, :on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save PCS Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision1996-01-19019 January 1996
- on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save PCS Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision
05000255/LER-1995-014, :on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis Documentation1996-01-15015 January 1996
- on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis Documentation
05000255/LER-1995-013, :on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as Required1995-12-0404 December 1995
- on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as Required
05000255/LER-1995-012, :on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt Connections1995-11-0202 November 1995
- on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt Connections
1999-09-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr ML18066A6681999-10-0505 October 1999 Safety Evaluation Concluding That Licensee Performing Tendon Surveillance in Accordance with Requirements of Plant Ts. Recommends That Licensee Take Appropriate Actions to Avoid Problems as Described in in 99-10 ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML20211N8211999-09-0303 September 1999 Safety Evaluation Supporting Amend 187 to License DPR-20 05000255/LER-1998-011, :on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With1999-09-0202 September 1999
- on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With
ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6251999-08-26026 August 1999 Safety Evaluation Supporting Relief Request of Quality & Safety to License DPR-20 05000255/LER-1999-002, :on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With1999-08-20020 August 1999
- on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With
ML18066A6051999-08-0909 August 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With ML18066A5841999-07-26026 July 1999 Safety Evaluation Re Relief Requests 2 & Portion of 1 Are Authorized Per 10CFR50.55(a)(3)(i) on Basis That Alternative Provides Acceptable Level Od Quality & Safety.Requests 3,5 & 7 Results in Hardship.Staff Denies Requests 1,4 & 6 ML18066A5601999-07-13013 July 1999 Draft Safety Evaluation Supporting Licensee Proposed Conversion of Current TS for Palisades Plant to Its. Concludes That Public Health & Safety Will Not Be Endangered & That Activities Conducted in Compliance with Regulations ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With ML20206J9511999-05-0606 May 1999 Safety Evaluation Supporting Amend 186 to License DPR-20 ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML20205Q5511999-04-13013 April 1999 Safety Evaluation Supporting Amend 185 to License DPR-20 05000255/LER-1999-001, :on 990310,noted Failure to Perform TS Surveillance Channel Check of Auxiliary Feedwater Flow Indication.Caused by Misinterpretation of Definition of Channel Check.Implementing Procedure Has Been Revised1999-04-0909 April 1999
- on 990310,noted Failure to Perform TS Surveillance Channel Check of Auxiliary Feedwater Flow Indication.Caused by Misinterpretation of Definition of Channel Check.Implementing Procedure Has Been Revised
ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With ML20207F2611999-02-22022 February 1999 Safety Evaluation Supporting Amend 184 to License DPR-20 ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With ML18066A3871999-01-28028 January 1999 Safety Evaluation Accepting License Request for Staff to Authorize Consumers Energy Proposed Alternative to Requirements of ASME Section XI Article IWA-5250 for Degraded Primary Coolant Pump Casing Bolts at Plant 05000255/LER-1998-014, :on 981227,control Rod Drive Seal Housing Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking. Faulted Control Rod drive-2 Seal Housing Was Replaced1999-01-26026 January 1999
- on 981227,control Rod Drive Seal Housing Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking. Faulted Control Rod drive-2 Seal Housing Was Replaced
05000255/LER-1998-013, :on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With1999-01-20020 January 1999
- on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With
05000255/LER-1998-012, :on 981215,discovered That MSIVs Were Slightly Open Based on Local Stem Position.Caused by High Packing Friction Introduced by Packing Replacement During 1998 Rfo. Completed Actions to Assure MSIVs Will Fully Close1999-01-14014 January 1999
- on 981215,discovered That MSIVs Were Slightly Open Based on Local Stem Position.Caused by High Packing Friction Introduced by Packing Replacement During 1998 Rfo. Completed Actions to Assure MSIVs Will Fully Close
ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With ML18066A3591998-12-28028 December 1998 Safety Evaluation Authorizing Licensee Request to Use ASME OMa-1996,Subsection Istd, Preservice & Inservice Exam & Testing of Dynamic Restraints, as Alternative to Requirements of ASME OMa-1988,Part 4 for Plant ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 05000255/LER-1997-011, :on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced1998-10-29029 October 1998
- on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18068A4571998-10-14014 October 1998 Correction to Safety Evaluation of Third 120-month Interval Inservice Insp Program & Associated Requests for Relief. Error Was Made in Preparation of Evaluation ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18068A4391998-09-25025 September 1998 Safety Evaluation Re Licensee 950523 Submittal of Rept Which Summarizes Results of USI A-46 Implementation Program, Established in Response to Suppl 1 to NRC GL 87-02 Through 10CFR50.54(f) Ltr ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant 05000255/LER-1998-010, :on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested1998-08-18018 August 1998
- on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
LD-98-024, Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency1998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant 05000255/LER-1998-009, :on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of PCS Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired1998-06-30030 June 1998
- on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of PCS Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review 1999-09-30
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text
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consumers
,,Power.*
PllWERINli
. MlcHlliAtn l'IUlliRESS.
Palisades -Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 February 21, 1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk *
. Washington, DC 20~55 r*.
'DOCKET 50-255 - LICENSE PPR PALISADES PLANT Thomas J. Palmlsano Plant_ General Manager LICENSEE EVENT: REPORT 97-002 - FAILURE TO MEET TECHNICAL SPECIFICATIONS"4.5.2d(1 )(b) FOR TESTING OF THE EMERGENCY -
. Licensee Event.Report 97-002 is attached. This event is reportable in accordance with 1 O CFR Part 50. 73(a)'(2)(i)(B) as a-co.ridition prohibited by Technical Specifications.* -*
SUMMARY OF COMMITMENTS This letter contains n6 new commitments and no revisions to existing commitments.
- -- -*----9703030529 97022l
- --- ' -- **.*:* ---~--, - ----
... PDR ADOCK 05000255 S
PDR
.~r~ ~
Thomas J. Palmisano -
Plant General Manager CC Administrator, Region.Ill, USNRC.
Project Manager, NRR, USNRC NRC Resident Inspector - Palisades Attachment 030100 1muDillIE111rn1nm~11U 11101m 1rn
A CMS' ENERGY COMPANY
NRC FORM388 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3160-4104 *.
(4195)
EXPIRES 4130/98 ES'IUlf<TED 1U1DEN PER RESPONSE TO COMPLY wmi lHIS MANDATORY INFORMATION COUECTION REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED LICENSEE EVENT REPORT. (LER)
INTO "!ME LICENSING PROCESS Nill FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT I* * ~. *.:..
BRANCH (T-1 F33);U.S. MJCLEAR REGULATORY COMMISSION, WASHINGTON, DC 2055S-0001, Nill. TO THE PAPERWORK REDUCTION PROJECT (315G-ll11W, OFFICE OF (See reverse for required number of digits/characters for each block)
MANAGEMENT Nill BUDGET, WASHINGTON. DC 20503 FACILITYNAME(1) CONSUMERS POWER COMPANY ER(2)
JR>of4 PALISADES NUCLEAR PLANT 05000255 TITLE (4) LICENSEE EVENT REPORT 97-002-FAILURE TO MEET TECHNICAL SPECIFICATIONS..:i.5.2d(1)(b) FOR TESTING OF THE EMERGENCY ESCAPE AIRLOCK EVENT DATE (5)
LER NUMBER (6)
REPORT DATE m OTHER FACILITIES INVOLVED (8)
MONTH D~Y YEAR YEAR I SEQUENTIAL REVISION MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NUMBER 05000 01
- 97.
FACILITY NAME DOCKET NUMBER 05000
. OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check one or more) (11)
MODE (9)
N 20.2201(b) 20.2203(a)(2)(v) x 50.73(a)(2)(i) 50.73(a)(2)(iii)
POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x)
LEVEL (10) 99.6 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71
- - i 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv)
OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v)
Specify in Abstract below or 20.2203{a){2){iv) 50.36{c){2) 50.73{a){2){vli) in NRC Form 366A LICENSEE CONTACT FOR THIS LER (12)
NAME
)
TELEPHONE NUMBER (Include Area Code)
Charles S. Kozup, Licensing Engineer
. (616) 764-2000 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT {13)
CAUSE**
SYSTEM COMPONENT MANUFACTURER, REPORTABLE
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPR_DS roNPRDS SUPPLEMENTAL REPORT EXPECTED (14)
MONTH DAY.
YEAR I YES x* I NO EXPECTED If.yes COMPLETE EXPECTED COMPLETION DATE SUBMISSION DATE {15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On.January 23, 1997, the plant was operating at 99.6% power.. During the*preparation of the P.alisades Improved Technical Specifications, it was recognized that Palisades was not in.
compliance with the Technical Specification Surveillance reql,.lir.ement 4.5.2d(1 )(b) for the emergency eseape air lock. At J528 on January 23, 1997, the emergency escape air-lock was ** -
declared inoperable and Technical Specification 4.0.3 was entered due. to the missed surveillance.
At 101 O on January 24, 1997, the emergency escape air lock testing was completed and the emergency escape air lock was d~clared operable.
Technical Specifications.
This testing restored compliance with
i I 4195 U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME 11 l PALISADES NUCLEAR PLANT LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKETl2\\
LER NUMBER 6l 05000255 YEAR I SEQUENTIAL REVISION NUMBER NUMBER
. 97 -
002 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
EVENT PESCRIPTION PAGE 13l 20F4 On January 23, 1997, the plant was operating at 99.6% power. During the preparation of the Palisades Improved Standard Technical Specifications, it was recognized that Palisades was not in compliance with the Technical Specification Surveillance requirement 4.5.2d(1 )(b), for the emergency escape air lock. This paragraph requires "... a reduced pressure test.for the door seals or a full air lock penetration test shall be performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after either each air lock door opening.... " At 1528 on January 23, 1997, the emergency escape air lock was declared inoperable and Technical Specification 4.0.3 was entered due to the missed surveillance. Technical Specification 4.0.3 allows for a delay up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to complete the surveillance prior to taking the required t~chnical specification action. The emergency escape air lock was tested to restore compliancewith Technical Specifications and declared operable at 1010 on January 24; 19~7.
This testing restored compliance with Technical Specifications.
- The Palisades emergency* escape air lock does not provide the capability to perform unrestrained between-the-seals tests. In our Licensee Event Report 87-026, dated September 21, 1987, we stated that we would perform a seal contact inspection and adjustment after every strongback removal. The practice at Palisades has been to reopen the outer door to gain access. to the.inner door to remove t~e strongbacks needed to perform the full air lock testing. In addition, the inner door is opened and both the inner and the outer door seals are inspected and adjusted if necessary to ensure seal contact* after the test.
On April 21, 1989, the NRC issued a violation to Palisades for failing to test the emergency escape air lock doors within three (3) days of opening the door. On May 22, 1989, we responded to the Notice of Violation and explained our position. On June 30, 1989, we submitted *our written do~umentation regarding the equivalency of a seal contact check to a between-the-seals test. In this submittal, we explained our plans to continue to use the-present methods for emergency -* *.--*
escape air lock testing.. *
. On June 1, 1989, the NRC approved a Technical Specification.change request, which made the 1 O CFR 50, Appendix J, testing requiremehts a part of Technical Specifications~ At that time, it was not recognized that the failure to pressure test as specified in Appendix J then became a Technical Specification violation in addition to being a violation of Appendix J.
A Technical Specification change request which requested approval of our current practices was submitted on March 25, 1991, but was withdrawn on July 29, 1991. On January 10, 1996, the Technical Specification change request was resubmitted with a Request for Exemption from 1 o CFR 50 Appendix J.
!. 4195 FACILITY NAME 11 l PALISADES NUCLEARPLANT U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET I?\\
05000255 LER NUMBER 6l YEAR I SEQUENTIAL ! REVISION NUMBER I NUMBER 97 -
00 2 -
00 PAGE 13l 30F4 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
CAUSE OF THE EVENT
The cause of this event was that in 1989, the Palisades personnel did not recognize that continuing the testing practices that were in place had become a violation of the Technical.
Specifications when the June 1, 1989, Technical SpecificationAmendment on containment penetration testing was issued by the NRC. This oversight occurred because the issues associated with the emergency escape air lock had been discussed previously with the NRC, and we believed we were technically justified in ou~ approach and our interpretations, and were*
proceeding on a course of action which ~ould resolve the outstanding issues. However, we.
overlooked the* fact that additional actions would be required to place the plant back in.to compliance with the Technical Specifications.
SAFETY SIGNIFICANCE
This 'occurrence has no safety significance. The Palisades technical position *had b~en previously docum~nted to the NRC on May 22 and June 30, 1989. The emergency escape air lock remained eapable of satisfying its design basis to se.al under accident conditions.
CORRECTIVE ACTION
The emergency escape air lock was tested to comply with the surveillance requirement. This..
testing restored compliance with Technical.Specifications on January 24, 1997.
- On January 26, 1997, the E)mergency escape air lock was tested again.. After this test,. the strongbackswere left on the*innerdoor, *eliminating th_e.. need'to open the"outerdoor fo remove the -
strongbacks. A temporary plant n:iodification had been processed to document that continued plant operation was satisfactory with the strongbacks on the inner door until the NRC completes its review of the pending Technical Specification chang~ request and the Request for Exemption to 10 CFR 50, Appendix J. This strongback prevents the opening 9f the emergency escape air lock inner door rendering it non-functional for egress from the containment, until the strongback can be removed by accessing it from outside of containment.
,; 4195 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION
- - nnCKETI?\\
PALISADES NUCLEAR 'PLANT
'LER NUMBER jS\\
YEAR I SEQUENTIAL NUMBER REVISION NUMBER 97 -
002 00
- TEXT (If more space Is required, use additional copies of NRC Form 366A) (17)
P4GE l3l 40F4 A majorTechnical*Specification change request is currently being developed to convertPalisades Technical Specifications to emulate the content and format of Improved Standard Technical Specifications. The plant review of this change will involve verification that the plant procedures correctly implement all requirements of the new Technical Specifications. This review will be sufficient to assure that all Technical Specification requirements are implemented.
PREVIOUS EVENTS Other events associated with containment integrity and air locks are License Event Reports 87~
026, dated September 21, 1987, and 83-.066, dated November 5, 1983.
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05000255/LER-1997-001-01, :on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator Repaired |
- on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator Repaired
| 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) | 05000255/LER-1997-002-01, :on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared Operable |
- on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared Operable
| 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 | 05000255/LER-1997-003-01, :on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be Verified |
- on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be Verified
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | 05000255/LER-1997-004, :on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS |
- on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS
| 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)(x) 10 CFR 50.73(a)(2)(iii) | 05000255/LER-1997-005, :on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired |
- on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired
| 10 CFR 50.73(a)(2) | 05000255/LER-1997-006, :on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities |
- on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities
| 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) | 05000255/LER-1997-007, :on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts |
- on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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 | 05000255/LER-1997-008, :on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed |
- on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed
| 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)(x) 10 CFR 50.73(a)(2)(iii) | 05000255/LER-1997-009, :on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure |
- on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | 05000255/LER-1997-010, :on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation |
- on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation
| 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)(x) 10 CFR 50.73(a)(2)(iii) | 05000255/LER-1997-011-01, Forwards LER 97-011-01 Re Starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps.Commitment,Listed | Forwards LER 97-011-01 Re Starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps.Commitment,Listed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000255/LER-1997-011, :on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced |
- on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
| | 05000255/LER-1997-012, :on 971017,deenergized Control Rods While in Power Operation.Caused by Failure of Individual Barriers to Prevent Inadequate Performance.Post Maint Testing Was Performed.Pages 5,6 & 7 of Incoming Submittal Not Included |
- on 971017,deenergized Control Rods While in Power Operation.Caused by Failure of Individual Barriers to Prevent Inadequate Performance.Post Maint Testing Was Performed.Pages 5,6 & 7 of Incoming Submittal Not Included
| | 05000255/LER-1997-013, :on 971110,determined Check Valves in Min Flow Recirculation Piping from Discharge of Each HPSI Pump Were Not Periodically Tested to Confirm Closure Capability.Caused by Inadequate Understanding.Database Revised |
- on 971110,determined Check Valves in Min Flow Recirculation Piping from Discharge of Each HPSI Pump Were Not Periodically Tested to Confirm Closure Capability.Caused by Inadequate Understanding.Database Revised
| 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) | 05000255/LER-1997-013, :on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability |
- on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability
| 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)(iii) |
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