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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18066A6271999-09-0202 September 1999 LER 98-011-01: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 990902 Ltr ML18066A6221999-08-20020 August 1999 LER 99-002-00: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 990820 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01: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 ML18066A2831998-08-18018 August 1998 LER 98-010-00: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 ML18066A2261998-06-30030 June 1998 LER 98-009-00: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 ML18066A1781998-06-0909 June 1998 LER 98-008-00: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 ML18065B2451998-05-13013 May 1998 LER 98-007-00: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 ML18065B1151997-12-0909 December 1997 LER 97-013-00: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 ML18067A7751997-11-11011 November 1997 LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved ML18067A7581997-10-30030 October 1997 LER 97-010-00: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 ML18067A7461997-10-23023 October 1997 LER 97-009-00: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. ML18067A7191997-10-10010 October 1997 LER 97-008-00: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 ML18067A6951997-09-24024 September 1997 LER 97-007-00: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 ML18067A5651997-06-0303 June 1997 LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested ML18067A5461997-05-12012 May 1997 LER 97-006-00: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 ML18067A4431997-03-24024 March 1997 LER 97-004-00: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 ML18067A4391997-03-21021 March 1997 LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired ML18067A4401997-03-21021 March 1997 LER 97-003-00: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.W/970321 Ltr ML18066A8931997-02-21021 February 1997 LER 97-002-00: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.W/970221 Ltr ML18066A8751997-02-0505 February 1997 LER 97-001-00: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.W/970205 Ltr ML18066A8041996-12-23023 December 1996 LER 96-014-00: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 ML18066A7831996-12-16016 December 1996 LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced ML18065A9951996-10-0404 October 1996 LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg ML18065A9171996-09-0909 September 1996 LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr ML18065A8961996-08-29029 August 1996 LER 96-011-00: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 ML18065A8811996-08-20020 August 1996 LER 96-005-01: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 ML18065A8741996-08-16016 August 1996 LER 96-010-00: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 ML18065A8651996-08-12012 August 1996 LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr ML18065A8601996-08-0202 August 1996 LER 96-006-01 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 ML18065A8321996-08-0101 August 1996 LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board ML18065A7691996-06-12012 June 1996 LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr ML18065A6901996-05-0101 May 1996 LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr ML18065A6681996-04-22022 April 1996 LER 96-007-00: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.W/960422 Ltr ML18065A5721996-03-11011 March 1996 LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded ML18065A5261996-03-0101 March 1996 LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr ML18065A5111996-02-19019 February 1996 LER 94-012-02: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.W/960219 Ltr ML18065A5061996-02-19019 February 1996 LER 96-004-00: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 ML18065A5021996-02-15015 February 1996 LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr ML18065A4581996-01-31031 January 1996 LER 96-001-00: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.W/960131 Ltr ML18065A4421996-01-19019 January 1996 LER 95-016-00: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.W/960119 Ltr ML18065A4041996-01-15015 January 1996 LER 95-014-00: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.W/960115 Ltr ML18065A3291995-12-0404 December 1995 LER 95-013-00: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.W/951204 Ltr ML18065A2361995-11-0202 November 1995 LER 95-012-00: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.W/951102 Ltr ML18065A2051995-10-20020 October 1995 LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised ML18065A0841995-09-18018 September 1995 LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr ML18065A0681995-09-14014 September 1995 LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line ML18065A0651995-09-0808 September 1995 LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment ML18064A8781995-08-28028 August 1995 LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage ML18064A8831995-08-21021 August 1995 LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr 1999-09-02
[Table view] Category:RO)
MONTHYEARML18066A6271999-09-0202 September 1999 LER 98-011-01: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 990902 Ltr ML18066A6221999-08-20020 August 1999 LER 99-002-00: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 990820 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01: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 ML18066A2831998-08-18018 August 1998 LER 98-010-00: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 ML18066A2261998-06-30030 June 1998 LER 98-009-00: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 ML18066A1781998-06-0909 June 1998 LER 98-008-00: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 ML18065B2451998-05-13013 May 1998 LER 98-007-00: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 ML18065B1151997-12-0909 December 1997 LER 97-013-00: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 ML18067A7751997-11-11011 November 1997 LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved ML18067A7581997-10-30030 October 1997 LER 97-010-00: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 ML18067A7461997-10-23023 October 1997 LER 97-009-00: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. ML18067A7191997-10-10010 October 1997 LER 97-008-00: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 ML18067A6951997-09-24024 September 1997 LER 97-007-00: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 ML18067A5651997-06-0303 June 1997 LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested ML18067A5461997-05-12012 May 1997 LER 97-006-00: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 ML18067A4431997-03-24024 March 1997 LER 97-004-00: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 ML18067A4391997-03-21021 March 1997 LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired ML18067A4401997-03-21021 March 1997 LER 97-003-00: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.W/970321 Ltr ML18066A8931997-02-21021 February 1997 LER 97-002-00: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.W/970221 Ltr ML18066A8751997-02-0505 February 1997 LER 97-001-00: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.W/970205 Ltr ML18066A8041996-12-23023 December 1996 LER 96-014-00: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 ML18066A7831996-12-16016 December 1996 LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced ML18065A9951996-10-0404 October 1996 LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg ML18065A9171996-09-0909 September 1996 LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr ML18065A8961996-08-29029 August 1996 LER 96-011-00: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 ML18065A8811996-08-20020 August 1996 LER 96-005-01: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 ML18065A8741996-08-16016 August 1996 LER 96-010-00: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 ML18065A8651996-08-12012 August 1996 LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr ML18065A8601996-08-0202 August 1996 LER 96-006-01 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 ML18065A8321996-08-0101 August 1996 LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board ML18065A7691996-06-12012 June 1996 LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr ML18065A6901996-05-0101 May 1996 LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr ML18065A6681996-04-22022 April 1996 LER 96-007-00: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.W/960422 Ltr ML18065A5721996-03-11011 March 1996 LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded ML18065A5261996-03-0101 March 1996 LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr ML18065A5111996-02-19019 February 1996 LER 94-012-02: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.W/960219 Ltr ML18065A5061996-02-19019 February 1996 LER 96-004-00: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 ML18065A5021996-02-15015 February 1996 LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr ML18065A4581996-01-31031 January 1996 LER 96-001-00: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.W/960131 Ltr ML18065A4421996-01-19019 January 1996 LER 95-016-00: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.W/960119 Ltr ML18065A4041996-01-15015 January 1996 LER 95-014-00: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.W/960115 Ltr ML18065A3291995-12-0404 December 1995 LER 95-013-00: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.W/951204 Ltr ML18065A2361995-11-0202 November 1995 LER 95-012-00: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.W/951102 Ltr ML18065A2051995-10-20020 October 1995 LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised ML18065A0841995-09-18018 September 1995 LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr ML18065A0681995-09-14014 September 1995 LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line ML18065A0651995-09-0808 September 1995 LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment ML18064A8781995-08-28028 August 1995 LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage ML18064A8831995-08-21021 August 1995 LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr 1999-09-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr. ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML18066A6271999-09-0202 September 1999 LER 98-011-01: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 990902 Ltr 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 ML18066A6221999-08-20020 August 1999 LER 99-002-00: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 990820 Ltr ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr 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 990402 Ltr 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 990302 Ltr ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr 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 990105 Ltr ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr 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 981103 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01: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 ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant ML18066A2831998-08-18018 August 1998 LER 98-010-00: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 ML18066A2771998-08-13013 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 ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A2261998-06-30030 June 1998 LER 98-009-00: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 ML18066A1781998-06-0909 June 1998 LER 98-008-00: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 ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18066A1741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr ML18066A2321998-05-31031 May 1998 Revised MOR for May 1998 for Palisades Nuclear Plant ML18068A4701998-05-31031 May 1998 Annual Rept of Changes in ECCS Models Per 10CFR50.46. ML18065B2451998-05-13013 May 1998 LER 98-007-00: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 ML18066A2331998-04-30030 April 1998 Revised MOR for Apr 1998 for Palisades Nuclear Plant ML18068A3461998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML18065B2071998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18066A2341998-03-31031 March 1998 Revised MOR for Mar 1998 for Palisades Nuclear Plant ML18068A3041998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr ML18066A2351998-02-28028 February 1998 Revised MOR for Feb 1998 for Palisades Nuclear Plant ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML18067A8211998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr 1999-09-30
[Table view] |
Text
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consumers
. General Manager POWERlNli lllllCHlliAN-S PROlillESS .
- 27780 .Blue Star Meinc>ria~. Highway. Covert. Ml 49043
April 27, 1992
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LICENSE *DPR"'20 "'_. Oi>A~rsADEs !>.LANT*~ *
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DOC.KET .50-255 . * * ,.
. L.ICENSEE EVENT REPORT 92'-024 ~-- INADVERTENT' OPENING OF* THE STATiON POWER* ..
Li,~en'see Event Report. ( LER) 92--024 is. attached.<*...Thi's event* is* rep.ortabl e *i rf..-. *. *. *. :~...* .*
- . -accordanc.e w*ith 10CFR50. 73 ( a)(2H iv)' as an* eveh(that -res~lted, in ari 'automa't i c *. * .
~ctuation'*of an engineered- safety *feature. *: * * * * * *
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I :1 I On March 27~ 1992, at 2226 ho~rs, with the plant in cold shutdown, s~utdo~n cooling flow ~as interrupted ~hen ~he 'C' bus ~u,plyirig power to t~e operating
- shutdown cooling pump was de-energized as a resu t of reaker testing on the station powet breaker. Und~rvoltage on the 'C~ bus resulted in both diesel generators starting. The interruption of shutdown coolinJ lasted for .. _ .
a~proximately four minutes. Durin~ the shtitdown cooling luw ihterrµption, t e core exit temperature increase approximately stx degrees fahrenheit.
- 1wo root causes for this event f:!X*ist. . The Shift Supervisor allowed work to proceed on the 'C' bus despite the ~ufdance provided. to him b{ the Operations Scheduler, and contrary to information provided in the ~enera operating procedures. In addition, *work proteeded beyond that whic~ was .authorized by the* Shi ft Sup.ervi sor. , * . * . ** .
.
Corrective action for this event included-immediate action to discuss the event with all mainten~nce and operations work shifts emphasizing the problems associated with deviating from procedures and approved work scope. Further corrective action includes evaluating the use of a more formal communications policy within the maintenance departments, training electrical repairman and supervisors on the breaker testing requirements .stated in administrative grocedures~ defining expectations for th~ responsibility of operating * .
reakers, relocating the taution placards to a more visible location within the breaker cubicle, evaluate modifyin~ the start-up and station safe~uards breakers to prevent operation in the -" est pas it ion, and modifying t e .
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operating prqcedure '
as necessary.
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- LICENSEE -NT AEP()AT ILIA> TEXT CONTINUA-N Palisades Plant T1llT ,. _ . . . ._._. __ _ _ltl/C ,,..,.._ ...." 1111
- EVENT DESCRIPTION On March.27, 1992, at 2226 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.46993e-4 months <br />, with the plant in cold ~hutdown, shutdown cooling was temporari.ly interrupted when the 'C' bus su~plying power to the
-0perating shutdown cooling pump [B~;P] was de-energized as a result ~f breaker testing on the station power breaker [FK;BKR]. Undervoltage on the
- c bus 1 1 resulted in both diesel- generators starting. The interruption of shutdown*
~ooling lasted for approximately four minutes. During the interrupti~n of shutdown. tooling, the pr.iniary coolant system (PCS) [AB] temperature increased.
S°F; based on one ~ore exit thermocouple, 7°F, based.on ariothet core exit thermocouple, and 1°F based on the s*hutdown cooling heat exchanger in let temperature t~ermocouple .. The .initial PCS temperature wa~ approximately 82°F.
This event is reportable to the NRC in a~co~dance with 10CFR50~73la)(~)(iv) as an ~vent that resulted *in an automatic actuation of an engineered safety .
feature (diesel generators).
CAUSE OF THE EVENT Two root causes for th{s event ~xist~:The Shift Supervisor.allowed work to proceed on the 'C' bus despite the guidance provided to *him by the Operations
- Scheduler, and contrary to information provided in the general' operating.
procedures.. In aqdition*, work pro~eeded beyond that which was authorized by the Shift Supervisor.*. * *
- This event does not involve the failure of any equi pm~nt i_mportant to safety.
ANALYSIS OF THE EVENT The P~lisades ~afety related Electr~cal Distribution System consist~ of two 2400V electrical buses which supply power to numerous loads in the plant, including the low pressure safety injection (LPSI) pumps which ~erve as the .
. Shutdown Cooling pumps. Each of these buses are normally powered by one of the following incciming breakers:* _:
- Diesel.Power These breakers have three possible positions wfthin their cubicles~ 1.
- Disconnect position - is the position in which the control power is disconnect~d from the breaker, the interlocks are not connected, and the
.breaker cannot be connected to a load. 2. Test position - in: this position
.control power* is conn~cted to the breaker, the interlocks are connected, and the breaker cannot be connected to i load. 3. Connect position - in which the control power is connected to the breaker, the interlocks are connected, and the breaker can be connected to a load.
CONTINUA~
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.It .is normal plant policy during shutdown cooling operations to maintain two independent power sources available to each of the two safety related buses,
'C' and 'D'. This is controlled via the operating proced~res. Also, the Operations Scheduling Supervisor communicates these requirements to the operating crews via the following:
- This infor~atiori is tontained in general operating procedure (GOP) 14, "Shutdown Cooling Operations;" Step 6.5.a and band is the ~ethod used to control equipment status with respect to Shutdown Risk Management iss~es.
Earlier in the 1992 Refueling Outage, the station safeguards supply breaker charging motor failed to stop when requ.ired. A spare breaker was placed in the breaker cubicle on the 'C.' bus and maintenance was performed on the normal
- breaker. On the "day~ shift of March 27~ 1992, the spare breaker was.replaced with the.normal breaker and subsequent testing indicated that the problem still existed with the normal breaker. As a result, the normal breaker was again .removed from the cubicle and the spare was put back in the 'C' bus. .
- This work was performed with all loads, including the operating shutdown cooling pump P-67A, po~er~d from 'D' bus. At. the end of the "day" shift on* .
March 27, 1992,. the safety related electrical distribution system was aligned with 'C' bus supplying all loads .. At that time, *'C' bus'. was powered from the.
itation safeguards power supply breaker;_ The 'D'. bu~ was not supplying loads because* testing on the 'D' bus was scheduled for *the _foll owing day.
Early ~n t~e "afternoon" shift of March 27, 199~, electrical mai~tenance
- finished work on the normai station safeguards breaker charging*motor. The
- breaker was successfully tested five times outside of the.cubicle. Based on the result~ of the succe~sf~l tests, the electrical repairman in charge
~equested that the spare ~reaker be removed from the cubicle and the normal breaker installed. The *shift Supervisor discussed the request with 'the Shift
- Enginee~ and dete~mined that the work could b~ compl~ted ~ith mini~um risk.
The Shift Supervisor and Shift Engineer discussed two options to complete the
. '
- Transfer all loads to*'D' bus, or;
- Trarisfer. 'C~ bus supply power from the station safeguards breaker to the start-up breaker (the alternate power supply).
. . .
The Shift Superv*isor elected to swap the 'C' bus supply from the station
. safeguards ~upply breaker to the start-up supply breaker. This transfer ~as successfully crimpleted. However, the electrical configuration did not comply ~ .
with* the Shutdown Cooling Equipment Availability sheets provided to the
Control Room by the Operations Scheduling Supervisor per General Operating Procedures (GOP) 14; "Shutdown Cooling Operations."
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Palisades Plant T'DT_1*~-* .... -~~_,..,.J!lllll'.~1171 The Shift Supervisor directed an Auxiliary Operator (AO).remove the 'spare' station safeguards supply.breaker from 'C' bus and replace it with the*normal breaker as the electrical repair-worker had requested; The Shift Supervisor directed the AO to leave.the normal breaker in the "conned" position with the chargirig.motor fuses installed. The control power fuses were not installed.
This would ~llow racking in the breaker but not allow breaker operation. The Shift Supervisor did not give permission to either the AO or the. electrical
.repair-worker*to do anything else with the breaker in the cubicle other than leave* it in the. "connect" position with charging motor fuses installed. The
- AO completed the work as di.rected by the Shift Supervisor .. During this time P-67A, _the operating shutdown ~o~ling pump, was powered from the 'C' bus,* ,
which in turn was supplied from the start-up power supply breaker.
- . Th~ Electri~al Mai~tenance Supervisor requested the electrical repair-worker and the AO to place the brea~er in the "test" position and to close the .
- breaker to test the charging motor. The Electrical Maintenance Supervisor
- wanted to ensure the charg,ing motor functioned properly and, therefore,. felt
- this action was w~rranted~
- Neither the AO or the electriccil repair-worker questioned the req~est based on their understanding of the approved ~ork scope.: .Caution signs* existed fn twtr areas. One on. the inside .of the start-:UP and stati oii safeguards breaker cu bi cl es to warri operators not to close the *
. breakers whjle the b~e~ker was in the "test"* position. These signs ara*poorly * *'
Jocated and are not rea~ily visib_le .. A second_ tautior:i sign js.on the outside . **,.*
of the breaker panel stating testing shall be done per Administrative Procedure 4w02. Wheri ~he breaker ~as .closed while in the "test" position, th~,
start-up power supply breaker opened and 'C' bus de-energized. The relay logic fo~ the start-up breakers and the Station* safeguards breakers on 'C' and
'D' bus is such that the.-bus. cannot be supplied from two power sources... Since the operating ~hutdown cooling pump was supplied from 'C' bus,* shutdown cooling was iriterrupted. * * .
RESPONSE_ TO EVENT
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Both di eselS gene.raters started* as a result of 1ow voltage on 'C' ,bus. The 1-1 diesel generator *did not synchronize to 'C' bus because the control power.
fuses were r:ibt installed iri the station safeguards breaker. This allowed the
- diesel generator logic to respond as. if.the station safeguards breaker was c.losed .to the bus. The .'D' bus was already powered from station* safeguards, the~efore, the 1-2 diesel generate~ did not synchronize to the bus~ The operator's responded using the Off-Normal* Operating Procedure (ONP} 17, "Loss
- of Shutdown* Cooling," and.manually latched the synchroniiing relay, allowing the. 1-1 diesel generator to synchronize to 'C' bus. The automatic load *
- sequencers then placed loads -0n 'C' bus. -LPSI pump P-678 was started after throttling closed.the injection.valves and shutdown cooling was restored less that 4 minutes after the ~C' bus initially de-energized. PCS temperature increased approximately seven d~grees fahrenheit. .
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On Monday, March 30, 1992, a Management .Review Board (MRB) was he_ld to review the Loss of 'C' b~s. and interruption of Shutdown Cooling incident which occurred on Friday, March 27, 1992. Th~ MRB was convened and clarified the following facts presented in the "Plant Personnel *statements" contained in the
- .Post-Trip Review Report.
- The Shift Supervisor releas~d the ~ork to th~ electric~1 repair-worker to test the breaker charging .motor in the 11
~onnect 11 position while the breaker was in the cubitle.
- The Shift Supervisor directed the AD.tQ refuove the e~isting (spare) breaker from the station start-up power breaker cubicle and to install the repaired (nor~al) breaker in the cubicle, leavin~ the.break~~ irr,the "connect" position and with the charging motor fuses installed. (The. * :
control power fuses were not installed.)
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- The discussions with the. AO and the electrical repair:..worker were independent af each other~** The AO was .unaware of the scope cif work for
- .which-the electrical repair-worker was approved. .
- The Ele.ctrical Maintenance Supervisor was not .involved in* either.of the conversations with the.Shift Supervisor and was, therefore, unaware of the approved scope of work. *. * *
- When the normal breaker was i~stalled in the cubicle, only the chargin~
motor .fuses were installed. The contra 1 power fuses were not i nsta 11 ed~.
- Wheh ~he Electrital *Maintenance Supervisor. requested the electrical repair-worker and AO to place the breaker in ~he "test" position and close th~ breaker, neither the electrical ~epair-worker or AO questioned the request based on their understanding of the approved work scope.
- The electrical repair-work.er racked the breaker from the "connect"
- position to the "test" position and closed the breakei. '(Th~ operation of equipment is the responsibility of the Operations Department.)
- The Shift Supervisor did not feel the work he authorfzed (transferring
'C' bus power from the station safeguards supply breaker to the start-up .1 supply breaker and replacing the station start-up breaker while lEaving the breaker in the "connect" position to test the tharging motor) was a
- risk to shutdown safety. *
- T~e-taution signs inside the br~aker cubicles, which had been placed* in the.cubicles as a tesult -0f ~revious similar events, were not clearly visible to the workers.
' ~.
- The caution* signs on the. front of the breaker cubicles, which state that .'
breaket t~sting shall be performed in a~cordance with the requirements of Administrative Protedure 4.02, "Control of Equipment Status," did not stop the event.
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ILi~> TEXT CONTINUA.
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- The* El ectri cal Mai ntehanc;e Super.visor *and e lectri cal . repair-worker were .. *
- ... not aware of previous problems w'ith t-esting these breakers while in the "tes~" position. The AO had trair:iing*on the previou_s~ problems but did not recall the testing problems .. - . -
.*toRRECTI~E ACtibN The follow~ng correitive actions were developed as a result of the*
investigation of thi~*incident: * , *
- _ Immediate ac-t ion .taken by Operat fons* Management~ was. to meet with ::a 11 shifts to dis~us~~the event and ex~ectations for* shutdown risk management. _ :
- T~e incident was .als9 djscussed with all maintenahte. shifts emphasiz'ing
- the probl~ms-associated with d~viating from.the .a~pro~ed.w6rk~scope.
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- 'lnvestig~te and evaJuate the use of :a 'more formal. communicatfons.policy.: .
within the maintenanc'e*departmentS. *Consider- the existing operatjons*."-.
,po}icy-in thi*S ev~l.uatio.n '.for.tonsistency. p.ur.poses. * * *
... , ** _1;. : '
- ~ . Trafn electrical rep.air-worker and :superv*i so rs .on* the breaker testing* ...
requirements stated in Administrative Procedure 4.02: Specifically, ,. __ **
- address* the problems with testing* incoming breakers racked in to t.he *,
"test~ positi4~. Incl~de expectations for breaker operations develop~d . **
by .op_eration~ in this .. traini_ng: . .. .. . - ,
- Define expectations for _breaker operations. Siiec i nca 11 y, . define account ab le depar.tments '*for breaker** <>per at ions in the "connect."; "test",
and "~i~C:onnect".positions.. .. * -:. ... *
-~ :
e'
'.
Pla-ce cauti,on placard.s which are:locatedjnside the breaker ¢ubi~les-in*
..; * -!
a more* vi s_i ble '.locati ori within ..the. br~aker c*ubj cl e. ,, _
- Evalu~t.ion. of: a .inodificati.~n to the start-up ,and. stafio_p- safeguards
- breakers to. preven.t 'operation* in the "test" position. * . . . _.*
~, *'
- 'Eyaluate GOP 14, Step 6.5 and Attachment 3 with respect to this event. -
- This evaluatiort:shoul~ ensure Operations Management's e~pectations are
.'clearly defi.ned *to thE? shift SROs via this procedure. *Modify' the *
- proce.dure-as necessary.: as a result of this evaluation-_.' ..
- ADDITIONAL INFORMATION None