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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
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consumers Power l'OWERINli MltHlliAN"S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 February 15, 1996 U S Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT LICENSEE EVENT REPORT 96-003 - AUXILIARY SHUTDOWN PANEL INVERTER LOW VOLTAGE CUT-OFF SETIING RESULTS IN UNAVAILABILITY OF PANEL Licensee Event Report (LER)96-003 is attached. This condition is reportable to the NRC in accordance with 10CFR50.73(a)(2)(ii) as a condition outside the plant design basis.
SUMMARY
OF COMMITMENTS
- This letter contains 2 new commitments as follows:
Revise Technical Specification surveillance procedure Q0-23, "Auxiliary Hot Shutdown Panel Checks", to include periodic testing and adjustment of the low voltage cut-off setpoint for the alternate shutdown panel inverter or develop another procedure to test this setpoint.
9602260150 6~8~b~ss
~DR ADOCK PDR A a.fS' ENCRGY COMPANY
I 2
Determine whether other, similar equipment setpoints exist which can cause inverters or battery chargers to shut down, and verify that appropriate testing is performed.
Richard W Smedley Manager, Licensing CC Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector - Palisades Attachment
ATTACHMENT CONSUMERS POWER COMPANY PALISADES PLANT DOCKET 50-255 LICENSEE EVENT REPORT 96-003 AUXILIARY SHUTDOWN PANE;L INVERTER LOW VOLTAGE CUT-OFF SETTING RESULTS IN UNAVAILABILITY OF PANEL
NRC Form 366 19*83)
- LICENSEE EVENT REPORT (LERI
- U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS NO. 31S0-0104 EXPIRES: 8/31/8S FACILITY NAME (1 I DOCKET NUMBER 121 PAGE 131 Consumers Power Company Palisades Plant I I I I I I I o s o o o 2 s s 1 I OF 0 I 7 TITLE 141 LICENSEE EVENT REPORT S6-003 - AUXILIARY SHUTDOWN PANEL INVERTER LOW VOLT AGE CUT-OFF SETTING RESULTS IN UNAVAILABILITY OF PANEL EVENT DATE (SI LER NUMBER (6) REPORT DATE (6) OTHER FACILITIES INVOLVED (8)
SEQUENTIAL REVISION FACILITY NAMES MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR N/A olslololol I 0 I 1 1 I s s 6 sis olol3 o Io 012 1 I s sis N/A olslololol I THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I: (Check one or more of the following/ 111 I OPERATING POWER LEVEL 1101 MODE (91 I , I o lo N
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- 73. 7l(b) 73.71° OTHER (Specify in Abstract
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- SO. 73(all211xl below and in Text, NRC Form 366AJ
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- * * * * * * * * * * * * >) . .*. LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER William L Roberts, Licensing Engineer I
6Ar,CrE6 7 1 6 1 4 1 -lalsl1l3 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC* REPORTABLE MANUFAC* REPORTABLE CAUSE SYSTEM COMPONENT TURER TO NPRDS CAUSE SYSTEM COMPONENT TURER TO NPRDS A E I1 I IN Iv h x Is Is Is y I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED (141 MONTH DAY YEAR EXPECTED n YES (If vu comDlete EXPECTED SUBMISSION DATE! rx-,
ABSTRACT IUmit to 1400 spaces, i.e., approximately fifteen sing/,,.space typewritten lines) 116)
NO SUBMISSION DATE (lSJ I I I On January 15, 1996, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, with the plant operating at 100% power, it was discovered that during the performance of work on September 27, 1995, technicians found the low voltage cut-off for the Alternate Shutdown Panel inverter set at approximately 120 volts DC input. The current Appendix R calculation for battery capacity shows that the initial battery terminal voltage will be less than 120 volts DC at the onset of a fire requiring use of the alternate shutdown panel, coincident with a loss of offsite power and a loss of battery chargers. Based upon this calculation, the alternate shutdown panel would not have operated as the battery voltage would not have been high enough to overcome the 120V low voltage setpoint. Fires in the Electrical Equipment Room, 1-D Switchgear Room, Cable Spreading Room and Auxiliary Building 590' corridor which require use of the alternate shutdown panel also have the potential to cause a loss of the station battery chargers. This circumstance would result in the alternate shutdown panel being powered directly from the station batteries to effect safe shutdown outside the Control Room. During the September work, the low voltage cut-off was reset to resolve the issue. The setpoint discrepancy was not identified as putting the plant outside its design basis until the work order was reviewed under the ongoing Appendix R enhancement program.
NRC Form 366A 19*831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION
- U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8131185 FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 131 PAGE 141 SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant t--~~~~~~~~~~~.._.......__.___.___.
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9 I6 - 0 I0 I3 - 0 I 0 6I 2 OF 0 I7 EVENT DESCRIPTION On September 27, 1995, the plant was operating at 100% power and Technical Specification Test Q0-23, "Auxiliary Hot Shutdown Panel Checks" was in progress. During the power-up sequence for the alternate shutdown panel, the DC input breaker to the panel tripped open. Repeated attempts to power the Alternate Shutdown Panel provided the same results.
Q0-23 was aborted, the panel declared inoperable, the appropriate LCO entered and an investigation into this failure to transfer control to the alternate shutdown panel was initiated. The investigation revealed that the Alternate Shutdown Panel inverter alarm board [EJ; INVT] had failed and needed to be replaced. During this trouble shooting it was also discovered that the inverter low voltage cut-off setpoint was set too high. Both of these problems were resolved, the equipment returned to service, and testing successfully completed under Q0-23. A plant condition report was initiated to evaluate the discrepancies. The evaluation should have discovered that the inverter low battery cut-off setpoint would have rendered the Alternate Shutdown Panel incapable of performing it's design basis function.
This low voltage setpoint problem was, however, not addressed in the plant condition report evaluation.
On January 15, 1996, during a review of the work order under the ongoing Appendix R Enhancement Program, it was discovered that during the evaluation of the work completed in September that the low voltage cut-off for the Alternate Shutdown Panel inverter was not addressed. Further review determined that the current Appendix R calculation for battery capacity shows that the initial battery terminal voltage will be less than 120 volts DC at the onset of a fire requiring use of the Alternate Shutdown Panel coincident with a loss of offsite power and a loss of battery chargers. Based upon this calculation, it was concluded that the Alternate Shutdown Panel VfOuld not have operated as the battery voltage would not have been high enough to overcome the 120V low voltage setpoint.
Therefore, in the event of a fire in the Electrical Equipment Room, 1-D Switchqear Room, Cable Spreading Room and Auxiliary Building 590' Corridor which causes a loss of station battery chargers, the Alternate Shutdown Panel would not have been available to effect a plant safe shutdown from outside the Control Room. During the September work, the low voltage cut-off was properly reset to resolve the issue.
CAUSE OF THE EVENT
- 1. Reviews have determined that the low voltage cut-off setpoint for the Alternate Shutdown Panel has not been identified as a variable whose setting is necessary to assure operability of the panel. No specific setting or tolerance can be confirmed to have been specified during the initial panel installation and checkout, and verifying this setpoint has not been a part of the periodic testing of the panel. Inadequate post modification and subsequent surveillance testing is one root cause of the event.
NRC Form 366A (9-631 I
1, U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS NO. 3150-0104 EXPIRES: 6131 /85 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME 11 I DOCKET NUMBER !21 LEA NUMBER (31 PAGE (41 SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant 0 I5 I0 I0 I0 I2 I5 I5 9 I6 - 0 ____
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- 2. When the repair work order was reviewed there was a failure to recognize that the low voltage setpoint could be a safety significant issue. The low voltage condition was not addressed as part of the evaluation of the deficiencies repaired under the work order.
- 3. A contributing cause is the lack of a thorough evaluation of industry experience information. As part of the evaluation of this low voltage event, it was discovered that a 1985 Industry Experience and Assessment document identified that a particular manufacturers inverter had a low shutoff voltage problem. A more questioning attitude with regards to this industry experience report could have led to the realization that the low voltage shut-off set point could be significant to inverter operation, and that we didn't monitor the low voltage cut-off setpoint for the Alternate Shutdown Panel.
ANALYSIS OF THE EVENT 10 CFR 50.48, Appendix R requires that an Alternate Shutdown Panel be designed and installed to provide a station where the plant could be brought to hot shutdown in the event that the control room could not be used as a result of a fire. The postulated fire may make the control room uninhabitable or disable enough of the control room equipment to render it not useful to control the plant. At Palisades, the fires that we have identified in this scenario result in postulated consequences that require using the Alternate Shutdown Panel. During this postulated scenario, the Alternate Shutdown Panel is being powered from the station batteries and the battery chargers are maintaining a high voltage on the battery system. If the postulated fire also renders both battery chargers inoperable, then the Alternate Shutdown Panel would be fed directly from the station batteries at a somewhat lower voltage. With the Alternate Shutdown Panel inverter low voltage setpoint cut-off set to a voltage higher than what the station batteries alone can provide, the Alternate Shutdown Panel could not be energized per procedure.
The failure of the Alternate Shutdown Panel to energize was discovered on September 27, 1995 during Technical Specification Surveillance Test 00-23" Auxiliary Hot Shutdown Panel Checks".
A plant condition report was written to document this condition and troubleshooting was initiated. At 2143 hours0.0248 days <br />0.595 hours <br />0.00354 weeks <br />8.154115e-4 months <br /> on September 27, the Alternate Shutdown Panel was declared inoperable and the plant was placed in a 7 day LCO per the requirements of Technical Specification 3.7.5. Two separate issues were identified that could cause the identified undervoltage problems. They were:
- 1. Component(s) within the inverter alarm undervoltage board failed causing the under voltage circuitry to spuriously activate even when the incoming DC voltage was held above the low voltage cut-off setpoint.
NRC Form 366A (9*83)
~
U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/BS LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER 121 LER NUMBER (3) PAGE (4)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company.
Palisades Plant 0 I5 I0 I0 I0 I2 I5 I5 9 I6 - qJ 0 I 3 - 0 I0 0 I4 OF 0 I7
- 2. The low voltage cut-off setpoint was set at approximately 120 VDC.
ISSUE# 1 Two circuit boards make up the inverter control logic, the inverter logic board and the alarm logic board. The inverter logic board sets the frequency of the output waveform, regulates voltage, and controls inverter turn-on/turn-off. In addition, the inverter logic board supplies +1 SVDC control power and +6.2VDC reference voltage to the alarm logic board. The alarm logic board is responsible for lighting lamps and controlling the status of alarm contacts to annunciate conditions existing within the inverter. In addition to its alarm functions, the alarm logic board is also responsible for monitoring DC input voltage to the inverter and will initiate a low voltage shutdown signal to the inverter logic board upon reaching the DC input voltage low voltage cut-off setpoint (adjustable on the alarm logic board).
l&C Technicians, in conjunction with a representative from the inverter manufacturer, and systems engineers were successful in troubleshooting the inverter failure down to component(s) on the inverter alarm board. The alarm board was signaling a low voltage cut-off shutdown to the inverter logic board even with the DC input voltage being held constant and well above the low voltage cut-off setpoint.
ISSUE# 2 During the initial troubleshooting of the inverter, it was discovered that the inverter low battery setpoint was set at approximately 124 VDC input, and the low voltage cut-off was set at approximately 120 VDC input. The low voltage cut-off was set to the minimum acceptable setting of 100.3 VDC, a value that was determined to be the optimum for the. design. The evaluation of the setting discrepancy was left for review under the plant condition report.
The review also assessed whether a potential electrical deficiency could have caused the low voltage cut-off setpoint to be driven to the out of design level that it was. After reviewing the data available, it appears that a undervoltage current failure was unlikely, and the two problems appear to be unrelated.
It is possible though, that a component failure downstream of this potentiometer (capacitor/op-amp/transistor), could have caused an increase in the low voltage cut-off setpoint. Further troubleshooting of the board would be required to support this, but the defective board had been discarded. Even if we were able to attribute the setting deficiency to another electrical problem, it is apparent that the low voltage cut-off setpoint has never been verified since the Alternate Shutdown Panel was installed.
Our reviews also determined that a 1985 Industry Experience and Assessment, General Electric Service Information Letter NO. 418, "Topaz Inverter Low Voltage Shutoff', chronicles a similar low voltage cut-off scenario for a Topaz inverter. It was identified that the review at the time only addressed the manufacturer of the inverter. Since we had no Topaz inverters on-site, no further reviews for this issue were recommended. This can be viewed as a missed opportunity to identify that
NRC Form 366A (9*83)
LICENSEE EVENT REPORT (LERI TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: B/31/85 FACILITY NAME 11 J DOCKET NUMBER 121 LER NUMBER 131 PAGE 141 SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant 0 I5 I0 I0 I0 I2 I5 I5 9 I6 - 0 Iu I 3 - 0 I0 0 I5 OF 0 I7 the low voltage cut-off problem could have generic implications, which might have led to the discovery that the low voltage cut-off setpoint for the Alternate Shutdown Panel was not being properly monitored.
SAFETY SIGNIFICANCE With the low voltage cut-off for the Alternate Shutdown Panel inverter set at approximately 120 volts DC and a known initial battery terminal voltage of less than 120 volts DC, it is reasonable to conclude that the panel would not have operated. Therefore, in the event of a fire in the Electrical Equipment Room, 1-D Switchgear Room, Cable Spreading Room, or the Auxiliary*
Building 590' corridor concurrent with a loss of offsite power and the loss of the station battery chargers, the Alternate Shutdown Panel would not hav.e been available. For a fire in any of these areas, both the existing and new Appendix R analysis credit the Alternate Shutdown Panel as being available.
The areas where a single fire may cause the loss of both battery chargers are Appendix R alternate shutdown areas. The Safe Shutdown Analysis is required by regulation to assume a loss of offsite power during the fire. In addition, the Appendix R fire is postulated to non-mechanistically affect all safe shutdown components in the area, even if the fire loading is not sufficient to cause such damage. Realistically, there is reasonable assurance that a fire in these areas would not progress to a state where safe shutdown equipment would be damaged. Any fire would be controlled by the installed automatic suppression system or fire brigade manual suppression such that either a loss of offsite power would not occur or that only one battery charger would be lost. Thus, the probability of a realistic fire causing both a loss of offsite power and a loss of both battery chargers in these areas is very low. T~e specific features for Fire Area 2 - Cable Spreading Room; Fire Area 3 D Switchgear Room; Fire Zone 13A -
Auxiliary Building 590'-0" Corridor; and Fire Area 21 - Electrical Equipment Room are addressed below.
Fire Suppression Actual Fire Fire Area Loading Design Spray Suppression Detection Pensjty Spray Pensjty Cable Spreading Room - FA 2 1.39 Hr 0.30 gpm/ft 2 0.60 gpm/ft 2 Yes 1-D Switchgear Room - FA 3 51 Min 0.20 gpm/ft 2 0.40 gpm/ft 2 Yes Aux Bldg 590' Corridor - FZ 13A 33 Min None in area N/A Partial Of concern Area Elec Equip Room - FA 21 7 Min 0.30 gpm/ft2 0.38 gpm/ft2 Partial Area
NRC Form 366A 19-631 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31 /65 FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 131 PAGE 141 SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant 0 I5 IQ IQ IQ I2 I5 I5 9 I6 - 0 I oj I 3 - Q IQ Q I6 OF 0 I7 From the above information, the two areas with a higher fire loading are the Cable Spreading Room and 1-D Switchgear Room. The combustible loading in both of these areas is composed of electrical cabling and electrical panels. However, both areas have automatic fire suppression provided over the cabling with an actual spray density of twice the design requirements. Also, separate automatic smoke detection is provided for these two areas that alarms in the Control Room. The postulated realistic fire in these areas would be a localized cable fire that should be quickly extinguished or controlled by the automatic suppression with twice the design spray density. The suppression spray would likely limit the fire size such that the redundant cables or battery chargers would not both be lost due to a single fire.
The Auxiliary Building 590' corridor rooms that contain the circuits of concern are very lightly loaded with combustible material. Specifically, the circuits are located in the Baler Room and Spent Fuel Pool Heat Exchanger Room which are within the Auxiliary Building 590' Corridor fire area .. The overall fire loading for the zone that includes these two areas is concentrated in the corridor that is outside a concrete wall or separated from these areas. However, no quantification has been made of the fire loading in these rooms. The partial area fire detection is localized in the concentrated area of cable routing in the corridor area. The light fire loading or transient combustibles brought into these areas would not likely create a fire large enough to damage the redundant circuits providing power to the battery chargers.
The Electrical Equipment Room has minimal fire loading and has a greater than 1O feet clear space between the redundant components and circuits located in this room. The automatic suppression and the partial detection is located directly over the in-situ combustibles. There is minimal likelihood of a realistic fire affecting redundant circuits in this room due to the phy~ical separation and positioning of automatic suppression directly over the areas of concern.
While the non-mechanistic Appendix R fire is postulated to damage the redundant circuits or components in the alternate shutdown areas described above, it is highly unlikely that a realistic fire could cause such damage. In addition, the areas with a higher fire loading have automatic suppression systems with as-built water spray densities of twice that required by the design specifications.
CORRECTIVE ACTIONS CORRECTIVE ACTIONS TAKEN Upon discovery of the low voltage set point problem the set point was readjusted to the minimum acceptable setting of 100.3 V. This corrected the identified problem.
NRC Form 366A 19*831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31 /85 FACILITY NAME 11 I DOCKET NUMBER 121 LER NUMBER 131 PAGE 14!
SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant o Io I 3 - 0 I0 0 I7 OF 0 I7 CORRECTIVE ACTIONS TO AVOID RECURRENCE
- 1. Revis*e Technical Specification Surveillance Procedure Q0-23,"Auxiliary Hot Shutdown Panel Checks" to include periodic testing and adjustment of the low voltage cut-off setpoint for the Alternate Shutdown Panel inverter or develop another procedure to test this.
- 2. Determine whether other similar equipment setpoints exist which can cause inverters or battery chargers to shut down, and verify that appropriate testing is performed.