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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 l!llCHlliA~ "S l'ROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 February 19, 1996 U S Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT LICENSEE EVENT REPORT 94-012-02 -THERMAL MARGIN MONITOR INTERNAL GROUND - REACTOR PROTECTIVE SYSTEM (RPS) DESIGN BASIS -
SUPPLEMENTAL REPORT Licensee Event Report (LER)94-012, Supplement 2, is attached. This supplement incorporates two commitment revisions that were previously reported to the NRC in two letters dated January 15, 1996.
This event was originally reported to the NRC as a condition outside of the design basis of the plant per 10CFR50.73(a)(2)(ii)(B).
9602270326 960219 PDR ADOCK 05000255 S PDR
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SUMMARY
OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments. It incorporates changes to commitments previously made in letters dated January 15, 1996.
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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 94-012-02 THERMAL MARGIN MONITOR INTERNAL GROUND REACTOR PROTECTIVE SYSTEM (RPS) DESIGN BASIS SUPPLEMENTAL REPORT J
NRCForm 366
.(9-83)
FACILITY NAME (1)
- LICENSEE EVENT REPORT (LER)
DOCKET NUMBER (2)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8131/85 PAGE (3)
Consumers Power Company Palisades Plant o Is Io Io Io I2 Is Is 1 I OF o Ia TITLE (4) Thermal Margin Monitor Internal Ground - Reactor Protective System (RPS) Design Basis .. Supplemental Report EVENT DATE 51 LER NUMBER 161 REPORT DATE IA1 OTI-IER FACILmEs INVOLVED 181
(') SEQUENTIAL **.*. REVISION FACILITY NAMES MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR NIA ol5lololol I ol4 217 9 4 914 - 0 I1 I 2 - 012 012 1 I 9 916 NIA ol51ojojoj I Tl-llS REPORT IS SUBMITTED PURSUANT TO Tl-IE REQUIREMENTS OF 10 CFR §:(Check one or more of the following) (11)
OPERATING
. MODE(9) N 20.402(b) 20.4050 .__ 50. 73(a)(2)(iv) .__ 73.71 (b)
POWER LEVEL (10) I - 20.405(a)(1)(1) 20.405(a)(1)(iQ 50.36(e)(1) 50.36(e)(2)
- 50. 73(a)(2)(v)
- 50. 73(a)(2)(vii) 73.710 OTI-IER (Specify in Abstract o o lo
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-- 20.405(a)(1)(iii) 50. 73(a)(2)(1) 50. 73(a)(2)(viii)(A) below and in Text, I < * * *-* * .\*-*.**-.. .-._-_-*. .*.
20.405(a)(1)(iv) 20.4051all1lM -
x 50. 73(a)(2)0i)
- 50. 731all2lliiil LICENSEE CONTACT FOR THIS LER 1121
- 50. 73(a)(2)(viii)(B) 50.731all2llxl NRC Form 366A)
NAME Clayton M Mathews, Licensing Engineer 6
AREACODE l1I 6 I 1 TELEPHONE NUMBER I I I - Ia I I1 I3 6 4 9 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN Tl-llS REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC-TURER REPORTABL E
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SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED
---, YES (If ve.., complete EXPECTED SUBMISSION DATE! h:-1 NO ABSTRACT (Limit lo 1400 *fJ'ICN, i.e., applOximately fifteen single-space typewritten lines) (16)
SUBMISSION DATE (15) I I I On April 27, 1994, with the plant in cold shutdown, it was determined that an internal ground in the Thermal Margin Monitor (TMM) causes a non-conformance with the Reactor Protective System (RPS) design basis. The TMM is part of the RPS and the RPS is designed to operate as an ungrounded system. The ground path in the TMM was connected to the pressurizer pressure measurement loop, the Nuclear Instrumentation (NI) System and the Primary Coolant System (PCS) temperature inputs. A second ground in the pressurizer pressure loop or in the PCS temperature transmitter loop could adversely affect the RPS accuracy and reliability.
The cause of this event is an internal ground in the TMM design which was not identified at the time of installation and the failure to recognize that this internal ground put the RPS outside of the FSAR design basis in that the RPS is designed to be ungrounded.
Modifications to effectively isolate the internal ground in the TMM from the pressurizer pressure circuitry and PCS temperature circuits were completed prior to plant heat-up.
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NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION
{9-83) APPROVED OMB NO. 3150-0104 EXPIRES: 8131/85 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FAaLrrv NAME (1) DOCKET NUMBER (2) LER NUMBER (3) PAGE(4)
SEQUEmlAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant 0 5 0 0 0 2 5 5 9 4 0 1 2 0 2 Q20FQ8 EVENT DESCRIPTION:
On April 27, 1994, the plant was in cold shutdown. During a re-evaluation of the Thermal Margin Monitor (TMM), PY-0102A (8, C & D), and its effects on the operability of the Reactor Protective System (RPS), it was determined that a resistance path to ground internal to the TMM caused a non-conformance with the design basis as stated in the Palisades FSAR section 7.2.7, "Effects of Failures". FSAR section 7.2.7, Analog Portion, Item 2 states that "Shorting the [signal] leads to an ungrounded voltage source, has no effect since the signal circuit is ungrounded." Section 3, states "Single grounds on the signal circuit have no effect. Double grounds would tend to cause the chann~I to fail in the safe direction". Similar statements are found in the FSAR section 7.2.7, "Logic Portion,"
Items 7 and 11 .
The FSAR section 7.2.7 Item 2 statement indicates the RPS analog signal circuits are designed to operate ungrounded. Despite this design requirement, the TMM had an internal ground path from the 24 volt de power supply through a 1OK ohm resistor to ground. This ground path was initially found connected from the TMM through the Thermal Margin/Low Pressure (TM/LP) bi-stable trip unit to the pressurizer pressure measurement loop, where an additional ground in the pressurizer pressure loop could establish a ground loop which may have a non-conservative influence on the pressurizer pressure signals of the RPS.
After finding the internal (as-designed) TMM ground and realizing the potential impact on the pressurizer pressure measurement loop, all four channels of the pressurizer pressure related equipment were conservatively declared inoperable pending further investigation. Although monthly surveillance by the l&C department would discover a second (unintentional) ground on the pressurizer pressure loop, the Operations department does not have a means to readily detect the second ground. The results of l&C testing in response to this event, by inducing actual grounds in the pressurizer pressure loop, identified the potential for causing non-conservative shifts in some loop signals or set-points.
Subsequent circuit analysis and testing performed on May 16, 1994 on the TMM inputs and outputs revealed that the TMM 1OK ohm ground is also connected from the TMM to the PCS instrumentation and the Nuclear Instrumentation (NI) systems. In the PCS instrumentation system, the ground is connected to the cold leg and the hot leg average temperature instruments, where an additional (unintentional) ground could establish a ground loop which may have a non-conservative influence on the temperature inputs to the TMM. The temperature inputs are used in the TM/LP trip setpoint calculation and in the variable high power trip calculation.
In the Nuclear Instrumentation (NI) System, the TMM internal ground is connected to the upper, lower, and upper-plus-lower power range detector signals. Testing performed on the NI signals indicates that an additional ground in these circuits has no effect on the NI system or on the RPS. This is due to the presence of buffer isolators located in the NI system in each of the NI signals. Operations does not have a method to detect a second ground on the temperature loops or on the NI systems.
NRC Form 366A
.(9-83)
FACILITY NAME (1)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER (3)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8131/85 PAGE (4)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant o I1 I 2 o 12 ol3 oF ola CAUSE OF THE EVENT:
The cause of this event is a signal common to earth ground in the Thermal Margin Monitor design which was not identified at the time the TMM's were installed. The cause of the event is also a failure to recognize that the presence of the internal grounds in the TMM placed the RPS outside of the FSAR design basis in that the RPS is designed to be ungrounded.
ANALYSIS OF THE EVENT:
One of the RPS trip parameters is the Thermal Margin/Low Pressure (TM/LP) calculated signal. In 1988, the original analog TM/LP calculators were replaced by digital Thermal Margin Monitors. The TMM function is to prevent reactor conditions from violating a minimum departure from nucleate boiling ratio (DNBR) by a continuously computed function of core power, reactor coolant maximum inlet temperature, core coolant system pressure and axial shape index. The TMM provides a signal to the TM/LP bi-stable trip unit which also receives an input signal from the pressurizer pressure measurement loop. The TM/LP bi-stable trip unit will generate alarm and trip signals based on the comparison of the trip setpoint input from the TMM and the pressure signal from the pressurizer pressure measurement loop.
In the course of troubleshooting a July 3, 1991 RPS trip (LER 91-012, dated 8/2/91 ), it was concluded that the source of power which energized the test portion of the bi-stable dual coil relays and contributed to the event, came from the TMM 24 volt de power supply. As a corrective action for the July 3, 1991 reactor trip event, the TMM vendor was contacted regarding a potential signal common to earth ground in the TMM. The vendor indicated there was none. Because of a continuing indication of a ground path, investigation by Palisades plant continued and eventually revealed tt.o existence of a 1OK ohm resistor which provided an internal ground path through the resistor to the power supply in the TMM, through setpoint indicator PIA-0102A (for Channel A), and to the signal common for the setpoint voltage transmitted to the TM/LP bi-stable trip unit. This signal propagated through the TM/LP bi-stable to the signal common of the pressurizer pressure measurement loop. Thus, if a short develops in the pressurizer pressure loop, the ground loop would be fed by the 24 volt de power supply in the TMM. It was determined that all four RPS channels were similarly affected.
The vendor was contacted regarding the removal of the 1OK ohm resistor which provided the ground path. The vendor did not support its removal because its removal would present the potential for a shock hazard to personnel near the chassis and the possibility of degradation of the equipment.
NRC Form 366A
.(9-83)
FACILITY NAME (1)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER (3)
U.S. NUCLEAR REGULA TORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8131185 PAGE{4)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant ol4 oF ols An engineering evaluation of the acceptability of the signal common to ground connection in the TMM and the ability of the RPS to satisfy FSAR 7.2.7, "Effects of Failures" was performed in response to Palisades plant corrective action E-PAL-91-014K and was completed July 23, 1993. The evaluation considered the ability of the RPS to perform its safety function given the TMM short to ground and the verification that an unintentional short to ground (single failure) would not cause an unnecessary RPS actuation or safety function. The evaluation concluded that for single shorts to ground in the pressurizer pressure loop, the short would only affect one channel out of four and that the short would be detectable on the setpoint indicator of the TMM. Monthly surveillance by the l&C department compare the displayed signal value to the TMM calculated signal and would detect a short on the pressurizer pressure loop by a deviation in the two values. At that time, it was concluded the RPS did not violate its Technical Specification requirements and was, therefore, considered operable.
In April 1994, during reviews of equipment for operability in consideration for heat-up from cold shutdown following an outage, the ability of the RPS to satisfy the design requirements in F.SAR section 7.2.7, given the TMM internal ground and the potential for additional grounds on the pressurizer pressure measurement loop, was re-evaluated. On April 27, 1994, it was decided that all four channels of the RPS pressurizer pressure measurement loops including the TMM-s should conservatively be declared inoperable pending further investigation because unintentional grounds on the pressurizer pressure loops were not readily detectible by the Operations department. This was deemed the prudent and conservative course of action considering the enhanced sensitivity to issues as part of the overall plant performance improvement plan. Additional evaluation and testing confirmed that for certain postulated grounds in the pressurizer pressure signal loops, the ground path established through the TMM grounding resistor could adversely affect some pressurizer pressure trip signals. ~
There were three opportunities where the non-conformance with the RPS des;gn requirements for an ungrounded system could have been recognized. First, it could have been recognized and tested for during the initial installation of the TMM modification (FC-628). Second, during replacement of the RPS trip relay coils in FC-888 following a July 3, 1991 RPS trip, a thorough design review of FC-888 could have identified the non-conformance. Third, an opportunity was missed during resolution of the corrective action for the July 3, 1991 RPS trip where removal of the TMM ground was considered.
During the TMM installation, the vendor's statement that the TMMs were ungrounded was accepted at face value and no additional testing or investigation was initiated to verify this design criteria. Had this been identified as a critical design characteristic, as required by the current modification procedures, verification of the ungrounded criteria would have been required at the time of installation.
During the design review of FC-888, the resolution focused on the design of the trip relay coils and on preventive maintenance to monitor the relay coil performance and not on the entire TMM design. The review relied heavily on a vendor letter discussing the design and construction of the replacement relays and concluded that the design was acceptable.
.-*-- ~. ~~
NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION
,(9-83) .
APPROVED OMB NO. 3150-0104 EXPIRES: 8131185 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (3) PAGE(4)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant 0 5 0 0 0 2 5 5 9 4 - 0 1 2 .. :J 2 Q 5 OF Q 8 When removal of the TMM ground connection was not supported by the vendor, an analysis was submitted which documented a justification to use the TMMs with the grounds in place. The analysis concluded that a second ground in the TM/LP pressure trip circuits of the RPS would be a single failure. It also concluded that the single failure would only affect one of the four channels and, therefore, since it would neither initiate a false protective action (reactor trip) nor prevent a proper protective action, it was deemed an acceptable configuration. It was not concluded at this time that the existing configuration did not comply with the associated licensing design basis. This conclusion was not reviewed by the corrective action review board prior to closeout of the activity.
SAFETY SIGNIFICANCE:
With the internal ground in the TMM, testing has demonstrated the potential for an additional single ground on the pressurizer pressure loop to cause a non-conservative shift in the pressure signal or
.. setpoint in that loop. All postulated ground paths establish current flow through the setpoint indicator of the TMM and are, therefore, detec;:table. Testing has also demonstrated the potential for an additional ground to cause a non-conservative shift in the temperature input signals to the TMM which affect the thermal power calculation.
For clarification, the following interpretation of the FSAR section 7.2.7 items 2, 3, 7 and 11 regarding the terms "grounds" and "no effect" is provided.
An "ungrounded" circuit is interpreted to mean a circuit in which the impedance of the circuit as measured to ground, is at a sufficiently high level such that with a addition of a single ground on the circuit there will be no significant effect on the instrument loop. "... no significant effect. .. "is interpreted to mean that a single ground (in addition to the circuit impedance of the circuit-to-ground) results in either no change in the circuit signal level, a change in the signal level in a conservative direction or a change in the signal level that is within the tolerances of the loop accuracy analyses.
Conversely, a "significant effect" is one where the change to the signal circuit is in a non-conservative direction and is outside the tolerances of the instrument loop accuracy analysis which could then impact the FSAR chapter 14 Safety Analyses.
... =- *~-1; **J
NRC Form 366A ffe-83)
FAOLITY NAME (1)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER (2) LER f,;UMBER (3)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EXPIRES: 8131/85 PAGE(4)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant _ 0 I5 I0 I0 I0 I2 I5 I5 9 I4 - (* I1 I 2 - 0 I2 0 I6 OF 0 I8 CORRECTIVE ACTION:
The corrective action process has been substantially upgraded in several respects. All conditions affecting installed plant equipment are now reviewed for the effect on equipment operability and a reportability review is conducted for all conditions identified. A new screening group has been established to identify those conditions which are significant and need plant management attention and detailed root cause analysis. There is increased management involvement in the corrective action process.
A modification has been implemented to effectively isolate the grounded TMM from the ungrounded pressurizer pressure loop of the RPS through the installation of an isolation device located external to the TMM.
On May 16, 1994, during the engineering of the modification to install isolation between the TMM signal and the TM/LP trip unit, an analysis revealed an additional ground path from the internal TMM 1OK ohm ground to the Nuclear Instrument inputs and the Primary Coolant System temperature inputs to the TMM. Testing performed on May 19, 1994 revealed that an additional ground inserted in the temperature transmitter loop could adversely affect the temperature signals but that an additional ground inserted in the NI input circuits had no effects on the TMM nor on the NI circuits.
A second modification was initiated which increases the impedance between the internal ground connection from the TMM to the temperature signal instrument loops. This was accomplished by installing three operational amplifier input devices internal to the TMM in place of jumpers in the NI input circuits. Identical input devices are currently in use in the TMM temperature input circuits; however, jumpers in the NI input circuits provide the ground path back to the temperature circuits.
The input devices will increase signal common-to-ground resistance to an acceptable value. Analysis and testing of the temperature instrument circuits .reveals that with the input devices installed on the NI inputs and an additional ground on the temperature circuits, there is no effect on the operation of the TMM or on the temperature instruments.
The modifications to: ( 1) provide electrical isolation between the TMM signal and the TM/LP trip unit to effectively separate the ground in the TMM pressurizer pressure circuitry and, (2) provide increased electrical resistance between the TMM temperature inputs and the TMM unit to effectively separate the grounded TMM from the ungrounded temperature circuits, were completed before plant heat-up.
A future modification will be pursued which will remove the internal resistance ground from the TMM, thus restoring the RPS and the TMM to an ungrounded state. This modification is currently scheduled for installation during the refueling outage following the 1995 refueling outage. The TMM vendor has indicated that this is a complex modification and the engineering and design changes needed to remove the internal ground cannot be completed in time for the 1995 refueling outage.
NRC Form 388A U.S. NUCLEAR REGULATORY COMMISSION
,lD-83) APPROVED OMB NO. 3150-0104 EXPIRES: 8131185 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (3) PAGE (4)
SEQUENTIAL REVl.310N YEAR NUMBER NUMBER Consumers Power Company Palisades Plant 0 5 0 0 0 2 5 5 9 4 -01 2-0 2 The modifications installed prior to commencing plant heat-up effectively isolate the grounded TMM from the ungrounded RPS. Raising the impedance of the ground in the TMM effectively restores the deficient condition to the design and licensing bases.
I. PRIOR TO PLANT HEAT-UP:
Actions A-D were accomplished prior to plant heat-up.
A. Isolate the TM/LP Pressure trip signal circuits from the internal TMM impedance.
B. Isolate the Primary Coolant System temperature and Nuclear Instrumentation System Power Range input signals to the TMMs by isolating those circuits from the internal TMM ground or raising the impedance level of the ground to an acceptable level.
C. Verify that all of the TMM inputs and outputs are effectively ungrounded after the completion of modifications and perform testing to verify the modified loops, the TMMs and the affected portions of the RPS function properly.
D. Test each TMM to validate that circuit isolation modifications do not effect the TMMs safety function.
II. TO PREVENT RECURRENCE:
A. Incorporate the Reactor Protective System's Failure Modes and Effects Analysis information in the Palisades Design Basis Documents.
B. Electrical and l&C engineering personnel have been provided with a summary of this event report.
C. The RPS Design Basis Document has been updated to include the work completed on the system and to clarify what an "ungrounded" signal is.
D. This event report has been incorporated into the appropriate accredited training programs.
E. The original commitment was to change the Nuclear Engineering and Construction Organization (NECO) Guidelines to ensure that all modifications are designed and tested appropriately to ensure that isolation and separation requirements are maintained. This action was not taken as described, as it is not reasonable to test for separation and isolation.
Separation is a factor of cable and device location. Engineering design and review are adequate to determine correct device location. Isolation is also a design function. Testing
... , -- .... *-_--*. <l
'i
. NRC Form 366A
-.'9-83)
FACILITY NAME (1)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER (3)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 EXPIRES: 8131185 PAGE(4)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Consumers Power Company Palisades Plant ola oF ola of the isolator is done at the time of procurement if adequate design documentation does not exist. =fhe*existing design procedures reference the appropriate design documents which specify the requirements for adequate electrical circuit separation and isolation.
F. An FSAR Change Request was initiated to clarify the definition of "ungrounded" and the "effects of a ground" in section 7.2.7.
G. Withdrawn.
H. It has been determined that additional surveillance procedures on the added TMM isolation devices will not be written, as an existing Technical Specification Surveillance procedure (Ml-2A) tests the isolators as part of the signal loop test.
I. It was determined that the need exists to periodically monitor unisolated TMM and RPS circuits for the presence of grounds. A new action has been initiated to develop a procedure to test RPS and TMM signal circuits for grounds.
J. A memo has been provided to all l&C technicians on the importance of, and methods to detect, grounds on floating systems.
K. Provide a memo summarizing the event to all department heads, members of the PRC and Management Review Board, emphasizing the need to recognize situations where the plant is not in compliance with design basis.