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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18065B1151997-12-0909 December 1997 LER 97-013-00:on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability ML18067A7751997-11-11011 November 1997 LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved ML18067A7581997-10-30030 October 1997 LER 97-010-00:on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation ML18067A7461997-10-23023 October 1997 LER 97-009-00:on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure. ML18067A7191997-10-10010 October 1997 LER 97-008-00:on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed ML18067A6951997-09-24024 September 1997 LER 97-007-00:on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts ML18067A5651997-06-0303 June 1997 LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested ML18067A5461997-05-12012 May 1997 LER 97-006-00:on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities ML18067A4431997-03-24024 March 1997 LER 97-004-00:on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS ML18067A4391997-03-21021 March 1997 LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired ML18067A4401997-03-21021 March 1997 LER 97-003-00:on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be verified.W/970321 Ltr ML18066A8931997-02-21021 February 1997 LER 97-002-00:on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared operable.W/970221 Ltr ML18066A8751997-02-0505 February 1997 LER 97-001-00:on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator repaired.W/970205 Ltr ML18066A8041996-12-23023 December 1996 LER 96-014-00:on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment ML18066A7831996-12-16016 December 1996 LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced ML18065A9951996-10-0404 October 1996 LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg ML18065A9171996-09-0909 September 1996 LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr ML18065A8961996-08-29029 August 1996 LER 96-011-00:on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments ML18065A8811996-08-20020 August 1996 LER 96-005-01:on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced ML18065A8741996-08-16016 August 1996 LER 96-010-00:on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected ML18065A8651996-08-12012 August 1996 LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr ML18065A8601996-08-0202 August 1996 LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit ML18065A8321996-08-0101 August 1996 LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board ML18065A7691996-06-12012 June 1996 LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr ML18065A6901996-05-0101 May 1996 LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr ML18065A6681996-04-22022 April 1996 LER 96-007-00:on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting modified.W/960422 Ltr ML18065A5721996-03-11011 March 1996 LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded ML18065A5261996-03-0101 March 1996 LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr ML18065A5111996-02-19019 February 1996 LER 94-012-02:on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD.W/960219 Ltr ML18065A5061996-02-19019 February 1996 LER 96-004-00:on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts ML18065A5021996-02-15015 February 1996 LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr ML18065A4581996-01-31031 January 1996 LER 96-001-00:on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS.W/960131 Ltr ML18065A4421996-01-19019 January 1996 LER 95-016-00:on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save Pcs Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision.W/960119 Ltr ML18065A4041996-01-15015 January 1996 LER 95-014-00:on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis documentation.W/960115 Ltr ML18065A3291995-12-0404 December 1995 LER 95-013-00:on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as required.W/951204 Ltr ML18065A2361995-11-0202 November 1995 LER 95-012-00:on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt connections.W/951102 Ltr ML18065A2051995-10-20020 October 1995 LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised ML18065A0841995-09-18018 September 1995 LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr ML18065A0681995-09-14014 September 1995 LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line ML18065A0651995-09-0808 September 1995 LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment ML18064A8781995-08-28028 August 1995 LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage ML18064A8831995-08-21021 August 1995 LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr 1999-09-02
[Table view] Category:RO)
MONTHYEARML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18065B1151997-12-0909 December 1997 LER 97-013-00:on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability ML18067A7751997-11-11011 November 1997 LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved ML18067A7581997-10-30030 October 1997 LER 97-010-00:on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation ML18067A7461997-10-23023 October 1997 LER 97-009-00:on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure. ML18067A7191997-10-10010 October 1997 LER 97-008-00:on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed ML18067A6951997-09-24024 September 1997 LER 97-007-00:on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts ML18067A5651997-06-0303 June 1997 LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested ML18067A5461997-05-12012 May 1997 LER 97-006-00:on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities ML18067A4431997-03-24024 March 1997 LER 97-004-00:on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS ML18067A4391997-03-21021 March 1997 LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired ML18067A4401997-03-21021 March 1997 LER 97-003-00:on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be verified.W/970321 Ltr ML18066A8931997-02-21021 February 1997 LER 97-002-00:on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared operable.W/970221 Ltr ML18066A8751997-02-0505 February 1997 LER 97-001-00:on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator repaired.W/970205 Ltr ML18066A8041996-12-23023 December 1996 LER 96-014-00:on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment ML18066A7831996-12-16016 December 1996 LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced ML18065A9951996-10-0404 October 1996 LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg ML18065A9171996-09-0909 September 1996 LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr ML18065A8961996-08-29029 August 1996 LER 96-011-00:on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments ML18065A8811996-08-20020 August 1996 LER 96-005-01:on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced ML18065A8741996-08-16016 August 1996 LER 96-010-00:on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected ML18065A8651996-08-12012 August 1996 LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr ML18065A8601996-08-0202 August 1996 LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit ML18065A8321996-08-0101 August 1996 LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board ML18065A7691996-06-12012 June 1996 LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr ML18065A6901996-05-0101 May 1996 LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr ML18065A6681996-04-22022 April 1996 LER 96-007-00:on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting modified.W/960422 Ltr ML18065A5721996-03-11011 March 1996 LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded ML18065A5261996-03-0101 March 1996 LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr ML18065A5111996-02-19019 February 1996 LER 94-012-02:on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD.W/960219 Ltr ML18065A5061996-02-19019 February 1996 LER 96-004-00:on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts ML18065A5021996-02-15015 February 1996 LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr ML18065A4581996-01-31031 January 1996 LER 96-001-00:on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS.W/960131 Ltr ML18065A4421996-01-19019 January 1996 LER 95-016-00:on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save Pcs Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision.W/960119 Ltr ML18065A4041996-01-15015 January 1996 LER 95-014-00:on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis documentation.W/960115 Ltr ML18065A3291995-12-0404 December 1995 LER 95-013-00:on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as required.W/951204 Ltr ML18065A2361995-11-0202 November 1995 LER 95-012-00:on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt connections.W/951102 Ltr ML18065A2051995-10-20020 October 1995 LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised ML18065A0841995-09-18018 September 1995 LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr ML18065A0681995-09-14014 September 1995 LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line ML18065A0651995-09-0808 September 1995 LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment ML18064A8781995-08-28028 August 1995 LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage ML18064A8831995-08-21021 August 1995 LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr 1999-09-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr. ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18066A1741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr ML18066A2321998-05-31031 May 1998 Revised MOR for May 1998 for Palisades Nuclear Plant ML18068A4701998-05-31031 May 1998 Annual Rept of Changes in ECCS Models Per 10CFR50.46. ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18066A2331998-04-30030 April 1998 Revised MOR for Apr 1998 for Palisades Nuclear Plant ML18068A3461998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML18065B2071998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18066A2341998-03-31031 March 1998 Revised MOR for Mar 1998 for Palisades Nuclear Plant ML18068A3041998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr ML18066A2351998-02-28028 February 1998 Revised MOR for Feb 1998 for Palisades Nuclear Plant ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML18067A8211998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr 1999-09-30
[Table view] |
Text
.. consumers Power *
. Plant Safety and Licensing Director
/llllCHIGAN-S PIUIGllESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 January 17, l 995 Nuclear Regulatory Commission*
Document Control Desk Washington, DC 20~55 DOCKET 50-255. - LICENSE DPR~ PALISADES PLANT LICENSEE EVENT REPORT 94:-012 THERMAL MARGIN MONITOR. INTERNAL GROUND -
REACTOR PROTECTIVE SYSTEM (RPS) DESIGN BASIS - SUPPLEMENTAL REPORT LiGensee Event Report (LER)94-012, Supplement 1, is ~ttached. This supplement includes a revis~d analysis of the event sectiori, as well as an extension of our estimated completion date for upgrading the Thermal Margin Monitor to the end of the refueling outage following the 1995 refueling outage. * * *
- This event was originally reported to the NRC as a condition outside the de~ign basis of the plant, per 10CFR50:73{a){2){ii){B).
SUMMARY
The following commitments 'were part of the original* LER and are still active':*
The-Fai)ure modes and affects analysis for the RPS will be updated to reflect the mbdifications performed to the RPS and the TMM as a result rif
. this event report.
The schedule for co~pleti~g the ~odifications to the Thermal Margin Monitors to remove the internal ground resistance from the TMM, has been
- changed from the 1995 refueling outage to the ~nd of the refueling following the 19~5 refueling. *
- 9501250114 950117 PDR ADOCK 05000255 " ~ ..
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A CMS' ENERGY COMPANY .
2 After the grounds are removed the need for th~ circuit isolation devices
.added as a result of .this event to the inputs and outputs of the TMM will be reevaluated.
The following are new commitments from the supplement:
A procedure will be developed to test RPS and TMM signal circuits for grOUDdS. .
A m.emo wi 11 be issued to all department heads, members of the PRC and Management Review Board emphasizing the need to recognize situations where.
the plant is not in com~liance with design basis.,
Kurt MHaas Plant Safety and Licensing Minager CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades.
Attachment
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NRC*Form 366 U.S. NUCLEAR REGULATORY COMMISSION.
(9-831" APPROVED OMBNO. 3160-0104 EXPIRES: 8/31 /86 LICENSEE EVENT REPORT (LERI .
FACILITY NAME 111 DOCKET NUMBER 121 PAGE 131 Palisades Plant o 5 o* o o 2 5 5 TITLE 141_ Thermal M13rgin Monitor Internal Ground - Reactor Protective System (RPS) Design Basis - Supplemental Report EVENT DATE 161 LER NUMBER 161 REPORT DATE 16) OTHER FAC1UTIES INVOLVED 18)
REVISION _FACILITY NAMES MONTH DAY YEAR YEAR . NUMBER MONTH
- DAY . YEAR NIA 0 6 0 0 0 0 4 2 7 9 4 9 4 0 1 2 o. 0 1 7. 9 5 NIA 0 6 0 0 0 THIS REPORT IS SUBMITTED PURS.UANT TO THE REQUIREMENTS OF10 CFR I: fCMclc on. f>!'tnOIY of 1M fo/JowingJ (11)
- OPERATING MODE 191 N 20.4021bl 20.406Ccl 60.7311l121Uvl 73.71(b)
. 20.40611111 llil 60.361cll11 60.7311l121M 73.71(cl 20.40611)11 )Iii) 60.361cll21 60.7311l1211viil OTHER (Specify in "Abatroct
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- LICENSEE CONTACT FOR THIS LER (121
.NAME TELEPHONE NUMBER AREA CODE William L Roberts, -St~ff Licensing Engineer 6 6 7 6 4 8 9 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 .
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MANUFAC* REPORTABLE MANUFAC, . R~PORTA8LE CAUSE
- TO NPROS. CAUSE SYSTEM COMPONENT TUR ER TO NPRDS SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED SUBMISSION YES Uf yes. comp/eta EXPECTED SUBMISSION DATE) . DATE (161
.; ABSTRACT (Limii ~ 1400 &paces, i.e., approximately nfttten .utg1_.Spke typewritttt~ lines) (16)
On. April i°7;" 1994,. with the plant iri. 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 ari
. ungrounded system. The ground path in the TMM *wa~ connected to the pressurizer pressure
- .'measurement loop, the Nuclear Instrumentation (NI) System and the Primary Coolant System (PCS) ,
temperature inpµts. A second ground in the pressurizer pressure loop or in the PCS temperatlJre.
- 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 *1 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
.circ:uitry and PCS temperature circuits were completed prior to plant heat-up. 1*
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NRC Forin 366A U.S. NUCLEAR REGULATORY COMM.ISSION Ui~B3l . . APPROVED OMB NO. 3160-0l04
. . EXPIRES: B/31 /86
-LICENSEE EVENT REPORT (LERI TEXT CONTINUATiON
. r FACILITY NAME (1) DOCKET NUMBER !21 . LER NUMBER !31 PAGE (41 SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades Plant 0600026694-0 2 - 0 . Q 2 OF Q 8 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, ite_m 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 t<;> cause the channel to fail in the safe direction"; .Similar statements are found in the FSAR section 7.2.7, "Logic Portion~" items 7 and 1l. .. '
. The FSAR section 1.2. 7 item 2 statement indicates the RPS analog signal circuits are designed to operate ungrounded. Despite this design requirement, the TMM h*ad an internal ground path ..
from the 24 volt de power supply through a 10K ohm resistor to ground. This ground path was
. 'initially fol.ind connectec,i from the TMM through the Thermal Margin/Low Pressure (TM/LP) bi-
~table 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 signaJs of the RPS.
- After finding the inte_rnal (as-designed)TMM ground and realizing the potential impact on the pressurizer pressure measurement loop, _all four channel.s 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 (unintehtional) ground on*
- ttie 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 pr~ssurizer pressure loop identified the potential for causing non-conservative shifts in some loop signals or setpoints.
Subsequent circui~ 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 conne.cted to the cold leg and the hot leg average temperature instruments, wher.e an additional (unintentional) ground couid establish a ground loop which may have a non-conservative influence on the temperature inputs to the TMM. Tt)e
- temperature inputs are used in the TM/LP trip setpolnt 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.
NRC. Form 38SA U.S. NUCLEAR REGULATORY COMMISSION
- . (9-83) APPROVED OMB NO. 3160-0104 .
EXPIRES: 8/31186 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
- FACILITY NAME ill DOCKET NUMBER 12) LER NUMBER (3) PAGE (4)
SEQUENTIAL REVISIOtj YEAR NUMBER NUMBER Palisades Plant 0 5 0 0 0 2 5 5 9 4. - 0 2 - 0 Q 3 OF Q 8 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.
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 qf 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 compµted 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 ala.rm and trip.signals 'based on the comparison of the trip setpoint input from the
- TMM and the pressure signal from the pressurizer pre_ssure 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 in_dication ofa ground path,-investigation by Palisades plant continued and eventually revealed the 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), an.d 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
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- U.S. NUCLEAR REGULATORY COMMISSION
. 19-83) APPROVED OMB NO. 3160,0104 EXPIRES: 8/31 /86 LICENSEE EVENT REPORT (LER) TEXT* CONTIN.UATION
. . FACILITY NAME 111 DOCKET NUMBER 121
- LER NUMBER 131 PAGE 14f SEQUENTIAL . REVISION YEAR NUMBER NUMBER Palisades Plant
- 0600026694 -o 2 - 0 0 4 OF 0 8 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 o.f Failures" was performed in response to Palisades plant corrective action E-PAL-91-014K and was completed July _23,
- 19.93. _The evaluation considered the ability of the RPS to perform its safety function given the TMM short to ground ar:id the verification that an ~nintentional 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 loo*p 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, du~ing reviews of equipment for operabilitY in consid.eration for hea*~-up from cold
- . shutdown following an outage, the ability of the RPS to satisfy the design req'uirements* in FSAR section 7.2.7, given the TMM internal ground and the potential for additional grounds on the pressurizer pressure measurement loop, was re-evalL1ated .. On April27, 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 investigatio.n because unintehtiona-1 grounds on the pressurizer pressure loops were not readily detectible by the Operations*
department .. This was deemed the prudent arid conservative course of action considering the *
' .. *enhanced sensitivity to issues as part of the overall plant performance improvement plat\...
Additional evaluation and testing confirmed that for certain postulated grounds in the pressurizer pressure signal loops, the ground pa_th 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 design requirements _ I* .
for an ungrounded system could have been recognized. First, it could have been- recognized and .-I tes.ted fpr during the initial installation of the TMM modification (FC-62Sh
- replacement of the RPS trip relay coils in FC-888 following a July 3, 1991 RPS trip, a thorough - I design review of FC:-888 could have identified the non-conformance.* Third, an opportunity was I missed during resolution of the corrective action for the July 3, 1991 RPS trip where removal of I-
- the TMM ground was considered. I
. . . . : . . \ . **I--
During the TMM* installation, the vendor's statement that the TM Ms were ungrounded was I
.. accepted at face value and no additional testing or investigation was initiated to verify this I design criteria. Had this been identified as a critical design characteristic, as required by the I current modification procedures, verification of the un'grounded criteria would have been. I required at the time of installation. .I I
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NRC'Form 366A U.S. NUCLEAR REGULATORY COMMISSION
,l&c631. APPROVED OMB NO. 3160-0104 EXPIRES*: 8/31 /BS
. LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 131 PAGE 141 SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades Plant 0 6 0 0 0 2 6 *5 9 4 - 0. 2 - 0 Q 5 OF Q 8 During .the design review of /FC-888, the resolution *focused on the design of the trip relay coils I and on 'preventive maintenance to monitor the relay coif performance .*and not on the entire TMM I
.- : design. The review relied heavily on a vendor letter discussing the design and construction of . I the re.placement relays* and. concluded that the *design was acceptable.
When removal of the TMM ground connection was not supported by the vendor, an analysis *
- I was submitted which documented a justification to use the TMMs with the grounds in place. I*
The analysis conclude.d that a second ground in the TM/LP pressure trip circuits of the RPS I would'be a single failure. It also concluded that the single failure would only affect one. of the I four channels and, therefore, since it would neither initiate a false protective action (reactor trip) I nor prevent a proper protective action, it was deemed an acceptable configuration. It was not I concluded. at this time that *the existing configuration did not comply with the associated I.
licensing desi.gn basis. This conclusion was not reviewed by the corrective a.ction review .bo*ard
. prior to closeout of the activity.* * *
,I.
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 ih 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 detectable. Testing h~s als9 demonstrated the potential for an additional: gro_und to cause a* non-conservative shift in the temperature input .
signals to the TMM which affect the the~mal power calculation.
. For .<?larification, 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* "un_grounded" 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~ II* ,
- :**.~no significant effect. : . ".is interpreted to mean that-a slngle 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 ch.ange 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.
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NRC Form 388A . U.S. NUCLEAR REGULATORY COMMISSION.
19-83) APPROVED OMB NO. 3160-0104 EXPIRES: 8/31 /86 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION
. FACILITY f<IAME 11 l DOCKET NUMBER 121 LER NUMBER. 131 PAGE 141 SEQUENTIAL REVISION YEAR
- NUMBER NUMBER Palisades Plant 0600026694-0 2 - 0 0 6 OF 0 8 CORRECTIVE ACTION*:
The corrective action process ha~ been substantially upgraded in sev~ral respects. All I conditions affecting installed plant equipment are now reviewed for the effect on equipment I operability and a reportability review is conducted for all conditions identified.* A riew screening I group has been established to identify those conditions which ate significant and need plant I.
. management attention and *detailed root cause analysis. There i$ increased management I involvement in the corrective action process. * *I
- A modification has been implement~d to effectively isolate the grounded TMM frmn the I
. ungroundedpressurizer f?ressure loop of the ~PS through the installation of an isolation device located external to the T.MM. * *
. On May 1.6, 1994, during the engineering of the modification to install Isolation between the
- . TMM signc;il 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 gro1,Jnd 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 i11itiated which increases the impedance between the internal ground I connect'ion from the TMM to the temperature signal instrument loops. This was accomplished.
- I by installing three operational a.mplifier input devices internal to the TMM in plac~ 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 pr.ovide the ground path back to the
, temperature circuits. Th.e input d~vices will increase signal commcm~to-ground resistance .to ari 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 .~ffect 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 TfV!M pressurizer pressure circuitry ahd, (2) provide increased electrical resistance* between the TMM temperature in pl.its and the TMM unit to effectively separate the grounded TMM froni the ungrounded temperature circuits; were I
. completed before plant heat-up. . . ' . . r A future modification will be pursued which will remove the internal resistance ground from the TMM, thus restoring the RPS and the Tl\t!M to an ungrounded state. This modification is .I currently scheduled for installation during the refueling outage following the 1995 refueling I
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'NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION
.(9-83) APPROVED OMB NO. 3160-0104 EXPIRES: 8/31/86 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION
- FACILITY NAME 11) .DOCKET NUMBER 121 LER NUMBER (3) PAGE 141 SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades Plant 0600026694-0 2 - 0 Q 7 OF Q 8 outage. The TMM vendor has indicated .. that this is a complex modification and the engineering I anddesign changes needed to remove the internal ground cannot be completed in time for the .I*
1995 refueling outage. I The modifications installed prior to commencing plant heat-up effectively isolate the grounded -I TMM from the ungrounded RPS. Raising the impedance of the ground in the TMM effectively *1 restores the deficient condition to the design and licensing bases.
I.- PRIOR TO PLANT HEAT-UP:
Actions A-D were accomplished pri_or to plant heat-up.
, A. Isolate the TM/LP Pressure trip signal circuits from the internal TMM impedanc_e.
B. Isolate the Primciry 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 ano 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 e_ach Tl\J1M to validate: that circuit isolcition modifications do not effect the TMMs safety function._
- 11. TO PREVENT RECURRENCE:
A. Upda.te the RPS' Failure Modes Effects Analysis to reflect the modifications performed to the RPS and the TMM *as a result of this Event Report.
B. Electrical and l&C engineering personnel have been provided with a summary of this .I event report.
C. The RPS Design Basis Document has been updated to include the work completed. on I, the system and to clarify what an "ungrounded" signal is.
- I D. This event report has been incorporated into the appropriate accredited training programs.
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NRC Form 366A U.S. NUCLEAR REGULATORY.COMMISSION
'. 19-B31 APPROVED OMB NO.* 3160-0104 EXPIRES: 8/31/86 .
. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 ._ . LER_NliMBER 131 PAGE 14)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Palisades Plant 0500025694-0 2 . - 0 Q 8 OF Q 8 E. The original commitment was to change the Nuclear Engineering and Construction I Organization (NECO) Guidelines to ensure that all modifications are designed and I.
. tested appropriately to ensure that isolation and separation requirements are I maintained. This action was riot taken as described, as it is not reasonable to test for I separation and isolation. Separation is a factor of cable and device location: I Engineering design and review are adequate to determine correct device location. . I Isolation is also a design function. Testing of the isolator is done at the time of * *1 procurement if adequa.te design documentation does not exist.
- The existing design* *- I procedures reference the appropriate design documents which spesify the* * *I requirements for adequate electrical circuit separation and isolation. 1.
- F. Change the. FSAFl t_o Clarify the definition of "ungrounded" and the "effects of a* *
. ground" in sectio~ 7 .. 2. 7. . . . .
.* G. Modify the TMMs to remove the internal ground and then reevaluate the need for*
. circuit isolation devices added by this event. report to the inputs and outputs of t.he TMM.
H.. It has been determined that additional surveillance procedures on. the added TMM I isolation devices will not be wr.itten, as an existlng Technical Specification . I*
Surveillance procedure (Ml-2A) tests the isolators as part of the signal loop test .
. I. *. It. was determined that the need exists to periodicaliy monitor unisolated TMM and 1*
RPS circuits for the presence of grounds. A new action has been initiated to develop I a procedure to test RPS and TMM signal circuits for grounds. I J. A memo has been provided _to all l&C technicians on the importan~e of, and methods
grounds on. floating systems. . .. *
.K. Provide a memo summarizing th.e event to all department heads, members of the PRC*
and Management Review Board, emphasizing the ne.ed to recognize situations where the plant is not in compliance with design basis.-*
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