|
---|
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 GB Slade General Manager l'llWERINli MICHlliAN-S l'llOlillESS
. Palisades Nuclear Plant:
- 27780 Blue Star Memorial Hi~hway, Covert. Ml 49043
- Nuclear Regulatory Commission .
Document Control Desk
LICENSEE EVENT REPORT 91-014-03, - SAFETY RELATED CIRCUITS ROUTED WITH OPPOSITE CHANNEL CIRCUITS - SUPPLEMENTAL REPORT . .
License~ Event Report (LER) 91-014:03 is .attach~d.
~ ' *-
basis.
The original. LER 91.-014 was dated August 8, 1991, and provided notification.
- that a physi~al separation and channelization d~ficiency existed with* cabling
- associated with three electrical schemes. In that LER we rioted that becaus~
of an ongoing Electrical Cable and Racew.ay Separatibn Issue Res.elution Plan, we exp.ected to. submit additional information on this subject, as we expected that additional deficiencies may be identified. Supplement 1 to LER 91.-014,
.*dated February 14, l992, prov.ided information concerning additional.
- deficienci~s, their stat~s~ and planned resolution. Supplement 2 to LER 91-014 provided information on a cabl~ s~paration and channelization
- deficiency identified with pressurizer level circuitry* cable .. This attached
- supplement provides.informatiorr on one additional cable separation and *
~hannelization.defiGiency associated with the plants redundant*~ngineered safeguards roo~ ~ir coolers. Because programs afe in place to address these*
deficiencies, and have been described in earlier revisions of this LER, no
- major changes have beeh made to .the descriptions in this LER except for the addition of the latest.deficiency to the attachment to the LER. Any changes d 4 ; t ; c a f l i n e in the right.hand margin.
Gerald B Slade General Manager CC Administrator, Region III, USNRC NRC Resident Inspectdr - Palisades
- Attachment 9205010259 920424 PDR ADOCK 05000255 S PDR
NllCtso:r** U.I. NUCLIAll lllGULATOllY Cm9t1DIC*
~1*
.-ovE:') OMI NO. J110~HM LICENSEE EVENT REPORT (LEA)
'ACILITY NAME 111 IDOCICIT ....all 121 I r*g* llll Palisades Plant o.1s101010121s1s 1 OF OIS
.*.--~ liTrntTr;L**;.-,'!;:-*.........--...~-~-~-~-~..".'".~~----;--...,---;....._--------...,-----...,--......J'-.::.....L:...L..:~;...J..:..J..:...JL.::_~_.1::_~..:...i.::..:..w~~
SAFETY RELATED CIRCUITS ROUTED WITH OPPOSITE CHANNEL CIRCUITS - SUPPLEMENTAL REPORT
. Liii NUMeElll.Cll llll'OllT DATE 171 . OTHlll 'ACILITIU llrVOLVIO Ill'
- YEAR f{ISl~~~:~~AL f:;}: : . : MONTH DAY *YEAR ~AClLITY .. AMU OOCKIT NUMalRlll N/A 01&1010101 I I oh 19 9 1 9l 1 - I 0 11 14
- ol3 0 14 214 91 2 N/A 01S1010101 I I ITTEO l'UllSUANT TO THI lllQUllllMINTI O' 10 Cfll §: /etr.d - or,,,_ of 1M fol-..,J 1111
Ol'lllATllllG 1--llOO-* -*.-II-I-~~--< 21Ull21111
-- 20.<IOlllol I0.71lo!llJlll*I .__ 1u1i.1
-- ---
POWlll ,.
- ao.*c.1111111 IO.JllolCll ID.714111JIM 71.71111
LIVIL i......
1101 or o 1o ao.*c.11111w1 I0.*101121 . I0.711811211 .. 1 ...._ OTHlll /$/#e/f'>; ;,, Ab<OWr 1#1-.11111 /ff Text, NRC ,,.,.,,,
-
~
I0.7Jlall21111
- ID.71lo!llJHwlllllAI .U,).
I0.71lo!llJllUI ID.71C.llillw1111191 .
LX. I0.7JC.llJIUUI 111.n1a11211.1 LICINIH CONTACT fOll THll Liii 1121 T LEPHONE NUMBER ARIA CODI Will~am L. Roberts, Staff Licen~ing Engineer
~LITI ONI .LINE fOR IACH COMPONENT fAILUlll OllClllllO IN THll. lllJIOflT 1111 CAUH SYSTEM COMl'ONENT* !REPORTABLE::::::::::::::::::-:::::::::::::::::.::::::: CAUSE SYSTEM COMl'ONENT TO NPRDS :::::::: :::::: :
- -:*-:-: :*:*::*:* *:*:*:-:*:*:>:*
- :::::::: : : : )j
- ::::::::: :::::::
- : :*:* : : : ){ )} :r::.
- '.*'.**=-:*:*:-. :=:=:*:*:-:;;. ::::
I I I I I I I- :::::-::::::::-,: :::: .;.::::: I I .I I I I I :*;.:.;*:**.*.-.*;*:* ::::
- ' I.
I
) >
- ::::::-:*: :::::::::::::::::::
}
H*'.**.*:*:-:*:*
O:*:*
.;*:-:-:.:*
t:::*:::::-:-:::.::::.;:-::::-:::::::
- .;
- ::::: .. :-:*:;.:::.:*:
I I I I i I *:-:-::::: *:*:**:*:* :::::-:::::::::
-
I I I I I I I ~.*.* :;;;;:;:;;;:;::*:*; :;.;;:;:: :;::
"""LIMINTAL RIPORT EXPECTED 11" y. YI IX'ICTl!D
. .
n IUIMISllON OATE 11111 YU (If llW. * - llJ<'IC'TED SVIMISSION. DA TEJ I I
1\81TflACT /Limit ,. l<<IO -
- I.a.. -x;;,,,,.,y fl,_ li'WI*-* ry_rre,, /in.V 1111 .
Through the on-going Palisades Configuration-Control Project a number of apparent discrepancies in circuit routing have been identified. Previ~us NRC correspondence dated September 4, 1990 and March 12,-19_91 provided details of the "Ci~cuit ~nd Raceway Schedule Enhancement Proje~t" and status of the projects .activities. The electrical .circuit channelization and separation deficiencies which have been evaluated at this time, while not conforming to FSAR criteria in all res_pects, have resulted in identification of very few conditi.ons involving a loss of ~lectrical ~r protection system independence; or noncompliance with 10CFRSO, Appendix R requirements". In those few cases compensatory measures and corrective actions have been taken as stipulated in plant Technical Specifications and/or the condition was promptly-correct~d~
The physical separation and channeli~ation deficierici~s that have been identified appear to result from two separate failures: 1) A non-uniform interpretation of design criteria for chann~lizing and routing electrical circuits, and 2) the unavailability of a single, complete .and reliable source of desfgn document*tion for electrical circuit routing and channelization.
At the time of the discovery of the latest discrepancy (engineered safeguards room cooler cfrcuitry channelization}, the plant was shutdown for a refueling outage..
IM31
,*-**** ., **-*
llllC *** - -
- NJ* "I *wC~iA* *1;.;,,.r:)** ==-***Oil
- .-01110 ~wt *O l'to-4*1).e . -
IO**o **~*,. -
..
~** *~* ** *&QI
- Palisades Plant Op 14 - - oI 3 o 12 oir. o 1s*
"",............ -------All"'.,.."" -
EV~NtDESCRIPTION T_he *Palisades Configuration Control Project (CCP) which was initiat~d in 1987
'included an effort to.veri.fy and correct plant electrical drawings, including the plant circuit and raceway schedule. - This effort involved development of a circuit and raceway schedule data.base, as well as-verification of selected portions.of circuit routings. Through this effort a number of apparent discrepancies in circuit routing have been identified. - This event involves_
approximately *40 circuits wh.ich were bel ie-ved. to be safety-related. cj rcuits routed with opposite channel circuits. Previous plant deviation reports
- involving apparently mls'-routed Circuits include D.-PAL-8~-147, D-PAL-90-40, D-PAL-90-221, and D-PAL-90-222. All of the apparently mis-routed circuits*
from these earlier deviation reports that have been evaluated,. have been dispositi.oned as either notb"eing safety-related and therefore channelized circuit rout~ng .is not an issue, or the cirtuit mis-routing .is nrit a ~afety
' concern because the failu~e of the cfrc~it does not lead to: undesirable consequences (i.e. the circuit fails safe). Additional backgrbund and*
information on the CCP circuit.and raceway_ enhancement *project was p~ovided to the NRC in our letter dated Septembe~ 4, 1990. * ~ st~t~s update on the proje~t c was provided. i,n -our letter dated March 12, 1991.
.
At- the time of th*e disc<?very -~of the 'latest discrepancy *(engineered safeg-uards
- roc;>m *cooler.s circuitry Channelization), the plant was shutdown for a refueling
-outage.* This event 'is :reportable as _a condition *outsid~ the des-ig!l _oasis of I
- . the pl ant. * * .
. Cause of the Event*
~he physical separation and-channelization deficiencies that have been _
id~ntified appear t~ result from two separate: failures: 1) A: non-uniform interpret~tion of design criteria for channelizing and routing el~ctrical circuits, and 2) the una~ailability of a single, complete and reliable source**
of design docum~ntation for electrical circuit r9Uting and channelization.
Analy~is of the Event .*.. ..
Cable. Separation_ Design Criteria The desig_n criteria wfrich were or-ig.inally used at Palisades to provide - -
physical independence between redundant electrical tircuits were submitted to the Atomi.c Energy Commission (AEC) on May 28, 1969. This submittal contained, in part, our response to a requ~st for information regarding the criteria and_
associated bases used at Palisades during initial design and installation of*
- el~ctrical circuits. The ~uidelines that are currently used during design of electrical cables and rateways are essentially unchanged from those of the "original design period and are r~flected in FSAR Section 8.5.3.1. FSAR Section 8.5.3.1 states that circuits belonging to safety-related power distribution channels, reactor prote~tion system channels, engineered safeguards channels or other _safety-related syste!:ll channels will be run in
llltC . . . . .
1~1 . . '"~- *'-C~Ua .*I~""'.~** ::..01*.1<>
. . UCINSll . , . AIPOffT ILIA> TIXT CONTINUA. "°
_OOC&IT ""'91* Ill .,
............ ...... '""
.*-Ov10 ~ ...
l'to-4*00 *
.
..... ...
~
~~!!-::1:~ ;-"'.!'..~~
Palisades Plant 911 - o 11 I 4 - 013 01 3 011 0 15 *.
separat~ raceway sy~tems; and that "physical separation; (dist~nce), is considered to ~e most reliable method of providing circuit separation and
- In practice, the.design criteria fbiphysical separation and independence of.
electrical circuits are primarily satisfied by* routing electrical cables in chanryelized cable raceways, and by maintaining a separation distance between.
these*channeliz~d raceways .. Thts method of providing physical separatio~
between redundant e_lectrical circuits meets the intent of currently accepted standards and guidelines and has been reviewed and determined tobe
.acceptable. Palisades was designed pri.or to issuance of Regulatory Guide
.* I. 75., "Physical Independence of Electrical Systems," the AEC General Design
- *. Criteria for physical independence of electrical circuits, or.the*asspciated IEEE standards (IEEE 279' IEEE 384) . . ' .
Circuit Separatjon and Channel izatipn Anomalies *>
We have identified several examples where the cha*nnelization of installed .
electrical cables does .not satisfy our original design criteria .. The actual
. *number of electrical cable_ separation and channelizat1on discre,pancies_
. identified so far represents only,_a very small percentage (less. than orie percent) *of the over thirteen thous~nd* electrical cables that we have evaluated~ As a res.ult of these cable routing anomalies, we 'f1ave unde.rtaken a*
- progral!'lmatic effort to identify and resolve those physfr:a1 separation and ..
channelization discrepancies that may exist, and we have.taken steps to
- prevent prcimulgation of iimilar di~crepancies in1he future~ We have also**
taken actions to address the physical separation. *and *channelization * . *
- deficiendes-whicb h.ave been.identified to date. * ..
The electrical circuit chanri~liiation and separat*i*o*n deficiencies which *have been ~valuated at this time, while not cdnforming t6.FSAR criteria in all respects, have resu.lted in identification of very few safety-significant
- conditions involving a loss of electric;al or protection _system independence or
- .noncompliance with. IOCFRSO, Appendix R requirements. *In those few cases. . ..
comp_ensatory measures and corrective actions h'ave been taken as stipulated .in plant*Technical Spec'ifications and/or the condition was promptly c,orrected..
- . Palisades has taken an aggressive pos.ition i.n its response to the identified eleetrical cable routing and channelization discrepancies *through the Electrical .Cable and Raceway Separation* Issue Resolution Plan . . This plan*
- addresses the causal factors for these conditions and proposes actions to prevent reoccurrence. The key provisions of this pl an include:
publication of clear procedural ,guidance relative to cable routing design .
. criteria, 2} availability of reliable circuit design- information, 3) field
- review of installed raceways, and -4) evaluation and resolution of identified cable routing*and ~hannelization discrepancies. As we have done in the past, we wiJl evaluate confirmed cable routing and separati~n discrepancies for safety-significance and *operability impact when they ~re identified, and*
. compensatory and corrective measures will be. pursued, as necessary ..
- ~** "1 *we~~** *IQ ... ~ .. *:i** :~***ooo
......,....,. ..
.
.-01110 ~ ... ..0 l'to~*G.
OOCUT . . . .1*111 '
..... ~**~***. *&QI >>
. ~alisades Plant o s o o o .2 *s s. 9*i 0 1 4.* .... 0. 3 4 011 0 5 1 :
- This _event is being reported under 10CFRSO. 73(a) (2)(1i) as a condition. outside
~the des1gn: basis of.the plant .. :*
Corrective Action* ..
- .. _Corrective. actions a~dressi ng .ci rc.uit channel i ti' -and separation . ta on .
defi-ciencie~ began with _the Electrical Cable and Raceway Separation Issue .
- Resolution Plani *A suimriary anq implementat:ion schedule for these ac;tions was provfded fo our September 4, 1990, "Submittal of. Add,.itfonal informati_on
- Related to the-Cir*cuit and Raceway Schedule Enhancement Project," and .a status update was* provide4 in our-March 12, 1991- lett~r. The_actions and their
.. FUrrent status are listed below: * *
- .. L * .The* des-i gn *'and n ~ens i ng :basis.: for thannel i zat.i on .and phys i ca i.
- *. : separation* of elect.rical circuits has been reconstituted _and * . . . .
- consolidated ,in a single.:dotument,_ the "Electrical S~paration. Desig*n * ..
- ,. C~iteria*~and Licens_i~g ~asis .. ". _* ... * ., . ... * . . *
.< . *.. * .'. ~. * . G~*i d~-~c~ *h~s~ been deve lOped Jn Admi ni strati v~
- Proc~dure ,'9 ~3~, ** . ** * .:** **'.
. . :;, -"Circu.it'. and Raceway Schedule!',~*. for contfol *and entry of _design* . ~ *~ *.::: . . _. -* ...
informat*ion-. in the)~a.~le_,*-~nd: Raceway Schedul_e (c~*sr datab~se . .
. :i.*,. *. . * * .** . , *,:* .*
o' C~ble ~outing.* requ.i ~'~merits and: .practi ~.ei ha~e **peen **_incorpo.rated- *i ntri * .. *.
Engilie~ring.-Guidelines: EM-22-.04~-- Ch'anne_l .Sepa*r~.tion ~- C'able;* * *':
- Routing* Instr_uctions;'" ..EM-:22-03, *"Fire Protection- - Cable *Route .... . ~
- Verification;'" EM-22-06; ."~able Routing - EEQ Requirements;'~ ****: *.
EGAD-PROJ.--:08, "Cable Sizing* Gujd.eline >Amp~city;-" and EGAD'.. PROJ*-03; * **' *' *
"Electrical Engine_erjng *sep,arat:ion Criter_ia; Prac.tiC:es and*_, ,. - . . ,:.
Except.ions; * . *. * ., * * * .. :: .* .. ;
. .' 1**."* . ** : ' *, . '
4~ A p_hysical:;rev1ew of *installed cable: raceways h_as been performed. fo order to identify i.nstallati9i:is *th~t do not -meet. desig.n * .
>req_ufreinents;_;. * ...-*.*.:._ *,** * * .,*'.*
,_-.
- 5;.*:~ Design tnforma~ion relative to the cha:~neli:£ation *and phy,sical
- roµting of electrical circuits and ra~eways will be erihanced._ Thts*-
attiori will tnclude validation ~nd.tcimpletion ~f informat.ion * .;:" ..
. . contained. in the .CRS database *and is currently expected to be
- comp_l ete *prior to ~eptember 30, 1992. * "..:
. . .
.6. * -Electrical cabie*:sepa-ration and channelization* anonial ies fdentified .
. during our review of physical *raceway installations .will .be
. evaluated and appropriate_ly dispositioned.. The sc_hedule* for* ,.
re solution of these i terns *iS. dependent on the number and' type of* .
. items identified during the revi~w.
.. ** .
llllC *** - -
- MJ* .IJ a iiwc~&****1c1.i1o.*'~** .::a.t***Qlil i..JCENSEE -NT -AIPOffr ILIA) TIXT CONTINUA-N * . - 0 .. 10 ~ ... "° l'to..,)*~
..... ............
........ l*'l*"
QOCUT llUMll* Ill * *~
. *&QI JI
- Palisades Plant 25591 05000 0 1. 4 - .0 3 5 011 0 5
" _..;;;..:. 1'1IT , . _ ...........-........ -. ..........,.,i71 .--
For the specific circuits in this LER, the Configu~ation Control Project (CCP)
Electrical Cable and Raceway Separation Issue Resolution Plan is intended to address the root cause of this event and no further corrective actions to
- prevent. recurrence are proposed at this time. Remedhl actions for the recently identified specific circuit routings are as follows:
,*
A.* Since only class IE circuits require physical separation of . .
channelized circuits, the safety classification of each potentially mis-routed circuit will be ~e~iewed.
- B. -The in-.plant routing of .each potentially' mis-routed safety-related channeli.zed circuit wilr b~ verified.
- A further investigation of t~e original plant design basis for.
physical separation of safety-related ~trcuits was completed. Bas~d.*
on the results of this review, the EGAD-PROJ-03, "Electrfcal Engin~ering Separation Criteria, Practices, and exception~," was revised. * * *
- D. Each confirmed circuit channelization def1ciency *will be evaluated with regards to *equipment _opera bi 1ity and 10Cl'R50. 59; 'Appropriate **
compensatory measures and corrective actions as stipulated in.plant .
. . Technical Specifications will also be taken .. A list .of confirmed .
- . circuit channelization deficiencies is p~ovided in. the attachment to
.*this LER. . . . .
E. Physical separation of improperly channelized, safety"'.related circ~its will be established on a sched~le.consistent.wtth the
. safety significance of the deviation. * *
.. If 1t i's determined that' failure of the _improperly channelized, safety-related circuit does not ad~ersely affect ac~omplishment of.a
- . safety function, the circuit may be left as currently routed. Such*
conditions will be clearly documented in the* Circuit and raceway sc~edule~ * * * * *
- F. Confidence in the accuracy *of the.circuit routing data in.the Circuit and Raceway Schedule was evaluated,. and it was determined ,.
that additional verification inspettions are not needed to assure *,
that circuit channelization deficiencies have been identified.
Addition~l fnfo~mation Previous submittals of this lER, dated August 8; 1991, February 14, 1992 and March 10, 1992 have identified information on other.cable separation discrepancies.
Attachment
'I' ... *.
LER 91-014 S~pplement 2 CONFIRMED CIRCUIT CHANNELIZATION AND SEPARATION DEFICIENCIES Scheme Scheme Name NUinber *Operable " Unreviewed
- Co11111elit of .. Safety Circuits Question 8293 Die~el Gener~tor Room 2 . No No When: the erinditicin was discovered a.
Cooling Fan V24C .
- temporary modification was performed to remove reliance on V24C;' This .
'
-
circuit has been re-routed to provide proper physical separation.
..
S65 Reactor Prcitection 1 *. Yes No Failure of circuit d6e~ not System adversely affect accomplishment.of the safety function.
... .1 IP 73
No . . Yes When the condition was discovered a Range Pressure . .. temporary modi fi.cati on was performed to discorinect the circuit.
physical separation will be
.. *established .
sos Service W~ter System 1 . Yes . No Failure of this c i r*cu it does not Valves adversely affect accomplishment of
.. the safety function .
"
G06R Diesel 1-2 Auxiliary 1 *No. No Fail~re of this circuit does not Skid adversely aff~ct accomplishment-of
"
the safety function in short term.
(2-4.hours). Long term operator
.actions are addressed in *plant
. .
proced~re~. Proper physical .
" separation will be established .
..
Sl6 Crimponent Cooling J . Yes No Failure of this circuit does not Water Valves* adversely affect accomplishment *of the safety *furict ion ..
'[r ..*
Attachment * '.
LER 91-014 Supplement 2 Scheme Scheme Name Numb£!r. Operable Unreviewed C011111ent of Safety ..
Cfrcuits Question 0408 .Control Rooin HVAC 1 Yes . No -failure of thts circuit does not Emergency.Actuation adversely affect accomplishment of the safety function; however, position indication for ventilation system dampers may be lost. This Regulatory Gui de 1. 97, Category 2
.. instrumentation is not required to meet the single failure criterion; S21 and Waste System . 19 Yes No Failure of these circuits does not S22 *Containment Iso1ati-0n adversely affect accomplishment of Valves *the S~fety function; however, containment *isolation valve position S25 and Miscellaneous 17 Yes No indication may be lost. This S26 Containment Isolation Regulatory Guide I. 97, Category 1 Valves instrumentation is required to*meet
. . the single failure criterion. The .
'
instrumentation was *not upgraded with regards to physical separation when Regulatory Guide 1.. 97 *was imposed by NRC Generic Letter 82-33 .
. This was due to our failure to .
recognize that physical separation criteria were not met. This conditi~n is being evaluated to determine if the circuits should .be
..
reverified to provide proper physical. separation, .or if *
,.
justifita~ion ~xtst~ to request NRC
. .
approval of a deviation from the
.
Regulatory Guide 1.97 requirements .
2
.* *-
. . . Attachment .* ., . .*' '.
- ' ** LER 91:-014. ,Suppl emetit:. 2 *:: .* *.,* .: ~ .
Scheme Scheme Name Number . Operabl~ Unrevi ewed . C011111ent of.** * * , Safety Circuits Question IL34 Pressurizer_'Wide :Range -No : ves*
- Redundant insirumentS have cables
-and Level * ~ . *~
rout_ed through one cable tray. .Both IL37 '.
.,
..
- level instruments are identified i.n
- ,.
I J.'
"*
- _the Te~hniial .Specifications .. Th~
cables will be re-routed to provide
~eparation ~s f~quired i~: FSAR
'8131 Engineered Safeguards 2 Yes .. *No* The fan*coolers are left channel but and Room Coolers fans V27A the power c~bles fot the fans ate 8133 and V27C .routed with right channel cables,.
through a control room floor elettrical penetration. Failure ~f
- -these circuits .does not adversely affect the accomplishment of the-*
.. safety function as the redundant' -
coolers cabl~s ,ate routed separat~ly
.. ' *~
f~om these-circuits. *
. *, t
. ! . . >
. . '* I',*
... ~J '
. .*..
. ,*
. '
.. *"'"** ' .
... ***** ...
.*.,
. *'*I
~
. '