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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML17313B0191999-07-16016 July 1999 LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure ML17313A9281999-05-0707 May 1999 LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs ML17313A8951999-04-14014 April 1999 LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked ML17313A8921999-04-13013 April 1999 LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc ML17313A8891999-04-0909 April 1999 LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr ML17313A8361999-03-0101 March 1999 LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr ML17313A7701999-01-15015 January 1999 LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised ML17313A6611998-10-24024 October 1998 LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements ML17313A5961998-09-14014 September 1998 LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired ML17313A5761998-09-0808 September 1998 LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters ML17313A5591998-08-28028 August 1998 LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr ML17313A5201998-07-30030 July 1998 LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr ML17313A4671998-06-19019 June 1998 LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced ML17313A4131998-06-0505 June 1998 LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria ML17313A3951998-05-26026 May 1998 LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation ML17313A3251998-04-0101 April 1998 LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7 ML17313A3131998-03-21021 March 1998 LER 98-001-00:on 980301,surveillance Test Deficiency Found During Qaa Leads to TS 3.0.3/4.0.3 Entry.Caused by Personnel Error.Personnel Responsible for Inadequately Performed SR Were Coached ML17313A2251998-03-0505 March 1998 LER 93-005-00:on 930309,CR Personnel Discovered Missed TS LCO Action & Subsequently Performed Surveillance Satisfactorily.Caused by Personnel Error.Appropriate Disciplinary Action issued.W/980305 Ltr ML17313A2241998-02-26026 February 1998 LER 98-001-00:on 980130,reactor Protection & ESFAS Instrumentation Not Bypassed within one-hour Allowed by TS Occurred.Caused by Inadequate Procedures.Expectation to Detect Alarm Conditions Was Emphasized to CR Personnel ML17313A2081998-02-10010 February 1998 LER 97-007-00:on 971006,TS Violation Occurred Due to Inadequate Shutdown Cooling Flow During Modes 5 & 6 Operation.Independent Investigation of Event Was Conducted IAW APS CA program.W/980210 Ltr ML17313A2041998-02-0505 February 1998 LER 97-006-00:on 971028,missed TS 4.0.5 SR Was Noted.Caused by Personnel Error.Independent Investigation of Event Is Being Conducted IAW W/Aps Corrective Action Program ML17313A1201997-11-12012 November 1997 LER 97-006-00:on 971020,manual Reactor Trip Occurred Due to Vibration & Bearing Temp Increases in Reactor Coolant Pump. Caused by Failed Lower Journal Bearing.Bearing Assembly Was Disassembled,Inspected & Rebuilt ML17312B7181997-10-0707 October 1997 LER 97-003-00:on 970907,inadvertent Loss of Power & EDG Start Occurred Due to Procedural Error.Changed Train a & Train B Edg/Ist ST Procedures to Consistently Reflect Proper Pretest Staging Hand switches.W/971007 Ltr ML17312B7051997-09-26026 September 1997 LER 97-003-01:on 970215,seven Main Steam Safety Valves Were Found Out of Tolerance Prior to Refueling Outage.Safety Analysis Performed Based Upon as-found MSSV Data Which Demonstrated That MSSVs Would Perform Safety Functions ML17312B5531997-07-0707 July 1997 LER 97-002-00:on 970528,SR for Core Protection Was Not Performed Due to Inadequate Procedures.Revised Procedures ML17312B5501997-07-0707 July 1997 LER 97-003-00:on 970211,notified of Trevitest Activities Indicating That Total of Seven MSSVs Had as-found Lift Set Pressures Greater than 3 Percent Allowed by TS 3.7.1.1. Investigation Conducted.Seven MSSVs replaced.W/970707 Ltr ML17312B4971997-06-13013 June 1997 LER 97-002-00:on 970531,RT Occurred.Caused by Spurious Opening of All Four Rt Switchgear Breakers.Independent Investigation of Event Being Conducted in Accordance W/Util Corrective Action Program ML17312B1461996-12-17017 December 1996 LER 96-007-00:on 961119,surveillance Test Deficiencies Were Found During GL 96-01 Review Leading to TS 3.0.3 Entries. Caused by Increase in Scope of Required Testing.Supplement Will Be submitted.W/961217 Ltr ML17312A9511996-09-0404 September 1996 LER 96-003-00:on 960809,open Auxiliary Bldg Door Caused Full Bldg Essential Filtration Inoperability.Caused by Personnel Error.C/As Under consideration.W/960904 Ltr ML17312A8641996-07-17017 July 1996 LER 96-001-00:on 960621,inaccurate Gas Calculations for Post Accident Sampling Sys Occurred.Caused by Surveillance Test Worksheet Errors.Independent Investigation of Event Being conducted.W/960717 Ltr ML17300B2541996-06-11011 June 1996 LER 96-001-01:on 960404,inappropriate Grounding of Equipment Resulted in Condition Outside Design Basis of Plant. Established Fire Watches Required for Affected Areas ML17312A8081996-06-0909 June 1996 LER 96-002-00:on 960514,Tech Spec Violation Occurred Due to Erroneous Surveillance Requirement.Caused by Incorporation of C-E Generic Ts.Investigation Being conducted.W/960609 Ltr ML17312A7751996-05-17017 May 1996 LER 96-003-00:on 960122,missed Surveillance for Logic Check of Logs 1 & 2 Safety Excore Bypasses.Caused by Procedural Error.Log Power Functional Test Revised to Check Logs 1 & 2 Bypasses Regardless of Power level.W/960517 Ltr ML17312A7511996-05-0606 May 1996 LER 96-001-00:on 960404,smoke Discovered in Back Boards Area of CR by Security Officer,Performing Hourly Fire Watch Tour. Caused by Improperly Grounded Circuit.Investigation for Inappropriate Grounding of Low Voltage Power Sys Initiated ML17312A7241996-04-25025 April 1996 LER 96-002-00:on 960401,inappropriate Work Practice Resulted in Esfa of Train B Edg.Night Order Was Issued to All Three Units Describing event.W/960425 Ltr ML17312A6861996-04-0606 April 1996 LER 95-007-01:on 950512,determined That Bench Settings of air-operated Letdown & Containment Isolation Valves Adversely Affected Ability of Valves to Perform 10CFR50 App R Safety Function.Affected Valves Modified ML17312A5631996-02-22022 February 1996 LER 95-016-00:on 951212,containment Spray TS Violation Occurred Due to Unrecognized Valve Failure.Shim/Band Was Placed Around Stator of 1JSIBUV665 Motor Operator to Maintain Stator in Correct position.W/960222 Ltr ML17311B3381996-01-0909 January 1996 LER 95-014-00:on 951209,reactor Tripped Following Degradation of Main FW Flow.Caused by Malfunction of Fwcs Power supply,NNN-D11,transfer switch.NNN-D11 Aligned to Normal Power supply.W/960109 Ltr ML17311B3331995-12-31031 December 1995 LER 95-013-00:on 951201,AFW Sys Was Outside Design Basis of Plant.Caused by Design Error.Performed Assessment to Demonstrate That Existing Condition Does Not Pose Addl Safety concerns.W/951231 Ltr ML17311B2801995-11-23023 November 1995 LER 95-011-00:on 951018,identified Procedural Deficiency W/Msiv & FWIV ISTs Due to Personnel Error.Verified Operability of MSIVs & FWIVs.W/951123 Ltr ML17311B2531995-10-20020 October 1995 LER 95-002-00:on 950924,identified That Abnormal Blowdown Valves to Blowdown Flash Tank (Bft) Isolated,Resulting in Reactor Core Power Exceeding 3,800 Mwt Due to Personnel Error.Procedure for Aligning Blowdown to Bft Revised ML17311B1991995-09-21021 September 1995 LER 95-010-00:on 950727,equipment Qualification of Air Handling Unit Caused Essential Cw Pump to Be Inoperable. Used Work Orders to Drill Weep Holes in Motor Lead Connection boxes.W/950921 Ltr ML17311B1741995-09-0404 September 1995 LER 95-004-01:on 950329,containment Electrical Penetration Overcurrent Protective Devices Found Outside Design Basis. Caused by Error on Part of Original Architect Engineer. Modified Affected Circuits Critical to Normal Operational ML17311B1561995-08-27027 August 1995 LER 95-003-00:on 950729,switchyard Voltage Dropped Below Administratively Imposed Limit of 524 Kv for Approx 10 Seconds Due to Transient Grid Voltage.No C/A Taken Since Transmission Sys Transient Short duration.W/950827 Ltr ML17311B1551995-08-25025 August 1995 LER 95-002-01:on 950303,identified That Slb Analyses Failed to Consider as Initial Condition One Percent SDM for All Rods in (ARI) Due to Lack of Coordination & Unclear Div of Responsibilities.Ari Core Data Book SDM Curves Modified ML17311B1211995-08-16016 August 1995 LER 95-005-00:on 950717,RT on Low SG Water Level Was Result Following Degradation of MFW Flow.Completed Evaluation of Event ML17311B0841995-07-28028 July 1995 LER 94-005-01:on 941019,completed TS Required Shutdown Due to Expiration of LCO Time Limit.Design Change Options Identified & Will Be Reviewed to Determine If Valve &/Or Motor Operator Replacement or Mod Necessary ML17311B0721995-07-20020 July 1995 LER 95-004-00:on 950706,identified Four Occassions Between 950407 & 0630 When Conditional Surveillance in TS LCO 3.8.4.1 Action a Not Performed Due to Inattention to Detail. CR Copy of Temporary Procedure 40TP-9ZZ04 Corrected ML17311B0081995-07-0606 July 1995 LER 95-003-00:on 950613,TS LCO 3.0.3 Entered Following Loss of Both Trains of Essential Cw Sys & Both Hydrogen Recombiners.Caused by Spurious Actuations Due to Broken EDG Speed Probe Connector.Connector replaced.W/950706 Ltr 1999-08-27
[Table view] Category:RO)
MONTHYEARML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML17313B0191999-07-16016 July 1999 LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure ML17313A9281999-05-0707 May 1999 LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs ML17313A8951999-04-14014 April 1999 LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked ML17313A8921999-04-13013 April 1999 LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc ML17313A8891999-04-0909 April 1999 LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr ML17313A8361999-03-0101 March 1999 LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr ML17313A7701999-01-15015 January 1999 LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised ML17313A6611998-10-24024 October 1998 LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements ML17313A5961998-09-14014 September 1998 LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired ML17313A5761998-09-0808 September 1998 LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters ML17313A5591998-08-28028 August 1998 LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr ML17313A5201998-07-30030 July 1998 LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr ML17313A4671998-06-19019 June 1998 LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced ML17313A4131998-06-0505 June 1998 LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria ML17313A3951998-05-26026 May 1998 LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation ML17313A3251998-04-0101 April 1998 LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7 ML17313A3131998-03-21021 March 1998 LER 98-001-00:on 980301,surveillance Test Deficiency Found During Qaa Leads to TS 3.0.3/4.0.3 Entry.Caused by Personnel Error.Personnel Responsible for Inadequately Performed SR Were Coached ML17313A2251998-03-0505 March 1998 LER 93-005-00:on 930309,CR Personnel Discovered Missed TS LCO Action & Subsequently Performed Surveillance Satisfactorily.Caused by Personnel Error.Appropriate Disciplinary Action issued.W/980305 Ltr ML17313A2241998-02-26026 February 1998 LER 98-001-00:on 980130,reactor Protection & ESFAS Instrumentation Not Bypassed within one-hour Allowed by TS Occurred.Caused by Inadequate Procedures.Expectation to Detect Alarm Conditions Was Emphasized to CR Personnel ML17313A2081998-02-10010 February 1998 LER 97-007-00:on 971006,TS Violation Occurred Due to Inadequate Shutdown Cooling Flow During Modes 5 & 6 Operation.Independent Investigation of Event Was Conducted IAW APS CA program.W/980210 Ltr ML17313A2041998-02-0505 February 1998 LER 97-006-00:on 971028,missed TS 4.0.5 SR Was Noted.Caused by Personnel Error.Independent Investigation of Event Is Being Conducted IAW W/Aps Corrective Action Program ML17313A1201997-11-12012 November 1997 LER 97-006-00:on 971020,manual Reactor Trip Occurred Due to Vibration & Bearing Temp Increases in Reactor Coolant Pump. Caused by Failed Lower Journal Bearing.Bearing Assembly Was Disassembled,Inspected & Rebuilt ML17312B7181997-10-0707 October 1997 LER 97-003-00:on 970907,inadvertent Loss of Power & EDG Start Occurred Due to Procedural Error.Changed Train a & Train B Edg/Ist ST Procedures to Consistently Reflect Proper Pretest Staging Hand switches.W/971007 Ltr ML17312B7051997-09-26026 September 1997 LER 97-003-01:on 970215,seven Main Steam Safety Valves Were Found Out of Tolerance Prior to Refueling Outage.Safety Analysis Performed Based Upon as-found MSSV Data Which Demonstrated That MSSVs Would Perform Safety Functions ML17312B5531997-07-0707 July 1997 LER 97-002-00:on 970528,SR for Core Protection Was Not Performed Due to Inadequate Procedures.Revised Procedures ML17312B5501997-07-0707 July 1997 LER 97-003-00:on 970211,notified of Trevitest Activities Indicating That Total of Seven MSSVs Had as-found Lift Set Pressures Greater than 3 Percent Allowed by TS 3.7.1.1. Investigation Conducted.Seven MSSVs replaced.W/970707 Ltr ML17312B4971997-06-13013 June 1997 LER 97-002-00:on 970531,RT Occurred.Caused by Spurious Opening of All Four Rt Switchgear Breakers.Independent Investigation of Event Being Conducted in Accordance W/Util Corrective Action Program ML17312B1461996-12-17017 December 1996 LER 96-007-00:on 961119,surveillance Test Deficiencies Were Found During GL 96-01 Review Leading to TS 3.0.3 Entries. Caused by Increase in Scope of Required Testing.Supplement Will Be submitted.W/961217 Ltr ML17312A9511996-09-0404 September 1996 LER 96-003-00:on 960809,open Auxiliary Bldg Door Caused Full Bldg Essential Filtration Inoperability.Caused by Personnel Error.C/As Under consideration.W/960904 Ltr ML17312A8641996-07-17017 July 1996 LER 96-001-00:on 960621,inaccurate Gas Calculations for Post Accident Sampling Sys Occurred.Caused by Surveillance Test Worksheet Errors.Independent Investigation of Event Being conducted.W/960717 Ltr ML17300B2541996-06-11011 June 1996 LER 96-001-01:on 960404,inappropriate Grounding of Equipment Resulted in Condition Outside Design Basis of Plant. Established Fire Watches Required for Affected Areas ML17312A8081996-06-0909 June 1996 LER 96-002-00:on 960514,Tech Spec Violation Occurred Due to Erroneous Surveillance Requirement.Caused by Incorporation of C-E Generic Ts.Investigation Being conducted.W/960609 Ltr ML17312A7751996-05-17017 May 1996 LER 96-003-00:on 960122,missed Surveillance for Logic Check of Logs 1 & 2 Safety Excore Bypasses.Caused by Procedural Error.Log Power Functional Test Revised to Check Logs 1 & 2 Bypasses Regardless of Power level.W/960517 Ltr ML17312A7511996-05-0606 May 1996 LER 96-001-00:on 960404,smoke Discovered in Back Boards Area of CR by Security Officer,Performing Hourly Fire Watch Tour. Caused by Improperly Grounded Circuit.Investigation for Inappropriate Grounding of Low Voltage Power Sys Initiated ML17312A7241996-04-25025 April 1996 LER 96-002-00:on 960401,inappropriate Work Practice Resulted in Esfa of Train B Edg.Night Order Was Issued to All Three Units Describing event.W/960425 Ltr ML17312A6861996-04-0606 April 1996 LER 95-007-01:on 950512,determined That Bench Settings of air-operated Letdown & Containment Isolation Valves Adversely Affected Ability of Valves to Perform 10CFR50 App R Safety Function.Affected Valves Modified ML17312A5631996-02-22022 February 1996 LER 95-016-00:on 951212,containment Spray TS Violation Occurred Due to Unrecognized Valve Failure.Shim/Band Was Placed Around Stator of 1JSIBUV665 Motor Operator to Maintain Stator in Correct position.W/960222 Ltr ML17311B3381996-01-0909 January 1996 LER 95-014-00:on 951209,reactor Tripped Following Degradation of Main FW Flow.Caused by Malfunction of Fwcs Power supply,NNN-D11,transfer switch.NNN-D11 Aligned to Normal Power supply.W/960109 Ltr ML17311B3331995-12-31031 December 1995 LER 95-013-00:on 951201,AFW Sys Was Outside Design Basis of Plant.Caused by Design Error.Performed Assessment to Demonstrate That Existing Condition Does Not Pose Addl Safety concerns.W/951231 Ltr ML17311B2801995-11-23023 November 1995 LER 95-011-00:on 951018,identified Procedural Deficiency W/Msiv & FWIV ISTs Due to Personnel Error.Verified Operability of MSIVs & FWIVs.W/951123 Ltr ML17311B2531995-10-20020 October 1995 LER 95-002-00:on 950924,identified That Abnormal Blowdown Valves to Blowdown Flash Tank (Bft) Isolated,Resulting in Reactor Core Power Exceeding 3,800 Mwt Due to Personnel Error.Procedure for Aligning Blowdown to Bft Revised ML17311B1991995-09-21021 September 1995 LER 95-010-00:on 950727,equipment Qualification of Air Handling Unit Caused Essential Cw Pump to Be Inoperable. Used Work Orders to Drill Weep Holes in Motor Lead Connection boxes.W/950921 Ltr ML17311B1741995-09-0404 September 1995 LER 95-004-01:on 950329,containment Electrical Penetration Overcurrent Protective Devices Found Outside Design Basis. Caused by Error on Part of Original Architect Engineer. Modified Affected Circuits Critical to Normal Operational ML17311B1561995-08-27027 August 1995 LER 95-003-00:on 950729,switchyard Voltage Dropped Below Administratively Imposed Limit of 524 Kv for Approx 10 Seconds Due to Transient Grid Voltage.No C/A Taken Since Transmission Sys Transient Short duration.W/950827 Ltr ML17311B1551995-08-25025 August 1995 LER 95-002-01:on 950303,identified That Slb Analyses Failed to Consider as Initial Condition One Percent SDM for All Rods in (ARI) Due to Lack of Coordination & Unclear Div of Responsibilities.Ari Core Data Book SDM Curves Modified ML17311B1211995-08-16016 August 1995 LER 95-005-00:on 950717,RT on Low SG Water Level Was Result Following Degradation of MFW Flow.Completed Evaluation of Event ML17311B0841995-07-28028 July 1995 LER 94-005-01:on 941019,completed TS Required Shutdown Due to Expiration of LCO Time Limit.Design Change Options Identified & Will Be Reviewed to Determine If Valve &/Or Motor Operator Replacement or Mod Necessary ML17311B0721995-07-20020 July 1995 LER 95-004-00:on 950706,identified Four Occassions Between 950407 & 0630 When Conditional Surveillance in TS LCO 3.8.4.1 Action a Not Performed Due to Inattention to Detail. CR Copy of Temporary Procedure 40TP-9ZZ04 Corrected ML17311B0081995-07-0606 July 1995 LER 95-003-00:on 950613,TS LCO 3.0.3 Entered Following Loss of Both Trains of Essential Cw Sys & Both Hydrogen Recombiners.Caused by Spurious Actuations Due to Broken EDG Speed Probe Connector.Connector replaced.W/950706 Ltr 1999-08-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17300B3811999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr ML17300B3271999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3 ML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML17313B0611999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr ML17313B0191999-07-16016 July 1999 LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure ML17300B3151999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr ML17313A9921999-06-21021 June 1999 Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated ML17313A9911999-06-18018 June 1999 Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys ML17313A9731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pvngs,Units 1,2 & 3.With 990608 Ltr ML17313A9281999-05-0707 May 1999 LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs ML17313A9201999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pvngs,Units 1,2 & 3.With 990512 Ltr ML17313A8951999-04-14014 April 1999 LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked ML17313A8921999-04-13013 April 1999 LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc ML17313A8891999-04-0909 April 1999 LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr ML17300B3071999-03-31031 March 1999 Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee. ML17313A8801999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pvngs,Units 1,2 & 3.With 990412 Ltr ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207H7471999-03-10010 March 1999 1999 Emergency Preparedness Exercise 99-E-AEV-03003 ML17313A8361999-03-0101 March 1999 LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr ML17313A8501999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Palo Verde Nuclear Generating Station.With 990311 Ltr ML17313A7791999-02-0505 February 1999 Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies ML17313A8061999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Pvngs,Units 1,2 & 3.With 990218 Ltr ML17313A7701999-01-15015 January 1999 LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised ML17313A7381998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.With 990113 Ltr ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML17313A7031998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pvngs,Unit 1,2 & 3. with 981209 Ltr ML17313A6701998-11-0404 November 1998 Rev 2 to PVNGS Unit 2 Colr. ML17313A6741998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pvngs,Units 1,2 & 3.With 981109 Ltr ML17313A6611998-10-24024 October 1998 LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements ML17313A6561998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for PVNGS Units 1,2 & 3.With 981007 Ltr ML17313A5961998-09-14014 September 1998 LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired ML17313A5761998-09-0808 September 1998 LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters ML17313A5591998-08-28028 August 1998 LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr ML20151S0941998-08-21021 August 1998 Rev 6 to COLR for PVNGS Unit 3 ML20151S0861998-08-21021 August 1998 Rev 4 to COLR for PVNGS Unit 1 ML20151S0901998-08-21021 August 1998 Rev 1 to COLR for PVNGS Unit 2 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 ML17313A5401998-08-13013 August 1998 Special Rept:On 980715,declared PASS Inoperable.Caused by Failure of Offgas Flush/Purge Control Handswitch HS0101. Handswitch Replaced & Post Maintenance Retesting Was Initiated ML17313A5301998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pvgns,Units 1,2 & 3.W/980812 Ltr ML17313A5201998-07-30030 July 1998 LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr ML17313A5791998-07-0707 July 1998 to PVNGS SG Tube ISI Results for Seventh Refueling Outage Mar & Apr 1998. ML17313A5001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/980710 Ltr ML17313A4671998-06-19019 June 1998 LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced ML17313A4521998-06-19019 June 1998 Rev 5 to COLR for Pvngs,Unit 3. ML17313A4501998-06-19019 June 1998 Rev 4 to COLR for Pvngs,Unit 3. ML17313A4131998-06-0505 June 1998 LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria ML17313A4211998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pvngs,Units 1,2 & 3.W/980609 Ltr ML17313A3951998-05-26026 May 1998 LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation ML17313A3691998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for PVNGS.W/980412 Ltr ML17313A3251998-04-0101 April 1998 LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7 1999-09-30
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ACCELERATED QISTRJBUTION DEMO&+RATION SYSTEM REGULATORY INFORMATION DISTRIBUTION'YSTEM (RIDS)
ACCESSION NBR:9207220217 DOC.DATE: '92/07/16 NOTARIZED: NO DOCKET FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi, 05000529 AUTH. NAME AUTHOR AFFILIATION BRADICH,T.R. Arizona Public Service Co. (formerly Arizona Nuclear Power.
LEVINE,J.M. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 92-004-00:on 920619,Unit 2 & Unit 3 loss of power ESFAS.
Caused by moisture intrusion in sliced section of one of Phase A cables. Phase A cable A respliced & meggared.
W/920716 -ltr. D DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER),
ENCL U SIZE:
ncident Rpt, etc. S
. NOTES:Standardized plant. 05000529 A
RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL, PD5 LA 1 1 PDS PD 1 1 D TRAMMELL,C 1 1 THOMPSON,C 1 1 INTERNAL: ACNW 2 .2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10, 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 2 2 NRR/DREP/PRPB11'RR/DST/SICB8H3 NRR/DST/SELB 8D 1 1 1 1 PLB8Dl 1 1 NRR/DST/SRXB 8E 1 1 REG RGNS L~FILE 02 01 1
1 1
1 RES/DSIR/EIB 1 1 EXTERNAL: EG&G BRYCE,J.H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 POOREPW.
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Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. 8OX 52034 ~ PHOENIX, ARIZONA85072-2034 192-00795-JML/TRB/KR JAMES M. LEVINE VICE PRESIDENT July 16, 1992 NUCLEAR PRODUCTION U. S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station Pl-37 Washington, D.C. 20555
Dear Sirs:
Sub)ect: Palo Verde Nuclear Generating St:ation (PVNGS)
Unit 2 Docket No. STN 50-529 (License No. NPF-51)
Licensee Event Report 92-004 File'2-020-404 Attached please find Licensee Event: Report (LER)92-004 prepared and submitted pursuant to 10CFR50.73. This LER reports a Unit 2 Train A Loss of Power (LOP)
Engineered Safety Feature Actuation System (ESFAS) actuation, and a Unit 3 Train B LOP ESFAS. actuation which occurred following a cable fault downstream of a startup transformer. -In accordance with 10CFR50.73(d), a copy of this supplement is being forwarded to the Regional Administrator, NRC Region V.
If you'have any questions, please contact T. R. Bradish, Compliance Manager, at (602) 393-5421.
Very truly yours, JML/TRB/KR Attachment cc: W. F. Conway (all with attachment)
J. B. Martin D. H. Coe INFO Records Center
~
~U<;i:t'2072202i7 PDR 920716 ADOCK 05000529 S PDR
LICENSEE EVENT REPORT (LER)
FACILITYHAI% (I ) DOCKET NVMSER (2) PACE 3 Palo Verde Unit 2 0 5 0 0 0 5 2 9 1 OF 0 8 TITLE (C)
Unit 2 and Unit 3 Loss of Power LOP ESFAS
- EVEtIT DATE(5) LER SER (C) REPORT A E(7) 0 R 8 INVOLVED(O)
FACILITYNAMES DOCKET NUMBER(S)
MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY Palo Verde Unit 3 osooo 530 0 6 199292 00 4 0 0 0 7 1 6 9 2 THIS REPORT IS SVSMTTED PURSUANT TO THE REOUIREMENTS OF 10 CFR N/A I: (Chock ono or tncro ot Iho foscwlno) (11) 0 5 0 0 0 OPERATINO MODE (0) 20A02(b) 20.COS(c) 50.73(a)(2)(tv) 73.71(b)
POWER 20A05(a)(I )(I) 50.35(c)(1) 50.73(a)(2)(v) 73.71(c)
LEVEL OTHER (Spot(0'lnAbotroct 1 p p 2IL405(a)(1)(T) 5045(cX2) 50.73(a)g)(vs) botctr arxfin ToxL NRC Form 20AOS(a)(1 jPI) 50.73(aX2)(mXA) Stttt4)
S0.73(a)(2'073(a)(2)P) 20AOS(a)(1@v) 50.73(a/2)(vtl)(B) 20AOS(a)(1)(v) 50.73(a)(2~tv 50.73(a)(2)(x)
UCENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER Th'omas R. Bradish, Compliance Manager 60 2393 5421 COMPLETE ONE UNE FOR EACH COMPONENT FAII VRE DESCRIBED IN THIS REPORT (13)
MANUFAC MANUFAC EPORTABL CAUSE SYSTEM COMPONENT CAUSE COMPOHENT TURER To NPRDS TURER Ng~g~>kC)/r"~Pr'Z SUPPLEMENTAL REPORT EXPECTED (IC) MONTH DAY YEAR EXPECTED SUBISSSION DATE (15)
YES (I/yoo. ccrnptoto EXPECTED SUBhtlSSIOH DATE) NO AssTRAcT (I)tntt tc wo opac on l ~ apprcxhta tory ltnoon ahotoopaco typowrttron Ihoa) (15)
At approximately 0520 MST on June 19, 1992, Palo Verde Units 2 and 3'ere in Mode 1 (POWER OPERATION) operating at approximately 100 percent power when Palo Verde Unit 2 experienced a Train A Loss of Power (LOP) Engineered Safety Feature Actuation System (ESFAS) actuation, and Unit 3 experienced a Train B LOP ESFAS actuation. A fault downstream of a startup transformer (NAN-X01) resulted in a loss of offsite power to the Unit 2 Train A and Unit 3 Train B Class lE 4.16 kV buses. The Unit 2 Train A Emergency Diesel Generator (EDG) and the Unit 3 Train B EDG started and loaded per design. The safety systems required to functioned performed as designed. There were no other ESFAS actuations and none were required. Units 2 and 3 continued to operate normally at 100 percent power throughout the event.
The cause of the fault downstream of NAN-XOl was moisture intrusion in a spliced section of one of the Phase'A cables located within a manhole between NAN-XOl and Unit 3's Train B non-Class 1E 13.8 kV Switchgear Bus, which resulted in a phase-to-ground fault on Phase A and a current differential between Phase A and Phases B and C. APS Engineering has determined that the moisture intrusion occurred due to inadequate application of heat shrink insulating material during the original cable installation in 1981 by Bechtel personnel. As corrective action, the faulted section of spliced cable was replaced.
There have been no .previous similar events reported pursuant to 10CFR50.73.
II R
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UCENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER PAGE PX SEOUENTIAL j, REVISION
'alo Verde Unit 2 NUMBER ;p NUMBER osooo52992 004 0 0 0 20F 0 8 DESCRIPTION, OF WHAT OCCURRED:
A. Initial Conditions:
At 0520 MST on June 19, 1992, Palo Verde Units 2 and 3 were in Mode 1 (POWER OPERATION) operating at approximately 100 percent power.
B. Reportable Event Description (Including Dates and Approximate Times of Major Occurrences):
Event Classification: An event or condition that resulted in an automatic actuation of an Engineered Safety Feature (ESF)(JE).
At approximately 0520 MST on June 19, 1992, Palo Verde Unit 2 experienced a Train A Loss of Power (LOP) Engineered Safety Feature Actuation System (ESFAS) (JE) actuation, and Unit 3 experienced a Train B LOP ESFAS 'actuation. This resulted from a loss of offsite power to the Unit 2 Train A and Unit 3 Train B Class lE 4.16 kV buses (EB)(BU). The Unit 2 Train A Emergency Diesel Generator (EK) (EDG) and the Unit 3 Train B EDG started,and loaded per design. The safety systems required to functioned performed 'as designed. Units 2 and 3 entered Technical Specification Limiting Condition for Operation (TS LCO) 3.8.1.1 ACTION a which states that two physically independent circuits from the switchyard to the .onsite Class 1E distribution system shall be OPERABLE. There were no other ESFAS actuations and none were required. Units 2 and 3 continued to oper'ate normally at 100 percent power throughout the event.
Immediately prior to the LOP ESFAS actuations, Startup Transformer (NAN-X01) (EA)(XFMR) phase winding ground differential trip alarms (ALM) came into the Units 1, 2, and 3 Control Rooms (NA). The NAN-XOl breakers 925 and 928 were observed to be open, indicating that the source of the fault current (i.e., NAN-X01) had been isolated. [NOTE: see the figure on page 8.]
Unit 2's Train A non-Class 1E 13.8 kV Switchgear Buses (NAN-S03 and NAN-S05) were deenergized as a result of the NAN-X01 breakers 925 and 928 opening. This resulted in the loss of offsite power to the Train A 4.16 kV Class lE bus (PBA-S03) and a Train A LOP ESFAS actuation. The ESF signal automatically load shed the Train A Class 1E bus and started the Train A Emergency Diesel Generator (EDG). The Train A EDG,started and assumed the loads as designed.
Unit 2 Control Room personnel (utility, licensed) entered Technical Specification Limiting Condition for Operation (TS LCO)
If UCENSEE EVENT REPORT (LER) TEXT CONTlNUATlON FACILITYKAME DOCKET KUMSER PAOE YEAR SEQUENTIAL R: REVISION NUMSER g! NUMSER Palo Verde Unit 2 osooo 529 9 2 004 0 003 OF 0 8 3.8.1.1 ACTION a when one circuit from the switchyard to the onsite Class 1E distribution system was declared inoperable, The NAN-XOl breakers 925 and 928 opening also deenergized Unit 3's Train B non-Class lE 13.8 kV Switchgear Buses (NAN-S04 and NAN-S06). This resulted in the loss of offsite power to the Train B 4.16 kV Class 1E bus (PBB-S04) and a Train B LOP ESFAS actuation.'he ESF signal automatically load shed the Train B Class 1E bus and started the Train B EDG. The Train B EDG started and assumed the loads as designed. The Unit 3 Control Room personnel (utility, licensed) entered TS LCO 3.8.1.1 ACTION a when one circuit from the switchyard to the onsite Class lE distribution system was declared inoperable.
There were no other ESFAS actuations and none were required. The safety systems for Units 2 and 3 responded as expected for a loss of offsite power scenario as discussed in Section I.J. Units 2 and 3 continued to operate normally at 100 percent power throughout the event.
At approximately 1733 MST, Unit 2 Control Room personnel reenergized the Train A non-Class 1E 13.8 kV Switchgear Buses (NAN-S03 and NAN-S05) from the alternate supply breaker feed from Startup Transformer NAN-X02. At approximately 2039 MST, Unit 3 Control Room personnel reenergized the Train B non-Class lE 13.8 kV Switchgear Buses (NAN-S04 and NAN-S06) from the alternate supply breaker feed from Startup Transformer NAN-X03. At approximately 2133 MST, Unit 2 exited TS LCO 3.8.1.1 ACTION a when offsite power was restored to Train A 4.16 kV Class lE bus (PBA-S03) from NAN-X02. At approximately 2339 MST, Unit 3 exited TS LCO 3.8.1.1 ACTION a when offsite power was restored to the Train B 4 '6 kV Class 1E bus (PBB-S04) from NAN-X03.
l Status of structures, systems, or components that were inoperable at the start of the event that contributed to the event:
Not applicable - no structures, systems, or components were inoperable at the start of the event which contributed to this event.
D. Cause of each component or system failure, if known:
An investigation of this event was conducted in accordance with the APS Incident Investigation Program. As part of the investigation, a root cause of failure analysis of the fault was performed by APS Engineering personnel (utility, nonlicensed).
There was no indication'f visible damage or alarms for NAN-X01.
APS Engineering determined that the Startup Transformer NAN-X01-
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER PAOE
~sk SEOUENTIAL ~>'EVISION NUMBER Yi NUMBER Palo Verde Unit 2 osooo52992 004 0 0 0 40F 0 8 related fault was due to a phase-to ground fault on a Phase A cable. The Phase A cable minimum acceptable insulation resistance was low when meggared, and the Phase B and C cables meggared within the acceptance range. There was no indication of a phase-to-phase fault. The fault was discovered at a spliced section in the cable located within a manhole between NAN-X01 and Unit 3's Train B non-Class 1E 13.8 kV Switchgear Bus (NAN-S06).
The investigation determined that moisture intrusion occurred in a spliced section of one of the Phase A cables located within a manhole between NAN-XOl and Unit 3's Train B non-Class 1E 13.8 kV Switchgear Bus (NAN-S06), resulting in a phase-to-ground fault on Phase A and a current differential between Phase A and Phases B and C. This resulted in the actuation of the transformer phase winding ground differential trip.
Failure mode, mechanism, and effect of each failed component, if known:
[NOTE: 'Startup Transformer NAN-X01 normally supplies offsite power to the Unit 2 Train A non-Class 1E 13.8 kV Switchgear Buses (NAN-S03 and NAN-S05) from the Z winding, and to the Unit 3 Train B non-Class 1E 13 ' kV Switchgear Buses (NAN-S04 and NAN-S06) from the Y winding.)
The cable fault resulted in the Unit 2 non-Class .1E 13.8 kV Intermediate Switchgear Bus NAN-S05 and Unit 3 non-Class lE 13'.8 kV Intermediate Switchgear Bus NAN-S06 experiencing a zero sequence voltage, and neutral amperage (amp) increasing on the 525 kV and the 13.8 kV Y winding sides of NAN-XOl. At approximately 0520 MST, the 525 KV switchyard (FK) circuit breakers PL925 and PL928 opened and isolated NAN-X01. This was immediately followed by the opening of Unit 3's Train B non-Class 1E 13.8 kV Intermediate Switchgear Bus M-S06 normal supply breaker M-S06C (resulting in a loss of power to Unit 3's NAN-S06 and NAN-S04) and Unit 2's Train A non-Class 1E 13.8 kV Intermediate Switchgear Bus NAN-S05 normal supply breaker NAN-S05D (resulting in a loss of power to Unit 2's NAN-S03 and NAN-S05).
For failures of components with multiple functions, list of systems or secondary functions that were also affected:
Not applicable - no failures of components with multiple functions were involved.
I LICENSEE EVENT REPORT (I.ER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER PAOE YEAR '5:? SEQUENTIAL <4 REVISION NUMBER NUMBER Palo Verde Unit 2 050005,29 9 2 004 0 0 0 8 TEXT For a failure that rendered a train of a safety system inoperable, estimated time elapsed from the discovery of the failure until the train was returned to service:
Not applicable - no failures that rendered a train of a safety system inoperable were involved.
H. Method of discovery of each component or syst: em failure or procedural error:
The cable fault located at the spliced area was discovered dur'ing an Engineering investigation immediately following the event.
There were no procedural errors which contributed to this event.
Cause of Event:
An investigation of this event was conducted in accordance with the APS Incident Investigation Program. As part of the investigation, a root cause of failure analysis of the spliced cable was performed by an APS laboratory. As discussed in Section I.E, the evaluation has determined that the failure mechanism is moisture intrusion in the spliced section of one of the Phase A cables located within a manhole between NAN-X01 and Unit 3's Train B non-Class 1E 13 ' kV Switchgear Bus (NAN-S06), which resulted in a phase-to-ground fault on Phase A and a current differential between Phase A and Phases B and C. Based on the information obtained from the APS laboratory, APS Engineering has determined that the moisture intrusion occurred due to inadequate application of Raychem heat shrink insulating material during the original cable installation in 1981 by Bechtel personnel (contractor, nonlicensed) (SALP Cause Code A: Personnel Error).
Safety System Response:
Following the loss of offsite power to Unit 2's Train A and Unit 3's Train B Class lE 4.16 kV buses, the respective Train A and Train B Emergency Diesel Generators started and energized their Train A and Train B ESF buses within the Technical Specification time requirement. Both Unit 2 and Unit 3's load sequencers initiated a Load Shed signal and subsequently resequenced the following safety systems on the respective buses as required by design:
Control Room Essential Ventilation (VI), Diesel Generator Essential Ventilation (VJ), Essential Battery Chargers and Voltage Regulators reenergized (BYC)(EI), Containment Normal Air Handling Units (AHU)(NH) restarted, Control Element Drive Mechanism Normal Air Handling Units (AHU)(AA)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER PACE SEC UENTIAI. .T REVISION NUMBER NUMBER Palo Verde Unit 2 osooo529'92 004 0 0 0 60F restarted, Auxiliary Feedwater Pump (P)(BA), Essential Cooling Vater Pumps (P)(BI), Essential Spray Pond Pumps (P)(BI), and Essential Chillers (CHU)(KM).
K. Failed Component Information:
Not applicable - no component failures were involved.
II. ASSESSMENT OF THE SAFETY CONSEQUENCES AND IMPLICATIONS OF THIS EVENT:
As part of the investigation, it was determined that no safety limits were violated and that the event (i.e., loss of offsite power) is bounded by previous analyses contained in the Updated Final Safety Analysis Report Chapters 6 and 15. The Unit 2's Train A and Unit 3's Train B Emergency Diesel Generators started properly and assumed the loads on the respective trains of the Class 1E 4.16 kV buses. The safety systems required to functioned performed as designed.
The event in Unit 2 and 3 did not result in any challenges to fission product barriers or result in any releases of radioactive materials.
There were no safety consequences or implications as a result of the events. The events did not adversely affect the health and safety of the public.
III. CORRECTIVE ACTION:
A. Immediate:
APS Operations personnel (utility, nonlicensed) quarantined Startup Transformer NAN-XOl and informed senior plant management.
Transformer oil analysis and doble and electrical meggar testing revealed that no damage to the transfoimer had occurred as a result of the event.
A visual inspection of the Phase A cable disclosed physical damage (i.e., burn marks). The Phase A cable was respliced and meggared.
B. Action to Prevent Recurrence:
During the next NAN-X01 outage, APS Engineering will perform additional testing to determine if other cables were inadequately spliced. APS regards, this to be an isolated event and that had the cable been spliced appropriately, this event would not have occurred. Therefore, no additional action is being taken.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER PACE NUMBER i
~~ SEOUENTIAI. $'E REVISION NUMBER Palo Verde Unit 2 osooo 52992 004 OF 0 IV. PREVIOUS SIMILAR EVENTS:
No other previous events have been reported pursuant to 10CFR50.73 where a faulted section of spliced cable resulted in a loss of offsite power..
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYHALD PAOE YEAR SEQUENTIAL REVISION NUMBER NUMBER Palo Verde Unit 2 osooo52992 004 O OOSoFO Westwing 1 Westwing 2 Kyrene North Gila De vers 922 932 942 982 992 915 935 945 985 995 918 928 938 948 998 Startup Startup Startup Transformer Transfor mer Transformer NAN-X01 y NAN-X02 y NAN-X03 y 3-NAN-SO6 1-NAN-SO6 2-NAN-SO6 2-NAN-SO5 1-NAN-SO5 3-NAN-SO5 to main generators & switchyard From NAN-X03Z unit atjx (ALTERNATE)
From NAN-X02Y tfansiDfnlefs MAN X03 (ALTERNATE) MAN-X02
- 'LAAJKAAJ NAN-S01A NAN-S06 NAN-S05 NAN-S01 NAN-S02 NAN-S03B NAN-SO3 NAN-S04 ESF XFMR ESF XFMR NBN-XO3 NBN-XO4 TO I TO NAN-S02 'AN-S01 PBA-SO3 PBB-SO4
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