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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 RIDS PROCESSIX REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9502160178 DOC.DATE: 95/02/07 NOTARIZED: NO DOCKET FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 AUTH. NAME AUTHOR AFFILIATION GRABO,B.A. 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 94-004-01:on 941006,class 1E batteries found in degraded condition. Caused by step decline in capacity caused by loss of positive active matl.TS LCO 3.8.2.2 action was entered to prevent positive reactivity additions.W/950207 ltr.
DISTRIBUTION CODE IE22T COPIES RECEIVED LTR TITLE: 50.73/50.9 Licensee Event Report (LER), 3IncidentRpt, ENCL SIZE etc.
/
NOTES:Standardized plant. 05000529 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 PD 1 1 HOLIAN, B 1 1 TRAN,L 1 1 INTERNAL: ACRS 1 1 AEOD/SPD/~B 1 1 AEOD/SPD/RRAB 1 1 +FILE CENTER~ 02 1 1 NRR/DE/ECGB 1 1 NRR/DE/EEI'B 1 1 NRR/DE/EMEB 1 1 NRR/DISP/PIPB 1 1 NRR/DOPS/OECB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRSS/PRPB 2 2 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN4 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 2 2 NOAC MURPHY,G.A 1 1 NOAC POORE,W. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1
<NOTE TO ALL"RIDS" RECIPIEYTS; PLEASE HELP US TO REDUCE O'ASTE! COYTACTTHE DOCL'iIEYTCONTROL DESK, ROOKI Pl-37 (EXT. 504.2083 ) TO ELI XIINATE YOL'R iAiIE PROiI DISTRIBUTIOY, LISTS I:OR DOCL'MEi'I'S YOL'Oi "I'L'L'I)!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 28
Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O, BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 JAMES M. LEVINE 192-00921-JML/BAG/BE VICE PRESIDENT NUCLEAR PRODUCTION February 7, 1995 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket Nos. STN 50-529 License Nos. NPF-51 Licensee Event Report 9440441 File: 95%20404 Attached please find supplement 1 to Licensee Event Report (LER) 9404 prepared and submitted pursuant to 10CFR50.73. This supplement provides additional information on the cause and corrective actions reported in the original submittal. In accordance with 10CFR50.73(d), a copy of this LER is being forwarded to the Regional Administrator, NRC Region IV.
If you have any questions, please contact Burton A. Grabo, Section Leader, Nuclear Regulatory Affairs, at (602) 3984492.
Sincerely, JMUBAG//pv Attachment cc: L. J. Callan (all with attachment)
K E. Perkins K E. Johnston INPO Records Center 9502160i78 950207 PDR ADOCK 05000529 8 PDR
LICENSEE EVENT REPORT (LER)
FACILITYNAME (1) DOCKET NUMBER (2) PAGE (3) 0 5 0 0 0 5 2 9 o" 2 Palo Verde Unit 2 1 1 ITLE (4)
Class 1E Batteries in a De raded Condition EVENT DATE 5 LER NUMBER 6 REPORT DATE OTHER FACILITIES INVOLVED 8 MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH FACILITYNAMES KET NUMBERS NUMBER NUMBER N/A 0 5 0 0 0 1 0 0 6 9 4 9 4 0 0 4 0 1 0 2 0 7 9 5 N/A 0 5 0 0 0 OPERATING IS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR (,: (Check one or more of the totlowlng) (11)
MODE(B) 5 20.402(b) 20.405(c) 50.73(a)(2') 73.71(b) 20.405(a)(1)(i) 50.38(c)(1) 5073(a)(2)(r) 73.71(c)
LEVEL(10) 20.405(s)(1)(i) 50.38(c)(2) 50.73(a) (2)(rb) OTHER (Specity In Abstract 20.405(a)(1)(iii) SO.73(a)(2)(i) 50.73(a) (2) (viii)(A) beiorr and in Text, NRC Form 20.405(a)(1)(iv) 50.73(a)(2) (ii) 50.73(a)(2)(VII)(B) 366A) 20.405(s) (1) (r) 50.73(a)(2) ris) 5073(a)(2)0()
LICENSEE CONTACT FOR THIS LER (1 2)
LEPHONE NUMBER Burton A. Grabo, Section Leader, Nuclear Regulatory Affairs EA CODE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THiS REPORT (1 3) 602393-6492 CAUSE MANUFAC- REPORTABLE CAUSE SYSTEM MANUFAC. REPORTABLE TURER TO NPRDS TURER TO NPRDS B E J BTRY A 6 2 6 SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR SUBMISSION YES (8 yes. complete EXPECTED SUBMISSION DATE) X NO DATE (1 5)
JIRAcz oman e Los <pecos \ ~, ~rrLsem I~a yyeeracn lees) on At approximately 2200 MST on October 7, 1994, Palo Verde Unit 2 was in Mode 5 (COLD SHUTDOWN), when Train A (battery banks A and C) was declared inoperable because a projection of the test results based upon anticipated degradation indicated that they did not meet the 90% criteria of Technical Specification Surveillance Requirement (TS SR) 4.8 2.1.e, rendering both
~ trains of Class 1E batteries inoperable. Train B (battery banks B and D) was declared inoperable (on October 1, 1994) because the measured capacity was slightly less than the required 901: capacity stated in TS SR 4.8.2.1.e.
Subsequent investigation has determined that Train B had been slightly below the 90% capacity as required by TS SR 4.8.2.1.e since February 1, 1994. Since both trains of batteries are required in Mode 1, Unit 2 operated in a condition prohibited by the plant's TS until it shutdown and reached Mode 5 on September 18, 1994 'his condition is being reported per 50.73(a)(i) (B) .
The Equipment Root Cause of Failure Analysis (ERCFA) has determined that the failure mode results from a step decline in capacity caused by a loss of positive active material. The loss of capacity is most likely due to the result of poor production control during manufacturing. No credible mechanism for sudden discharge failure has been found. A 50.73(a)(2)(vii) notification is also being made by this LER.
There have been no previously similar events reported pursuant to 10CFR 50.73.
1 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER LER NUMBER PAGE YEAR ii):"" SEOUENTIAL,::..:.j. REVISION NUMBER NUMBER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 0 2 OF 1 2 I. DESCRIPTION OF WHAT OCCURRED:
A. Initial Conditions:
At 2200 MST on October 7, 1994, Palo Verde Unit 2 was in Mode 5 (COLD SHUTDOWN) with Pressurizer pressure of 10 psia and a Main Coolant Temperature of 107'F.
B. Reportable Event
Description:
Event Classification: Any operation or condition prohibited by the plant's Technical Specifications.
Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple systems or two independent trains ox channels to become inoperable in a single system designed to: A)
Shut down the reactor and maintain it in a safe shutdown condition; B) Remove residual heat; C) Control the release of radioactive material; or D)
Mitigate the consequences of an accident.
At approximately 2200 MST on October 7, 1994, Palo Verde Unit 2 was in Mode 5 (COLD SHUTDOWN), when Train A (battery banks A and C) was declared inoperable because a projection of the test results based upon anticipated degradation indicated that they did not meet the 90%
criteria of Technical Specification Surveillance Requirement (TS SR) 4.8.2.1.e, rendering both trains of Class 1E batteries inoperable.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER LER NUMBER PAGE YEAR <<?;:::::.<<: SEQUENTIAL :<<.;<<".:REVISION NUMBER 4+! NUMBER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 0 3oF1 2 EXT Train B (battery banks B and D) had been declared inoperable on October 1, 1994 because the measured capacity was slightly less than the required 90% capacity stated in TS SR 4.8.2.l.e. TS SR 4.8.2.1.e, states the following in part:
At least once per 60 months, during shutdown, by verifying that the battery capacity is at least 804.
(Exide) or 904. (AT&T) of the manufacturer's rating when subjected to a performance discharge test. This performance discharge test may be performed in lieu of the battery service test required by Surveillance Requirement 4. 8.2.2.d.
Subsequent investigation has conservatively determined that Train B had been slightly below the 90~ capacity as required by TS SR 4.8.2.1.e since it was last tested on February 1, 1994. Since both trains of batteries are required in Mode 1, Unit 2 operated in a condition prohibited by the plant's TS until it shutdown and reached Mode 5 on September 18, 1994.
During the recent mid-cycle outage, Unit 2 was performing TS SR 4.8.2.1.e to satisfy the IEEE Standard 450-1980 requirement to capacity test new batteries within the first two years of service. On September 23, 1994, the test results for battery banks A and C were 91.6: and 90.6% respectively. While the test results met TS SR, the capacity of the battery banks were below what was expected. As a result, the B and D battery banks were capacity tested. On October 1, 1994, the B and D battery banks were declared inoperable because the measured capacity was slightly less than the required 90% capacity stated in TS SR 4.8.2.1.e.
As a result of this unexpected degradation, Electrical Maintenance Engineering (utility, non-licensed) performed an individual cell and battery capacity evaluation on previous tests of banks A, B, C, and D, factory tests, and additional testing on the Unit 2 spare cells.
Il LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AGILITYNAME DOCKET NUMBER LER NUMBER PAGE YEAR SEaUENTIAI. REVlSION NUMBER NUMBER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 0 4 OF 1 2 EXT The evaluation concluded that the failure mechanism causes the batteries to degrade during the discharge/recharge cycle, therefore, the projections for battery capacity from this evaluation indicated that all four battery banks in Unit 2 were inoperable.
Subsequently, on October 7, 1994, battery banks A and C were also declared inoperable because a projection of the test results based upon anticipated degradation indicated that they did not meet the 90: criteria of TS SR 4.8.2.1.e.
Based on this new information, a condition prohibited by the plant's TS has been identified. TS 3.8.2.1 requires that both trains of Direct Current (DC) sources be operable in Modes 1 through 4. Due to the fact that the degradation mechanism is related to discharge/recharge cycling of the batteries, APS has concluded that battery banks B and D were conservatively at 89.0% and 88.3%
capacity respectively following the ST performed in February 1, 1994. Therefore, battery banks B and D have been slightly below the 90. capacity as required by TS SR 4.8.2.1.e since February 1, 1994. Unit 2 operated in Mode 1 with this condition until it shutdown for the September mid-cycle outage and was in Mode 5 on September 18, 1994.
On October 9, 1994, APS submitted'a proposed TS amendment to Specification 3/4.8.2, DC Sources, under emergency circumstances.
APS has concluded that the failure mechanism causes the batteries to degrade during the discharge/recharge cycle and that the projected capacities of the banks following the last capacity discharge test are: 1) Bank A, 78.82'.,
- 2) Bank B, 82.49 ' 3) Bank C, 76.73%, and 4) Bank D, 81.75%. As such, all banks were above the calculated
! design minimum capacity of 53'. at all times.
I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER LER NUMBER PAGE YEAR SEQUENTIAL REVISION NUMBER NUMBER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 0 5 OF 1 2 EXT The amendment asked for approval to suspend the requirements of TS 4.0.1 and 4.0.4 until entry into Mode 4 coming out of the fifth refueling outage or upon any deep discharge of the battery. On October 13, 1994, TS amendment 71 was approved by the NRC.
Therefore, on October 13, 1994, battery banks A, B, C, and D were declared operable.
C. Status of structures, systems, or components that were inoperable at the start of the event that contributed to the event:
As stated in Section I.B above, Train B (battery banks B and D) of the Class 1E batteries were inoperable since February 1, 1994. However, based on information at the time Train B was believed to be operable because of its capability to pass the surveillance test requirements.
D. Cause of each component or system failure, if known:
The failure mode results from a step decline in capacity caused by a loss of positive active material. Improper curing or contamination during fabrication may have been factors contributing to loss of positive active material.
The loss of capacity is most likely the result of poor production control during manufacturing. No credible mechanism for sudden discharge failure has been found.
E. Failure mode, mechanism, and effect of each failed component, if known:
Based on testing of the Unit 2 spares, the degradation mechanism appears to be aggravated by charge/discharge cycling of the cells and is not age related. Deep discharge cycling of the cells resulted in a loss of capacity for the Round Cells installed in Unit 2 during cycle 5. Each subsequent cycle degraded about the same fraction of capacity. The test results indicated that the battery capacities tended to stabilize at approximately 55% after 6 capacity discharge tests.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER LER NUMBER PAGE YEAR SEQUENTIAL REVISION NUMSER NUMSER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 0 6 OF 1 2 EXT APS has concluded that the failure mechanism for the Unit 2 cells, causes the batteries to degrade during the discharge/recharge cycle and that the projected capacities of the banks following the last capacity discharge test are: 1) Bank A, 78.82%, 2) Bank B, 82.49%, 3) Bank C, 76.73'., and 4) Bank D, 81.75:. As such, all banks were above the calculated design minimum capacity of 53'. at all times.
F. For failures of components with multiple functions, list of systems or secondary functions that were also affected:
The DC banks A and B provide control power for Alternating Current (AC) load groups 1 and 2 respectively. These banks also provide vital instrumentation and control power [JC] for channels A and B, respectively, of the reactor protection and Emergency Safety Features (ESF) systems and diesel generators [DG]
A and B respectively.
The DC banks C and D provide vital instrumentation and control power [JC] for channels C and D, respectively, for the reactor protection and ESF systems, and other safety-related loads as referenced in Table 8.3-6, Class 28 DC System Loads, of the Updated Final Safety Analysis Report (UFSAR). There was no safety significance due to the degraded capacity of the batteries. The batteries had sufficient capacity for the safety-related loads following a design basis event. See Section II for details'.
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:
As a result of the battery testing and evaluations since September 23, 1994, APS has determined that battery discharge testing decreased the capacity of batteries by approximately 10% each time they are tested.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER LER NUMBER PAGE YEAR SEQUENTIAL REVISION NUMBER NUMBER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 0 7oF 1 2 EXT Therefore, Train B battery banks B and D have been inoperable from February 1, 1994, to October 13, 1994.
APS has concluded that the failure mechanism causes the batteries to degrade during the discharge/recharge cycle and that the projected capacities of the banks following the last capacity discharge test are: 1) Bank A, 78.82%,
- 2) Bank B, 82.49%, 3) Bank C, 76.73%, and 4) Bank D, 81.75%. As such, all banks were above the calculated minimum capacity of 53'. at all times.
H. Method of discovery of each component or system failure or procedural error:
As discussed in Section I.B., the degraded battery bank capacities were found during the performance of TS SR 4.8.2.l.e to satisfy the IEEE Standard 450-1980 rec(uirement to capacity test "new batteries within the first two years of service.
I. Safety System Response:
Not applicable -- there were no safety system responses and none were necessary.
J. Failed Component Information:
The battery banks consist of AT&T LINEAGE 2000 Round Cell batteries, model KS-20472 List 1H. The cells are high specific gravity acid with a name plate rating of 1850 Ampere-Hour. The cells, each having a nominal ICV (individual cell voltage) of 2.08 VDC, are series connected to provide the 125 VDC battery bank voltage.
II. ASSESSMENT OF THE SAFETY CONSEQUENCES AND IMPLICATIONS OF THIS EVENT:
Four Class lE Direct Current (DC) power banks designated as channel A, B, C, and D are provided in each unit.
These channels consist of 125V DC bus [BU], 125V DC battery bank , and a battery charger [BYC] .
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER LER NUMBER PAGE YEAR SEQUENTIAL REVISION NUMBER NUMBER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 0 SOF1 2 EXT Train A consists of channels A and C and Train B consists of channels B and D. Both DC Trains are required to be operable in Modes 1 through 4 per TS LCO 3.8.2.1 and one DC Train is required to be operable in Modes 5 and 6 per TS LCO 3.8.2.2.
The DC power sources are required to ensure that sufficient power is available to supply safety-related equipment required for safe plant shutdown and the mitigation and control of accident conditions.
Therefore, a change in battery capacity requirements does not involve a significant increase in the probability of an accident previously evaluated.
APS has determined, through calculation and test, that the most highly loaded battery bank can continue to perform its safety-related function with its capacity as low as 53% of the original installed capacity. Capacity discharge tests run in September 1994, indicate capacities of 91.6% for bank A, 89.0'. for bank B, 90.6%
for bank C, and 88.3'. for bank D.
APS has concluded that the failure mechanism causes the batteries to degrade during the discharge/recharge cycle and that the projected capacities of the banks following the last capacity discharge test are: 1) Bank A, 78.82%,
- 2) Bank B, 82.49%, 3) Bank C, 76.73., and 4) Bank D, 81.75% As such, all banks were above the calculated minimum capacity of 53% at all times.
An analysis showed that the projected capacities of the battery banks will provide at least 15'. margin above that required for safety-related loads. To accomplish this 11 cells in Bank A, 4 cells in Bank B, 12 cells in Bank C, and 4 cells in Bank D were replaced.
The projected capacities are expected to be in excess of 85: for each bank. As such, the battery banks have sufficient capacity for the safety-related loads following a design basis event.
ll LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACIUTY NAME DOCKET NUMBER LER NUMBER PAGE YEAR SEQUENTIAL REVISION NUMBER NUMBER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 0 9 OP 1 2 EXT In addition, the majority of the degradation of the battery cells occurs during discharge testing of the batteries.
Therefore, since no discharge testing of the batteries will be performed between now and the next refueling outage, the battery capacity will remain above that needed to fulfill the required safety function.
The event did not result in any challenges to the fission product barriers or result in any releases of radioactive materials. Therefore, there were no adverse safety consequences or implications as a result of this event.
This event did not adversely affect the safe operation of the plant or the health and safety of the public.
III. CORRECTIVE ACTION:
A. Immediate:
~ On October 7, 1994, battery banks A and C were declared inoperable based on projection of anticipated degradation. TS.LCO 3.8.2.2 Action a was entered to prevent any positive reactivity additions.
~ On October 9, 1994, APS submitted a proposed TS amendment to Specification 3/4.8.2, DC Sources, under emergency circumstances. The amendment asked for approval to suspend the requirements of TS 4.0.1 and 4.0.4 until entry into Mode 4 coming out of the fifth refueling outage or upon any deep discharge of the battery. Also, several compensatory actions were placed on the Unit 2 batteries in accordance with the TS amendment submittal. On October 13, 1994, TS amendment 71 was approved by the NRC. Therefore, on October 13, 1994, battery banks A, B, C, and D were declared operable.
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LICENSEE EVENT REPORT (LER) TEXT CONTINuATION FACILITYNAME DOCKET NUMBER LER NUMBER PAGE YEAR SEQUENTIAL REVISION NUMBER NUMBER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 1 OOP1 2 EXT
~ To eliminate transportability to Units 1 and 3, previous battery test data from Units 1 and 3 were reviewed and compared to the Unit 2 battery performance data. Additional testing on the Unit 1 and 3 spares provided reasonable assurance that the observed Unit 2 failure was not transported to Unit 1 or 3.
B. Action to Prevent Recurrence:
During the Unit 2 fifth refueling outage APS will replace all of the cells from the original ATILT lot in the 4 Class lE batteries for Unit 2. Also, the 23 replacement cells and the 8 spare cells used from Units 1 and 3 will be replaced. The Unit 2 fifth refueling outage is scheduled to begin on February 4, 1995. In addition, two cells in Unit 1, which were from the same lot as the original Unit 2 cells, will be replaced during the fifth refueling outage for Unit 1 which is scheduled for April 1995.
IV. PREVIOUS SIMILAR EVENTS:
There have been no similar events to this type of failure reported pursuant to 10CFR50.73.
V. ADDITIONAL INFORMATION:
On October 13, 1994, APS received NRC approval to suspend provisions 4.0.1 and 4.0.4 of TS for battery capacity testing requirements until entry into Mode 4 following the fifth refueling outage. Both trains of Class lE batteries were declared operable on October 13, 1994, and a Unit 2 restart began. Unit 2 reached Mode 1 (POWER OPERATIONS) on October 17, 1994.
1 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION I'ACIUTYNAME DOCKET NUMBER LER NUMBER PAGE YEAR SEQUENTIAL REVISION NUMBER NUMBER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 1 1oF EXT APS has been working with ATILT and CkD Power to obtain replacement batteries for installation into Unit 2 during the fifth refueling outage. As a result of the degradation identified in the Unit 2 batteries, which is not evident in the batteries of Unit 1 or Unit 3, APS Engineering revised the commercial-grade dedication requirements for the replacement batteries.
The dedication was revised to require,two successful two-hour capacity discharge test within a nominal capacity value of each other.
It was reasoned that the Unit 1, Unit 3 battery banks and each of their spare cells had not shown degradation on their second, and in some cases third discharges whereas the Unit 2 batteries showed degradation on its second discharge.
APS has completed testing on four banks of replacement cells. In order to provide backup cells for Unit 2 in case problems were uncovered while operating until the fifth refueling, one bank of batteries were shipped directly to Palo Verde prior to dedication testing at the CED factory. These batteries exhibited degradation of capacity during their second discharge test. Tests performed at the factory on the other three battery banks showed acceptable capacity upon their second test. APS then decided to perform additional discharges of some batteries at Palo Verde, upon receipt, to preclude 3.)
charging method differences between the method employed by APS and by the factory, and 2) transportation difficulties as a potential causes of the observed capacity reduction. Each of these batteries has exhibited reduced capacity upon the second discharge at Palo Verde and each subsequent discharge.
Some of the possible causes of the loss of capacity have been investigated by APS. The most probable cause is the frequency at which the cells were discharged and recharged.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITYNAME DOCKET NUMBER LER NUMBER PAGE YEAR SEQUENTIAL REVISIO NUMBER NUMBER Palo Verde Unit 2 0 5 0 0 0 5 2 9 9 4 0 0 4 0 1 1 2 oF1 2 EXT Due to the effort to assure that the replacement cells were acceptable to use, repeated charging and discharging was performed on the battery strings. It is most probable that discharging and then recharging over relatively short intervals (approximately 10 days) does not allow sufficient time for the cells to recover.
At this point in time, APS has not established a final root cause for the replacement cell performance.
However, enough testing has been performed (37 discharge tests on 343 cells) to be able to confidently predict the installed capacity of the selected cells. Four additional groups of batteries have been manufactured and have completed two successful discharge tests at the factory. These cells will be used as replacement cells for Unit 2.
APS is continuing to work with ATILT and C6D Power to determine the cause of the capacity reduction. It has been shown by APS however, that enough cells can be obtained prior to the fifth refueling outage which, when installed, will assure that all four channels of batteries will be greater than or equal to 100. capacity.
Results of the joint APS, ATILT and CED Power testing will be assessed against conclusions drawn for the cells installed in Unit 2 cycle 5. If any changes affect this Licensee Event Report, a supplement will be submitted.
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