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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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LICENSEE EVENT REPORT (LER)AGILITY NAME (I)Palo Verde Unit 2~DOCKET NUMBER (2)PAGE (3)0 5 0 0 0 5 2 9 1OFO 7 ITLE (4)Technical S ecification Violation Due to Missed Surveillance Re uirement EVENT DATE 5 MONTH LER NUMBER 6 YEAR SEOVENTIaL REVI8IOII REPORl'ATE MONTH DAY YEAR OTHER FACIUTIES INVOLVED 6 NUMBERS N/A 0 7 0 6 9 5 9 5-0 0 4-0 0 0 7 2 0 9 5 N/A Is REPoRT Is BUBMITTED PvRsvANT To THE REovIREMENTs oF 10 cFR C (cnecx one or more or tne~)(1 1)MODE (6)POWER LEVEL(to)1 Q Q 20.402(b)20.45(s)(1)(i) 20.45(s)(1)(rr) 20.405(s)(t)(iii)20.45(a)(1)(iv) 20.405(a)(1}(v) 2(L<<5(c)50.35(c)(1) 50.35(c)(2) 50.73(a)(2)Oi 50.73(a)(2)(4) 50.73(s)(2)(rii)
LICENSEE CONTACT FOR THIS LER 1 50.73(s)(2)(rr) 50.73(a)(2)(v) 50.73(s)(2)(vb) 50.73(a)(2)(v5i)(A) 50.73(s)(2)(via7(B) 50.73(a)(2)(r) 73.71(b)73.71(c)OTHER (Specify in Abstract beiovv snd In Text, NRC Form 365A)AME Burton A.Grabo, Section Leader, Nuclear Regulatory Affairs EPHONE NVMBER 6 0 2 3 9 3-6 4 9 2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRIBEO IN THIS REPOR T 13 MANVFAC.TVRER REPORTABLE, TO NPROS MANUFAC-TURER REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 YES (N yes, complete EXPECTED SV BMISQON DATE)X TRACT (Limn tO 1400 SPaCee, Le., SPPrOXimateIY Triteen Sin6Ie SPaoe tPPanrrisen Snea)(1 5)EXPECTED SUBMISQON DATE (1 5)MONTH DAY YEAR On July 6, 1995, at approximately 1200 MST, Palo Verde Unit 2 was in Mode 1 (POWER OPERATION), operating at approximately 100 percent power when Control Room personnel i.dentified four occasions between April 7, 1995 and June 30, 1995 when the conditional surveillance in TS Limiting Condition for Operation (LCO)3.8.4.1 ACTION a had not been performed.
TS LCO 3.8.4.1 ACTION a requires veri,fication at least once per 7 days that inoperable electrical containment penetration circuit breakers remain open.On April 7, 1995 and June 16, 1995, the reactor cavity sump pump circuit breaker had not been verified.On April 7, 1995 and June 9, 1995, the normal access air filtration unit space heater circuit breaker had not been verified.A TS violation occurred when Unit 2 did not comply with the TS LCO 3.8.4.1 ACTION a.An independent investigation of this event is being conducted in accordance
'with the APS Corrective Action Program.A preliminary investigation has determined that the cause of the event is attributed to inattention to detai,l by the Control Room personnel performing the conditional surveillance.
A human performance evaluation will be performed as part of the investigation.
As correcti,ve action, a night order was issued to alert Control Room personnel of the event and to stress the importance of proper configuration control and attention to detail.If necessary, coaching will be administered followi.ng the outcome of the human performance evaluation.
There have been no previous similar events reported pursuant to 10CFR50.73.
I71508010014
'7150720 PDR ADC)CK 0500052'7I 5 PDR t
LICENSEE EVENT REPORT (LER)TEXT CONTINUATION AQLITY NAME Palo Verde Unit 2 DOCKET NUMBER LER NUMBER TEAR SEQUENTIAL
'EIIISO NUMBERNUMBER PAGE 1.REPORTING REQUIREMENT:
0 5 0 0 0 5 2 9 9 5-0 0 4-0 0 0 2 of 0 7 This LER 529/95-004-00 is being written to report a condition prohibited by the plant's Technical Specifications (TS)as specified in 10 CFR 50.73(a)(2)(i)(B).Specifically, at approximately 1200 MST on July 6, 1995, Palo Verde Unit 2 was in Mode 1 (POWER OPERATION), operating at approximately 100 percent power when Control Room personnel (utility, licensed)identified four occasions between April 7, 1995 and June 30, 1995 when the conditional surveillance in TS Limiting Condition for Operation (LCO)3.8.4.1 ACTION a had not been performed.
TS LCO 3.8.4.1 ACTION a requires verification at least once per 7 days that inoperable electrical containment (NH)penetration circuit breakers remain open.On April 7, 1995 and June 16, 1995, the reactor (AC)cavity sump pump circuit breaker had not been verified.On April 7, 1995 and June 9, 1995, the normal access air filtration unit space heater circuit breaker had not been verified.A TS violation occurred when Unit 2 did not comply with the TS LCO 3.8~4.1 ACTION a.2.EVENT DESCRIPTION:
Prior to the event, on March 29, 1995, APS Engineering personnel (utility, non-licensed) determined that redundant overcurrent protection was not provided on thirty-four (34)electrical containment penetration circuits in each of Palo Verde Units 1, 2, and 3.This event was reported in LER 528/529/530/95-004-00 dated April 27, 1995.Control Room personnel in each unit declared the 34 affected containment penetration conductor overcurrent protective devices inoperable and entered the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ACTION statement of TS LCO 3,8.4.1 to (1)restore the protective devices to OPERABLE status, or (2)deenergize the circuits by tripping the associated backup circuit'reaker or by racking out or removing the inoperable device.At that time, Unit 1 was preparing to shut down on April 1, 1995 for its"fifth refueling outage.APS requested, and was granted, a notice of enforcement discretion to extend the allowed outage time for TS LCO 3.8.4,1 to April 4, 1995 in order to allow the performance of steam generator (AB)high temperature chemical cleaning prior to cooling down to Mode 5 (COLD SHUTDOWN).
Unit 1 entered Mode 5 at approximately 1008 on April 3, 1995 and exited TS LCO 3.8.F 1.The 34 protective devices were returned to OPERABLE status prior to the Mode 4 (HOT SHUTDOWN)entry on May 18, 1995.
LICENSEE EVENT REPORT (LER)TEXT CONTINUATION AQUlY NAME Palo Verde Unit 2 DOCKET NUMBER LER NUMBER'f EAR SECWENTIAL PAGE 0 5 0 0 0 5 2 9 9 5-0 0 4 0 0 0 3 Cf 0 7 In Units 2 and 3, required modifications had been completed on nine (9)of the 34 containment penetration circuits required to be energized for safe plant operation within the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed by TS LCO 3.8.4.1.On March 31, 1995, the remaining 25 circuits were deenergized and the affected systems or components were declared inoperable.
An approved clearance document was generated to track tag placement and tag removal for the circuits and affected systems and components.
A TS Component Condition Repozt (TSCCR)was generated to track the inoperable TS components.
The TSCCR was to include a hardcopy list of inoperable circuit breakers and affected TS equipment.
On April 6, 1995, APS Engineering personnel determined that three (3)of the 25 circuits had adequate existing protection for the associated containment penetrations and removed the 3 circuits from the list of electrical penetrations with deficient ovezcurrent protection.
On April 7, 1995, appropriate tags were removed from the equipment and the TSCCR and clearance was reconciled with the remaining 22 deficient cizcui.ts.
A temporary procedure (40TP-9ZZ04) was approved on April 6, 1995 to satisfy the conditional surveillance in TS LCO 3.8.4.1 ACTION a by verifying at least once per 7 days that the 22 affe'cted circuits remain deenezgized until appropriate plant modifications were performed to allow energizing the affected circuits.40TP-9ZZ04 requires (Step 8.1.1)a check of the TSCCR to determine the status of the modifications to the electrical penetrations, (Step 8.1.2)a placement of"N/A" in the initial block for any penetrations which have the required modifications completed, and (Step 8.1.3)verification of the remaining ci,rcuits which do not have the required modifications completed.
The first performance of 40TP-9ZZ04 was scheduled for April 7, 1995 and subsequent performances every 7 days thereafter.
At approximately 1000 MST on June 30, 1995, during a review of 40TP-9ZZ04 previously performed at approximately 0145 MST on June 30, 1995, Control Room personnel discovered that reactor cavity sump pump circuit breaker (NHN-M1014) had not been verified open and determined that the verification was required as indicated in the TSCCR.-When the Control Room personnel retrieved the Control Room copy of 40TP-9ZZ04 to perform the verification for NHN-M1014, they discovered that the procedure copy contained handwritten N/A's in four initial blocks, including the block for NHN-M1014.
The procedure copy was reviewed against the TSCCR and two blocks were found to be pre-N/A'd in which the required modifications to the electrical penetrations were not performed.
One block corresponded to NHN-M1014 and the other to the normal access air filtration unit space heater circuit breaker (NHN-D15-06).
Control Room personnel removed the N/A', verified NHN-M1014 was open prior to exceeding the 7 days allowed Ij LICENSEE EVENT REPORT (LER)TEXT CONTINuATION Palo Verde Unit 2 DOCKET NUMBER LER NUMBER yEAR BEQUENTlAL RENSO NUMBER NUMBER PAGE 0 5 0 0 0 5 2 9 9 5-0 0 4-0 0 04of07.by TS LCO 3.8.4.1, and notified Control Room supervision of the procedural problem (i.e., pze-N/A'd initial blocks).An investigation was initiated, and included a review of the previous.performances of 40TP-9ZZ04 in both Units 2 and 3 since April 7, 1995.Several performances of 40TP-9ZZ04, in Uni.t 2 only, included blocks with N/As that were questionable.
At approximately 1200 MST on July 6, 1995, as part of the investigation, Control Room personnel identified four occasions in Unit 2 between April 7, 1995 and June 30, 1995 when the condi.tional surveillance in TS LCO 3.8.4.1 ACTZON a had not been performed in that the initial blocks in 40TP-9ZZ04 were inappropriately N/A'd.A summary of the performances of 40TP-9ZZ04 for Unit 2 is provided below.04/07/95*04/14/95 04/21/95 04/28/95 05/05/95 05/12/95 05/19/95 05/26/95 06/02/95 06/09/95*06/16/95*06/23/95 06/30/95*Denotes NHN-M1014 and NHN-D15-06 were inappropriately N/A'd.All deficient circuit breakers were appropriately verified, NHN-M1014, NHN-D15-06, and the steam generator wet layup pump motor space heater (NHN-D10-20) were inappropriately N/A'd by the reactor operator'(utility, licensed).
However,.the auxiliary operator (utility, non-licensed) performing 40TP-9ZZ04 stated that he had checked all the circuits in the TSCCR.All deficient circuit breakers were appropriately verified.All deficient circuit breakers were appropriately verified.All deficient circuit breakers were appropriately verified.All deficient circuit breakers were appropriately verified.All deficient circuit breakers were appropriately verified.All deficient circuit breakers were appropriately verified.This was the first appearance of the pre-N/A'd version of 40TP-9ZZ04.
The blocks for NHN-M1014 and NHN-D15-06 were initialed as verified.40TP-9ZZ04 was pre-N/A'd.
NHN-D15-06 remained inappropriately N/A'd.NHN-M1014 was initialed as verified.This was not a pre'N/A'd version of 40TP-9ZZ04.
However, NHN M1014 was inappropriately N/A'd.All deficient circuit breakers were appropriately verified.40TP-9ZZ04 was pre-N/A'd.
However, the N/A's for NHN-M1014 and NHN-D15-06 were appropriately crossed out and the block initialed as verified.All deficient circuit breakers were appropriately verified.40TP-9ZZ04 was pre-N/A'd.
The N/A for NHN-D15-06 was appropriately crossed out and the block initialed as verified.NHN-M1014 was inappropriately N/A'd.However, the error was detected prior to the expiration of the 7 days.the surveillances that were inappropriately performed.
t I LICENSEE EVENT REPORT (LER)TEXT CONTINUATION AQUTY NAME Palo Verde Unit 2 DOCKET NUMBER LER NUMBER YEAR SEQUENRAL REIASIO NUMBER NUMBER PAGE 0 5 0 0 0 5 2 9 9 5-0 0 4-0 0 05of 0 7 TS LCO 3.8.4.1 ACTION a requizes verification at least once per 7 days that inoperable electrical containment penetration circuits breakers remain open.On April 7, 1995 and June 16, 1995, the reactor cavity sump pump circuit breaker had not been verified.On April 7, 1995 and June 9, 1995, the normal access aiz filtration unit space heater circuit breaker had not been verifi.ed.
A TS violation occurred when Unit 2 did not comply with the TS LCO 3.8.4.1 ACTION a and the 7 days were exceeded for each circuit.3.ASSESSMENT OF THE SAFETY CONSEQUENCES AND THE IMPLICATIONS OF THIS EVENT: The OPERABILITY of the containment penetration conductor overcurzent protective devices ensures that the fault current through a containment penetration feedthrough is less than its damage curve.This design feature prevents the circuits from delivering short-circui,t currents of a magnitude and duration which could cause thermal damage to the penetrations.
The primary protective devices installed on the 31 affected circuits were OPERABLE and capable of performing their safety function.Only the added assurance of the redundant containment protective devices was in question.Nine (9)of the circuits had required modifications completed within the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed by TS LCO 3.8.4.1.The remaining 22 circuits were deenergized and the affected systems or components were declared inoperable on March 31, 1995.Although a total of 4 circuits were not procedurally verified to be deenergized at least once per 7 days on 3 occasions, an administrative control (clearance) that was in place indicated that the circuits remained deenezgized throughout the event.There were no adverse safety consequences or implications as a result of this event.The event did not result in any challenges to the fission product barriers or result in any releases of radioactive materials.
This event did not adversely affect the safe operation of the plant oz the health and safety of the public.CAUSE OF THE EVENT: An independent investigation of this event is being conducted in accordance with the APS Corrective Action Program.A preliminary investigation has determined that the cause of the event is attributed to inattention to detail by the Control Room personnel performing the conditional surveillance in that they i.nappropriately N/A'd inoperable circuit breakers during the TSCCR reviews (SALP Cause Code A: Personnel Error).No common cause could be found amongst the three occurrences.
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LICENSEE EVENT REPORT (LER)TEXT CONTINUATION ACIUlY NAME Palo Verde Unit.2 DOCKET NUMBER LER NUMBER YEAR SEOVENllAL RPAQO NUMBER NUMBER PAGE 0 5 0 0 0 5 2 9 9 5-0 0 4-0 0 06cf07 The preliminary investigation identified several contributing factors listed below: l.Administrative barriers such as closure reviews by Control Room supervision and surveillance reviews by the Shift Technical Advisor were not effective in identi.fying these occurrences.
2.The Control Room copy of 40TP-9ZZ04 was not corrected when the handwritten N/A's were initially discovered in the procedure on June 2, 1995'he Control Room copy remained inappropriately marked foz 4 more weeks.3.When discrepancies were thought to exist between the TSCCR and the its supporting documentation regarding circuits which may or may not have the required modification, the discrepancies were not brought to resolution.
Although the list of affected circuits in the TSCCR package correctly denoted the circuits which had the zequi.red modifications completed, the TSCCR list was not reconciled into a new list following each update, but marked out and annotated as to the intent of the markings.A human performance evaluation wi,ll be performed as part of the investigation.
If information is developed that would significantly affect the reader's understanding or perception of this event, a supplement will be submitted.
No unusual characteristics of the work.location (e.g., noise, heat , poor lighting)directly contributed to this event.There were no procedural errors involved.5.STRUCTUREI SYSTEMS OR COMPONENT INFORMATION Although the containment penetration conductor overcurrent protective devices were inoperable, they did not contribute to this event.There were no component or system failures involved in this event.No failures of components with multiple functions were involved.No failures that rendered.a train of safety system inoperable were involved.6.There were no safety system responses and none were necessary.
CORRECTIVE ACTIONS TO PREVENT RECURRENCE:
The Control Room copy of 40TP-9ZZ04 was corrected (i.e., the handwritten N/A's were removed).In addition, subsequent performances of 40TP-9ZZ04 will be controlled under the surveillance testing program.Therefore, a 7 I]I LICENSEE EVENT REPORT (LER)TEXT CONTINUATION ACIUTY NAME Paio Verde Unit 2 DOCKET NUMBER LER NUMBER'TEAR SEQUENllAL NUMBER REDO NUMBER PAGE 0 5 0 0 0 5 2 9 9 5-0 0 4-0 0 07of 0 7 controlled copy will be delivered to the Control Room by the surveillance procedure control group each time 40TP-9ZZ04 is to be performed.
A night order was issued to alert Control Room personnel of the event'nd to stress the importance of proper configuration control and attention to detail.If necessary, coaching will be administered following the outcome of the human performance evaluation.
Other actions to prevent recurrence identified during the investigation will be tracked under the Corrective Action Tracking System.7.PREVIOUS SIMILAR EVENTS: Although previous events attributed to Control Room personnel error have been reported in the past three years, no events have been reported pursuant to 10CFR50.73 which involve the same cause (i.e., inappropriately N/A'ing the initial block).