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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
[Table view] |
Text
pej.oa.rr Y Z REGULAT% IS881BPlg DM'%830TIONLSTEM (RIDE)
DEACCESSION NBR:9505190265 DOC.DATE: 94/12/23 NOTARIZED: NO DOCKET FACZL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 AUTH. NAME AUTHOR AFFILIATION GRABO,B.A. Arizona Public Service Co. (formerly Arizona Nuclear Power LEVZNEgJ.M. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION P
SUBJECT:
LER 94-008-00:on 941126,controlled reactor shutdown commenced to isolate & repair leaking pressurizer vent valves,per TS limiting condition for operation 3.4.10,action (a ) . Valves reworked. W/941223 1 tr .
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL'IZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc.
NOTES:STANDARDIZED PLANT 05000528 R RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME'D4-2 LTTR ENCL ID CODE/NAME LTTR 'ENCL PD 1 1 HOLIAN, B 1 1 TRAN,L 1 1 INTERNAL: ACRS 1 1 2 2 AEOD/SPD/RRAB 1 1 1 1 NRR/DE/ECGB 1 1 NRR/DE/EELB 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/DSSA/SPLB 1 1 NRR/DSSA/SPSB/B 1 1 D NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN4 FILE 1 1 p
L ST LOBBY WARD LITCO BRYCE,J,H 01'XTERNAL:
1 1 NOAC MURPHY,G.A 1 1 NOAC POORE,W.
NRC'DR 1 1 NUDOCS FULL TXT VOTE TO ALL"RI DS" RECIPIENTS:
PLEASE HELP US TO REDUCE O'ASTE! COiNTACTTHE DOCL'MEi! COi'TROL i
DESK. ROOih! Pl.37 (EXT. 504-T033 ) TO ELIWIIYATE YOUR YAihIE FROiI DIS'I'Rl Dl."I'ION LIS I S FOR DOC!.'NIEY, I'S YOU DOi "I EED!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 28
AY GS '9S 11t36 CONPLI CE 1
Arizona Public Service Company
, PALO VEROE NUCLEAR GENERATING STATION P.O, 2OX 5~334 - PFIOENIX. ARIZONA II5072-'2334 192-0091 7-JML/BAG/DLK, JAMES M: LEVINE December 23, 1994 VICE PAESIOENT 4tICI.Eett PnOIIVC((Oe U. S. Nuclear Regulatory. Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555
Dear Sirs:
Sub)ect:
Vnits 1 License.Event Report File: 94420-404
~
Palo Verde Nuclear Generating Station (PVNGS),
Docket No. STN 50-828 {Ucenee No.-NPF<1)
P Attached please find License Event Report (LER) 94-008-00. prepared and submitted pursuant,to 10 CFR 50.73. 'Unit 1 intentionally isolated a. Reactor: Coolant System (RCS) vent path and entered Technical Specication'Limiting Condition for Operation,(TS LCO) 3.4.10, ACTlON, (a) to repair seat leakage on the pressurizer solenoid operated vent valves (RCA-HV-103.and RCB-HV-105). Unit 1 shut down and cooled down to comply with Technical Specifications white repairing RCA-HV-103 and, RCB-HV-105.
ln accordance with 10 CFR 50.73(d), a copy of this LER is being forwarded to the Regional Administrator,, NRC Region, fV.
lf you have any questions, please contact Burton A. Grabo, Section, Leader, Nuclear Regulatory Affairs, at (602) 393-6482.
Sincerely, JML/BAG/DLK/pv Attachment cc: L J. Callan (all with attachment)
K. E. Perkins K E. Johnston INPO Remrds Center 9505190265 94%223 PDR ADQCK 05000528 S PDR
41 V
MAY 85 '95 11)36 CONPLIA CE P.3
~ e ~~ w LICENSEE EVENT REPORT (LER)
ACILITYRANE (I) DOCKET NVMOCR (2) 0 5 0 0 0 5 2 8 t <' 8 I Palo Verde Unit 1 ITLS (e)
Technical S ecificationRe uiredPlantShutdownto Re air Leakin PressurizerVentPathV dies',
REPORT DAZE OTHER FACalllCR RIVDLVCO F osooo 9 4 9 4 - 0 0 8 2OAO2(a) 2OeOS(e)O)(I) 0 0 2 3 REPORT IS SUGMATED pURSUANT To THE REouREAIENzs oF 10 cFR c (caecal ann at Inate at Ine 2(x<<S(c)
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TS.TT(c) 20AOS(e)(1 gii) OT)%R (SFecTT k LEVELS0) 9 SOSO(C)(2) 2O,COS(e)(I )Oii) SOTS(e)(2)O~ SOTS(e~))(A) ae)ow nnd In TeR, Ic Farm 20 eOS(e)(I++ 60.TS(AM2)(e) 50.TS(e)(2)(e~e SOSA) 2(LlOS(eXI)IV) S(LTS(e)(2)OL) SO.TS(e)(2)OO
~ CONTACT FOR TIFS LER (12)
'urton A. Grabo, Section Leader, Nvciear,Regulatory Affairs FALURE DESCRSED M TNT REPORT PO) 8.02393-6 ~ 92 IlANUFAC REPORTASLS REPORTASLE TURER TO NFROS TO IA%
sQppLAAIRNTALREpoRT ExpEOTED (Ie) hXFKCZED MOttDI DAY YEAR SUSMSSION bATE (1S)
TRAcT (Len>> nI 1cx) epeaee. Le., AFFKet~lz hneen ano1eeaece TFewnaen Lace) (Ia)
On November 25, 1994, at approximately 0220 MST, Unit 1 Control Room personnel elected to. voluntarily enter Technical Specification Limiting Condition for operation (TS LCO) 3'.4.10, II) ACTION (a) to isolate and repair the pressurizer vent, valv>s (RCA-HV-103 and RCB-HV-105) which ware exhibiting symptoms of abnormal valve position indication and seat leakage.
i(I On November 26, 1994, at approximately 0103 MST, Palo Ver'de Unit 2 was in Mode 1 (POWER OPFRATION), operating at, approximately 1
98 percent power when control Room personnel commenced a controlled reactor shutdown to comply with TS LCO 3.4.10, ACTXON (a). At 0440 MST, the reactor was manually tripped .from 19 percent reactor power in accordance with approved procedures and the plant was stabilized in Mode 3 (HOT STANDBY) by approximately 0538 MST. Control Room personnel continued the Reactor Coolant System (RCS) cooldown and entered Mode 4 (HOT SHUTDOWN) at 1400 MST on November 26, 1994. The plant shutdown and cooldown to Mode 4 were uncomplicated.
Thex'e have been no previous similar events xaported'ursuant to 10 CPR Soe73 in the last three years.
I t'1AY GS '95 1,1:37 CONPLI E P.4 LlCENSEE EVENT REPORT (LER) TEXT CONTlNUATION QOCKET NUMBER yEAR LER NUMBER SEQvEMllAL NUMBER R&ASlo NUMBER
'A Palo Verde Unit 1 0 5 0 0 0 5 2 8 9 4 - 0 0 8 - 0 0 0 2 o 0 8 X- DESCRXPTXON OF .WHAT OCCURRED:
A. Xnitial Conditions:
On November 26, 1994, at 0103 MST, Palo Verde Unit 1 was in Mode 1 (POWER OPERATION), operating at approximately 98 percent power.
B- Reportable Event Description (Xncluding Dates and Approximate Times of Major Occurrences):
Event Classification: Completion of a plant shutdown required by Technical Specifications (TS).
On November 26, 1994, at approximately 0103 MST, Palo Verde Unit 1 Control Room personnel (utility, licensed).
commenced a controlled reactor (AC) shutdown to comply with TS Limiting Condition for Operation (LCO) 3.4.10, ACTION (a). At 0440 MST, the reactor was manually tripped from 19 percent reactor power in accordance with approved procedures, and the plant was stabilized in Mode 3 (HOT STANDBY) by approximately 0538 MST. Control Room personnel continued the Reactor Coolant System (RCS (AB) cooldown and entered Mode 4 (HOT SHUTDOWN) at, 1400 MST on November '26, 1994. The plant shutdown and cooldown to Mode 4 were uncomplicated.
Prior to the event, control Room personnel observed valv position indication (V)(ZI) for RCA-HV-103 and RCB-HV-10 functioning abnormally (e.g., periodic dual position indication, full open indication, and flickering closed indication) and momentary indication of increased pressure in the reactor drain tank (RCT)(DRN)(TK) along with a corresponding pressure drop in the RCS. Control Room personnel performed 40ST-9RC02, "Computer Calculation of RCS Water Inventory Balance 4.4.5.2.-1.c,"
to verify total RCS leakage was within acceptable limits Total RCS leakage was calculated to be 0.14 gpm (within
0 Cl NAY GS '9S 11:38 CONPLI E P.S LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER LER NUMBER PA BMVEMIIAI. REV~
NUMBER NUMBER Palo Verde Unit 1 0'5 0'0 0 5 2 8 94'-008-0003 c 0 8 the maximum, allowable TS 3.4,.5.2 limits of 1.0 gpm UNIDENTIFIED LEAKAGE or 10 gpm IDENTIFIED LEAKAGE). The safety function of RCA-HV-103 and RCB-HV-105 is to open and provide a vent path for the Reactor Coolant System via the pressurizer (AB),. Minor valve seat leakage by itself will not prevent the valves from performing their safety function or cause the valves to be INOPERABLE.
Based on the abnormal valve position indication and the pressure, fluctuations in the reactor drain tank and RCS, a containment (NH) entry was made at power on November 25, 1994 to isolate the pressurizer steam space vent (AB) path (close RCE-V090). The pressurizer steam space vent path was declared INOPERABLE at 0220 MST. On November 25, 1994, Unit 1 elected to voluntarily enter TS LCO 3 4.10, ACTION, (a) to isolate and repair the pressurizer vent valves (RCA-HV-103 and RCB-HV-105) whic, were exhibiting symptoms of abnormal valve position indication and seat leakage. TS LCO 3.4.10 ACTION (a) states:
"With only one of the above required reactor coolant system vent (AB) paths [reactor vessel head (AB) and pressurizer steam space] OPERABLE, from either location restore both paths at that location to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least -HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />."
On November 26, 1994, at 0103., Unit 1 commenced a controlled reactor shutdown and cooldown to Mode 4.
Following the reactor shutdown, Operations personnel (utility, non-licensed) isolated the remaining,RCS vent path (reactor vessel vent path) to completely isolate RCA-HV-103 and RCB-HV-105 for maintenance. With both RC vent paths INOPERABLE, on November 26, 1994, at 1525 NST Control Room personnel exited TS LCO 3.4.10, ACTION (a) and entered TS LCO 3.4.10, ACTION (b), which states:
"With none of the above required reactor coolant system vent paths OPERABLE, from either location .restore at
45 II MAY QS '9S 11I38 COHPLI CE LlCENSEE EVENT REPORT (LER) TEXT CONTINUATION OOCKET NUMBER LER NUMSER SEQUENAAL EVISO NUMBER NUMBER Palo Verde Unit 1 0 5 0 0 0 5 2 8 9 4 - 0 0 8 - 0 0 04o 38 least one path at that location to OPERABLE status withi the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY within th next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours."
Unit 1 remained in Mode 4 until RCA-HV-103 and RCB-HV-1G were repaired, and both RCS vent paths were restored to OPERABLE status. Control Room personnel exited TS LCO 3.4.10, ACTION (b) on November 28, 1994, at 1804 MST, after satisfactory completion of post maintenance retesting and 73ST-1XI24, "Section XI Valve Stroke Timin:
and Position Indication Verification >> Mode 5 and 6 Reactor and Pressurizer Vent Valves" on RCA-HV-103 and RCB-HV-105. Unit 1 entered Mode 3 at approximately 2122 MST on November 28, 1994.
C. Status of structures, systems, or components that were inoperable at the start of the event that contributed to the event:
Prior to the event, RCA-HV-103 and RCB-HV-105 were exhibiting symptoms of abnormal valve position indicatio and seat leakage. Even though RCA-HV-.103 and RCB-HV-105 were able to perform their safety function, both valves were intentionally isolated to prevent abnormal operatio?
and repair the seat leakage. Isolating RCA-HV-103 and RCB-HV-105 rendered the pressurizer steam space vent pat!
INOPERABLE. Unit 1 shut down to Mode 4 to comply with TS LCO 3.4.10 ACTION (a) .
Cause of each component or system failure, if known:
Because RCA-HV-103 and RCB-HV-105 were able to perform their intended safety function, prior to being isolated for maintenance, neither valve was considered to have failed. Both valves did require maintenance to stop valve seat leakage which prompted isolating the pressurizer steam space vent path and shutting down Unit 1 to comply with TS LCO 3.4.10, ACTION (a); An independent investigation of this event, including an Ecgxipment Root Cause Failure Analysis (ERCFA) on
0 MAY 85 '95 11:39 CONPL CE P.7 L1CENSEE EVENT REPORT (LER) TEXT CONTlNUATlON ACILITYNAME DOCKET NUMBER LER NUMBER gEAR sEoUEHTNl. RENsio NUMBER MUSSED Palo Verde Unit 1 94-008-00 PA<'5000528 0 5 o ') 8 RCA-HV<<103 and RCB-HV-105, was initiated in accordance with the APS Incident Investigation Program. The preliminary findings of the ERCFA determined that the cause of the leakage was due to corrosion/erosion of the primary and secondary pilot valve seating surfaces. The reason for the degraded seating surfaces on the primary and secondary pilots was attributed to the harsh environment (i.e., high temperature, high pressure saturated steam, with boric acid carryovex) that the valves are exposed to.
RCA-HV-103 and RCB-HV-105 are Solenoid-Operated Valves (SOV) (PSV), designed with a seal welded bonnet. The condition of the seating surfaces on the primary and secondary pilots degraded, to the point of unacceptable leakage,'hereby prompting the unplanned reactor shutdown.
E. Failure Mode, mechanism,, and effect. of each failed component, if known:
Not applicable no component failures were involved.
Fox failures of components with multiple functions, list of systems, or secondary functions that were also affected:
Not applicable no failures of components with multiple functions were involved.
G. For a failure that xendered a train of a safety system inopexable, estimated time elapsed from the discovery of the failuxe until the txain was returned to service:
No failures occurred that rendered a train of a safety system INOPERABLE; however, the pressurizer steam space vent path was intentionally rendered INOPERABLE when RCE-V090 was closed to isolate RCA-HV-103 and RCB-HV-105 for repaixs. The pressurizer steam space vent path was INOPERABLE for approximately 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br />.
Ik
'I r,
NAY 85 '95 11:39 CONPLI CE P.S LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER LER NUMBER PA SEQUEHllAI. EVlQO Palo Verde Vnit1 05000528 94-.008-0006 0 8 H. Method of discovery of each component or system failure or procedural error:
There were no component or system failures or procedural errors identified. Pressurizer vent valves RCA-HV-103 and RCB-HV-105 did require maintenance to stop valve sea leakage. Prior to the event, valve position indication for RCA-HV-103 and RCB-HV-105 was observed functioning abnormally (e.g., periodic dual position indication, ful open indication, and flickering closed indication) and the valves were exhibiting symptoms of seat leakage.
Cause of Event:
The cause of the event (completion of a plant shutdown required by TS) was attributed to the voluntary entry into TS LCO 3.4.10, ACTION (a) to repair RCA-HV-103 and RCB-HV-105. Unit 1. shut down to Mode 4 to comply with TS LCO 3.4.10, ACTION (a) (SALP Cause Code x: Other).
No unusual characteristics of the work location (e.g.,
noise, heat, poor lighting) directly contributed to this event. There were no procedural errors or personnel errors which contributed to this event.
Safety System Response:
Not applicable there were no safety system responses and none were necessary.
K. Failed:Component Information:
Although no component failures were involved, the leakin pressurizer vent valves (RCA-HV-103 and RCB-HV-105) are SOVs, manufactured by Target Rock Corporation. The Node number for both valves is 76HH-008.
i Cl ;~
I:
1
NAY GS '95 11(48 CONPLI CE P.9 LICENSEE EVENT REPORT (LERj TEXT CONTINUA'nON DOCKETNUMBER LER NUMBER'~R PP sGoU&ETlAL Palo Verde Vnit1 0 5 0 0 0 5 2 8 9 4 - 0 0 8 - 0 0 0 7 ( 0 8 L. Assessment of the Safety Consequences and Xmplications c this Event:
The Unit 1 shutdown and cooldown to Node 4 were controlled evolutions. The manual trip of the reactor from low power (19 percent) and the resulting transient had minimal impact on the plant. The plant shutdown anG cooldown were uncomplicated. The event did not result i any challenges to the fission product barriers or result in any releases of radioactive materials. Therefore, there were no adverse safety consequences or implicatior.
as a result of this event. This event, did not adversely affect the safe operation of the plant or the. health anc safety of the public.
XXX. CORRECTIVE ACTION:
Xmmediate:
Control Room Personnel voluntarily entered TS LCO 3.4.3.0 ACTION (a) to isolate the pressurizer steam space vent path and subsequently performed a controlled shutdown to Mode, 4- An independent investigation of this event, including an ERCFA on RCA-HV-103 and RCB-HV-105, was initiated in accordance with the APS Xncident Investigation Program. RCA-HV-103 and RCB-HV-105 were reworked in accordance with the APS Maintenance Program and returned,to service.
As part of the ERCFA, the maintenance history for RCA-HV-103 and RCB-HV-105 and other SOVs of the. same design in similar applications was reviewed to determine transportability. The review identified other SOVs in Unit 1 as well as Units 2 and. 3 of the same design and i similar applications whose valve internals have not been inspected and refurbished. While some of the SOVs identified during the maintenance history review have some minor seat leakage, the analysis determined the valves are fully capable of performing their intended safety function and do not warrant further immediate corrective action.
0 MAY 85 '95 11:48 CONPLI CE P. 18 r
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER LER NUMBER PA<
YEAR sEQUEMTlAL REvlso NUMBER ~8ER Palo Verde Unit 1 0 5'0 0 0 5 2 8 9 4 - 0 0 8 - 0 0 0 8 o: l 8 B. Action to Prevent Recurrence; Additional actions to prevent recurrence are heing tracked under the commitment action tracking system.
These actions include inspecting and refurbishing the SOVs identified in the maintenance history review (discussed above) over the next two refueling outages in each respective unit.
IV. PREVIOUS SIMILAR EVENTS:
There have been no previous similar events reported pursuant to 10 CFR 50r73 in the last three years.
V. ADDITIONAL INFORMATION:
Unit 1 entered Mode 2 (STARTUP) at approximately 1601 MST an November 29, 1994 and returned to Mode 1 at approximately 0251 HsT, on November 30, 1994. Unit 1 was synchronized on the gric at approximately 1159 MST on November 30, 1994.
Ik 0