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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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Text
LICENSEE EVENT REPORT (LER)
ACILflYNAME ('I ) DOCI(ET NUMBER (2) PAGE (3)
Palo Vercfe Unit 1 0 5 0 0 0 5 2 8 1oF08
(<)
Safety Injection Discharge Check Valve Reverse Flow Causes Condition Outside Design Basis EVENT DATE 6 LER NUMBER 6 REPORT DATE OTHER FACIUTIES INVOLVED 6 YEAR YEAR SEQUENTIAL REVISION 0 5 0 0 0 5 2 9 0 5 0 7 8 9 8 - 0 0 6 - 0 0 0 6 0 5 9 8 Unit 3 0 5 0 0 0 5 3 0 OPERATING IS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR g: (Check one or more ot the foaorrln9) (11)
MODE (9) 20A02(b) 20.45(c) M.73(aX2XN) 73.71(b)
POWER 20.45(sX1Xi) 50.36(cX1) 50.73(sX2Xv) 73.71(c)
LEVEL(to) $ P P 20.45(aXt~i 50.36(cX2) 50.73(aX2Xvi) OTHER (SPeci/7 in Abstract 20.45(sX1Xi) X 50.73(aX2Xi) 50.73(aX2Xvw+A) bekxtr and in Text, NRC Form 20.45(aXt Xiv) X 50.73(aX2Xi) SO.73(aX2XviXB) 2IL45(sXIXv) 50.73(aX2Xi) 50.73(aX2Xx)
LICENSEE CONTACT FOR THIS LER (12)
ELEPHONE NUMBER CODE Daniel G. Marks, Section Leader, Regulatory Affairs 6 0 2 3 9 3 - 6 4 9 2 COMPLETE ONE UKE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEM COMPONENT MANUFAC REPORTABLE CAUSE SYSTEM COMPONENT MANUFAC REPORTABLE TURER TO NPRDS TURER TO NPRDS A B Q V B 3 5 0 B B Q V B 3 5 0 SUPPLEMENTAL REPORT EXPECTED (16) EXPECTED MONTH DAY YEAR SUBMISSION YES (IfYes, ccmpkrte EXPECTED SUBMISSION DATE) DATE (15) 0 8 0 7 9 8 TRAOT (Lama to 1600 spaces, Le., approxsmately fsteen se9~ Ypeevntten ines) (16)
On May 7, 1998, Palo Verde Units 1, 2 and 3 were in Mode 1 (POWER OPERATION),
operating at approximately 100 percent power when engineering personnel determined there was sufficient evidence to conclude the Unit 1 "A" train High Pressure Safety Injection pump discharge check valve would not have performed its intended function from October 17, 1996, until April 11, 1998.
Engineering personnel believed, at that time, that the use of enhanced assembly instructions during the Unit 1 seventh refueling outage had corrected the condition. However on May 13, 1998, it was determined that current valve alignment was suspect, and the valve was declared inoperable. Subsequent testing of the "A" train valve revealed that reverse flow through the check valve was sufficient to cause less than minimum injection flow from the redundant train "B" HPSI system. After testing the check valve it was disassembled, examined and reassembled, whereupon it met acceptance criteria.
Based on the "as-found" condition of'he Unit 1 "A" train check valve, the Unit 2 "B" train check valve was tested on May 14, 1998, and it also demonstrated excessive reverse flow. The Unit 2 valve was reworked and further engineering examination revealed no other check valves were rendered inoperable by the condition.
No previous similar events have been reported pursuant to 10CFR50.73 in the last three years.
'7)806l60057 67)80605 PDR ADGCK 05000528 8 PDR
JA LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AGILITY NAME DOCKET NUMBER LER NUMBER, PAGE SEOUENTIAL REVISION NUMBER NUMBER Palo Verde Unit 1 0 5 0 0 0 5 2 8 9 8 - 0 0 6' 0 0 0 2 of 0 8
- 1. REPORTING REQUIREMENT:
This LER 528/98-006-00 is being submitted'ursuant to the following 10 CFR 50.73 criteria. In addition, a RETRACTION of one of the reporting criteria used during related Emergency Notification System (ENS) reports 34227 and 34246 (made pursuant to 10 CFR 50.72) is included.
10 CFR 50 '3(a)(2)(ii)(A and B)
Due to disc misalignment of the Unit 1 "A" and Unit 2 "B" train High Pressure Safety Injection (HPSI)(ECCS)(BQ) pump discharge check valves (V), the design basis minimum flow would not have. been met during a Loss of Coolant Accident (LOCA) design basis event (DBE).
If one HPSI pump is assumed to fail, the redundant HPSI train could not produce required minimum flow due to reverse flow through the opposite train's check valve, a condition where the Units were outside of the design basis and in an unanalyzed cond'ition.
10 CFR 50.73(a)(2)(i)(B)
The discs in the Unit 1 "A" train, and Unit 2 "B" train HPSI discharge check valves were misaligned for extended periods of time and resulted in a condition where Limiting Conditions for Operation (LCO) Allowed Outage Times (AOT) were unknowingly exceeded and that resulted in an operation or condition prohibited by the plant's Technical Specifications (TS). In addition, TS 3.0.3 was entered for brief periods from when the suspect valves were declared, inoperable based on engineering judgment, until they could be isolated from the redundant HPSI trains.
10 CFR 50.73(a)(2)(vii)(B and D)
The failure mechanism (immediate cause) of the Unit 1 "A" train and Unit 2 "B" train HPSI discharge check valves,was vertical misalignment of the disc which resulted in interference between the disc and valve body and incomplete valve closure. The failure mechanism was attributed to a common-cause error in assembling the valves which was a result of inadequate vendor and work instructions and/or personnel errors. Therefore, the assembly error led to multiple failures in systems designed to remove residual heat and mitigate accidents.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKETNUMBER LER NUMBER PAGE SEQUENTIAL RENSION NUMBER NUMBER Palo Verde Unit 1 0 5 0 0 0 5 2 8 9 8 - 0 0 6 - '0 0 0 3 of 0 8 ENS 34227 and 34246 On May 14 and 15, 1998, PVNGS reported that the Unit 1 "A" train 2 "B" train HPSI pump discharge check valves had back-leakage and'nit in excess of acceptance criteria, which indicated design basis minimum flow might not be met (ENS 34227 and 34246 respectively).
The condition was reported as being outside the design basis for an .
extended period time,, and the system did not have suitable redundancy (50.72(b)(1)(ii)(B)). In addition, since the check valves could potentially divert 'flow from the redundant ECCS system, a condition that could have prevented the fulfillment of a safety function, the condition was also reported under 50.72(b)(2)(iii)(D).
Subsequent review of NUREG 1022, Revision 1, has revealed that it is not necessary to assume an additional random single failure in systems reported under 50.72(b)(2)(iii)(D) and therefore, this portion of the ENS reports is hereby RETRACTED.
- 2. EVENT DESCRIPTION:
On March 12, 1998, just prior to the beginning of Unit 1',s seventh refueling outage, the surveillance test procedure for the HPSI pump discharge check valves was revised to include new acceptance criteria for reverse flow testing.. The Unit 1 check valves were the first to be tested using the new acceptance criteria and on April 9, 1998, the Unit 1 "A" train check valve failed to meet the acceptance criteria. Upon disassembly, engineering personnel (other utility personnel) concluded that the valve disc was vertically misaligned high.
Engineering and Maintenance (other utility personnel) personnel believed, at that time, that the vertical misalignment had been corrected during rework of the valve on April 11, 1998, because revised instructions had been used to assemble the valve and post maintenance testing demonstrated acceptable reverse direction flow. A significant condition investigation was initiated to determine the root cause of the surveillance test failure. At this time, engineering personnel evaluated other HPSI pump discharge check valve surveillance test records and determined the inadequate HPSI delivery was not a concern, based on the test results.
On May 7, 1998, Palo Verde Units 1, 2 and 3 were in Mode 1 (POWER OPERATION), operating at approximately 100 percent power when engineering personnel determined there was sufficient evidence to conclude the Unit 1 "A" train check valve would not have performed its intended function from October 17, 1996, until April 11, 1998, when the valve was, reworked.
Although not able to confirm at the time, engineering, personnel suspected the valve disc may have been misaligned as early as 1992.
LlCENSEE EVENT REPORT (LER) TEXT CONTINUATlON ACIUTYNAME DOCKETNUMBER LER NUMBER PAGE SEOUENTIAL REVISION NUMBER NUMBER Palo Verde Unit 1 0 5 0 0 0 5 2 8 9 8 - 0' 6 - 0 -0 0 4 of 0 8 EXT Engineering concluded, based on a review of the Unit 1 "A" train test data, that the Unit 1 "B" train HPSI delivery flow would not have been met for certain design basis events. If, during these events, the "A" train HPSI pump is assumed to flail, the redundant "B" train HPSI system would not meet design basis minimum flow due to reverse flow through the "A" train check valve.
As the root cause investigation was proceeding, on May 13, 1998, engineering personnel suspected, based on measurements taken from a spare valve, that the Unit 1 "A" HPSI discharge check valve may not have been assembled correctly on April 11, 1998, as previously thought. Engineering personnel also suspected that if the valve disc was posi'tioned too low in the valve body it could result in a condition where the outside, upper edge of the disk could get caught under the inside upper edge of the seat causing the disk to "cock" open, similar to events described in Information Notice 89-62.
Engineering personnel informed Unit 1 Operations management (other utility personnel) of their suspicions regarding the check valve's condition and the valve was declared inoperable on May 13, 1998, at 1432 MST., The Unit 1 "A" HPSI system was already inoperable and TS 3.5.2.(a) entered at this time due to maintenance activities unrelated to the check valve condition.
Unknowingly, when the "A" HPSI check valve was declared inoperable, the effect was to make inoperable the "B" train HPSI flowpath,, which in effect, was entry into TS 3.0.3. At 1545 MST on May 13, 1998, .the "A" train HPSI pump was isolated, thereby effectually exiting TS 3 .3 condition.
On May 14, 1998, at 0615 MST, the Unit 1 "A" train HPSI discharge check valve was tested using a new. test procedure and the valve failed to meet reverse direction flow acceptance criteria. The NRC was notified (ENS 34227) of the test failure. Work began immediately to disassemble and inspect the valve, which confirmed the suspected vertical misalignment of the valve disc. The apparent cause of the misalignment was attributed to a measurement error that occurred during the April'9, 1998, disassembly of the valve. The valve was re-assembled, correcting the misaligned disc condition and when tested met the acceptance criteria, with no observable leakage. Operations personnel returned the valve to an operable status and exited the TS LCO 3.5.2(a) at 1756 MST.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AGILITYNAME DOCKETNUMBER LER NUMBER PAGE yEAR sEaUENTIAI. RensIoN NUMBER NUMBER Palo Verde Unit 1 0 5 0 0 0 5 2 8 9 8 - 0 0 6 - 0 0 0 5 of08 Based on the dimensional data from the spare check valve and the Unit 1 "A" train valve, engineering personnel initiated external dimensional checks on the remaining HPSI pump discharge check valves. Dimensional data, maintenance work history and surveillance test records were used to create a matrix which identified valves potentially misaligned and susceptible to "cocking". Engineering personnel established a testing sequence for the remaining valves, based upon this matrix.
Data indicated the Unit 2 "B" train check valve had previously passed surveillance testing requirements, but had exhibited elevated reverse direction flow and external measurements indicated that the disc might be misaligned. Engineering personnel recommended to Unit 2 Operations management that the Unit 2 valve be declared inoperable based on their suspicions regarding the check valve's condition and the "B" train HPSI pump was declared inoperable on May 14, 1998, at 2155 MST and actions were taken to test the valve.
Unrealized by Unit 2 Operations personnel at the time, was that when the "B" HPSI pump was declared inoperable, the effect was to make the "A" train HPSI flowpath inoperable, which in effect, was entry into TS 3.0.3.
This condition existed until 2235 MST on May 14, 1998, when the "B" HPSI injection valves were isolated.
On May 15, 1998, at 1322 MST, the Unit 2 "B'rain check valve failed to meet acceptance criteria. The NRC was notified (ENS 34246) of the test failure. The valve was re-assembled, correcting the misaligned disc condition and when tested met the acceptance criteria, with no observable leakage. Operations personnel returned the valve to an operable status and exited the TS LCO at 0915 MST, on May 16, 1998.
To provide additional assurance that the remaining HPSI pump discharge check valves (Unit 3. "B" train, Unit 1 "B" train, Unit 2 "A" train and Unit 3 "A" train) were operable, each was tested in the order prescribed by the engineering matrix. By May 17, 1998, each valve had been tested and had demonstrated acceptable performance in accordance with the surveillance test acceptance criteria. However, the Unit 1 HPSI "B" train and the Unit 3 HPSI "B" train valves had dimensional values which suggested they may be susceptible to the disc cocking condition in the future and they were reworked by May 26, 1998 to optimize valve alignment.
41 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AGILITYNAME DOCKETNUMBER LER NUMBER PAGE YEAR SEQUENTIAL REVISION NUMBER'UMBER Palo Verde Unit 1 0 5 0 0 0 5 2 8 9 8.- 0 0 6 - 0 0 06of 0 8 EXT 3 ~ 'ASSESSMENT OF THE SAFETY CONSEQUENCES AND IMPLICATIONS OF THIS EVENT:
The event did not result in any challenges to the fission product barriers or result in any offsite releases. Therefore there were no actual adverse safety consequences as a result of the event. However, it is known that design basis minimum flow could not have been maintained due to the reverse flow through the opposite train's check valve, a condition where the Units were outside of the design basis and in an unanalyzed condition.
The safety significance of the failed HPSI check valves was evaluated by reviewing possible failure modes. The limiting failure mode has been determined to be degraded HPSI flow delivery of the operating train as a result of reverse flow through the failed check valve. Safety evaluations are being conducted to assess the potential impact at this time.
A determination has been made that Updated Final Safety Analysis Report (UFSAR) Chapter 15 Design Bases Event (DBE), Main Steam Line Break Return to Power (All Modes), and the UFSAR Chapter 6 ECCS Performance Analysis need further evaluation to determine the potential safety impact due to the degraded HPSI flow. Additionally Fire Protection events that are impacted by the degraded HPSI condition also require further evaluation.
All other Chapter 15 DBEs were determined to not be impacted by this condition. A supplement to this LER will report the evaluation conclusions.
The Probabilistic Safety Analysis (PRA) group (other utility personnel) performed a preliminary assessment of the degraded HPSI flow condition.
Initiating events that were impacted were identified and a review of operator responses was conducted.
PRA's review revealed that Operator response to this event is covered by existing plant procedures and training. Emergency procedures 40EP-9E003, "Loss of Coolant Accident" and 40EP-9E009, "Functional Recovery" address identification of the degraded HPSI flow condition and the required actions to recover the Inventory Control Safety Function. Adequate instrumentation exists for the Operating staff to diagnose the degraded HPSI flow condition.
l LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AOII.AYNAME DOCKETNUMBER LER NUMBER PAGE SEOUENTIAL REVISION NUMBER NIIMBER Palo Verde. Unit 1 1 0 5'0 0 0 5 2 8 9 8 - 0 0.6 - 0 0 07 of 0 8 HPSI pump reliability, which is also used by PRA in determining the safety signi;ficance of this condition has historically been very good. In reviewing the history of failure and demands being tracked for the Maintenance Rule, from the period 1994 to present, there have been no HPSI pump or motor failures in approximately .614 demands. This supports the current estimated failure probability of 6.73 E-4 for the HPSI pump. Now that the final HPSI degraded flow condition is determined, the PRA group will perform an assessment of the risk increase associated with this condition.
- 4. STRUCTURES,, SYSTEMS, OR COMPONENTS INFORMATION:
The valves affected by the described condition are manufactured by Borg-Warner and are ASME Class 2, 4 inch, 1500 pound, bonnet pressure seal swing check valves. The disc assembly is suspended from the underside of the valve bonnet.
- 5. CAUSE OF THE EVENTS:
The Unit 1 Train "A" and Unit 2 train "B" HPSI pump discharge check valves failed because the valve discs became "cocked" under the top of the valve seat, preventing full closure. The cause for the valve discs being cocked open is due to vertical misalignment which was attributed to inadequate maintenance instructions. The-primary contributor to the inadequate maintenance instructions was inadequate vendor information.
On April 9, 1998, when the Unit 1 "A" train HPSI was disassembled the as-found measurements were incorrectly recorded which led to vertical disc misalignment when the valve was reassembled on April 11, 1998. This was attributed to personnel error.
Missed opportunities to identify the condition included: 1) Surveillance test procedures did not ensure the valve discs were seating and 2) lessons learned from in-house, and industry operating experience reports were not effectively incorporated into maintenance and testing procedures.
The cause of the TS 3.0.3 entries is being evaluated and the cause. of the condition will be provided in the supplement to this LER.
- 6. CORRECTIVE ACTIONS TO PREVENT RECURRENCE:
Immediate corrective actions were implemented to restore the affected valves to an operable condition. All HPSI discharge check valves discs have been determined to be assembled correctly.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AC flAYNAME DOCKETNUMBER LER NUMBER PAGE SMUENTIAL REVlSION NUMBER NUMBER Palo Verde Unit.1 EXT
'0 '5 0 0 0 5 2 8 9 8 - 0 0 6 - 0 0 08of08 The maintenance instructions in use for check valve assembly had been revised on November 7, 1994 and are currently considered adequate to perform the activity. However, the check valve maintenance instructions will be revised to include more detailed installation instructions and drawings'ngineering has completed transportability reviews for all other Borg-Warner. bonnet hung pressure seal check valves susceptible to vertical disc misalignment caused by retaining ring position.
Engineering is evaluating transportability to other Inservice Test'ing (IST) program check valves with closure functions and this action will be completed by July 31, 1998.
Surveillance Test procedures for IST program check valves with closure functions are being reviewed to confirm that the acceptance criteria is appropriate and this action is expected to be completed by, July 17, 1998.
An evaluation will be conducted to determine if other industry operating experience information on complex component assemblies has been properly incorporated and this action will be August 31, 1998.
Engineering Support Personnel will be briefed on this event during quarterly industry events training this action will be completed by December 31, 1998.
A Safety Analysis summary report will be completed by July 24, 1998 and will, be included in the LER supplement.
"Late entries" were documented in the Unit 1 and 2 "Unit Logs" to note the entries into TS 3.0.3 Condition Report Disposition Requests were written
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and the entries are being evaluated in accordance with the corrective action program.
7 ~ PREVIOUS SIMILAR EVENTS:
No other previous events have been reported pursuant to 10 CFR 50.73 in the last three years.
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