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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
ACCELERATED DISIIUBUTION DEMONSHRATION SY%TM 0~I REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9003130597
'DOC.DATE 90/03/02 NOTARIZED:
NO DOCKET~FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi'05000529 AUTH.NAME AUTHOR AFFILIATION BRADISH,T.R.
Arizona Public Service Co.(formerly Arizona Nuclear Power LEVINE,J.M.
Arizona Public Service Co.(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT'FFILIATION
SUBJECT:
LER 89-005-01:on 890310,loss of power to alternate plant'ventilation effluent radiation monitor.W/8 ltr.DISTRIBUTION CODE: ZE22T COPIES RECEIVED:LTR 1 ENCL~.SIZE: TITLE:.50.73/50.9'icensee Event Report (LER),, Incident Rpt, etc..NOTES:Standardized plant.'05000529 RECIPIENT ID CODE/NAME P.D5 LA PETERSON,S.
INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DS P NRR/DET/ECMB 9H NRR/DET/ESGB 8D NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB 8E RES/DSIR/EZB COPIES LTTR ENCL 1 1 1 1 2 2 1'2 2 1 1 1, 1 1'2 2 1 1 1 1 1 1 ACRS AEOD/DSP/TPAB DEDRO NRR/DET/EMEB9H3 NRR/DLPQ/LHFB11 NRR/DOEA/OEAB11 NRR/DST/SELB 8D N PLB8D1 G F 02.R FILE 01 2 2 1 1 1.1'1 1 1'1 1 1 1 1 1 1 1'1 1 RECIPIENT COPIES'D CODE/NAME~LTTR ENCL PD5 PD 1 1 EXTERNAL: EGGG WILLIAMS,S LPDR NSIC MAYS,G'UDOCS FULL TXT, NOTES: 4 4 1.1 1 1 1 1-L ST LOBBY WARD NRC PDR NSIC'URPHY,G.A 1'1 1 1.1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US.TO REDUCE WAS'!CONTACT THE.DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM'.DISTRIBUTION C FULL TEXT CONVERSION REQUIRED-TOTAL NUMBER'OF COPIES REQUIRED: LTTR 38 ENCL 38 P.
il Ik Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O.BOX 52034~PHOENIX.ARIZONA 85072-2034 JAMES M.LEVINE VICE PRESIDENT NUCLEAR PRDDVCTIDN 192-00636-JML/TRB/DAJ; Marh 2, 1990 U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sirs:
Subj ect: Palo Verde Nuclear Generating Station (PVNGS)Unit 2Docket No.STN 50-529 (License No.NPF-51)Licensee Event Report 89-005-01 File'0-020-404 Attached please find Supplement Number 1 to Licensee Event Report (LER)No.89-005-00 prepared and submitted pursuant to 10CFR50.73.
This report is being submitted to update the scheduled date for implementing a design modification.
The schedule has been revised'ue to the unavailability of parts.In accordance with 10CFR50.73(d), we are herewith forwarding a copy of the LER to the Regional Administrator of the Region V office.If you have any questions, please contact'T.R.Bradish, (Acting)Compliance Manager at (602)393-2521.Very truly yours, JML/TRB/DAJ/k)
Attachment CC: W.F~Conway E., E.Van Brunt J.B.Martin D'.H.Coe M.J.Davis A.C.Gehr INPO Records Center (all with attachment)
EF gg 9003i30597 900302 PDR ADOCK 0 000529 PDC 0
II'(C FORM~(849(U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT.ILER)APPROVED OMB NO.3(504)104 EXPIRES: 4(30(92 IMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REGUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS ANO REPORTS MANAGEMENT BRANCH (P430), U.S.NUCLEAR REGULATORY COMMISSION.
WASHINGTON.
OC 20555, AND TO THE PAPERWORK REDUCTION PROIECT (31500104).
OFFICE OF MANAGEMENT ANO BUDGFT,WASHINGTON, DC 20503.FACILITY NAME (II Palo Verde Unit 2 DOCKET NUMBER lll I'A 5 3)o so oo529>OFQ TITLE (41 Loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor EVENT DATE (5)LKR NUMBER (6)REPORT OATK (7)OTHER FACILITIES INVOLVED (5)MONTH OAY YEAR YEAR SEQUENTIAL NUMBE rl RavraroN NUMSErr MONTH OAY YEAR FACILITY NAMES N/A DOCKET NUMBFR(SI 0 5 0 0 0 0 3 1 0 8 9 8 9 ,005 0 1 0 3 0 2 9 0 N/A 0 5, 0 0 0 OPERATING MODE (9)1 POWER LEYEL 1 0 0 20.402(b)20.405(~)Oil()20A05(~)it)(B)20.405(~)l1)(E(l 20AOBla)(1)I(rl 20.405(e)lt l(r)'X 20A05(cl 50DS(a)(I I 50.35(cl(2) 50.73(~)(2)(I)50.73(el(1)
(4)50.73(a I (110((l LICENSEE CONTACT FOR THIS LER (12I 50,73(a)(2)(lrl 50.73(a)(2((el 60.73(a)(1)(rill 50.73(al(2)(air(l IA)50,73(~)(2)(r(II)(B) 50,73(~)(2((x)THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFR (): (Chrch one or morr of thr forlornnfi (1'I 73.71 Br)73.7((c).OTHER (Sprcily (n Ahrrract hrlow and In Trit, HRC Form 35EAI NAME AREA CODE TELEPHONE NUMBER Thomas R.Bradish, (Actin)Compliance Manager 6 02 39 3-25 21 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER EPORTABL'E TO NPROS XB.o r r, ic'41~c 4.v CAUSE SYSTEM'OMPONENT MANUFAC.TURER Sc 96xccT.EPORTABLE P TO NPROS+, 6 Mrr.Exk SUPPLEMENTAL REPORT EXPKCTKD l(4)MONTH OAY YEAR YES (If yrr, comoirtr EXPECTED SVEhrISSION DATEI NO EXPECTED SUBMISSION DATE HSI ABSTRACT (Limit to 1400 rprcrr, ir., roproiimrtrly fifteen u'nplr rprcr ryprrrn'ttrn linn((151 On March 10, 1989, at approximately 2200 MST, Palo Verde Unit 2 was in Mode 1 (POWER OPERATION) at approximately 100 percent power when a Ghemistry Effluent Technician (contractor, non-licensed) discovered that the Preplanned Alternate Sampling System (IL)for the Plant Ventilation was inoperable.
The circuit breaker, which supplies the electrical power (EC), had opened and deenergized the alternate system.With the alternate sampling inoperable, Unit 2 operated in a condition contrary to Technical Specification (TS)3.3.3.8.At approximately 2210 MST,, the power to the Preplanned Alternate Sampling System power was restored.No safety system responses occurred and none were necessary.
The cause of the event was electrical loads in excess of the circuit capacity resulting in the circuit breaker which supplied electrical power opening.A Design Modification has been issued to supply dedicated power to these loads..Similar events were reported in LER 529/87-14, 529/88-13, 530/88-07, and 528/89-03.
NRC F orm 355 (559)
II Ik P NRC FORM 366A~(SJ(9(ILS.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINuATION APPROVEO OMS NO.31500104 EXPIAES: 4/30/92 ESTIMATED SUAOEN PER AESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION AEQUESTI 500 HRS.FORWARD COMMENTS REGAROING SUAOEN ESTIMATE TO THE RECOROS ANO RFPORTS MANAGEMENT SRANCH (P430I, U.S.NUCLEAR REGULATORY COMMISSION/WASHINGTON.
OC 20555, ANO TO THE PAPERWORK REDUCTION PROJECT (3150410iI.
OFFICE OP MANAGEMENT ANO SUOGET,WASHINGTON, OC 20503.FACILITY NAME I'l COCKET NUMSEA (21 YEAR LER NUMSEA (Sl SEaUENTIAL NUMBER e II CV IS IO N NUMQ~Il PAGE LS)Palo Verde Unit 2 TKXT ill ma>>rl>>er*mewed.UJP PI/I/o'or>>l//RC
%%dmI 35SAS/(IT(0 S,O 0 0" 5 298'9 0 0 5 01 02 OF 0 6 I..DESCRIPTION OF WHAT OCCURRED: A.Initial Conditions:
On March,10, 1989 at approximately 2200 MST, Palo Verde Unit 2 was in Mode 1 (POWER OPERATION) at approximately 100 percent power.B.Reportable Event Description (Including Dates and Approximate Times of Major Occurrences):
Event Classification:
Condition Prohibited by the Plant's Technical Specification (TS)On March 10, 1989, at approximately 2200 MST, a Chemistry Effluent Technician (contractor, non-licensed) discovered that the Preplanned Alternate Sampling Program (PASP)(IL) for the Plant Ventilation (VL)was inoperable.
The circuit breaker, which supplies the electrical power (EC), had opened and'eenergized the alternate system.With the alternate sampling system inoperable, Unit 2 operated in a condition contrary to TS 3.3.3.8.Prior to.the event, on December 6, 1989 at approximately 0700 MST, the normal Plant Ventilation low and high range effluent monitors (RU-143 and RU-144)(IL) were decl'ared inoperable due to intermittent spiking of the low range detector (RU-143).Appropriate actions were initiated in accordance with approved procedures'he'se actions included the installation of the Preplanned Alternate Sampling System on a portable cart within one hour in accordance with TS 3.3.3.8 ACTION 37 and.40.The alternate sampling system.taps into the Plant vent and utilizes a particulate and charcoal cartri'dge for sample collection with an in-line flow gauge and sampling pump.The alternate sampling system is electrically powered from a local outlet.~Following the installation of the alternate sampling system, the process and sample flow rates were verified a minimum of every four hours pursuant to TS 3.3.3.'8 ACTION 36.On March 10, 1989, at approximately 2005 MST, a process and alternate sampling system flow check was performed.
At this time, the alternate sampling system was energized and operable.During, conduct of a PASP cart flowrate check at approximately 2200 MST, a Chemistry Technician (contractor, non-licensed) discovered that the PASP sample cart had lost power.The Chemistry Technician started a portable electric generator and restored NRC Form 366A 1669(
0 J L, NRC FOAM SSSA (889)ILS.NUCLEAR REGULATORY COMMISSION LICENSEE.EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMS NO.3)500104 EXPIRES: 8/30/92 ESTIMATED 8URDEN PEA RESPONSE TO COMPLY WTH THIS INFOAMATION COLLECTION REQUEST: SOB)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT 8RANCH IP430), U.S.NUCLEAR REGULA'TORY COMMISSION, WASHINGTON.
DC 20555, AND TO THE PAPERwoRK AEDUGTIDN PADJEGT 13)504104).
DFF)cE.OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20M3.FACILITY NAME Ill DOCKET NUMSEA 12)YEAR LER NUMSER (51 err SEQUENTIAL NUMtt R:oYg RtVdlON NUMetR PAGE ISI Palo Verde Unit 2 TEXT///more epooe ie nqcwerL rue//too'o/JVRC Form 35849/I)7),o s o o o 52 989-0 0 5 0 1 03 ot'06 power to the sample cart at approximately 2210 MST;At approximately 2220 MST, the Chemistry Technician notified the~Shift Supervisor (utility, licensed)of the loss of power to the sample cart.The Shift Supervisor dispatched an Auxilia+Operator (utility, non-licensed) to reset the electrical breaker that supplied the affected outlets;and this was accomplished at approximately 2230 MST.The Chemistry Technician then transferred the power supply back to the normal outlet.C'.Status of structures, systems, or components that were inoperable at the start of the event that contributed to the event: As stated in,Section I.B, the.Plant Ventilation Radiation Monitors, RU-143 and RU-144 were inoperable for corrective maintenance.
No other structures, system, or components were inoperable at the start of the event that contributed to the event.D.Cause of each component or system failure,, if known: Not applicable
-no component However, as stated in Section alternate sampling system was opened.or system failures were involved.I.B, electrical power to the interrupted when the circuit breaker E.Failure mode, mechanism, and effect of each failed component, if known: Not applicable
-no failures were noted.F.For failures of components with multiple functions, list of systems or secondary functions that were also affected: Not applicable
-no component failures were involved.G.For failures that rendered a train of a safety system inoperable, estimated time elapsed from the discovery of the failure until the trains were returned to, service: Not applicable
-no failures were involved.However, the alternate sampling system was discovered inoperable on March 10, 1989 at approximately 2220 MST.The alternate sampling system was made operable at approximately 2210 MST.The total elapsed time was approximately 10 minutes.N AC Forro 35SA)589)
- 0 ,J NRC FORM 366A (549)'LS.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT, IL'ER)'EXT CONTINUATION APPROVEO OMS NO.3(504104 EXPIRES: 4/30/92 ESTIMATED'SURDEN PER RESPONSE TO'COMPLY'WTH THIS INFORMATION COLLKCTION REQUEST: 500 HRS.FORWARD COMMENTS REGARDING SURDEN ESTIMATE TO THE RECORDS'ND REPORTS MANAGEMENT BRANCH (P430), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK.REDUCTION PROJECT (31504104).
OFFICE OF MANAGEMENT AND 6 UDG ET, WASHINGTON, DC 20503;FACILITY NAME (I)DOCKET NUMBER (2)LER NUMSER (6)YEAR~WC 66004NWAI.
+g r)6YISrorr rrUM66R i.NUM664 PAGE (3)Palo Verde Unit 2 o's o o,o:52 9 89-,0 05'01 0 4.QF'06'EXT lll more spece/4 reFr/'rer/
use er/r/iriorre/HRC Forrrr 3654'sl (17).H.Method'f discovery of each c'omponent or system failure or procedu'ral'rror:
r Not applicable
-no-component or system-failures or, procedural errors w'ere involved.Cause of Event: r The root cause of the event was.temporary and permanent el'ectrical loads in excess of the.circuit capac'ity.
In response.
the circuit.breaker opened and caused a loss of electrical power to: the alternate sampling system.Without electri.'cal power, the sampling pump can not draw a, sample from the Plant Ventilation.
K.Safety System Response:, Not applicable
-no safety'syste'm responses occurred'nd none were.'ecessary.
7 Failed Component Informati:on:
Not applicable
-no component failures were involved.ASSESSMENT OF THE SAFETY CONSEQUENCES AND IMPLICATIONS.
OF THIS EVENT: No adverse safety consequences or implications, resulted from this, event.The alternate system was determined to be inoperable for up to one hour and 55 minutes.Upon discovery of'he loss.of power, the"alternate sampling system power was restored within, approximately ten minutes.-The TS 3.3.3.8 ACTION 40 permits 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to install the alternate sampling system.No significant radiation levels were measured before or after'the event.III.CORRECTIVE ACTIONS A.,Immediate Power was restored to the alternate sampling, system.B.A'ction to Prevent Recurrence:
A Design Modification has been issued to supply dedicated power to the sample cart in all three units.Implementation of the design modification in Units 1,, 2, and 3 is expected by September 1990.NRC Form 366A (549) t NRC FORM 3SSA (B49)US.NUCLEAR REGULATORY COMMISSION LICENSEE EYENT REPORT ILER)TEXT CONTINUATION'PPROVED OMB NO.31504104'XPIR ESI A/30192 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION" REOVESTI 500 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS ANO,REPORTS MANAGEMENT BRANCH IP430), V.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON.
OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 13)504105).
OFFICE OF MANAGEMENT AND BUDGET,WASHINGTON.
DC 20503: FACILITY NAME (11 Palo Verde-Unit 2-'-TEXT (JF mere TP¹eo lf reeM'rfd, Ir JO eddreenar WRC Femr 3SSAYJ ()7)DOCKET NUMBER (2l YEAII o 6 o.o o 5 29 89 LER NUMBER (Sl~<>55 OUf NTIAL NUMSf R.-00 5?SE REVISION lliUMOf R-0 1 PAGE (3)05 OF 0 As interim, corrective action while awaiting the plant.change, power has been supplied to the PASP sample carts from a welding outlet to minimize the possibility of an overload condition when RU-141 (condenser Air Removal Exhaust Radiation Monitor)or RU-143 (Plant Ventilation Exhaust Radiation Monitor)are inoperable.
Additionally, when RU'-141 or RU-143 are inoperable, the PASP sample.cart is electrically powered such that a loss of this power will provide an alarm in the-Control Room;IV.PREVIOUS-SIMILAR EVENTS': Four previous events have occurred which are similar to the event: LER 529/87-014 described an event where the alternate sampling system for the Fuel Building Ventilation Radiation Monitor (RU'-145)had been turned off and rendered inoperable.
As corrective action to prevent recurrence, a placard was installed on the cart which identifies the cart as a Technical.
Specification piece of equipment.
Since the event described in this LER involves the, overloading and subsequent tripping of the power supply breaker, the corrective action described in LER 87-014 would not.have prevented the event described in this LER.2)LER'29/88-013 described an event where the.alternate sampling system for Normal Plant Ventilation Radiation Monitor (RU-143)had.been rendered inoperable.
when the circuit breaker opened.As corrective action to prevent recurrence, an Engi'neering Evaluation Request was issued to evaluate the feasibility of supplying alternate.power to the loads.This evaluation had progressed to the point of a conceptual study when this event occurred and thus, did.not pr'event the event.3)LER 530/88-007 described an event where the alternate sampling system for the Condenser Vacuum Pump/Gland Seal Exhaust'Radiation.
Monitor (RU-141)became electrically disconnected from a nearby electrical outlet and thus, rendered inoperable.
As action to'reventrecurrence, the involved individual was counseled,'additional training was performed, and enhanced labeling for the sample cart was developed.
Additionally, an evaluation was initiated to upgrade the installation of the sample cart.The evaluation discussed is part'of the conceptual'tudy discussed as corrective action in Section III.B of this LER..Installation of these upgrades would not have prevented the event described in this LER.Also, counseling, training, and'abeling would not have prevented the event discussed in this LER.N RC Fono 35SA (ILS9) il 0 NRC50RM355A (5491 (LS.NUCLEAR REGULATORY.
COMMISSION LICENSEE EVENT REPORT (LER)'EXT CONTINUATION APPROVED OMB NO.3150d104'XP(RES:
e/30192-.ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH'THIS INFORMATION COLLECTION REQUEST: 50AI HRS.FORWARD COMMENTS REGAROINQ BURDEN ESTIMATE TO THE RECORDS ANO REPORTS MANAGEMENT BRANCH (P-5301, U.S.NUCLEAR REGULATORY COMMISSION.
WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3(5001041, OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAMC (11 DOCKET NUMBER (2)(.ER NUMBER (51 YEAR rg@CCQVCNTIAI, jj%RCVNKIN NVMSCR 5 NVMCCR PAGE (31'alo Verde Unit 2 TEXT (if move epeoe ie eovvv'ved, we edve'v(ovve(NRC Fomv 36SASU (IT(o-s o o o 52 9 89-00 5-01 0 6 o" 0-6 4)LER 528/89-003 described'n event where the alternate sampling system for the Fuel Building Exhaust Radiation Monitor (RU-145)became.inoperable when the circuit breaker opened.As corrective action to prevent recurrence, a Design Modification had been issued to supply dedicated power so the sample care.Implementation of'his-change is expected by September 1990.Since this change has not been installed in the unit, it.did not prevent this event.NRC Fovm 355A (5091 0 Ik