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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B1111997-11-10010 November 1997 LER 97-011-00:on 971010,HPCS Battery Charger Failed.Caused by Failure of a Phase Firing Control Circuit Board Due to Aging During 7 Yrs of Use.Hpcs Sys Was Immediately Declared inoperable.W/971110 Ltr ML17292B1151997-11-0707 November 1997 LER 97-010-00:on 970906,discovered That TS SR 3.4.5.1 for Identified Portion of RCS Total Leakage Would Not Be Able to Perform within Time Limits of SR 3.0.2.Caused by Inadequate Methods.Method of Meeting SR 3.4.5.1 Established ML17292B0641997-09-24024 September 1997 LER 97-004-01:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Indication of Entry Into Region a of power-to-flow Map.Caused by Inadequate Attention to Detail.Established Event Evaluation teams.W/970924 Ltr ML17292B0241997-08-18018 August 1997 LER 97-009-00:on 970717,discovered Error in Recently Performed Inservice Testing procedure,OSP-TIP/IST-R701. Caused by Procedure Inadequacy.Plant Procedure OSP/TIP/IST-R701 Will Be changed.W/970818 Ltr ML17292B0291997-08-15015 August 1997 LER 97-008-00:on 970716,wire Seal Used to Lock Containment Instrument Air Pressure Control valve,CIA-PCV-2B,found Not Intact.Cause of Misadjustment of CIA-PCV-2B Unknown.Event Will Be Communicated to Plant employees.W/970815 Ltr ML17292B0201997-08-15015 August 1997 LER 97-S01-00:on 970718,failure to Take Compensatory Measure for Inoperative Microwave Security Zone Occurred. Caused by Personnel Error.Training Will Be Conducted W/ Appropriate Members of Security force.W/970815 Ltr ML17292A9481997-07-23023 July 1997 LER 97-007-00:on 970611,voluntary Rept of Automatic Start of DG-1 & DG-2 Was Experienced.Caused by Undervoltage Condition on Electrical Busses SM-7 & SM-8.Circulating Water Pump CW-P-1C Control Switch Placed in pull-to-lock.W/970723 Ltr ML17292A9201997-06-26026 June 1997 LER 97-006-00:on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for SP.W/970626 Ltr ML17292A8331997-04-28028 April 1997 LER 97-004-00:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Entry Into Region a of power-to-flow Map Following Planned Trip of Single Mfp. Event Evaluation teams,established.W/970428 Ltr ML17292A8311997-04-28028 April 1997 LER 97-005-00:on 970327,valid Reactor Scram Signal Received Due to Low Water Level Condition During Preparations for SRV Testing.Caused by Risks & Consequences of Decisions Not Completely Identified.Restored Water level.W/970428 Ltr ML17292A8251997-04-21021 April 1997 LER 97-003-00:on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time exemption.W/970421 Ltr ML17292A7431997-03-20020 March 1997 LER 97-002-00:on 970218,determined That Rod Block Monitor (RBM) Calibr Values Were Not Set IAW Tech Specs.Caused by Calibr Procedures Inadequacies.Revised & re-performed RBM Channel Calibr procedures.W/970330 Ltr ML17292A7401997-03-13013 March 1997 LER 97-001-00:on 970211,reactor Water Cleanup Sys Blowdown Flow Isolation Setpoint Was Slightly Above TS Allowable Valve Occurred Due to Calculation Error.Lds Fss LD-FS-15 LD-FS-16 Were Declared inoperable.W/970313 Ltr ML17292A6641997-01-22022 January 1997 LER 96-009-00:on 961220,miscalculation of Instantaneous Overcurrent Relay Settings Resulted in Inoperability of safety-related Equipment.Caused by Utilization of Inappropriate Design.Testing Was completed.W/970122 Ltr ML17292A6461997-01-0606 January 1997 LER 96-008-00:on 961205,failure to Comply with TS Action Requirement for Emergency Core Cooling Sys Actuation Instrumentation Occurred Due to Unidentified Inoperability Condition.Pmr initiated.W/970106 Ltr ML17292A6371996-12-19019 December 1996 LER 96-007-00:on 961122,electrical Breakers Were Not Seismically Qualified in Test/Disconnect Position.Circuit Breaker Mfg Did Not Consider Raced Out Breaker Position During Testing.Relocated Circuit breakers.W/961217 Ltr ML17292A4121996-08-0808 August 1996 LER 96-006-00:on 960709,average Power Range Monitor Rod Block Downscale Surveillance Not Performed Prior to Entry Into Mode 1.Caused by long-standing Misinterpretation of Requirements of Tss.Procedures revised.W/960808 Ltr ML17292A3801996-07-24024 July 1996 LER 96-004-00:on 960624,plant Was Manually Scrammed by Control Room Personnel Due to Reactor Water Level Transient Experienced During Testing of Digital Feedwater Sys.Caused by Programming Error.Sys Was corrected.W/960724 Ltr ML17292A3771996-07-24024 July 1996 LER 96-005-00:on 960624,determined Missed Surveillance Test Re Channel Check of Average Power Range Monitor.Caused by Inadequate Procedures.Revised Surveillance Procedure Re When APRM Checks Must Be performed.W/960724 Ltr ML17292A3641996-07-12012 July 1996 LER 96-003-00:on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures revised.W/960712 Ltr ML17292A3361996-06-20020 June 1996 LER 96-002-00:on 960504,critical Bus SM-8 Lost Power When Supply Breaker 3-8 Tripped.Caused by Personnel Error. Operators Counselled & Procedures revised.W/960620 Ltr ML17292A2861996-05-24024 May 1996 LER 96-001-00:on 960425,inadvertent ESF Actuations Occurred Due to Tripping of Temporary Power Supply to IN-3.Caused by Personnel Error.Operations Restored to IN-3 Loads & Reset ESF actuations.W/960524 Ltr ML17291B0891995-10-19019 October 1995 LER 95-011-00:on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct deficiency.W/951019 Ltr ML17291A9021995-07-0707 July 1995 LER 95-010-00:on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures written.W/950707 Ltr ML17291A9031995-07-0707 July 1995 LER 95-009-00:on 950607,inadvertent MSIV Closure Occurred During Surveillance Test Due to Poor Communication Between Test Team.Determined That MSIV Closure Not Valid Because Closure Not Triggered by Plant conditions.W/950707 Ltr ML17291A8501995-06-0808 June 1995 LER 95-006-01:on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup ML17291A8101995-05-12012 May 1995 LER 95-008-00:on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl clarity.W/950512 Ltr ML17291A7841995-05-0505 May 1995 LER 95-007-00:on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid ML17291A7801995-05-0404 May 1995 LER 95-006-00:on 950405,main Turbine Trip Occurred During Performance of Surveillance Test Due to Protective Sys Relay Failed.Replaced Failed Relay Before Plant startup.W/950504 Ltr ML17291A7851995-05-0303 May 1995 LER 95-005-00:on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be incorporated.W/950503 Ltr ML17291A7071995-03-25025 March 1995 LER 95-004-00:on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card replaced.W/950325 Ltr ML17291A7011995-03-20020 March 1995 LER 95-002-00:on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control repositioned.W/950320 Ltr 1999-07-20
[Table view] Category:RO)
MONTHYEARML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B1111997-11-10010 November 1997 LER 97-011-00:on 971010,HPCS Battery Charger Failed.Caused by Failure of a Phase Firing Control Circuit Board Due to Aging During 7 Yrs of Use.Hpcs Sys Was Immediately Declared inoperable.W/971110 Ltr ML17292B1151997-11-0707 November 1997 LER 97-010-00:on 970906,discovered That TS SR 3.4.5.1 for Identified Portion of RCS Total Leakage Would Not Be Able to Perform within Time Limits of SR 3.0.2.Caused by Inadequate Methods.Method of Meeting SR 3.4.5.1 Established ML17292B0641997-09-24024 September 1997 LER 97-004-01:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Indication of Entry Into Region a of power-to-flow Map.Caused by Inadequate Attention to Detail.Established Event Evaluation teams.W/970924 Ltr ML17292B0241997-08-18018 August 1997 LER 97-009-00:on 970717,discovered Error in Recently Performed Inservice Testing procedure,OSP-TIP/IST-R701. Caused by Procedure Inadequacy.Plant Procedure OSP/TIP/IST-R701 Will Be changed.W/970818 Ltr ML17292B0291997-08-15015 August 1997 LER 97-008-00:on 970716,wire Seal Used to Lock Containment Instrument Air Pressure Control valve,CIA-PCV-2B,found Not Intact.Cause of Misadjustment of CIA-PCV-2B Unknown.Event Will Be Communicated to Plant employees.W/970815 Ltr ML17292B0201997-08-15015 August 1997 LER 97-S01-00:on 970718,failure to Take Compensatory Measure for Inoperative Microwave Security Zone Occurred. Caused by Personnel Error.Training Will Be Conducted W/ Appropriate Members of Security force.W/970815 Ltr ML17292A9481997-07-23023 July 1997 LER 97-007-00:on 970611,voluntary Rept of Automatic Start of DG-1 & DG-2 Was Experienced.Caused by Undervoltage Condition on Electrical Busses SM-7 & SM-8.Circulating Water Pump CW-P-1C Control Switch Placed in pull-to-lock.W/970723 Ltr ML17292A9201997-06-26026 June 1997 LER 97-006-00:on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for SP.W/970626 Ltr ML17292A8331997-04-28028 April 1997 LER 97-004-00:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Entry Into Region a of power-to-flow Map Following Planned Trip of Single Mfp. Event Evaluation teams,established.W/970428 Ltr ML17292A8311997-04-28028 April 1997 LER 97-005-00:on 970327,valid Reactor Scram Signal Received Due to Low Water Level Condition During Preparations for SRV Testing.Caused by Risks & Consequences of Decisions Not Completely Identified.Restored Water level.W/970428 Ltr ML17292A8251997-04-21021 April 1997 LER 97-003-00:on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time exemption.W/970421 Ltr ML17292A7431997-03-20020 March 1997 LER 97-002-00:on 970218,determined That Rod Block Monitor (RBM) Calibr Values Were Not Set IAW Tech Specs.Caused by Calibr Procedures Inadequacies.Revised & re-performed RBM Channel Calibr procedures.W/970330 Ltr ML17292A7401997-03-13013 March 1997 LER 97-001-00:on 970211,reactor Water Cleanup Sys Blowdown Flow Isolation Setpoint Was Slightly Above TS Allowable Valve Occurred Due to Calculation Error.Lds Fss LD-FS-15 LD-FS-16 Were Declared inoperable.W/970313 Ltr ML17292A6641997-01-22022 January 1997 LER 96-009-00:on 961220,miscalculation of Instantaneous Overcurrent Relay Settings Resulted in Inoperability of safety-related Equipment.Caused by Utilization of Inappropriate Design.Testing Was completed.W/970122 Ltr ML17292A6461997-01-0606 January 1997 LER 96-008-00:on 961205,failure to Comply with TS Action Requirement for Emergency Core Cooling Sys Actuation Instrumentation Occurred Due to Unidentified Inoperability Condition.Pmr initiated.W/970106 Ltr ML17292A6371996-12-19019 December 1996 LER 96-007-00:on 961122,electrical Breakers Were Not Seismically Qualified in Test/Disconnect Position.Circuit Breaker Mfg Did Not Consider Raced Out Breaker Position During Testing.Relocated Circuit breakers.W/961217 Ltr ML17292A4121996-08-0808 August 1996 LER 96-006-00:on 960709,average Power Range Monitor Rod Block Downscale Surveillance Not Performed Prior to Entry Into Mode 1.Caused by long-standing Misinterpretation of Requirements of Tss.Procedures revised.W/960808 Ltr ML17292A3801996-07-24024 July 1996 LER 96-004-00:on 960624,plant Was Manually Scrammed by Control Room Personnel Due to Reactor Water Level Transient Experienced During Testing of Digital Feedwater Sys.Caused by Programming Error.Sys Was corrected.W/960724 Ltr ML17292A3771996-07-24024 July 1996 LER 96-005-00:on 960624,determined Missed Surveillance Test Re Channel Check of Average Power Range Monitor.Caused by Inadequate Procedures.Revised Surveillance Procedure Re When APRM Checks Must Be performed.W/960724 Ltr ML17292A3641996-07-12012 July 1996 LER 96-003-00:on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures revised.W/960712 Ltr ML17292A3361996-06-20020 June 1996 LER 96-002-00:on 960504,critical Bus SM-8 Lost Power When Supply Breaker 3-8 Tripped.Caused by Personnel Error. Operators Counselled & Procedures revised.W/960620 Ltr ML17292A2861996-05-24024 May 1996 LER 96-001-00:on 960425,inadvertent ESF Actuations Occurred Due to Tripping of Temporary Power Supply to IN-3.Caused by Personnel Error.Operations Restored to IN-3 Loads & Reset ESF actuations.W/960524 Ltr ML17291B0891995-10-19019 October 1995 LER 95-011-00:on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct deficiency.W/951019 Ltr ML17291A9021995-07-0707 July 1995 LER 95-010-00:on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures written.W/950707 Ltr ML17291A9031995-07-0707 July 1995 LER 95-009-00:on 950607,inadvertent MSIV Closure Occurred During Surveillance Test Due to Poor Communication Between Test Team.Determined That MSIV Closure Not Valid Because Closure Not Triggered by Plant conditions.W/950707 Ltr ML17291A8501995-06-0808 June 1995 LER 95-006-01:on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup ML17291A8101995-05-12012 May 1995 LER 95-008-00:on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl clarity.W/950512 Ltr ML17291A7841995-05-0505 May 1995 LER 95-007-00:on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid ML17291A7801995-05-0404 May 1995 LER 95-006-00:on 950405,main Turbine Trip Occurred During Performance of Surveillance Test Due to Protective Sys Relay Failed.Replaced Failed Relay Before Plant startup.W/950504 Ltr ML17291A7851995-05-0303 May 1995 LER 95-005-00:on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be incorporated.W/950503 Ltr ML17291A7071995-03-25025 March 1995 LER 95-004-00:on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card replaced.W/950325 Ltr ML17291A7011995-03-20020 March 1995 LER 95-002-00:on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control repositioned.W/950320 Ltr 1999-07-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999 LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr ML17292B5571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With 990210 Ltr ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error ML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML17292B4791998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr ML17292B5741998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with 990225 Ltr ML17284A8231998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7831998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for WNP-2.With 981007 Ltr ML17284A7491998-09-10010 September 1998 WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998. ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7681998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for WNP-2.With 980915 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for WNP-2.W/980810 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6751998-06-30030 June 1998 Ro:On 980617,flooding of RB Northeast Stairwell with Consequential Flooding of Two ECCS Pump Rooms.Caused by Inadequate Fire Protection Sys Design.Pumped Out Water from Affected Areas to Point Below Berm Areas of Pump Rooms ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17284A6491998-05-31031 May 1998 Rev 0 to COLR 98-14, WNP-2,Cycle 14 Colr. ML17292B4031998-05-31031 May 1998 Monthly Operating Rept for May 1998 for WNP-2.W/980608 Ltr ML17292B3921998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for WNP-2.W/980513 Ltr ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3371998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for WNP-2.W/980409 Ltr ML17292B2641998-03-0404 March 1998 Performance Self Assessment,WNP-2. ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B2911998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for WNP-2.W/980313 Ltr ML17284A7971998-02-17017 February 1998 Rev 28 to Operational QA Program Description, WPPSS-QA-004.With Proposed Rev 29 ML17292B3591998-02-12012 February 1998 WNP-2 Cycle 14 Reload Design Rept. 1999-09-30
[Table view] |
Text
~CCei~~~reu Sra~aurrOX DZVrOrgmmIOX SVSTiM REGULATO Y INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9212010342 DOC.DATE: 92/11/25 'OTARIZED: NO DOCKET
. FACIL:5()-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397
"'AUTH.NAME AUTHOR AFFILIATION FULLER,R.E. Washington Public Power Supply System BAKER,J.W. 'ashington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 92-041-00:on 921027,determined that past low grid voltage conditions caused offsite power source to be inoperable. Caused by inaccurate procedures.TS procedure have been changed to incorporate offsite power.W/921125 -ltr.
DISTRIBUTION CODE: ZE22T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 CLIFFORD,J 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 NRR/D9TQSPLB8D1 1 1 NRR/DST/SRXB 8E 1 1 qjgG-QQ> 02 1 1 RES/DSZR/EIB 1 1 hGN5 FILE Ol 1 1 EXTERNAL: EG&G BRYCEiJ.H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHYiG.A 1 1 NSIC POOREgW 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL RIDS RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.
ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31
I ai WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 November 25, 1992 G02-92-0259 Docket No. 50-397 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 LICENSEE EVENT REPORT NO.92-041 Transmitted herewith is Licensee Event Report No.92-041 for the WNP-2 Plant. This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of repoitability, corrective action taken, and action taken to preclude recurrence.
Sincerely,
. W. Baker WNP-2 Plant Manager (Mail Drop 927M)
JWB/REF/lr Enclosure CC: Mr. J. B. Martin, NRC - Region V Mr. W. Ang, NRC Resident Inspector (Mail Drop 901A, 2 Copies)
INPO Records Center - Atlanta, GA Mr. D. L. Williams, BPA (Mail Drop 399)
UwVVd.a 9212010342 921125 PDR ADOCK 05000397
LICENSEE EVE REPORT (LER)
AGILITY NAME (1) DOCKET NUHB R ( ) PAGE (3 Washln ton Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 I DF 7 ITLE (4)
PAST LOW 230KV GRID VOLTAGE CONDITIONS CAUSED THE OFFSITE POWER SOURCE TO BE INOPERABLE MULTIPLETIMES EVENT DATE (5 LER NUHBER REPORT DATE 7 OTHER FACILITIES INVOLVED 8 HONTH DAY YEAR YEAR SEQUENTIAL EVI SION HOHTH DAY YEAR FACILITY HAHES KET NUHB RS(5)
'd NUHBER UHBER 5 0 I 0 2 7 9 2 0 4 1 0 0 I I 2 5 9 2 5 0 P ERAT ING HIS REPORT IS SUBHITTED PURSUANT TO THE REOUIREHEHTS OF 10 CFR 5: (Check one or more of the following) (11 ODE (9) I ONER LEVEL 0.402(b) 0.405(C) 0.73(a)(2)(iv) 7.71(b)
(10) 0.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.73(c) 0.405(a)(1)(ii) 0.36(c) (2) 0.73(a (2)(vii) THER (Specify in Abstract 0.405(a)(1)(iii) X 0.73(a) (2)(i) 50.73(a)(2)(viii)(A) elow and in Text, NRC 0.405(a)(1)(iv) 0.73(a) (2)(ii) 0.73(a)(2)(viii)(B) ore 366A) 20.405(a)(1)(v) 50 '3(a (2)(iii) 50.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER (12)
AHE TELEPHONE NUHBER REA CODE R.E. Fuller, Licensing Engineer -
5 0 9 7 7 4 1 4 8 COHPLETE OHE LINE FOR EACH COHPOHEHT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEH COHPOHENT HAHUFACTURER EPORTABLE CAUSE SYSTEH COHPONENT HANUFACTURER EPORTABLE 0 NPRDS TO NPRDS SUPPLEHENTAL REPORT EXPECTED (14) EXPECTED SUBHISSION HOHTH DAY YEAR ATE (15)
YES (If yes, conqiete EXPECTED SUBMISSION DATE) NO TllAc1 nb)
On October 27, 1992, a System Engineer determined that, due to past low grid voltage conditions, one offsite power source would have been unable to operate the design basis loads from that source. During specific periods of low voltage conditions, the offsite power source should have been considered inoperable and the appropriate Technical Specification Action Statement (TSAS) entered.
No immediate corrective actions were required because the current offsite grid voltages were well above the minimum acceptable values.
The root causes of the TS violations were inaccurate procedures, equipment limitations, and less than adequate management methods to ensure use of a correct low grid voltage acceptance criteria to determine the availability of the offsite power sources.
The corrective actions taken include changing the surveillance procedure to incorporate the correct minimum acceptable grid voltages and provide continuous monitoring of the offsite power sources.
Further corrective actions include formalizing the process for the development of TS surveillance acceptance criteria and installing Control Room alarms for low grid voltage conditions.
The safety significance of this condition is negligible. The probability of design basis conditions occurring coincident with the periods of low grid voltage is extremely low. This condition posed no threat to the health and safety of Plant personnel or the public.
LICENSEE EVENT REPORT ( ER)
TEXT CONTINUATION AGILITY HAHE (1) OOCKET NUMBER (2) LER NUMBER (8) AGE (3) ear utaber ev. No.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 2 4 1 0 2 F 7 ITLE (4)
PAST LOW 230KV GRID VOLTAGE CONDITIONS CAUSED THE OFFSITE POWER SOURCE TO BE INOPERABLE MULTIPLE TIMES n ii'n Power Level - 100%
Plant Mode - 1 (Power Operation) ven De ri in On October 27, 1992, a System Engineer determined that, due to past low grid voltage conditions, the Startup transformer (TR-S) would have been unable to operate the design basis loads. The unacceptable low voltage conditions occurred three times during 1988 and twice during 1990. During the period of low voltage conditions, TR-S should have been considered inoperable and the appropriate Technical Specification Action Statement (TSAS) entered.
WNP-2 has two independent offsite power circuits. They consist of a 230KV line supplied from the Bonneville Pow'er Administration (BPA) Ashe substation to TR-S and a 115KV line supplied from Benton substation to the WNP-2 backup transformer (TR-B).
During the Electrical Distribution System Functional Inspection (EDSFI) in March 1992, the System Engineer provided the NRC with five years of voltage data for 230KV offsite power source per their request. The NRC reviewed 2 years of the data and identified a minimum low voltage condition of 228KV. This was satisfactory to the inspectors and no further action was required. However, in parallel, the System Engineer independently reviewed the five years of data dating from July 1987 to January 1992.
The data indicated one instance when grid voltage had dropped to 226KV while the Plant.was shutdown.
The minimum acceptable grid voltage at that time was 226,2KV. Since only one offsite power source is required by Technical Specifications (TS), the identified low voltage condition did not represent a TS violation. However, the System Engineer alerted BPA that they could cause WNP-2 to shutdown by allowing the grid voltage to drop below the minimum acceptable value. In August 1992, the degraded voltage relay setpoint calculations were revised. In October 1992, the System Engineer realized that the revised calculations implied the minimum acceptable 230KV grid voltage was 230KV and not 226.2KV.
The implication was that the grid voltage had to be above the corresponding degraded voltage relay maximum reset value to assure availability of the offsite source. Based upon the earlier review of the grid voltage history, the System Engineer initiated a Problem Evaluation Request (PER) to document the discrepancy. After initiating the PER, the System Engineer reviewed the grid voltage history again and determined that the 230KV source had dropped below 230KV a total of 23 times between 1987 and 1991.
The low voltage conditions occurred during the July and August time frame, when the summer peak loads occur.
LICENSEE EVENT REPORT {LER)
TEXT CONTINUATION ACTLTTY NAHE (1) OOCKET NUHBER (2) LER NUHBER (B) AGE (3) umber ev. No.
Washington Nuclear Plant - Unit 2 2 4 1 0 3 F 7 ITLE (4)
PAST LOW 230KV GRID VOLTAGE CONDITIONS CAUSED THE OFFSITE POWER SOURCE TO BE INOPERABLE MULTIPLE TINES From surveillance data, the System Engineer determined the actual reset values of the degraded voltage relays for the 23 low voltage periods. Out of the 23 low voltage periods, the System Engineer identified five times during Plant operation when two offsite power sources were required to be operable and the supply voltag'e to TR-S was below the minimum operable voltage. Had the design basis loads sequenced onto TR-S, the degraded voltage relays would have tripped and not reset. This would have'resulted in a transfer of the loads to the backup source for Divisions 1 and 2 and the respective diesel-generator (DG) for the High Pressure Core Spray (HPCS) System. The low voltage conditions occurred on July 21, August 23 and August 24, 1988 for 2, 6 and 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, respectively, and August 6 and August 9, 1990 for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> each.
mmediate orr iv A i n No immediate corrective actions were identified. The minimum acceptable grid voltage values for, TR-S and TR-B are 230KV and 111.3KV, respectively. The supply voltages to TR-S and TR-B were well above the minimum acceptable values and the season for peak demand had past when the low grid voltage conditions to TR-S were identified as having occurred. Therefore, WNP-2 is currently in compliance with the Technical Specifications (TS).
Furth r Ev I ion n rrec ive A i n
'A. ~EA E I. This event is considered reportable per 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the Plant's Technical Specifications. The Plant Technical Specification Section 3.8.1.1 requires "As a minimum, the following A.C. electrical power sources shall be OPERABLE: a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system..."
The current draw from starting the design basis loads could cause the bus voltage to drop below the dropout trip point of the degraded bus voltage relays. A degraded voltage relay trip initiates an 8-second time delay timer. As the sequenced motor accelerates, the voltage will recover. If the bus voltage has not been restored -to or above the reset voltage trip point within 8 seconds, which is higher than the dropout trip point, the bus loads are transferred to the alternate supply (TR-B, if available, or Division 1 and 2 DGs, and the Division 3 HPCS DG). The grid voltage to TR-S during the five low voltage periods described above corresponded to bus voltages that would have been below the actual reset voltage value for the degraded bus voltage relays with all design basis loads operating. Therefore, the TR-S offsite power source is considered to have been inoperable during these periods because the degraded voltage relays would not have reset to support design basis loads.
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION ACILITY RANE (i) OOCKET NUNBER (2) LER NUNBER (8) AGE (3) ear umber ev. No.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 4 1 4 F 7 ITLE (4)
PAST LOW 230KV GRID VOLTAGE CONDITIONS CAUSED THE OFFSITE POWER SOURCE TO BE INOPERABLE MULTIPLE TINES The TSAS was not entered during any of the above described low voltage periods as required by the TS. The voltage was never measured below 230KV for TR-S during performance of the TS surveillance procedure, PPM 7.4.8.1.1.1.1. Plant personnel were unaware of the low voltage conditions because the'TS requires the offsite power-sources to be monitored only once per seven days. This is too infrequent to detect the low voltage conditions. There is no other Plant procedure that requires more frequent monitoring of the offsite power sources. Although there is a voltmeter for each offsite source in the Control Room, there is no alarm function provided if it goes below the minimum acceptable value. In addition, the accuracy and resolution of the existing voltmeter does not allow for this measurement.
Prior to June 1991, the acceptance criteria for operability of the offsite power sources in PPM 7.4.8.1.1.1.1 had been inappropriately based on whether the grid was energized or not. Operability of an offsite power source cannot be established without a minimum acceptable voltage criteria. It had been assumed that BPA would maintain the grid voltage at the levels advertised in their annual voltage schedule. This did not occur. This deficiency in prior revisions to the surveillance procedure was first identified during the root cause evaluation of this LER.
In May 1991, a Plant Operations Engineer requested that the System Engineer determine the minimum acceptable grid voltage for TR-S and TR-B for inclusion in the above procedure. Based on an informal evaluation by the Design Engineer, the minimum supply voltage acceptance criteria for operability of TR-S was determined to be 226.2KV. This value inappropriately corresponded to the degraded voltage relay minimum analytical dropout setpoint value. This acceptance criteria was included in the June 1991 revision (Revision 6) of PPM 7.4.8.1.1.1.1.
The degraded voltage relay setpoint calculations were revised in August 1992. The revised calculations changed the dropout setpoints. The Design Engineer reviewed the evaluation for the minimum grid voltage acceptance criteria of 226.2KV. The Design Engineer determined the minimum acceptable grid voltage criteria established in June 1991 was inappropriately based on the degraded voltage relay minimum analytical dropout setpoint value. The relay dropout trip point will normally be reached on a motor start. However, the steady-state bus voltage must return, with all design basis loads operating, to a value higher than the maximum reset trip point to ensure an inadvertent transfer to the alternate source does not occur. Therefore, the minimum acceptable grid voltage should have been based on the degraded voltage relay maximum reset voltage trip point.
- 2. A preliminary evaluation determined the root causes of the TS violations were: 1) inaccurate procedures, 2) equipment limitations, and 3) less than adequate management methods. With respect to the first root cause, early revisions of the surveillance procedure were inaccurate because they did not contain adequately specified acceptance criteria to detect an inoperable condition of the offsite power sources. For the second root cause, equipment limitations did not allow continuous monitoring of the grid voltage nor,was the accuracy and resolution of the instrumentation adequate
LICENSEE EVENT REPORT ER)
TEXT CONTINUATION AGILITY HAHE (1) DOCKET KUHBER (2) LER HUHBER (8) AGE (3) ear umber ev. Ko.
Washington Nuc1ear P'lant - Unit 2
'I 0 5 0 0 0 3 9 4 1 5 F 7 ITLE (4)
PAST LOW 230KV GRID VOLTAGE CONDITIONS CAUSED THE OFFSITE POWER SOURCE TO BE INOPERABLE MULTIPLE TIMES to measure the grid voltage. Therefore, periods of potentially inoperable conditions went undetected between surveillance periods. The third root cause was use of an incorrect and non-conservative minimum acceptable grid voltage value for TR-S in the surveillance procedure. The criteria may have allowed an inoperable condition to be accepted had low voltage conditions been observed.
Less than adequate management methods did not provide a formalized process to ensure all acceptance criteria in TS surveillance procedures were based on a referenceable document. The informal evaluation lacked a clear description of the purpose for the evaluation, documentation of the assumptions made in the evaluation, and an independent peer review. Incorporation of one or more of these elements of a formal evaluation could have precluded use of an incorrect and nonconservative acceptance criteria.
- 3. A review was performed of the instrumentation used in the above TS surveillance procedure to measure the voltage of the respective offsite power sources. The results indicated that the accuracy of the Control Room metering for the 230KV grid is inadequate to assure the operability of the offsite power source.
- 4. There were no other structures, components, or systems inoperable prior to the event which contributed to the event. In addition, five years of data for the 115KV system were examined and the grid voltage to TR-B was found to have been above the minimum acceptable value when TR-B was considered operable, Also, the data indicated that grid voltage fluctuations to TR-B were not sensitive to seasonal peak demands. Therefore, it is believed that there were no inoperable periods of low voltage conditions to TR-B and no further investigations were performed in this area.
B. F rther rr tive Ac i n T ken
- 1. The TS surveillance procedure PPM 7.4,8.1.1.1.1 has been changed to incorporate the correct acceptance criteria for operability of the two offsite power sources.
- 2. An agreement has been made between the Supply System and BPA for the appropriate BPA load dispatcher to immediately notify the WNP-2 Control Room if the grid voltage to either TR-S or TR-B goes below the minimum allowable values of 232KV and 112KV, respectively. These values was based upon a 1% accuracy error of the instrumentation used to monitor the grid voltage.
- 3. The TS surveillance procedure PPM 7.4.8.1.1.1.1 has been changed to require the voltage readings
. for the'offsite power sources be obtained from more accurate voltmeters at BPA.
- 4. The Engineering Department has implemented a formal process by which responses to Operations requests will be referenceable.
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION AC1LITY NAHE (1) OOCKET NUHBER (2) LER NUHBER (8) AGE (3) ear umber ev. No.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 0 7 2 4 1 0 6 F 7 1TLE (4)
PAST LOW 230KV GRID VOLTAGE CONDITIONS CAUSED THE OFFSITE POWER SOURCE TO BE INOPERABLE MULTIPLE TIMES
- 5. The Technical Specification Improvement Project will review TS surveillance acceptance criteria for a referenceable technical bases. A,technical basis will be identified or developed for those criteria identified as having no technical bases.
C. F her rr iveA i n I. The root cause analysis will be completed, and, if there is a significant change in the root causes or corrective actions planned to be taken, a supplemental LER will be submitted by December 27, 1992.
- 2. Plant procedure PPM 1.5.1, Technical Specification Surveillance Testing Program, will be changed by December 31, 1992 to require a referenceable technical bases for all future new or revised acceptance criteria used in TS surveillance procedures.
- 3. A microwave alarm system from the Ashe Substation will be installed by June 1, 1993 to provide Control Room annunciation of a low grid voltage condition to TR-S.
- 4. The Supply System and BPA will develop an agreement on an acceptable voltage schedule to minimize the occurrence of unacceptable low grid voltages.
~fi ~
There is no safety significance associated with this condition. The backup offsite power source, TR-B, was
'always available during the low grid voltage periods to TR-S. The TS requires the HPCS DG to be operable when HPCS is required to be operable. Also, TR-S would have still remained available for use if the loads had been transferred to TR-B. Transfer would have occurred as a result of load starting. Once
,the loads were started, the Reactor Operators could have transferred the loads back to TR-S. In addition, a transfer during the low grid voltage conditions would have only occurred in response to a LOCA, which results in the highest load demand on TR-S. The probability of a LOCA occurring during one of the five low voltage periods is negligibly small. This condition posed no threat to the health and safety of Plant personnel or the public.
imilar Events LER 85r63 documents a momentary fault on the grid feeding TR-S on December 7, 1985 when TR-S was supplying power to the Class 1E buses. The low grid voltage condition caused primary undervoltage relays on the buses to trip which caused the Division 1 and 2 diesel-generators to automatically start. However, there is a 2 second time delay initiated by the primary undervoltage relay before the transfer to an alternate source is made. Since the fault was momentary, the 2-second timer had not timed out before the voltage was restored and a transfer of the loads to the backup transformer, TR-B, did not occur. This event differs
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION AGILITY IIAHE (I) 00CKET HINBER (2) LER NUMBER (8) AGE (3) ear umber ev. IIo.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 4 I 7 F 7 ITLE (4)
PAST LOW 230KY GRID YOLTAGE CONDITIONS CAUSED THE OFFSITE POWER SOURCE TO BE INOPERABLE MULTIPLE TINES from the low grid voltage conditions described above in that TR-S was in standby and was not supplying power to the Class 1E buses. Also, the event described in LER 85-63 involved the primary undervoltage relays as opposed to the degraded voltage relays. In addition, the degraded voltage relays would not have tripped at the low grid voltage conditions under non-LOCA conditions because the bus voltages would have remained above the maximum dropout trip point.
E~ff T f f system Q~m~nn Annunciator System IB Plant AC Distribution System EA Class 1E Power System EB (Degraded Voltage and Undervoltage Relay)
High Pressure Core Spray System BG Emergency Power For HPCS EK