|
---|
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
ACCEIERA D DOCUMENT DIST VTION SYSTEM REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION 5BR:9301040268 DOC.DATE: 92/12/28 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION POCHE,R.J. Washington Public Power Supply System BAKERFJ.W. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 92-041-01:on 921027,offsite power source determined inoperable during brief periods of prior operaton due to low voltage condition on 230KV grid. Caused by design deficiency 6 inadequate mgt methods.TS procedure changed.W/921228 ltr.
DISTRIBUTION CODE: ZE22T COPIES RECEIVED!LTR 3 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- DST/8 B8D1 1 1 NRR/DST/SRXB 8E 1 1 EG F LE 02 1 1 RES/DSIR/EIB 1 1 ILE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 2 2 L ST LOBBY WARD 1 1 NSIC MURPHYFG.A NRC PDR 1 1 1 NSIC POOREFW. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACI'HE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 PP
ti WASHINGTON PUBLIC, POWER SUPPLY SYSTEM F.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 December 28, 1992 G02-92-273 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. 92-041-01 Transmitted herewith is Licensee Event Report No. 92-041-01 for the WNP-2 Plant. This report is submitted in response to the report requirements of '10CFR 50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence. This supplement reflects final results and conclusions from the root cause analysis of this event.
'Sincerely, J. W. Baker
-2 Plant Manager (Mail Drop 927M)
JWB/REF/lr Enclosure CC: Mr. J. B. Martin, NRC - Region V Mr. R. Barr, NRC Resident Inspector (Mail Drop 901A, 2 Copies)
INPO Records Center - Atlanta, GA Mr. D. L. Williams, BPA (Mail Drop 399) 9'301040268 921228 PDR ADOCK 05000397 S PDR
LICENSEE EVE% REPORT (LER)
AGILITY NAHE (I) DOCKET UHB R ( ) AGE (3)
Washin ton Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 I DF ITLE (4)
OFFSITE POWER SOURCE INOPERABLE DURING SEVERAL BRIEF PERIODS OF PRIOR OPERATION DUE TO LOW VOLTAGE CONDITION ON THE 230KV GRID EVENT DATE 5) LER NUHBER 6) REPORT DATE 7 OTHER FACILITIES INVOLVED 8 MONTH DAY YEAR YEAR SEQUENTIAL ~:: EVI SION HONTH DAY YEAR FACILITY NAHES CKET NUHBERS(S)
HUHBER :j:; UHBER 000 I 0 2 7 9 2 9 2 0 4 I 0 I 1 2 2 8 9 2 000 P ERAT ING HIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR 5: (Check one or more of the following) (ll ODE (9) I OVER LEVEL 0.402(b) 0.405(C) 0.73(a)(2)(iv) 77.71(b)
(10) 0.405(a) (1) (1) 0.36(c)(1) 0.73(a)(2)(v) 73.73(c) 0.405(a)(1)(ii) 50.36(c)(2) 0.73(a)(2)(vii) THER (Specify in Abstract 0.405(a)(1)(iii) X 50.73(a)(2)(i) 0.73(a)(2)(viii)(A) elow and in Text. NRC 0.405(a)(1)(iv) 50.73(a)(2)(ii) 0.73(a)(2)(viii)(B) orm 366A) 0.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER (12)
TELEPHONE NUHBER REA CODE R. Z. Poche, Licensing Engineer 5 0 9 7 7 - 4 1 4 5 COHPLETE OHE LINE FOR EACH CDHPOHEHT FAILURE DESCRIBED IH THIS REPORT (13)
CAUSE SYSTEH COHPOHEHT HAHUFACTURER EPORTABLE CAUSE SYSTEH COMPONENT HAHUFACTURER EPORTABLE 0 HPRDS TO HPRDS 5'<7,':"
SUPPLEHENTAL REPORT EXPECTED (14) XPECTED SUBHISSIOH HOHTH DAY YEAR ATE (15)
YES (if yes, c iete EXPECTED SUBHISSIOH DATE) HD nuCr IIII On October 27, 1992, it was determined that one of two offsite power sources would not have been capable of supplying design basis loads during several brief periods of prior plant operation due to low voltage conditions on, the 230KV grid. The 230KV offsite power source should have been considered during these periods, and the appropriate Action Statement should have been entered. Grid 'noperable voltages were well above minimum acceptance values when these low voltage conditions were identified.
The root causes of this condition were: 1) design deficiencies resulting from inadequate consideration of the need to develop grid voltage acceptance criteria and provide accurate grid voltage monitoring instrumentation, and 2) less than adequate management methods to ensure that correct acceptance criteria were used to determine the availability of offsite power sources. Contributing causes were: a technically inaccurate procedure, insufficient monitoring of grid voltage, and inadequate instruments for grid monitoring. Corrective actions include: correcting surveillance procedures, providing continuous monitoring of the offsite power sources, and formalizing the acceptance criteria development process for surveillance procedures.
Backup power sources were available during periods coinciding with low voltage conditions, and the probability. of a design basis accident occurring coiricident with a low grid voltage condition was extremely low. Therefore, this condition was not safety significant.
LICENSEE EVENT REPORR)
TEXl CONTINUATION ACIL1TY HAME (1) DOCKET HOMBER (2) LER HUMBER (8) AGE (3 ear umber ev. Ho.
Washington Nuclear Plant - Unit 2 0 S 0 0 0 3 9 7 2 4 1 1 2 F 8 1TLE (4)
~ . OFFSITE POWER SOURCE INOPERABLE DURING SEVERAL BRIEF PERIODS OF PRIOR OPERATION DUE TO LOW VOLTAGE CONDITION ON THE 230KV GRID Pl n ition Power Level - 100%
Plant Mode - 1 (Power Operation)
Even D ri tion On October 27, 1992, it was determined that one of the two offsite power sources for WNP-2 would not have been capable of supplying design basis loads during several brief periods (three times in 1988, 2 times in 1990) of prior plant operation due to low voltage conditions on the 230KV grid. The 230KV offsite power source should have been considered inoperable during these periods of low grid voltage, and the appropriate Technical Specification Action Statement should have been entered. However, the low grid voltage condition was not recognized during the times when it existed.
An Electrical Distribution System Functional Inspection (EDSFI) was conducted during the first quarter of 1992, and included a review of offsite power sources. In order to support the inspection, historical grid voltage data was collected for the offsite power sources. While collecting this data, the System Engineer noted that voltage on the 230KV grid was not as constant as expected. In response, the System Engineer initiated an independent review of the previous five years of grid voltage data for offsite power sources.
This review was performed during the same approximate time period as the EDSFI.
During review of 230KV grid data, the System Engineer identified one instance when 230KV grid voltage was below the surveillance procedure acceptance criteria value of 226.2KV. Grid voltage during this occurrence was 226KV. At the time when this low voltage condition occurred; the plant was shut down .
and the other offsite power source was available. Consequently, this low voltage occurrence did not represent a Technical Specification violation because only, one offsite power source is required to be operable when the plant is shut down. The System Engineer subsequently alerted Bonneville Power Authority (BPA) that allowing grid voltage to drop below minimum acceptable values could adversely affect operability of required offsite power sources.
The System Engineer's review of historical data for the 115KV grid concluded that voltages for this offsite power source remained above minimum acceptable values at all times when it was required to be operable.
The historical data also indicated that voltages on the 115KV grid are not as sensitive to seasonal peak demands as are voltages on the 230KV grid, It is believed that there were no periods of low Voltage on the 115KV grid that adversely affected operability of this offsite power source.
LICENSEE EVENT REPORR)
TEXT CONTINUATION AGILITY NAHE (1) OOCKET NUHBER (2) LER NUHBER (8) AGE (3) ear umber ev. No.
Washington Nuclear Plant - Unit 2 3 9 0 5 0 0 0 7 2 041 1 3 F 8 ITLE (4)
OFFSITE POWER SOURCE INOPERABLE DURING SEVERAL BRIEF PERIODS OF PRIOR OPERATION DUE TO LOW VOLTAGE'CONDITION ON THE 230KV GRID Subsequent to completion of EDSFI and System Engineer reviews of historical data for the offsite power sources, the calculation for degraded voltage relay setpoints was revised in August 1992. In October 1992, after reviewing the revised calculation, the System Engineer realized that the minimum acceptable voltage for the 230KV grid was 230KV, and not 226.2KV, as previously assumed.
The acceptance criteria value of 226.2KV was based on the dropout setpoint for degraded voltage during review of the calculation it became apparent that the minimum 230KV grid voltage had to relays.'owever, be above the corresponding maximum reset value for these relays in order to assure availability of the 230KV offsite source under design basis conditions. Based upon his earlier review of 230KV grid voltage history, the System Engineer, prepared a Problem Evaluation Request (PER) to document this discrepancy and initiated a follow-up review of historical data for the 230KV grid. This review determined that the 230KV grid had briefly dropped below 230KV on 23 occasions between 1987 and 1991.
From surveillance data, it was possible to determine the actual reset values for'the degraded voltage relays during each of these low voltage periods. Out of the 23 low voltage periods, five instances of prior plant operation were identified when both offsite power sources were required to be operable and the 230KV grid voltage was below the minimum acceptable value. The five low voltage conditions coincide with seasonal peak loads, and occurred on July 21, August 23 and August 24, 1988, (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, (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> each).
Immedi e rr tive Action No immediate corrective actions were identified. The minimum acceptable grid voltage values for the 230KV and 115KV offsite power sources were well above the minimum acceptable values when the conditions described in this report were identified, and it was not the peak electrical demand season.
WNP-2 is currently in compliance with the Technical Specifications for offsite power sources.
F her Evalua i n an rrective Acti n A. F rther Ev 1 ti n
- 1. This event is considered reportable per 10CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications. During the five low voltage conditions on the 230KV grid, the applicable Action Statement for Technical Specification 3.8.1.1 was not entered, and required operability .
demonstrations for A.C. power sources were not performed. 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...."
LICENSEE EVENT REPOIO(LER)
TEXT CONTINUATION AClLITY NAME (1) OOCKET NUMBER (2) LER NUMBER (8) AGE (3) ear umber ev. No.
Washington NucleaT Plant - Unit 2 0 0 3 9 7 0 5 0 2 41 i 4 F 8 ITLE (4)
OFFSITE POWER SOURCE INOPERABLE DURING SEVERAL BRIEF PERIODS OF PRIOR OPERATION DUE TO LOW.VOLTAGE CONDITION ON THE 230KV GRID
- 2. WNP-2 has two independent offsite power circuits: a 230KV line from the BPA Ashe substation to the WNP-2 startup transformer (TR-S), and a 115KV line from=Benton substation to the WNP-2 backup transformer (TR-B). A degraded voltage condition on TR-S resulting from low voltage on the 230KV grid initiates a delay timer. Ifbus voltage does not recover to the degraded voltage relay reset value within the allotted time, bus loads are automatically transferred to an alternate supply. The alternate supply for loads associated with the High Pressure Core Spray (HPCS)
System is the HPCS diesel generator. The alternate supply for other loads is TR-B, if it is available, or the Division 1 and 2 emergency diesel generators.
The starting currents associated with design basis loads can cause bus voltage. on TR-S to drop below the dropout trip point for degraded voltage relays and initiate the time delay timer. As each sequenced motor accelerates, bus voltage will typically recover above the rest value and reset the timer. However, if bus voltage is not restored to, or above, the degraded voltage relay reset value, which is higher than the dropout trip point, before the delay timer times out, bus loads are transferred to the alternate supply.
During the five low voltage periods, voltages for the 230KV grid supply corresponded with TR-S bus voltages that are below the actual reset value for degraded bus voltage relays. If design basis loads had sequenced onto TR-S during one of these periods, the degraded voltage relays may have tripped and not reset. This condition would have resulted in automatic transfer of TR-S loads to backup sources. Therefore, the 230KV offsite power source is considered to have been inoperable during the periods of low grid voltage because it may not have been capable of supporting design basis loads.
The Action Statement for Technical Specification 3.8.1.1 was not entered during the five low voltage periods because the low grid voltage conditions were not identified during the brief periods when they existed. Surveillance related monitoring of grid voltages is only required on a weekly basis, and is not likely to detect infrequent and brief low grid voltage conditions. There are no alarms or other continuous grid monitoring provisions to inform operators when grid voltages are below minimum acceptable values. Furthermore, if a low voltage condition had existed on the 230KV during performance of surveillance testing, grid voltage acceptance criteria were not adequate to allow detection, and the voltmeters used to monitor offsite power sources do not have sufficient accuracy and resolution to support determination of grid voltage acceptability.
LICENSEE EVENT REPORR)
TEXT CONTINUATION AGILITY NAME (1) 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 2 41 i 5 F 8 ITLE (4)
OFFSITE POWER SOURCE INOPERABLE DURING SEVERAL BRIEF PERIODS OF PRIOR OPERATION DUE TO LOW VOLTAGE CONDITION ON THE 230KV GRID Prior to June 1991, the acceptance criteria for operability of offsite power sources provided in surveillance procedures was based on whether or not the grid was energized. However, operability of offsite power sources cannot be established without a minimum acceptable voltage criteria. Grid voltage verification was not previously believed to be necessary because it was assumed that BPA would maintain grid voltage at the levels advertised in their annual voltage schedule. This deficiency in prior revisions to the surveillance procedure was first identified during the root cause evaluation for this LER.
In May 1991, a Plant Operations Engineer requested the System Engineer determine the minimum acceptable grid voltage for TR-S and TR-B for inclusion in the surveillance procedure used to verify offsite power source operability. Subsequently, in response to an informal request from the System Engineer, the Design Engineer provided a value of 226;2KV as the minimum supply voltage that could be used for determining operability of TR-S.
The 226.2KV acceptance criteria value incorrectly corresponds to the minimum analytical dropout setpoint value for degraded voltage relays instead of the minimum grid voltage assumed in the 230KV grid calculation. This incorrect acceptance criteria value was included in the June 1991, revision of the weekly surveillance procedure. As a note, 230KV has historically been assumed as the minimum grid voltage necessary to prevent load transfer during design basis conditions in calculations involving the 230KV offsite power source.
- 3. The root causes of the condition described in this report are: 1) plant/equipmeht related design deficiencies involving inadequate consideration of monitoring and operability requirements for offsite power sources, and 2) less than adequate management methods to assure sufficient information was available to support the development of adequate acceptance criteria for offsite power sources.
- 1) The plant design did not consider the need to develop acceptance criteria for offsite grid voltages, or provide accurate monitoring of voltage levels on the offsite grid. There are no alarms or other indications to alert operators of low grid voltage conditions, and the accuracy of installed grid monitoring instruments is not sufficient to support evaluation of grid voltage acceptability.
- 2) Formalized programs and processes were'not adequate to ensure that acceptance criteria in Technical Specification surveillance procedures were based on identifiable technical references.
This resulted in development and incorporation of inadequate acceptance criteria into the surveillance procedure that is used to determine operability of the 230KV grid.
Contributing causes to the condition described in this report are: 1) a technical inaccuracy in a surveillance procedure, and 2) a plant/equipment related design deficiency involving instrument display accuracy and resolution.
LICENSEE EVENT REPORR)
TEXT CONTINUATION ACILITY NANE (1) DOCKET NURSER (2) LER NNBER (8) AGE (3) t ear umber ev. No.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 2 4 1 i 6 F 8 ITLE (4)
OFFSITE POWER SOURCE INOPERABLE DURING SEVERAL BRIEF PERIODS OF PRIOR OPERATION DUE TO LOW VOLTAGE CONDITION ON THE 230KV GRID
- 1) Early revisions of the surveillance procedure used to perform weekly verification of the offsite power sources were inaccurate because they only verified the availability of offsite power sources, and did not verify voltage levels. Subsequent revisions incorporated an acceptance criteria for minimum 230KV grid voltage, but remained inadequate because the value was not correct. Additionally, although grid voltage verifications were scheduled on the frequency required by Technical Specifications, this was not frequently enough to allow detection of brief voltage decreases associated with summer peak load conditions. the'elatively
- 2) A review of Technical Specification instrumentation used to measure the voltage of offsite power sources was performed. The results indicate that the accuracy of Main Control Room metering for the 230KV grid is inadequate to assure the operability of the offsite power source.
There were no other structures, components, or systems inoperable prior to the event which contributed to the event. Inappropriate selection of the degraded voltage relay dropout point as an acceptance criteria value for determining operability of the 230KV grid involved an error by nonlicensed, utility personnel.
hr rr iv A i nTken
- 1. The Technical Specification surveillance procedure used to verify offsite power source voltages has been changed to reflect the correct acceptance criteria-for operability of the two offsite power sources. Additionally, this procedure now directs that voltage readings for the offsite power sources be obtained from more accurate voltmeters at BPA.
- 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 values of 232KV and 112KV, resIMctively. When these values were determined, the accuracy of instrumentation used to monitor grid voltages was considered.
- 3. The Technical Specification Improvement Project will review the acceptance criteria for Technical surveillance procedures for a technical reference. A technical basis will be identified 'pecification or developed for those criteria identified as having no technical bases.
C. F h r rr iv Acion
- 1. Plant procedure PPM 1.5.1, Technical Specification Surveillance Testing Program, will be changed by December 31, 1992, to require an identifiable technical reference as the basis for all future new or revised acceptance criteria used in Technical Specification surveillance procedures.
LICENSEE EVENT REPORTER)
TEXT CONTINUATION ACILlTY KAME (1) OOCKET NUMBER (2) LER MUMBER (8) AGE (3) ear umber ev. No.
Washington Nuclear Plant - Unit 2 9
0 5 0 0 0 3 7 2 4 1 1 7 F 8 ITLE (4)
OFFSITE POWER SOURCE INOPERABLE DURING SEVERAL BRIEF PERIODS OF PRIOR OPERATION DUE TO LOW VOLTAGE CONDITION ON. THE 230KV GRID
- 2. 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.
- 3. The Supply System and BPA will develop an agreement on an acceptable voltage schedule to minimize the occurrence of unacceptably low grid voltages. This action is scheduled for completion.
by June 1, 1993.
f i nifi nc The HPCS diesel generator and-TR-B are provided as backup power sources for loads associated with TR-S. The HPCS diesel generator is required by Technical Specifications to be operable whenever HPCS is required to be operable, and TR-B was available during the periods of low 230KV grid voltage.
Therefore, backup power was always available for loads associated with TR-S during the periods of low grid voltage. However, even if loads had been transferred to TR-B and the HPCS diesel generator as a result of design basis loads starting, it would not have adversely affected the availability of required equipment, and reactor operators could have tr'ansferred the loads back to TR-S once the loads had started.
A load transfer during low grid voltage conditions would most probably only occur in response to a design basis accident, which results in the highest load demand on TR-S. Backup power sources were available during periods coinciding with low voltage conditions, and the probability of a design basis accident occurring coincident with one of the five, brief periods of low grid voltage was negligibly small.
Consequently, the condition described in this report posed no threat to the health and safety of plant personnel or the public, and was not safety significant.
imil r Event An event involving a momentary fault on the 230KV grid was described in LER 85-63. The resulting low grid voltage condition during this event caused primary undervoltage relays on TR-S to trip, and the Division 1 and 2 diesel-generators to start. The condition described in this report involved degraded voltage relays, and not primary undervoltage relays, and did not involve a grid fault. Therefore, the condition described in this report differs from the low grid voltage event described in LER 85-63.
'ICENSEE EVENT REPORTR)
TEXT CONTINUATlON ACILITY KAHE (I) OOCKET KUHBER (2) LER KUHBER (8) AGE (3 ear umber ev. Ko.
Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 2 4 I I 8 F 8 ITLE (4)
OFFSITE POWER. SOURCE INOPERABLE DURING SEVERAL BRIEF PERIODS OF PRIOR OPERATION DUE TO LOW VOLTAGE CONDITION ON THE 230KV GRID EII Inf rm i n Text Ref rence E~ll! f
$ ggem mQ~m~nn Annunciator System IB Plant AC Distribution System EA Class 1E Power System (Degraded Voltage EB and Undervoltage Relays)
High Pressure Core Spray System (HPCS) BG Emergency Power For HPCS EK