|
---|
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
ACCELERATED THJBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 9006200446 DOC.DATE: 90/06/13 NOTARIZED:
NO FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION FIES,C.L.Washington Public Power Supply System POWERS,C.M.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000397
SUBJECT:
LER 90-010-00:on 900517,secondary containment ESF actuation caused by inadequate work control.W/9 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc.NOTES RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DSP NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB11 NRR/DST/SELB SD NRR DST/SPLBSD1 EG 2 GN5 FILE 0 EXTERNAL: EGGG STUART,V.A LPDR NSIC MAYS,G NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4 4 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD ACRS AEOD/DS P/TPAB DEDRO NRR/DET/EMEB9H3 NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB SE RES/DSIR/EIB L ST LOBBY WARD NRC PDR NSIC MURPHY,G.A COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1~H~S OOCUMFN HP,g PPFN SCANNED NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 36 ENCL 36 ii WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 Docket No.50-397 June 13, 1990 Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555
Subject:
NUCLEAR PLANT NO.2 LICENSEE EVENT REPORT NO.90-010
Dear Sir:
Transmitted herewith is Licensee Event Report No.90-010 for the WNP-2 Plant.This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence.
Very truly yours, C.H.Powers (H/D 927M)WNP-2 Plant Hanager CMP:lr
Enclosure:
Licensee Event Report No.90-010 cc: Hr.John B.Hartin, NRC-Region V Hr.C.J.Bosted, NRC Site (M/D 901A)INPO Records Center-Atlanta, GA Hs.Dottie Sherman, ANI Hr.D.L.Williams, BPA (H/D 399)VOaC200~O6 S 00SZ3 PDR ADOCK 05000397 S PDC YjP~
N<<~GEIM 366 (BEET U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)APPROVED OMB NO.3(504H04 EXP IR ESI'4/30/92 ESTIMATED BURDEN PEA AESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HAS, FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P630), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPE4WORK REDUCTION PROJECT (31500104).
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME (Il Washington Nuclear Plant-Unit 2 econ ary on a)nmen ngineere a e y ea ure Caused by Inadequate Work Control DOCKET NUMBER (2I PAGE 3 0 5 0 0 03 97>oFO c ua son EVENT DATE (SI LER NUMBE4 (6)AEPOAT DATE (7)OTHF 4 FACILITIES INVOLVED (8)MONTH DAY YEAR YEAR rr'Sex SEQVBNTIAL
- 6/A NUMBER~tr%REVISION MONTH WP: NUMBER OAY YEAR FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 0 0 517 909 0 010 00 06 139 0 0 5 0 0 0 OPERATING MODE (8)POW6 R LEVEL P P P (10)20A02(b)20.405(~)(1)(I)20.405(rill)(ill 20A05(el(1)(iiil 20.405(e)(I)(Ivl 20A05(e I (1)(v I 20.405 (c)50.38 I c)(1l 60.38(cl(2) 50.73(~)(2)(Il 50.73(~)(2)(ii)50.73(el(2)(IIB LICENSEE CONTACT FOR THIS LER (12)50.73(e)(2)(ivl 60.73(eH2)(v) 50.73(e)(2)(vEI 60.73(~)(2)(villi(A) 50.73(e)(2)(villi(B) 60.73(e)(2)(x)THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CF 4 ()I (Check onr or more ol the IollowinFI (11)73.7)(B)73.71(c)OTHER ISprcify ln Abstrrct brlowrrxtin Trxt, HRCForm 366AI NAME C.L.Fies, Compliance Engineer TELEPHONE NUMBER AREA CODE 50 937 7-203 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBEO IN THIS REPO4T (13)CAUSE SYSTEM COMPONENT MANUFAC.TUAER EPORTABLE P~x$x~CAUSE SYSTEM COMPONENT MANUFAC.TURER REPORTABLE
'N'kjpjQ TQ NPADS:+c M~gpss@.o>R NB'EIQNN SUPPLEMENTAL REPORT EXPECTED (14)YES III yrr, compte tr EXPECTED SUSIyIISSIOII DA TEI NO ABSTRACT ILlmlt to lr00 sprcrs, I r., rpproxlmrtrly Ilftren slnolrrpecr typewritten linrsl 118)EXPECTED SUBMISSION DATE IIS)MONTH DAY YEAR During the reactor refueling outage on May 17, 1990, at 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br /> a Secondary Containment isolation occurred.This Engineered Safety Feature (ESF)actuation resulted in the shutdown of non-safety related HVAC equipment, the actuation of containment isolation valves, and the startup of various safety related systems such as Standby Gas Treatment.
Plant maintenance workers were replacing auxiliary relays as part of the normal preventative maintenance program when they inadvertently placed two channels in the tripped condition which initiated the ESF actuation.
The root cause for this event was inadequate work control which allowed work to proceed simultaneously on two safety-related divisions when no provisions had been made for such an activity.Immediate corrective action was taken to place the Secondary Containment systems in their normal configuration.
There is no safety significance associated with this event.ESF isolations and actuations occurred as designed for the plant configuration at the time of the event.'ccordingly, this event posed no threat to the health and safety of the public or plant personnel.
NRC Form 368 (569)
I l~~~I It It II~4 II r c Ik Ir I t>~I\ll~j NRC FORM 366A (64)9)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVEO 0M B NO.31600104 EXPIRES: 4/30/92 ES ATEO BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION AEQVEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND AEPORTS MANAGEMENT BRANCH (P4)30), U.S.NUCLEAR REGULATOAY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31600)04), OFFICE OF MANAGEMENT ANO BUDGET, WASHINGTON, OC 20503.FACILI'TY NAME (1)Washington Nuclear Plant-Unit 2 TEXT/ll rrroro 4/rooo/4 ror)o/rod, rrro oddldono/NRC%%drrrr 38549/(I 2)DOCKET NUMBER (2)o s o o o 397 9 0 LER NUMBER (6)"'EOVENTIAL M NUMBER-0 0"eg?REVISION NVMBER 0 0 PAGE (3)oF0 3 Plant Conditions Power Level-0%Plant Mode-5 Event Descri tion During the reactor refueling outage on May 17, 1990, at 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br /> a Secondary Con-tainment Isolation Engineered Safety Feature (ESF)Actuation occurred.At the time of the actuation maintenance work was being performed by Plant Maintenance workers on General Electric Model HFA auxiliary relays.This ESF Actuation initiated a Balance of Plant (BOP)isolation involving Group 3 (Primary and Secondary Contain-ment Ventilation and Purge Systems)and part of Group 4 (Miscellaneous Balance of Plant Systems).These two Groups are part of the Nuclear Steam Supply Shutoff System (NSSSS)that provides overall isolation of plant systems in response to various process parameters.
During refueling (Mode 5)the Primary Containment can be open to the Secondary Containment and this isolation function is limited to Secondary Containment although Primary Containment isolations will occur if com-ponents have not been deactivated.
In addition to the isolations, the Secondary Containment ESF actuation causes the normal Reactor Building (Secondary Containment) heating and ventilating supply and exhaust fans to stop and Reactor Building pressure control is transferred to the safety-related Standby Gas Treatment (SGT)system which was initiated by this event.Immediate Corrective Action Plant operators took imediate corrective action to place the systems back in their normal configuration.
The restoration of systems, including the shutdown of SGT, was completed at 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br />.Further Evaluation and Corrective Action A.Further Evaluation 1.This event is being reported per the requirements of 10CFR50.73(a)(2
)(iv)as an"......event or condition that resulted in manual or automatic actuation of an Engineered Safety Feature (ESF)......".
2.Further evaluation showed work was in progress on the Division I manual actuation relay (MS-RLY-K35A) which put the HAH channel in the tripped condition.
When work started on the HBA channel relay (MS-RLY-81B) this caused a full trip on the outboard relay cabinet (RC-1)which resulted in the Secondary Containment Isolation.
NRC Form 366A (669) 0~~I I I," IMI~'$l bl~'lk<>~4 t H>.',J.><1~c~~~~~0<<E NRC FORM 366A (84)9)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED 0 M 6 NO.31500104 EXPIRES: 4/30/92 ES ATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50J)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P4)30), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504)104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILI'TY NAME (1)DOCKET NUMBER (2)LER NUMBER (8): : SEOUENTIAL P4I'EVISION NR.w NUMBER'tee'UMBER PAGE (3)Washin ton Nuclear Plant-Unit 2 TEXT//I moro tptot it r//I/rtd, Iree odd/1/one/P/RC Form 386A'4/07)0500039790
-01 0-00 OF 0 3.The root cause was inadequate work control which allowed work to proceed simultaneously on two safety related divisions when no provisions had been made for such an activity.4.There were no structures, components or systems that were inoperable prior to the start of this event which contributed to the event.B.Further Corrective Action 1.Work control procedures will be reviewed to determine if additional steps need to be added to control Division related work.2.The current work control administrative process will be reviewed with Plant Maintenance Department Supervisor and Engineering personnel.
Safety Si nificance There is no safety significance associated with this event.ESF isolations and actuations occurred as designed for the plant configuration at the time of the event.Accordingly, this event posed no threat to the health and safety of the public or plant personnel.
Similar Events None EIIS Information Text Reference EIIS Reference Secondary Containment Nuclear Steam Supply Shutoff System Primary Containment Standby Gas Treatment Main Steam Relay K35A (MS-RLY-K35A)
Main Steam Relay K81B (MS-RLY-K81B)
System C BH SB SB~Com onent RLY RLY NRC Form 368A (84)9) v I l II~tl ll4 d~v drrd-4144~~4 4 I 1,, I I ll II I)d, r I v I,v I lt I" d'.!~II d I I~4 4 IIII r i" Idh 4 I~" It I~li V 4.t I, I~II II t ttI , I Id 4'I.tt"4,'I I tl'td tl!I 4 tI 4 II I I>~4 r"dr i Id I'l I II'I dd 14'.rh'I I, IOl>>I I I v~I II I vll ldV I Id!Id 3 4.)hdI)4 I I V 41 I 4 4 I It 4 tl ACCELERATED D>TRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 9006200446 DOC.DATE: 90/06/13 NOTARIZED:
NO FACIL:50-397 WPPSS Nuclear Project, Unit, 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION FIES,C.L.Washington Public Power Supply System POWERS,C.M.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000397
SUBJECT:
LER 90-010-00:on 900517,secondary containment ESF actuation caused by inadequate work control.W/9 ltr.DISTRIBUTION CODE: IE22T.COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DS P NRR/DET/ECMB 9H NRR/DLPQ/LHFB1 1 NRR/DOEA/OEAB1 1 NRR/DST/SELB 8 D PLBSD1 R ILE 01 EXTERNAL EG&G STUART I V~A LPDR NSIC MAYS,G NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4 4 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD ACRS AEOD/DS P/TPAB DEDRO NRR/DET/EMEB9H3 NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB SE RES/DSIR/EIB L ST LOBBY WARD NRC PDR NSIC MURPHY I G A COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1.1 1'NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 36 ENCL 36 I
c ti WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 Docket No.50-397 June 13, 1990 Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555
Subject:
NUCLEAR PLAN1 NO.2 LICENSEE EVENT REPORT NO.90-010
Dear Sir:
Transmitted herewith is Licensee Event Report No.90-010 for the WNP-2 Plant.This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportabi lity, corrective action taken, and action taken to preclude recurrence, Very truly yours, C.H.Powers (H/D 927H)WNP-2 Plant Hanager CHP:lr
Enclosure:
Licensee Event Report No.90-010 cc: Hr.John B.Hartin, NRC-Region V Hr.C.J.Bosted, NRC Site (H/D 901A)INPO Records Center-Atlanta, GA Hs.Dottie Sherman, ANI Hr.D.L.Williams, BPA (H/D 399)9006200446 900613 PDR ADOCK 05000="97 PDC YP~
NRC F,OEIM 366 (63)9l V.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)APPROVEO 0MB NO.31504)104 EXP IR ES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTt 50.0 HAS.FORWARD COMMENTS REGARDING BUADEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P4)30).U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON.
DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 131500104), OFFICE OF MANAGELAENT AND BUDGET, WASHINGTON, DC 20503, FACILITY NAME (1I Washington Nuclear Plant-Unit 2 econ ary on alnmen nglneere a e y ea ure Caused by Inadequate Work Control DOCKET NUMBER (2)PA 8 3l 0 5 0 0 03 97'FO c ua ion MONTH DAY YEAR EVENT DATE (SI YEAR LER NUMBER (6)SEQUENTIAL
)4:: NUMBER REPORT DATE (7I N: RSV+~MONTH DAY YEAR...I NUMBER DOCKET NUMBERISI 0 5 0 0 0 FACILITY NAMES OTHER FACILITIES INVOLVED (8)0 517 9 0 9 0 01 0 00 06 139 0 0 5 0 0 0 OPERATING MODE (BI POWE R LEVEL P P 0 (10)'e,.AX~4g"-.g'/9y:.NAME 20.402(B)20.406(~I (1)(i)20.405(c l(1)(ill 20.405(e l(1)(ill)20A05(~l(1)(lcl 20.405(e)(I
)(I)20.405(cl 60.38 (cl (1)50.38(c)(2)50.73 I~)(2 I (il 50.73(~)(2)(ill 50.73(e)(2)(l ill LICENSEE CONTACT FOA THIS LER (12I 50.73(e)(2)(irl 50.73(~)LS I (rl 50.73 (4 l(2)(rII)50,73(~l(2)(r BI)(A I 50,73(~l(2)(rllil(BI 60,73 I~I (2)(n)THIS REPORT IS SUBMITTED PURSUANT T 0 THE RLOUIREMENTS OF 10 CFR (I:/Check one or more of the follow/no/(ll 73.71(BI 73.71(cl OTHER/Specify in Ahttrect OelOw end In Tent, IIRC form 366AI TELEPHONE NUMBER C.L.Fies, Compliance Engineer AREA CODE 50 937 7-03 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPOAT (13I CAUSE SYSTFM COMPONENT MANUFAC TURER TO NPADS:-~8881," CAUSE SYSTEM COMPONENT MANUFAC TVRER EPORTABLE TO NPADS Iyr.S~c.b.AS.PIC.IN'9..PNM KB.M%I((SUPPLEMENTAL REPOAT EXPECTED (14)EXPECTED SUBMISSION DATE (15)MONTH DAY YEAR YES/lf yf 6 comPlete EXPECTED SVEMISSIDII DA TEI NO ABsTRAGT/Limit to/400 tpecet, l.e., eppronlmetefy II fteen tlnple tpece typewrinen hnetl 118)During the reactor refueling outage on May 17, 1990, at 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br /> a Secondary Containment isolation occurred.This Engineered Safety Feature (ESF)actuation resulted in the shutdown of non-safety related HVAC equipment, the actuation of containment isolation valves, and the startup of various safety related systems such as Standby Gas Treatment.
Plant maintenance workers were replacing auxiliary relays as part of the normal preventative maintenance program when they inadvertently placed two channels in the tripped condition which initiated the ESF actuation.
The root cause for this event was inadequate work control which allowed work to proceed simultaneously on two safety-related divisions when no provisions had been made for such an activity.Immediate corrective action was taken to place the Secondary Containment systems in their normal configuration.
There is no safety significance associated with this event.ESF isolations and actuations occurred as designed for the plant configuration at the time of the event.Accordingly, this event posed no threat to the health and safety of the public or plant personnel.
NRC Form 386 (54)9)
NRC FORM366A (689)r U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMB NO.31500104 EXPIRES: 4/30)92 ESTIM ED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 500 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P830), U.S, NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504)104).
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)SEQUENTIAL NVMSSR SBIS REVISION Srll NVMSSR PAGE (3)Washington Nuclear Plant-Unit 2 TEXT llf IIXNP<<>>4~14 nqIP)PIL u44 44'diO'O44ISRC F4'6649)(IT)o s o o o 397 9 0 0 0-0 0 OF 0 3 Plant Conditions Power Level-OX Plant Mode-5 Event Descri tion During the reactor refueling outage on May 17, 1990, at 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br /> a Secondary Con-tainment Isolation Engineered Safety Feature (ESF)Actuation occurred.At the time of the actuation maintenance work was being performed by Plant Maintenance workers on General Electric Model,HFA auxiliary relays.This ESF Actuation initiated a Balance of Plant (BOP)isolation involving Group 3 (Primary and Secondary Contain-ment Ventilation and Purge Systems)and part of Group 4 (Miscellaneous Balance of Plant Systems).These two Groups are part of the Nuclear Steam Supply Shutoff System (NSSSS)that provides overall isolation of plant systems in response to various process parameters.
During refueling (Mode 5)the Primary Containment can be open to the Secondary Containment and this isolation function is limited to Secondary Containment although Primary Containment isolations will occur if com-ponents have not been deactivated.
In addition to the isolations, the Secondary Containment ESF actuation causes the normal Reactor Building (Secondary Containment) heating and ventilating supply and exhaust fans to stop and Reactor Building pressure control is transferred to the safety-related Standby Gas Treatment (SGT)system which was initiated by this event.Immediate Corrective Action Plant operators took immediate corrective action to place the systems back in their normal configuration.
The restoration of systems, including the shutdown of SGT, was completed at 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br />.Further Evaluation and Corrective Action A.Further Evaluation 1.This event is being reported per the requirements of 10CFR50.73(a)(2)(iv) as an"......event or condition that resulted in manual or automatic actuation of an Engineered Safety Feature (ESF)......".
2.Further evaluation showed work was in progress on the Division I manual actuation relay (MS-RLY-K35A) which put the"AH channel in the tripped condition.
When work started on the HBH channel relay (MS-RLY-81B) this caused a full trip on the outboard relay cabinet (RC-1)which resulted in the Secondary Containment Isolation.
NRC Form 366A (689)
NRC FORM 366A (689)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINuATION APPRQVEO 0MB NO.31504108 EXPIRES: el30)92 ESTIMAIED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-5301.U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31500104).
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME (11 DOCKET NUMBER (21 YEAR LER NUMBER (6)SEOUENTIAL)II 6 NUMBER~6 REV IS ION NUM8EII PAGE (3)Washin ton Nuclear Pl ant-Unit 2 TEXT III mar S>>oe JI I88II)cad, IIee ed)IPdoINJ HRC Farm 366ABJ (12)0 5 0 0 0 3 9 7 9 0 0 1 0 0 0 3 OF 0 3 3.The root cause was inadequate work control which allowed work to proceed simultaneously on two safety related divisions when no provisions had been made for such an activity.4.There were no structures, components or systems that were inoperable prior to the start of this event which contributed to the event.B.Further Corrective Action 1.Work control procedures will be reviewed to determine if additional steps need to be added to control Division related work.2.The current work control administrative process will be reviewed with Plant Maintenance Department Supervisor and Engineering personnel.
Safety Si nificance There is no safety significance associated with this event.ESF isolations and actuations occurred as designed for the plant configuration at the time of the event.Accordingly, this event posed no threat to the health and safety of the public.or plant personnel.
Similar Events None EIIS Information Text Reference EIIS Reference Secondary Containment Nuclear Steam Supply Shutoff System Primary Containment Standby Gas Treatment Main Steam Relay K35A (MS-RLY-K35A)
Main Steam Relay K81B (MS-RLY-K81B)
System C BH SB SB~Com onent RLY RLY NRC Form 366A (689)
C 4 p!N