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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B1111997-11-10010 November 1997 LER 97-011-00:on 971010,HPCS Battery Charger Failed.Caused by Failure of a Phase Firing Control Circuit Board Due to Aging During 7 Yrs of Use.Hpcs Sys Was Immediately Declared inoperable.W/971110 Ltr ML17292B1151997-11-0707 November 1997 LER 97-010-00:on 970906,discovered That TS SR 3.4.5.1 for Identified Portion of RCS Total Leakage Would Not Be Able to Perform within Time Limits of SR 3.0.2.Caused by Inadequate Methods.Method of Meeting SR 3.4.5.1 Established ML17292B0641997-09-24024 September 1997 LER 97-004-01:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Indication of Entry Into Region a of power-to-flow Map.Caused by Inadequate Attention to Detail.Established Event Evaluation teams.W/970924 Ltr ML17292B0241997-08-18018 August 1997 LER 97-009-00:on 970717,discovered Error in Recently Performed Inservice Testing procedure,OSP-TIP/IST-R701. Caused by Procedure Inadequacy.Plant Procedure OSP/TIP/IST-R701 Will Be changed.W/970818 Ltr ML17292B0291997-08-15015 August 1997 LER 97-008-00:on 970716,wire Seal Used to Lock Containment Instrument Air Pressure Control valve,CIA-PCV-2B,found Not Intact.Cause of Misadjustment of CIA-PCV-2B Unknown.Event Will Be Communicated to Plant employees.W/970815 Ltr ML17292B0201997-08-15015 August 1997 LER 97-S01-00:on 970718,failure to Take Compensatory Measure for Inoperative Microwave Security Zone Occurred. Caused by Personnel Error.Training Will Be Conducted W/ Appropriate Members of Security force.W/970815 Ltr ML17292A9481997-07-23023 July 1997 LER 97-007-00:on 970611,voluntary Rept of Automatic Start of DG-1 & DG-2 Was Experienced.Caused by Undervoltage Condition on Electrical Busses SM-7 & SM-8.Circulating Water Pump CW-P-1C Control Switch Placed in pull-to-lock.W/970723 Ltr ML17292A9201997-06-26026 June 1997 LER 97-006-00:on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for SP.W/970626 Ltr ML17292A8331997-04-28028 April 1997 LER 97-004-00:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Entry Into Region a of power-to-flow Map Following Planned Trip of Single Mfp. Event Evaluation teams,established.W/970428 Ltr ML17292A8311997-04-28028 April 1997 LER 97-005-00:on 970327,valid Reactor Scram Signal Received Due to Low Water Level Condition During Preparations for SRV Testing.Caused by Risks & Consequences of Decisions Not Completely Identified.Restored Water level.W/970428 Ltr ML17292A8251997-04-21021 April 1997 LER 97-003-00:on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time exemption.W/970421 Ltr ML17292A7431997-03-20020 March 1997 LER 97-002-00:on 970218,determined That Rod Block Monitor (RBM) Calibr Values Were Not Set IAW Tech Specs.Caused by Calibr Procedures Inadequacies.Revised & re-performed RBM Channel Calibr procedures.W/970330 Ltr ML17292A7401997-03-13013 March 1997 LER 97-001-00:on 970211,reactor Water Cleanup Sys Blowdown Flow Isolation Setpoint Was Slightly Above TS Allowable Valve Occurred Due to Calculation Error.Lds Fss LD-FS-15 LD-FS-16 Were Declared inoperable.W/970313 Ltr ML17292A6641997-01-22022 January 1997 LER 96-009-00:on 961220,miscalculation of Instantaneous Overcurrent Relay Settings Resulted in Inoperability of safety-related Equipment.Caused by Utilization of Inappropriate Design.Testing Was completed.W/970122 Ltr ML17292A6461997-01-0606 January 1997 LER 96-008-00:on 961205,failure to Comply with TS Action Requirement for Emergency Core Cooling Sys Actuation Instrumentation Occurred Due to Unidentified Inoperability Condition.Pmr initiated.W/970106 Ltr ML17292A6371996-12-19019 December 1996 LER 96-007-00:on 961122,electrical Breakers Were Not Seismically Qualified in Test/Disconnect Position.Circuit Breaker Mfg Did Not Consider Raced Out Breaker Position During Testing.Relocated Circuit breakers.W/961217 Ltr ML17292A4121996-08-0808 August 1996 LER 96-006-00:on 960709,average Power Range Monitor Rod Block Downscale Surveillance Not Performed Prior to Entry Into Mode 1.Caused by long-standing Misinterpretation of Requirements of Tss.Procedures revised.W/960808 Ltr ML17292A3801996-07-24024 July 1996 LER 96-004-00:on 960624,plant Was Manually Scrammed by Control Room Personnel Due to Reactor Water Level Transient Experienced During Testing of Digital Feedwater Sys.Caused by Programming Error.Sys Was corrected.W/960724 Ltr ML17292A3771996-07-24024 July 1996 LER 96-005-00:on 960624,determined Missed Surveillance Test Re Channel Check of Average Power Range Monitor.Caused by Inadequate Procedures.Revised Surveillance Procedure Re When APRM Checks Must Be performed.W/960724 Ltr ML17292A3641996-07-12012 July 1996 LER 96-003-00:on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures revised.W/960712 Ltr ML17292A3361996-06-20020 June 1996 LER 96-002-00:on 960504,critical Bus SM-8 Lost Power When Supply Breaker 3-8 Tripped.Caused by Personnel Error. Operators Counselled & Procedures revised.W/960620 Ltr ML17292A2861996-05-24024 May 1996 LER 96-001-00:on 960425,inadvertent ESF Actuations Occurred Due to Tripping of Temporary Power Supply to IN-3.Caused by Personnel Error.Operations Restored to IN-3 Loads & Reset ESF actuations.W/960524 Ltr ML17291B0891995-10-19019 October 1995 LER 95-011-00:on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct deficiency.W/951019 Ltr ML17291A9021995-07-0707 July 1995 LER 95-010-00:on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures written.W/950707 Ltr ML17291A9031995-07-0707 July 1995 LER 95-009-00:on 950607,inadvertent MSIV Closure Occurred During Surveillance Test Due to Poor Communication Between Test Team.Determined That MSIV Closure Not Valid Because Closure Not Triggered by Plant conditions.W/950707 Ltr ML17291A8501995-06-0808 June 1995 LER 95-006-01:on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup ML17291A8101995-05-12012 May 1995 LER 95-008-00:on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl clarity.W/950512 Ltr ML17291A7841995-05-0505 May 1995 LER 95-007-00:on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid ML17291A7801995-05-0404 May 1995 LER 95-006-00:on 950405,main Turbine Trip Occurred During Performance of Surveillance Test Due to Protective Sys Relay Failed.Replaced Failed Relay Before Plant startup.W/950504 Ltr ML17291A7851995-05-0303 May 1995 LER 95-005-00:on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be incorporated.W/950503 Ltr ML17291A7071995-03-25025 March 1995 LER 95-004-00:on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card replaced.W/950325 Ltr ML17291A7011995-03-20020 March 1995 LER 95-002-00:on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control repositioned.W/950320 Ltr 1999-07-20
[Table view] Category:RO)
MONTHYEARML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B1111997-11-10010 November 1997 LER 97-011-00:on 971010,HPCS Battery Charger Failed.Caused by Failure of a Phase Firing Control Circuit Board Due to Aging During 7 Yrs of Use.Hpcs Sys Was Immediately Declared inoperable.W/971110 Ltr ML17292B1151997-11-0707 November 1997 LER 97-010-00:on 970906,discovered That TS SR 3.4.5.1 for Identified Portion of RCS Total Leakage Would Not Be Able to Perform within Time Limits of SR 3.0.2.Caused by Inadequate Methods.Method of Meeting SR 3.4.5.1 Established ML17292B0641997-09-24024 September 1997 LER 97-004-01:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Indication of Entry Into Region a of power-to-flow Map.Caused by Inadequate Attention to Detail.Established Event Evaluation teams.W/970924 Ltr ML17292B0241997-08-18018 August 1997 LER 97-009-00:on 970717,discovered Error in Recently Performed Inservice Testing procedure,OSP-TIP/IST-R701. Caused by Procedure Inadequacy.Plant Procedure OSP/TIP/IST-R701 Will Be changed.W/970818 Ltr ML17292B0291997-08-15015 August 1997 LER 97-008-00:on 970716,wire Seal Used to Lock Containment Instrument Air Pressure Control valve,CIA-PCV-2B,found Not Intact.Cause of Misadjustment of CIA-PCV-2B Unknown.Event Will Be Communicated to Plant employees.W/970815 Ltr ML17292B0201997-08-15015 August 1997 LER 97-S01-00:on 970718,failure to Take Compensatory Measure for Inoperative Microwave Security Zone Occurred. Caused by Personnel Error.Training Will Be Conducted W/ Appropriate Members of Security force.W/970815 Ltr ML17292A9481997-07-23023 July 1997 LER 97-007-00:on 970611,voluntary Rept of Automatic Start of DG-1 & DG-2 Was Experienced.Caused by Undervoltage Condition on Electrical Busses SM-7 & SM-8.Circulating Water Pump CW-P-1C Control Switch Placed in pull-to-lock.W/970723 Ltr ML17292A9201997-06-26026 June 1997 LER 97-006-00:on 970527,non-performance of Surveillance Requirement 3.6.1.3.2 for Blind Fanges,Was Noted.Caused Because Misunderstanding of Intent of Specs.Added Five Structural Assemblies for SP.W/970626 Ltr ML17292A8331997-04-28028 April 1997 LER 97-004-00:on 970327,plant Operators Manually Scrammed Reactor as Required by TS Due to Entry Into Region a of power-to-flow Map Following Planned Trip of Single Mfp. Event Evaluation teams,established.W/970428 Ltr ML17292A8311997-04-28028 April 1997 LER 97-005-00:on 970327,valid Reactor Scram Signal Received Due to Low Water Level Condition During Preparations for SRV Testing.Caused by Risks & Consequences of Decisions Not Completely Identified.Restored Water level.W/970428 Ltr ML17292A8251997-04-21021 April 1997 LER 97-003-00:on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time exemption.W/970421 Ltr ML17292A7431997-03-20020 March 1997 LER 97-002-00:on 970218,determined That Rod Block Monitor (RBM) Calibr Values Were Not Set IAW Tech Specs.Caused by Calibr Procedures Inadequacies.Revised & re-performed RBM Channel Calibr procedures.W/970330 Ltr ML17292A7401997-03-13013 March 1997 LER 97-001-00:on 970211,reactor Water Cleanup Sys Blowdown Flow Isolation Setpoint Was Slightly Above TS Allowable Valve Occurred Due to Calculation Error.Lds Fss LD-FS-15 LD-FS-16 Were Declared inoperable.W/970313 Ltr ML17292A6641997-01-22022 January 1997 LER 96-009-00:on 961220,miscalculation of Instantaneous Overcurrent Relay Settings Resulted in Inoperability of safety-related Equipment.Caused by Utilization of Inappropriate Design.Testing Was completed.W/970122 Ltr ML17292A6461997-01-0606 January 1997 LER 96-008-00:on 961205,failure to Comply with TS Action Requirement for Emergency Core Cooling Sys Actuation Instrumentation Occurred Due to Unidentified Inoperability Condition.Pmr initiated.W/970106 Ltr ML17292A6371996-12-19019 December 1996 LER 96-007-00:on 961122,electrical Breakers Were Not Seismically Qualified in Test/Disconnect Position.Circuit Breaker Mfg Did Not Consider Raced Out Breaker Position During Testing.Relocated Circuit breakers.W/961217 Ltr ML17292A4121996-08-0808 August 1996 LER 96-006-00:on 960709,average Power Range Monitor Rod Block Downscale Surveillance Not Performed Prior to Entry Into Mode 1.Caused by long-standing Misinterpretation of Requirements of Tss.Procedures revised.W/960808 Ltr ML17292A3801996-07-24024 July 1996 LER 96-004-00:on 960624,plant Was Manually Scrammed by Control Room Personnel Due to Reactor Water Level Transient Experienced During Testing of Digital Feedwater Sys.Caused by Programming Error.Sys Was corrected.W/960724 Ltr ML17292A3771996-07-24024 July 1996 LER 96-005-00:on 960624,determined Missed Surveillance Test Re Channel Check of Average Power Range Monitor.Caused by Inadequate Procedures.Revised Surveillance Procedure Re When APRM Checks Must Be performed.W/960724 Ltr ML17292A3641996-07-12012 July 1996 LER 96-003-00:on 960615,required Surveillance Test Not Performed When Required by TS 3.4.1.3.Caused by Inadequate Procedures.Implementing Surveillance Procedure & Reactor Plant Startup Procedures revised.W/960712 Ltr ML17292A3361996-06-20020 June 1996 LER 96-002-00:on 960504,critical Bus SM-8 Lost Power When Supply Breaker 3-8 Tripped.Caused by Personnel Error. Operators Counselled & Procedures revised.W/960620 Ltr ML17292A2861996-05-24024 May 1996 LER 96-001-00:on 960425,inadvertent ESF Actuations Occurred Due to Tripping of Temporary Power Supply to IN-3.Caused by Personnel Error.Operations Restored to IN-3 Loads & Reset ESF actuations.W/960524 Ltr ML17291B0891995-10-19019 October 1995 LER 95-011-00:on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct deficiency.W/951019 Ltr ML17291A9021995-07-0707 July 1995 LER 95-010-00:on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures written.W/950707 Ltr ML17291A9031995-07-0707 July 1995 LER 95-009-00:on 950607,inadvertent MSIV Closure Occurred During Surveillance Test Due to Poor Communication Between Test Team.Determined That MSIV Closure Not Valid Because Closure Not Triggered by Plant conditions.W/950707 Ltr ML17291A8501995-06-0808 June 1995 LER 95-006-01:on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup ML17291A8101995-05-12012 May 1995 LER 95-008-00:on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl clarity.W/950512 Ltr ML17291A7841995-05-0505 May 1995 LER 95-007-00:on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid ML17291A7801995-05-0404 May 1995 LER 95-006-00:on 950405,main Turbine Trip Occurred During Performance of Surveillance Test Due to Protective Sys Relay Failed.Replaced Failed Relay Before Plant startup.W/950504 Ltr ML17291A7851995-05-0303 May 1995 LER 95-005-00:on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be incorporated.W/950503 Ltr ML17291A7071995-03-25025 March 1995 LER 95-004-00:on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card replaced.W/950325 Ltr ML17291A7011995-03-20020 March 1995 LER 95-002-00:on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control repositioned.W/950320 Ltr 1999-07-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999 LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr ML17292B5571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With 990210 Ltr ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error ML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML17292B4791998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr ML17292B5741998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with 990225 Ltr ML17284A8231998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7831998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for WNP-2.With 981007 Ltr ML17284A7491998-09-10010 September 1998 WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998. ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7681998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for WNP-2.With 980915 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for WNP-2.W/980810 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6751998-06-30030 June 1998 Ro:On 980617,flooding of RB Northeast Stairwell with Consequential Flooding of Two ECCS Pump Rooms.Caused by Inadequate Fire Protection Sys Design.Pumped Out Water from Affected Areas to Point Below Berm Areas of Pump Rooms ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17284A6491998-05-31031 May 1998 Rev 0 to COLR 98-14, WNP-2,Cycle 14 Colr. ML17292B4031998-05-31031 May 1998 Monthly Operating Rept for May 1998 for WNP-2.W/980608 Ltr ML17292B3921998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for WNP-2.W/980513 Ltr ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3371998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for WNP-2.W/980409 Ltr ML17292B2641998-03-0404 March 1998 Performance Self Assessment,WNP-2. ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B2911998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for WNP-2.W/980313 Ltr ML17284A7971998-02-17017 February 1998 Rev 28 to Operational QA Program Description, WPPSS-QA-004.With Proposed Rev 29 ML17292B3591998-02-12012 February 1998 WNP-2 Cycle 14 Reload Design Rept. 1999-09-30
[Table view] |
Text
AC CELE RATED IH. BUTION DE MONSTERII ON SYF1'EM REGULATO Y INFORMATION DISTRIBUTION SYSTEM (RIDS)
(> ACCESSION NBR:8807060451 DOC.DATE: 88/06/28 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION ARBUCKLE,J.D. Washington Public Power Supply System POWERS,C.M. Washington Public Power Supply System RECZP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 88-014-00:on 880512,voluntary rept of RWCU sys resin tank spill due to RWCU valves being open.
W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR / ENCL TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.
/ SIZE:
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ZD CODE/NAME LTTR ENCL PD5 LA 1 1 'PD5 PD 1 1 SAMWORTH,R 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DFST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2
/SZB 9A 1 1 NUDOCS-ABSTRACT 1 1 REG FIL@ 02 1 1 RES TELFORDgJ 1 1 RE DX7EIB 1 1 RES/DRPS DEPY 1 1 RGN5 FILE 01 1 1 EXTERNAL'G&G WZLLIAMSiS 4 4 FORD BLDG HOY g A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRZSiJ 1 1 NSIC MAYS iG 1 1 h
TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44
NRC Form 355 U.S. NUCLEAR REGULATORY COMMISSION (0 83)
APPROVED OMB NO, 3150-010l EXPIRES: BI3(I88
, LICENSEE EVENT REPORT {LER)
FACILITY NAME (II DOCKET NUMBER (2) pAGE 13) t-U 0 5 0 0 0 3 ioF08
""oluntary Report of Reactor Water Cleanup (RWCU) System Resin Tank Spill Due To RWCU Val Bein 0 en - Cause Unknown EVENT DATE ISI LER NUMBER (6) REPORT DATE (7I OTHER FACILITIES INVOLVED (8)
MONTH OAY YEAR YEAR SEOUENTIAL ro.6 REVISK>N MONTH DAY YEAR FACILITYNAMES DOCKET NVMBERISI rien NUMBER C.i NUMBER 0 5 0 0 0 51 28 888 0 14 000 6 2 8 THIS AEPOAT IS SUBMITTED PURSUANT T 0 THE REOVIREMENTS OF 10 cFA 8 8 ICnrcir onr or morr of tnr Iorlovvinp) Ill 0 5 0 0 0 (J:
OPERATING MODE (1) 20.402(b) 20.405(c) S0.73( ~ l(2) liv) 73.71(5)
POvv c o t0 405rx'i(II(ir %h nnrrl ill 50 73( ~ l(t)(vl 73,71(ti LEVEL (10) 20.405( ~ ) Ill(irl 50.35(c)(2) 50.73(rl(2)(viil OTHER ISorcrfp in ASINrtt Orlovrrnd In Trxt, HRC Form 20.405(r) ll)(iii) 50.73(r I (2) ( I) 50.73(c) (2 l(viii)IAI 366AI CP@P@PpX tOABSI ~ I(1)(ivl 50.73( ~ l(2l(ii) 50.73( ~ l(21(viii)(8 I r~~gir'Yy@.ij~r 20AOS( ~ )ll)(v) S0.73( ~ ) (2l liiil 50.73( ~ )(2)lxl Voluntary r.42r+riprvcofor -%.
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER AREA CODE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS AEPORT (13)
MANUFAC. REPORTABLE MANUFAC. EPORTABLE CAUSE SYSTEM COMPONENT TVREA TO NPRDS CAUSE SYSTEM COMPONENT TVRER TO NPRDS
&PARlid~
'+@('Kr.':r'SS" SUPPLEMENTAL REPORT EXPECTED (14I MONTH DAY YEAR EXPECTED SUBMISSION DATE OSI YES III yrr, comolrtr EXPECTED SUBMISSION OATEI NO AssTRAcT ILimir to tr00 torcrr, lr., rooroximrrrlF fifurn rlnprr torrr tvorvvrrtrrn Iinrrl (15)
On May 12, 1988 at approximately 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, a Plant Radwaste Control Room Operator (RWO) discovered that a Reactor Water Cleanup (RWCU) System resin spill had occurred during recirculation of RWCU Phase Separator Tank RWCU-TK-104B. The tank was being recirculated in preparation for transfer of resin to a shipping container. Recirculation of the tank was started at 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br />, and tank level reading was noted by the RWO to be 50%. At 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br />, while taking log readings, the RWO noted that tank level was 34%. Contrary to procedural requirements, immediate investigation of the level change was not performed because the RWO thought (erroneously) the change was due to a defective level gauge. The RWO rechecked tank level again at 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br /> and noted it was still decreasing. The RWO then proceeded to the tank location, discovered resin being discharged into Floor Drain FDR-SUMP-W2 and noted that approximately two cubic feet of resin slurry had splashed onto the floor around the drain. At 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br />, the RWO secured the recirculation pump (RWCU-P-28) and closed the tank suction and discharge valves.
Further investigation revealed that RWCU Sample Line Isolation Valves RWCU-V-442/443 had been open which created a flow path which resulted in the spill. The cause of the valves being open is indeterminate. At 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br /> the valves were closed by means of the control switches and, at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, the RWO confirmed that the drainage had stopped.
Upon recommendation of the Plant Manager, the Shift Manager. declared an "Unusual- Event" at 1903 hours0.022 days <br />0.529 hours <br />0.00315 weeks <br />7.240915e-4 months <br />. At 2025 hours0.0234 days <br />0.563 hours <br />0.00335 weeks <br />7.705125e-4 months <br />, Health Physi cs had completed clean up of the immediate area and contained the resin in FDR-SUMP-W2. At this time, the Shift Manager terminated the "Unusual Event" classification.
Further corrective actions include 1) tagging shut and de-energizing RWCU-V-442/443, 2) counseling the RWO involved on the importance of monitoring the status of operational tasks, 3) performing a review of other similar (e.g. infrequently used) Radwaste Syste Valves, and 4) providing additional training on "High" and "High-High" Radiation Areas.
This LER is submitted as a voluntary report. BFIp70(E,ppgl 8gpgpB PDR ADOCI(; 05000397
NRC Fons 35$ A U.S. NUCLEAR REGULATORY COMMISSION (943)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3150M)Os EXPIRESIB/31/BB FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (5) PACE (3)
SEOUENTIAL REVISION YEAR;~g NUMSER NUM ER Washington Nuclear Plant - Unit 2 TEKT /I/ mors e>>cs /I I/o/oisrE Irss ~ HRC Fons R5l 9/ ((7) o s o o o 3 9 7 8 8 014 0 0 0 2 or- 08 Plant Conditions a) Power Level - 0%
b) Plant Mode - 5 (Refueling)
Event Descri tion On May 12, 1988 at approximately 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, a Plant Radwaste Control Room Operator (RWO) discovered that a Reactor Mater Cleanup (RMCU) System resin spill had occurred during recirculation of RMCU Phase Separator Tank RWCU-TK-1 04B. The tank was being recirculated in preparation for transfer of resin slurry to a shipping container.
At '1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br />, the RWO began the recirculation of RWCU-TK-104B in accordance with Plant Procedure (PPM) 2.11.1, "Solid Waste Processing System." Tank level reading was noted by the RMO to be 50'X. The RMO then proceeded to perform his normal duties and at 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br />, while taking log readings, he noted that the tank level was 34"..
Immediate investigation of the level change was not performed because the RWO thought (erroneously) the change was due to a defective level gauge. (The RWO had remembered a recent level gauge problem on an equipment drain tank and thought this situation was similar.) He also did not investigate any further due to the many activi ties in progress in the Radwaste Control Room at this time. However, not investigating the level change was contrary to a caution statement in PPM 2.11.1 which directs the operator to monitor tank level and, resin sludge is likely leaking out.
if it drops, isolate the tank immediately because At 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br />, the RWO checked tank level again and noted it was still decreasing.
The RWO then proceeded to the RWCU-TK-104B location (Radwaste Building - Elevation 437' and discovered resin being discharged down a scupper into a Floor Drain (FDR-SUMP-W2). He also noted that approximately two cubic feet of resin slurry had splashed onto the floor around the drain. The RWO immediately left the area, returned to the Radwaste Control Room and, at 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br />, secured the recirculation pump (RWCU-P-28) and closed the RWCU-TK-104B suction and discharge valves. He then informed the Shift Support Supervisor (SSS) of the situation, who in turn notified the Shift Manager and Health Phyics personnel. At 1725 hours0.02 days <br />0.479 hours <br />0.00285 weeks <br />6.563625e-4 months <br />, the SSS, RWO and Health Physics personnel arrived at the area of the spill. Health Physics personnel immediately monitored the area and found that their readings indicated 2-3 R/hr at one inch, with no airborne activity present. The area was posted "NO ENTRY" by Health Physics personnel at 1735 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.601675e-4 months <br />.
At this time the Shift Manager, SSS and RWO went to the Radwaste Control Room -to review System Flow Diagrams in an attempt to identify the drain path. After reviewing the flow diagrams, they suspected that the, drain path was through a sample line on the RWCU-P-28 discharge. Although the flow diagrams show'ed a shut-off switch for Sample Line Isolation Valve RWCU-V-442, the location of the switch was (However, the location of valve position indication for Sample Line not'dentified.
Isolation Valve RWCU-V-443 was identified in PPM 2.11.1). Unable to locate the switches, the SSS contacted an off-duty SSS who informed him that they were in the "AU Concentrator Room (Radwaste Building - Elevation 467').
NRC FORM SOEA s U.S.G/rO:19BBDd24 538/ESS (943)
NRC For RI SSSA U.S, NUCLEAR REOULATORY COMMISSION ITS I LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVEO OMS NO. O'ISOMI04 EXPIRES: SISI/88 FACILITY NAME III OOCKET NUMSER ISI LER NUM8ER (SI ~ AOE IS)
- rg~ SEQUENTIAL REVISION NVMSER Pg NVM EII Washington Nuclear Plant -'nit 2 p s p p p 3 9 014 0 0 3 OF 08 TEXT III'oro spooe II rNPrlsrf, Iroo IRFRRmsl lYRC Form SSSAS I II Tl At 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br />, the SSS found the control switches for RWCU-V-442/443 and noted they
. were both in the open position, but the indicating lights were not functional (subsequent investigation revealed that the red Lopen] lights had been removed and the green Lclosed] lights were burned out). The 'SSS then placed the control switches for both valves in the "close" position, and heard the air actuation (both valves are air-operated and are in series).
The SSS dispatched the RWO to the area of the spill and, at 1800 hours, the RWO confirmed that drainage had stopped. It was also noted at that time that RWCU-TK-104B level was 265.
At 1820 hours, the Shift Manager returned to the Control Room and was informed that an Area Radiation Monitor (ARM-29: Radwaste Building - Elevation 437') had alarmed and was fluctuating between 80 and 100 MR/hr. Being aware of the spill, the Shift Manager contacted Health Physics personnel for information on radiation levels. He was informed that readings at the scene were 2-3 R/hr at 18 inches; however, actual readings logged on the survey map indicated readings of 2-3 R/hr at one inch.
Proceeding with followup management notifications, the Shift Manager contacted the Assistant Operations Manager and the Plant Manager to brief them on the incident.
Upon the recommendation of the Plant Manager, an 'Unusual Event" was declared at 1903 hours0.022 days <br />0.529 hours <br />0.00315 weeks <br />7.240915e-4 months <br />. The Shift Manager, utilizing the CRASH Network, notified the State, County, Department of Energy, and the Supply System Security Communications Center. In addition, PA announcements were made and the NRC was notified by means of the ENS Line.
At 2025 hours0.0234 days <br />0.563 hours <br />0.00335 weeks <br />7.705125e-4 months <br />, Health Physics personnel had completed clean up of the immediate area and contained the resin in Floor Drain Sump FDR-SUMP-W2. At this time, the Shift Manager terminated the "Unusual Event" classification.
This LER is submitted as a Voluntary Report.
Immediate Corrective Action Recirculation pump RWCU-P-28 was secured, Sample Line Isolation Valves RWCU-V-442/443 were closed, the area of the spill was cleaned up, the resin was contained in FDR-SUMP-W2, and the NUnusual Event" classification terminated.
Further Evaluation and Corrective Action A. Futher Evaluation
- l. The immediate cause of this event was valves RWCU-V-,442 'and RWCU-V-443 being open. The root cause for the valves being open is indeterminate. As shown in Figure 1, this configuration created the following unknown leakage paths:
o RWCU-V-442 and RWCU-V-443 Open (Resin Leakage Path)
NRC FORM SSS* +U.S.OPOI1055442$ SSSIE55 ISSSI
NRC form SSSA U.S, NUCLEAR REGULATORY COMMISSION
)943)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3150-010E EXPIRES: 8/31/88 DOCKET NUMSER 12) LER NUMSER LS) PAGE 13)
SEQllENTIAL REVISION NVM ER NUMPER Washington Nuclear Plant - Unit 2 0 s 0 0 0 3 9 1 4 0 0 4 OF 0 8 TEXt /N mo/9 Efoco /o /o)/rkorL ow /re/'orN/ HRC Fomr 3//$ 43/ (17)
With both valves open, and the start of RWCU-P-28, RWCU resin slurry was pumped through the valves to the drain system. As a result of RWCU-TK-104B level changes, it is estimated that 1,000 gallons was inadvertently drained from the tank. This equates to a resin loss of approximately 25-30 cubic feet. The bulk of the resin was contained in the liquid radwaste processing system.
o RWCU-V-442 Open (Condensate Leakage Path)
Condensate water was supplied through COND-V-325, down a 1/2N pipe and through RWCU-V-442 to the drain. It is estimated that the leakage through this flow path was 3.4 gpm.
- 2. An investigation was ,,performed in an attempt to determine when valves RWCU-V-442 and 443 had been opened. It was discerned that the valves were opened by means of the control switches around 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on April 28, 1988, because an abrupt increase in FDR-SUMP-W2 run time also occurred at that time. At least two attempts were made to identify the leakage; however, the actual source into the sump (a scupper drain port) was not checked because was identified as an Equipment Drain (EDR) on Plant drawings instead of an it FDR. Upon closing RWCU-V-442 and 443 on May 12, 1988, FDR-SUMP-W2 run time returned to historical values.
- 3. At the request of the Plant Manager, a Plant Security investigation was conducted to determine the circumstances surrounding the incident. There was no evidence or suspicion to conclude that the opening of RWCU-V-442 and 443 was a deliberate act.
- 4. A review of was noted PPM that 2.11.1, "Solid Waste Processing System," was performed and RWCU-V-442 is not listed on the valve checklist, and neither it RWCU-V-442 nor 443 are mentioned in Section B,N Reactor Water Cleanup Phase Separators Operation (RWCU-TK-104A/B).N
- 5. The locations and setpoints of the Area Radiation Monitors (ARMS) in the spill area were reviewed and are as follows:
o ARM-28 is located approximately 90 feet from the geometric center of the spill area. The setpoint for this ARM is 50 mR/hr.
o ARM-29 is located approximately 18 feet from the geometric center of the spill area. The setpoint for this ARM is 100 mR/hr. The setpoint was changed from 75 mR/hr on February 29, '1988 to reduce the frequency of alarm conditions due to increased background radiation levels (75 mR/hr) associated with the RWCU recirculate and transfer line which is located approximately 12 feet from the detector. The alarm conditions were masking other alarms coming in on Main Control Room annunciators from Radwaste Area Radiation Monitors. There was not a problem by increasing the setpoint because the monitor would continue to alert personnel to changes in area radiation levels.
NRC WORM SESA RU.S GPO:18$ $ W82E 53$ /855 19831
~ r, . ~ ~ r NRC Forrrr 3SEA U.S. NUCLEAR REOULATORY COMMISSION (943)
LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVED OMS NO. 3(50-0(CO EXPIRES: 8/3'I/88 FACILITYNAME (11 DOCKET NUMBER Il) LER NUMSER (8) ~ AOE (3)
SSOUENTIAL R+3 IIS V IS IO N NPR NVMSSII NUM SN Washington Nuclear Plant TEXT lllmore <<>>ce le e/o/rerL Iree ~ - Unit AIRC Forrrr 3//EAE/ I IT) 2 o s o o o 3 9 014 0 0 5 OF 0 8 Area Radiation Monitor recorder points in the Main Control Room were reviewed to determine if ARM-28 had also alarmed. The review was unsuccessful because, although the scales are color-coded (Red Scale = ARM-l, 3 and 3A:
Green Scale = all others), all recorder pens contained black ink. As a result, it was impossible to differentiate the recordings and verify if ARM-28 alarmed. However, it is unlikely that ARM-28 alarmed dur ing the event due to the distance of the monitor from, and activity levels of, the spill.
- 6. The area of the spill had been previously identified as a "High-High" Radiation Area by use of a yellow flashing light (identifies exposures in excess of lR/hr). Prior to entry into this area, Health Physics must be notified and the proper dosimetry obtained. Although the RWO left the area immediately upon discovering the spill, he had entered the area without the required dosimetry, and did not understand the meaning of the yellow flashing light in relation to anticipated exposure levels.
- 7. A review of PPMS 11.2.7.1, "Area Posting", and 11.2.7.3, "Entry Into and Egress from High Radiation Areas", was performed .to determine adequacy with proper posting requirements and consistency with the Plant Technical Specifications. For areas greater than 1,000 mR/hr, where no enclosure exists for the purpose of locking, and where no enclosure can be reasonably constructed around the individual .areas, PPM 11.2.7.3 requires that such areas be barricaded, posted and flashing light activated as a warning device. This direction is consistent with the wording in the Technical Specifications.
For areas greater than 1,000 mR/hr, PPM 11.2.7. 1'equires that such areas either be locked or, if no enclosure exists for the purpose of locking, the areas shall be barricaded, posted and a flashing light activated as a warning device. Although the wording is not entirely consistent with that of the Technical Specifications, the intent of the procedure is to lock access to such areas where possible.
As a result, either the shield doors at the entrance to the spill area should have been closed and locked, or an enclosure should have been constructed at that location.
B. Further Corrective Action
- 1. RWCU-V-442 and 443 were tagged shut and de-energized.
- 2. PPM 2.11.1 was deviated to include RWCU-'-442 on the valve checklist. The required condition for both RWCU-442 and 443 on the valve checklist is "closed."
- 3. The RWO involved in this event was counseled on the importance of monitoring the status of operational tasks, including procedural compliance and believing Plant instrumentation unless proven otherwise.
NRC FORM SOFA e U 8 OPO 10884 82S 838/SSS (083)
0 NRC ForIII 355A Ug, NUCLEAR REOULATDRY COMMISSION l943 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED DMB NO. 3150WIOO EXPIRES: 5/31/BS FACILITY NAME I\I DOCKET NUMBER l2l LER NUMBER (SI PACE I3I Sf DUE NTIAL g~IR REVISION YEAR X~
NUM fR ~: NUM fR Washington Huclear Plant - Unit 2 0 s 0 0 0 3 9 7 88 014 0 0 06oF 0 8 TEXT /I/moro opoc>> /I rofoPR/, ooo arfo'one///RC Form SSLS 3/ IITI
- 4. The Shi ft Support Supervi sor' sensi tivity was increased to the manpower needs in the Radwaste Control Room during heavy work periods.
- 5. A review of the Radwaste System will be performed for the purpose of identifying any similar valves (e.g. infrequently used) such as RWCU-V-442 and 443.
- 6. The Plant drawing (M607, Sheet 3) which incorrectly identified the FDR scupper drain port as an EDR source will be revised.
- 7. The Area Radiation Monitor recorder pen colors were restored to the correct design configuration (red and green). In addition, an evaluation will be performed to determine if the current design of the recorder can be changed to better differentiate between ARM recordings.
- 8. The shield doors at the entrance to the spill area were closed and locked.
- 9. A Plant equality Assurance survey was conducted to provide an indication of the level of knowledge of Plant personnel regarding radiation barriers. The results of the survey indicated that many of the survey population did not have a clear understanding of "High" Radiation Areas, "High-High" Radiation Areas and ARMS. Accordingly, additional training will be provided to Plant personnel to enhance understanding of "High" and NHigh-High'adiation Areas with respect to proper dosimetry and actions required prior to entering such areas during normal and abnormal Plant conditions.
- 10. Plant procedure 11.2.7.1 is in . the process of being revised to make consistent with the wording in the Plant Technical Specifications it and PPM 11.2.7.3.
Simliar Events Hone Safety Si nificance There is no safety significance associated with this event in relation to the general public. However, Plant personnel either were, or could have been, impacted as follows:
- l. Although the RWO immediately left the spill area upon discovery, that he could have exceeded the Supply System daily administrative exposure limit it is possible (300 mrem) by not recognizing the significance of the yellow flashing light in relation to anticipated exposure levels.
- 2. The decontamination crew (consisting of three individuals) accumulated a total collective dose equivalent of 0.195 man-rem during recovery operations. The RWO involved received 70 mrem during his shift on the day of the spill.
N R C F 0 R M SSO A *U.S.OPO:ISBN%24 535/SBS I9431
NRC form SSSA U.S. NUCLEAR REGULATORY COMMISSION (943)
LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVEO OM8 NO. 3(SGM(04 EXPIRES: 8/31/88 FACILITY NAME (Il COCKET NUMBER (2) (.ER NUMSER IS) PAGE (3)
S F. Q U E N T I AL rl E V IS IQ N OIIP NUM E II NUM S II Washington Nuclear Plant Unit 2 0 5 0 0 0 3 9 1 4 0 0 >> O8 TEXT /R moro t/rtct N /t//re L ott ts//O'ot///RC /omr 3(ELE 3/ (IT)
The spilled resin slurry was contained in FDR-SUMP-W2. The location of the sump is a low traffic area and is protected by the use of radiological postings. In addition, the shield doors at the entrance to the spill area have since been closed and locked.
It should also be noted that the spill area configuration is such that emptying the entire resin tank could not have resulted in a release of radioactive material.
EIIS Information Text Reference EIIS Reference System Component Reactor Water Cleanup (RWCU) System CE RWC U-TK-1 04B CE TK F D R-SUMP-'II'2 DRN RWC U-P-28 CE p RhrCU V 442/443 CE ISY ARM-28/29 IL 45 COND-V-325 SD V NRC FORM SSSO *U.S.GPO.(98M&24 S3S/4dd (983)
NRC Sera 844A U.S. NUCLSAR RSGULATORY COMMISSION 19891 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVSO OMS NO. S)50&)de S)ASPIRES: 4/S1/R)
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~
Richland, Washington 99352 Docket No. 50-397 June 28, 1988 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO.88-014
Dear Sir:
Transmitted herewith is Licensee Event Report No.88-014 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. Powers (M/D 927M)
WNP-2 Plant Manager CMP:lg
Enclosure:
Licensee Event Report No.88-014 cc: Mr. John B. Martin, NRC - Region V Mr. C.J . Bosted, NRC Site (M/D 901A)
INPO Records Center - Atlanta, GA Ms. Dottie Sherman, ANI Mr. D.L. Williams, BPA (M/D 399)