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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045F6631993-06-25025 June 1993 LER 93-014-00 on 930529,logic Sys Functional Testing Was Incomplete Due to Test Procedure Deficiencies.Temporary Procedure Changes made.W/930625 Ltr ML20045D9081993-06-23023 June 1993 LER 93-013-00:on 930525,automatic Reactor Scram Occurred When APRM E Spiked While Indicated Water Level Approx 6%. Possibly Caused by Spiking of LPRM Input of APRM E. Radiation Sources Replaced W/Stronger sources.W/930623 Ltr ML20045D2971993-06-18018 June 1993 LER 93-012-00:on 930519,isolation Occurred When Rhr/Lpci Pump B Started in Shutdown Cooling Mode & Inboard & Outboard Isolation Valves Closed.Caused by Pressure Transient.Test Program Developed to Obtain Necessary data.W/930618 Ltr ML20045D1201993-06-16016 June 1993 LER 92-015-01:on 920317,deficiencies W/Potential to Effect Safe Shutdown During Postulated Fires Identified Due to Lack of Commitment to Fire Protection Implementation by Mgt.Plant Mods scheduled.W/930616 Ltr ML20045A3931993-06-0303 June 1993 LER 91-029-01:on 911130 & 1213,false Primary Containment High Radiation Isolation Sys Occurred.Caused by Filters Attached to Input of Monitors.Correct Operation of Isolation of Primary Containment Vent & Valves confirmed.W/930603 Ltr ML20044F6211993-05-19019 May 1993 LER 93-010-00:on 930420,HPCI Declared Inoperable Due to Grounded Electric Circuit on Turbine Steam Supply Valve. Caused by Personnel Inattention to Detail.Personnel Counseled Re Need for Attention to detail.W/930519 Ltr ML20044F6111993-05-19019 May 1993 LER 93-009-00:on 930420,noted That Abrupt Reduction in Feedwater Flow Resulted in Rapidly Decreasing Rwl.Caused by Loose Electrical Connection on Reactor Feed Pump A.Post Trip Evaluation Conducted to Prevent recurrence.W/930519 Ltr ML20044D2051993-05-11011 May 1993 LER 93-008-00:on 930412,identified That SJAE Radiation Monitor Had Increased.Caused by Failure to Identify Need to Obtain an Offgas Sample.Daily Instrument Surveillance Test changed.W/930511 Ltr ML20044B6181993-02-11011 February 1993 LER 93-035-01:on 920825,circuit Breaker Supplying Power to Load Ctr step-down Transformer Tripped Due to High Phase Current & Grounding.Caused by Deteriorated Transformer Coil Insulation.Transformer Rebuilt & reinstalled.W/920211 Ltr ML20024H0831991-05-13013 May 1991 LER 91-005-00:on 910412,torus Water Temp Instrumentation Declared Inoperable.Caused by Uncertainty of 3.52 F. Conservative 4 Degree Bias Installed in Torus Water Instrumentation Software program.W/910513 Ltr ML20024G6831991-04-17017 April 1991 LER 91-004-00:on 910318,unmonitored Release of Radioactivity Detected Outside Auxiliary Boiler Bldg.Caused by Personnel Error & Deficiencies in Procedures.Contaminated Surfaces Covered W/Reinforced Plastic covers.W/910417 Ltr ML20028H8611991-01-25025 January 1991 LER 90-025-01:on 901115 & 1226,in Total,Five Svc Water to Emergency Svc Water Swing Check Valves Failed to Close During Testing.Caused by Corrosion Problems.Valve Internals Replaced W/Stainless Steel components.W/910125 Ltr ML20028G9451990-09-25025 September 1990 LER 90-003-01:on 900129,core Overpower Events Occurred Due to Feed Flow Transmitter Calibr.Caused by Previously Unidentified Vendor Design Error,Error Introduced as Result of Plant Mod & Improper prioritization.W/900925 Ltr ML20043J0861990-06-21021 June 1990 LER 90-017-00:on 900526,instrument Setpoint Drift Exceeds Tech Spec Limit for HPCI Turbine Trip on High Reactor Water Level.Cause Unknown.Transmitter Included in Program for Weekly Monitoring of Rosemount transmitters.W/900621 Ltr ML20043B9831990-05-23023 May 1990 LER 90-016-00:on 900424,automatic Isolation Signal Closed Suction Valves from Reactor Water Recirculation Sys.On 900425,suction Valves Closed & RHR Pump Tripped.Caused by Chattering Pressure Switch.Switches replaced.W/900523 Ltr ML20043A9601990-05-21021 May 1990 LER 90-015-00:on 900420,discovered That Prerequisite Surveillance Test of source-range Monitors Not Performed Prior to Beginning Replacement of LPRMs on 900419.Caused by Procedure Deficiency.Lprm Procedure revised.W/900521 Ltr ML20042G8311990-05-10010 May 1990 LER 90-014-00:on 900410,primary Containment Isolation Check Valve Declared Inoperable Due to Missing Spring.Caused by Personnel Error.Performance of HPCI Turbine Exhaust Drain Sys Will Be Monitored During HPCI testing.W/900510 Ltr ML20042G8301990-05-0909 May 1990 LER 90-013-00:on 900409,shutdown Cooling Automatically Isolated During Transfer of Bus.Probably Caused by Contract Personnel Accidentally Knocking Jumper Loose.Procedures Re Controls on Jumpers Will Be revised.W/900505 Ltr ML20042F7531990-05-0303 May 1990 LER 90-012-00:on 900404,normal & Emergency Svc Water Valves Found to Be Inoperable.Caused by Excessive Build Up of Corrosion on Valve Surfaces & Accumulation of Silt.Valves Cleaned & Restored to svc.W/900503 Ltr ML20012E0071990-03-21021 March 1990 LER 90-005-00:on 900220,HPCI Sys Inoperable Resulting in 7 Day Limiting Condition for Operation.Caused by Sticking or Binding in Remote Servo.Remote Servo replaced.W/900321 Ltr ML20012C5161990-03-0909 March 1990 LER 90-004-00:on 900207,isolation of RCIC Sys Occurred, Resulting in Initiation of 7-day Limiting Condition of Operation.Caused by Failure of Master Trip Unit.Subj Unit replaced.W/900309 Ltr ML20012B4351990-03-0202 March 1990 LER 90-003-00:on 900129,when More Accurate Transmitters Placed in Svc,After Calibr Span Values Adjusted,Indicated Power Exceeded Core Thermal Power Limit.Caused by Incomplete Review of Manual.Transmitters recalibr.W/900302 Ltr ML20006E8621990-02-16016 February 1990 LER 90-001-00:on 900119,reactor Scram Occurred During Calibr of Reactor Water Level Instrumentation,Resulting in Valve Packing Leak & Causing False Low Water Level.Caused by Rapid Valve Movement.Event reviewed.W/900216 Ltr ML20006E9221990-02-15015 February 1990 LER 90-002-00:on 900215,reactor High Pressure Isolation Logic Tripped & Isolated RHR Shutdown Cooling Sys B as Sys Being Started.Hydraulic Pressure Transient Suspected as Cause.Operating Procedure revised.W/900215 Ltr ML20006E2101990-02-12012 February 1990 LER 89-019-01:on 891031,HPCI Turbine Declared Inoperable Due to Electrical Ground in Speed Control Circuit.Caused by Conductive Corrosion Products Between Amphenol Type Connector & Mounting Plate.Connector cleaned.W/900212 Ltr ML20006E2291990-02-0808 February 1990 LER 89-018-01:on 891008,HPCI High Steam Flow Signal Closed HPCI Outboard Steam Supply Isolation Valves,Causing Isolation of Logic Circuit.Caused by Overly Conservative Value for Flow Isolation Signal.Sensor vented.W/900208 Ltr ML20011E1431990-01-29029 January 1990 LER 89-020-01:on 891105,reactor Scram Initiated by High APRM Neutron Flux from Pressure Transient from Turbine Control Valve Closure.Caused by Void Collapse in Core Moderator. Computer Programming Changed Re Transient data.W/900129 Ltr ML20006C1571990-01-26026 January 1990 LER 89-026-00:on 891105,reactor Scram from Full Power Occurred Due to Problems W/Turbine electro-hydraulic Control Sys.On 891220,contractor Notified Util That Valves Tested Did Not Actuate within Setpoint as required.W/900126 Ltr ML20005E8541990-01-0202 January 1990 LER 89-025-00:on 891130,isolation Signal Closed Outboard Isolation Valves on Steam Supply Line to HPCI Sys,Rendering HPCI Sys Inoperable & Initiating 7-day Limiting Condition for Operation.Caused by Excess steam.W/900102 Ltr ML20042D3961989-12-27027 December 1989 LER 89-024-00:on 891129,RCIC Sys Inoperable for 14 Minutes During Monthly Surveillance Test.Caused by Personnel Error. Outboard Isolation Valve Opened & Critique & Discussion W/ Technicians Held to Increase Event awareness.W/891227 Ltr ML20011D1351989-12-12012 December 1989 LER 89-023-00:on 891112,reactor Scram Occurred During Scheduled Surveillance Test of Safety Relief Valves.Caused by High Neutron Flux Signal Due to Steam Pressure Transient. Change Made to Surveillance Test ST-22B.W/891212 Ltr ML19332F4751989-12-0707 December 1989 LER 89-022-00:on 891107,determined That Elastomeric Seals in 33 Snubbers Had Not Been Replaced within Plant 7-yr Svc Life Guideline.Caused by Failures in Mgt of Maint Records. Snubbers Replaced as necessary.W/891207 Ltr ML19332F4511989-12-0505 December 1989 LER 89-020-00:on 891105,reactor Scram Occurred Due to Failure in Electronic Control Card of electro-hydraulic Control Sys.Caused by Void Collapse in Core Moderator. Circuit Boards Sent to Vendor for analysis.W/891205 Ltr ML19332E6241989-11-30030 November 1989 LER 89-019-00:on 891031 & 891103,HPCI Sys Declared Inoperable Due to Electrical Ground in Speed Control Circuit.Caused by Buildup of Conductive Corrosion Products. Connector Cleaned & Sys Returned to svc.W/891130 Ltr ML19332F0471989-11-30030 November 1989 LER 89-021-00:on 891031,circuit Breaker for RCIC Inboard Injection Valve to Feedwater Sys Tripped During Required Valve Testing.Caused by Fault in Motor Winding Insulation. New Motor installed.W/891130 Ltr ML19325F2791989-11-13013 November 1989 LER 89-007-01:on 890509,surveillance of Fire Barrier Penetrations,Per Tech Spec 4.12.F Not Conducted within Allowed Time Period.Caused by Misinterpretation of Fire Protection Ref Manual.Fire Watch established.W/891113 Ltr ML19327C1351989-11-0707 November 1989 LER 89-015-01:on 890918,two Remote Manually Operated Diaphragm Air Operated Isolation Valves Failed Closing Time Acceptance Criteria.Caused by Buildup of Iron Oxide Sludge. Valves Disassembled & Cleaned ML19327B9821989-11-0606 November 1989 LER 89-018-00:on 891008,HPCI High Steam Flow Signal Closed Isolation Valves for Outboard Steam Supply & Steam Line Warning.Caused by Air in Sensing Sys Leading to Unstable Oscillation.Pressure Sensor Vented & calibr.W/891106 Ltr ML19324B1151989-10-23023 October 1989 LER 88-008-01:during 1988 Refuel Outage,One Primary Containment Penetration Exceeded Tech Spec 4.7.A.2.b Limit When Subjected to Local Leak Rate Testing.Leakage Attributed to Wear.Valves replaced.W/891023 Ltr ML19327B1521989-10-20020 October 1989 LER 89-017-00:on 890920,ESFAS Initiated Group II Primary Containment Isolation Signal Triggering RHR & LPCI Sys Isolations.Caused by Cognitive Human Error in Not Finding Isolation Signal.Fuse Replaced & Sys restarted.W/891020 Ltr ML19327B1501989-10-18018 October 1989 LER 89-016-00:on 890918,scram Signal Automatically Initiated During Transfer of Power Supply for Reactor Protection Sys. Caused by Lack of Caution Statement in Procedure.Procedure Revised to Add Time Caution for Bus transfers.W/891018 Ltr ML19327B1331989-10-18018 October 1989 LER 89-015-00:on 890918,two of Nine Remote Manually Operated Diaphragm Air Operated Containment Isolation Valves Failed Acceptance Criteria for Closing Time.Caused by Buildup & Hardening of Iron Oxide Sludge.Valves cleaned.W/891018 Ltr ML20024A8271983-06-20020 June 1983 LER 83-023/01T-0:on 830607,water Seepage Discovered from Weld in Stainless Steel Pipe Section of Control Rod Hydraulic Return Line.Caused by Intergranular Stress Corrosion Cracking.Piping Will Be removed.W/830620 Ltr ML20024A8571983-06-18018 June 1983 LER 83-021/03L-0:on 830605,rod Block Calibr Not Performed within 7 Days of 830603 Planned Reactor Shutdown.Caused by Inadequate Mgt Controls to Implement Tech Specs.Procedures to Be revised.W/830618 ML20024A8631983-06-16016 June 1983 LER 83-022/03L-0:on 830607,during Performance of Local Leak Rate Testing of Containment Spray,Penetration X-39A Found W/ Leakage That May Exceed Tech Spec Limits.Cause Undetermined. Details Will Be Provided within 30 days.W/830616 Ltr ML20028D6951983-01-11011 January 1983 LER 82-057/03L-0:on 821216,during Normal Operation,Reactor Scrammed on High Neutron Flux on Power Range Monitors. Caused by Reactor Pressure Spike Created by Sudden Closure of One MSIV Due to Improper Maint.Procedure Changed ML20027B5291982-09-10010 September 1982 LER 82-041/03X-1:on 820830,during Surveillance Test,Both Standby Liquid Control Sys Squib Valves Actuated.Caused by Operator Pulling Wrong Fuses.Operator Counseled ML20052F9721982-05-0303 May 1982 LER 82-003/01X-1:on 820302,during Normal Shutdown Operations,Only Two Intermediate Range Monitors in Trip Sys a Were Operable.Caused by Personnel Error & Inadequate Procedures.Procedures Revised ML20052E2811982-04-30030 April 1982 LER 82-017/03L-0:on 820402,MSIV 10% Closure Position Switches on Two Valves Did Not Trip When Tested.Caused by Mechanical Drift of Valve Position Switch Operating Cams. Adjustment Made ML20052C2511982-04-20020 April 1982 LER 82-005/01X-1:on 820315,during Normal Operation, Containment Oxygen Concentration Exceeded 4% Limit for Approx 6-h.Caused by Personnel Error.Startup Checkoff List Revised 1993-06-03
[Table view] Category:RO)
MONTHYEARML20045F6631993-06-25025 June 1993 LER 93-014-00 on 930529,logic Sys Functional Testing Was Incomplete Due to Test Procedure Deficiencies.Temporary Procedure Changes made.W/930625 Ltr ML20045D9081993-06-23023 June 1993 LER 93-013-00:on 930525,automatic Reactor Scram Occurred When APRM E Spiked While Indicated Water Level Approx 6%. Possibly Caused by Spiking of LPRM Input of APRM E. Radiation Sources Replaced W/Stronger sources.W/930623 Ltr ML20045D2971993-06-18018 June 1993 LER 93-012-00:on 930519,isolation Occurred When Rhr/Lpci Pump B Started in Shutdown Cooling Mode & Inboard & Outboard Isolation Valves Closed.Caused by Pressure Transient.Test Program Developed to Obtain Necessary data.W/930618 Ltr ML20045D1201993-06-16016 June 1993 LER 92-015-01:on 920317,deficiencies W/Potential to Effect Safe Shutdown During Postulated Fires Identified Due to Lack of Commitment to Fire Protection Implementation by Mgt.Plant Mods scheduled.W/930616 Ltr ML20045A3931993-06-0303 June 1993 LER 91-029-01:on 911130 & 1213,false Primary Containment High Radiation Isolation Sys Occurred.Caused by Filters Attached to Input of Monitors.Correct Operation of Isolation of Primary Containment Vent & Valves confirmed.W/930603 Ltr ML20044F6211993-05-19019 May 1993 LER 93-010-00:on 930420,HPCI Declared Inoperable Due to Grounded Electric Circuit on Turbine Steam Supply Valve. Caused by Personnel Inattention to Detail.Personnel Counseled Re Need for Attention to detail.W/930519 Ltr ML20044F6111993-05-19019 May 1993 LER 93-009-00:on 930420,noted That Abrupt Reduction in Feedwater Flow Resulted in Rapidly Decreasing Rwl.Caused by Loose Electrical Connection on Reactor Feed Pump A.Post Trip Evaluation Conducted to Prevent recurrence.W/930519 Ltr ML20044D2051993-05-11011 May 1993 LER 93-008-00:on 930412,identified That SJAE Radiation Monitor Had Increased.Caused by Failure to Identify Need to Obtain an Offgas Sample.Daily Instrument Surveillance Test changed.W/930511 Ltr ML20044B6181993-02-11011 February 1993 LER 93-035-01:on 920825,circuit Breaker Supplying Power to Load Ctr step-down Transformer Tripped Due to High Phase Current & Grounding.Caused by Deteriorated Transformer Coil Insulation.Transformer Rebuilt & reinstalled.W/920211 Ltr ML20024H0831991-05-13013 May 1991 LER 91-005-00:on 910412,torus Water Temp Instrumentation Declared Inoperable.Caused by Uncertainty of 3.52 F. Conservative 4 Degree Bias Installed in Torus Water Instrumentation Software program.W/910513 Ltr ML20024G6831991-04-17017 April 1991 LER 91-004-00:on 910318,unmonitored Release of Radioactivity Detected Outside Auxiliary Boiler Bldg.Caused by Personnel Error & Deficiencies in Procedures.Contaminated Surfaces Covered W/Reinforced Plastic covers.W/910417 Ltr ML20028H8611991-01-25025 January 1991 LER 90-025-01:on 901115 & 1226,in Total,Five Svc Water to Emergency Svc Water Swing Check Valves Failed to Close During Testing.Caused by Corrosion Problems.Valve Internals Replaced W/Stainless Steel components.W/910125 Ltr ML20028G9451990-09-25025 September 1990 LER 90-003-01:on 900129,core Overpower Events Occurred Due to Feed Flow Transmitter Calibr.Caused by Previously Unidentified Vendor Design Error,Error Introduced as Result of Plant Mod & Improper prioritization.W/900925 Ltr ML20043J0861990-06-21021 June 1990 LER 90-017-00:on 900526,instrument Setpoint Drift Exceeds Tech Spec Limit for HPCI Turbine Trip on High Reactor Water Level.Cause Unknown.Transmitter Included in Program for Weekly Monitoring of Rosemount transmitters.W/900621 Ltr ML20043B9831990-05-23023 May 1990 LER 90-016-00:on 900424,automatic Isolation Signal Closed Suction Valves from Reactor Water Recirculation Sys.On 900425,suction Valves Closed & RHR Pump Tripped.Caused by Chattering Pressure Switch.Switches replaced.W/900523 Ltr ML20043A9601990-05-21021 May 1990 LER 90-015-00:on 900420,discovered That Prerequisite Surveillance Test of source-range Monitors Not Performed Prior to Beginning Replacement of LPRMs on 900419.Caused by Procedure Deficiency.Lprm Procedure revised.W/900521 Ltr ML20042G8311990-05-10010 May 1990 LER 90-014-00:on 900410,primary Containment Isolation Check Valve Declared Inoperable Due to Missing Spring.Caused by Personnel Error.Performance of HPCI Turbine Exhaust Drain Sys Will Be Monitored During HPCI testing.W/900510 Ltr ML20042G8301990-05-0909 May 1990 LER 90-013-00:on 900409,shutdown Cooling Automatically Isolated During Transfer of Bus.Probably Caused by Contract Personnel Accidentally Knocking Jumper Loose.Procedures Re Controls on Jumpers Will Be revised.W/900505 Ltr ML20042F7531990-05-0303 May 1990 LER 90-012-00:on 900404,normal & Emergency Svc Water Valves Found to Be Inoperable.Caused by Excessive Build Up of Corrosion on Valve Surfaces & Accumulation of Silt.Valves Cleaned & Restored to svc.W/900503 Ltr ML20012E0071990-03-21021 March 1990 LER 90-005-00:on 900220,HPCI Sys Inoperable Resulting in 7 Day Limiting Condition for Operation.Caused by Sticking or Binding in Remote Servo.Remote Servo replaced.W/900321 Ltr ML20012C5161990-03-0909 March 1990 LER 90-004-00:on 900207,isolation of RCIC Sys Occurred, Resulting in Initiation of 7-day Limiting Condition of Operation.Caused by Failure of Master Trip Unit.Subj Unit replaced.W/900309 Ltr ML20012B4351990-03-0202 March 1990 LER 90-003-00:on 900129,when More Accurate Transmitters Placed in Svc,After Calibr Span Values Adjusted,Indicated Power Exceeded Core Thermal Power Limit.Caused by Incomplete Review of Manual.Transmitters recalibr.W/900302 Ltr ML20006E8621990-02-16016 February 1990 LER 90-001-00:on 900119,reactor Scram Occurred During Calibr of Reactor Water Level Instrumentation,Resulting in Valve Packing Leak & Causing False Low Water Level.Caused by Rapid Valve Movement.Event reviewed.W/900216 Ltr ML20006E9221990-02-15015 February 1990 LER 90-002-00:on 900215,reactor High Pressure Isolation Logic Tripped & Isolated RHR Shutdown Cooling Sys B as Sys Being Started.Hydraulic Pressure Transient Suspected as Cause.Operating Procedure revised.W/900215 Ltr ML20006E2101990-02-12012 February 1990 LER 89-019-01:on 891031,HPCI Turbine Declared Inoperable Due to Electrical Ground in Speed Control Circuit.Caused by Conductive Corrosion Products Between Amphenol Type Connector & Mounting Plate.Connector cleaned.W/900212 Ltr ML20006E2291990-02-0808 February 1990 LER 89-018-01:on 891008,HPCI High Steam Flow Signal Closed HPCI Outboard Steam Supply Isolation Valves,Causing Isolation of Logic Circuit.Caused by Overly Conservative Value for Flow Isolation Signal.Sensor vented.W/900208 Ltr ML20011E1431990-01-29029 January 1990 LER 89-020-01:on 891105,reactor Scram Initiated by High APRM Neutron Flux from Pressure Transient from Turbine Control Valve Closure.Caused by Void Collapse in Core Moderator. Computer Programming Changed Re Transient data.W/900129 Ltr ML20006C1571990-01-26026 January 1990 LER 89-026-00:on 891105,reactor Scram from Full Power Occurred Due to Problems W/Turbine electro-hydraulic Control Sys.On 891220,contractor Notified Util That Valves Tested Did Not Actuate within Setpoint as required.W/900126 Ltr ML20005E8541990-01-0202 January 1990 LER 89-025-00:on 891130,isolation Signal Closed Outboard Isolation Valves on Steam Supply Line to HPCI Sys,Rendering HPCI Sys Inoperable & Initiating 7-day Limiting Condition for Operation.Caused by Excess steam.W/900102 Ltr ML20042D3961989-12-27027 December 1989 LER 89-024-00:on 891129,RCIC Sys Inoperable for 14 Minutes During Monthly Surveillance Test.Caused by Personnel Error. Outboard Isolation Valve Opened & Critique & Discussion W/ Technicians Held to Increase Event awareness.W/891227 Ltr ML20011D1351989-12-12012 December 1989 LER 89-023-00:on 891112,reactor Scram Occurred During Scheduled Surveillance Test of Safety Relief Valves.Caused by High Neutron Flux Signal Due to Steam Pressure Transient. Change Made to Surveillance Test ST-22B.W/891212 Ltr ML19332F4751989-12-0707 December 1989 LER 89-022-00:on 891107,determined That Elastomeric Seals in 33 Snubbers Had Not Been Replaced within Plant 7-yr Svc Life Guideline.Caused by Failures in Mgt of Maint Records. Snubbers Replaced as necessary.W/891207 Ltr ML19332F4511989-12-0505 December 1989 LER 89-020-00:on 891105,reactor Scram Occurred Due to Failure in Electronic Control Card of electro-hydraulic Control Sys.Caused by Void Collapse in Core Moderator. Circuit Boards Sent to Vendor for analysis.W/891205 Ltr ML19332E6241989-11-30030 November 1989 LER 89-019-00:on 891031 & 891103,HPCI Sys Declared Inoperable Due to Electrical Ground in Speed Control Circuit.Caused by Buildup of Conductive Corrosion Products. Connector Cleaned & Sys Returned to svc.W/891130 Ltr ML19332F0471989-11-30030 November 1989 LER 89-021-00:on 891031,circuit Breaker for RCIC Inboard Injection Valve to Feedwater Sys Tripped During Required Valve Testing.Caused by Fault in Motor Winding Insulation. New Motor installed.W/891130 Ltr ML19325F2791989-11-13013 November 1989 LER 89-007-01:on 890509,surveillance of Fire Barrier Penetrations,Per Tech Spec 4.12.F Not Conducted within Allowed Time Period.Caused by Misinterpretation of Fire Protection Ref Manual.Fire Watch established.W/891113 Ltr ML19327C1351989-11-0707 November 1989 LER 89-015-01:on 890918,two Remote Manually Operated Diaphragm Air Operated Isolation Valves Failed Closing Time Acceptance Criteria.Caused by Buildup of Iron Oxide Sludge. Valves Disassembled & Cleaned ML19327B9821989-11-0606 November 1989 LER 89-018-00:on 891008,HPCI High Steam Flow Signal Closed Isolation Valves for Outboard Steam Supply & Steam Line Warning.Caused by Air in Sensing Sys Leading to Unstable Oscillation.Pressure Sensor Vented & calibr.W/891106 Ltr ML19324B1151989-10-23023 October 1989 LER 88-008-01:during 1988 Refuel Outage,One Primary Containment Penetration Exceeded Tech Spec 4.7.A.2.b Limit When Subjected to Local Leak Rate Testing.Leakage Attributed to Wear.Valves replaced.W/891023 Ltr ML19327B1521989-10-20020 October 1989 LER 89-017-00:on 890920,ESFAS Initiated Group II Primary Containment Isolation Signal Triggering RHR & LPCI Sys Isolations.Caused by Cognitive Human Error in Not Finding Isolation Signal.Fuse Replaced & Sys restarted.W/891020 Ltr ML19327B1501989-10-18018 October 1989 LER 89-016-00:on 890918,scram Signal Automatically Initiated During Transfer of Power Supply for Reactor Protection Sys. Caused by Lack of Caution Statement in Procedure.Procedure Revised to Add Time Caution for Bus transfers.W/891018 Ltr ML19327B1331989-10-18018 October 1989 LER 89-015-00:on 890918,two of Nine Remote Manually Operated Diaphragm Air Operated Containment Isolation Valves Failed Acceptance Criteria for Closing Time.Caused by Buildup & Hardening of Iron Oxide Sludge.Valves cleaned.W/891018 Ltr ML20024A8271983-06-20020 June 1983 LER 83-023/01T-0:on 830607,water Seepage Discovered from Weld in Stainless Steel Pipe Section of Control Rod Hydraulic Return Line.Caused by Intergranular Stress Corrosion Cracking.Piping Will Be removed.W/830620 Ltr ML20024A8571983-06-18018 June 1983 LER 83-021/03L-0:on 830605,rod Block Calibr Not Performed within 7 Days of 830603 Planned Reactor Shutdown.Caused by Inadequate Mgt Controls to Implement Tech Specs.Procedures to Be revised.W/830618 ML20024A8631983-06-16016 June 1983 LER 83-022/03L-0:on 830607,during Performance of Local Leak Rate Testing of Containment Spray,Penetration X-39A Found W/ Leakage That May Exceed Tech Spec Limits.Cause Undetermined. Details Will Be Provided within 30 days.W/830616 Ltr ML20028D6951983-01-11011 January 1983 LER 82-057/03L-0:on 821216,during Normal Operation,Reactor Scrammed on High Neutron Flux on Power Range Monitors. Caused by Reactor Pressure Spike Created by Sudden Closure of One MSIV Due to Improper Maint.Procedure Changed ML20027B5291982-09-10010 September 1982 LER 82-041/03X-1:on 820830,during Surveillance Test,Both Standby Liquid Control Sys Squib Valves Actuated.Caused by Operator Pulling Wrong Fuses.Operator Counseled ML20052F9721982-05-0303 May 1982 LER 82-003/01X-1:on 820302,during Normal Shutdown Operations,Only Two Intermediate Range Monitors in Trip Sys a Were Operable.Caused by Personnel Error & Inadequate Procedures.Procedures Revised ML20052E2811982-04-30030 April 1982 LER 82-017/03L-0:on 820402,MSIV 10% Closure Position Switches on Two Valves Did Not Trip When Tested.Caused by Mechanical Drift of Valve Position Switch Operating Cams. Adjustment Made ML20052C2511982-04-20020 April 1982 LER 82-005/01X-1:on 820315,during Normal Operation, Containment Oxygen Concentration Exceeded 4% Limit for Approx 6-h.Caused by Personnel Error.Startup Checkoff List Revised 1993-06-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARJAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data JAFP-99-0261, Monthly Operating Rept for Aug 1999 for Jafnpp.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Jafnpp.With JAFP-99-0236, Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with ML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept JAFP-99-0211, Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with1999-06-0202 June 1999 Annual Summary of Changes,Tests & Experiments for 1997/1998. with JAFP-99-0181, Monthly Operating Rept for May 1999 for Jafnpp.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Jafnpp.With JAFP-99-0166, Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With JAFP-99-0142, Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0092, Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc JAFP-99-0011, Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20198F9991998-12-0404 December 1998 Assessment of Licensing Basis for Use of Containment Overpressure Credit for Net Positive Suction Head Analyses Power Authority of State of New York,James a Fitzpatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves JAFP-98-0396, Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195J7521998-11-18018 November 1998 Rev 7 to Jaf Colr ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20197G6221998-11-0606 November 1998 Non-proprietary Rev 7 to HI-971661, Licensing Rept for Reracking of Ja FitzPatrick Sfp ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI JAFP-98-0360, Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20155C2821998-10-30030 October 1998 Non-proprietary Rev 0 to GENE-187-30-1598 Np, CRD Bolting Flaw Evaluation for Ja FitzPatrick Nuclear Power Plant ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 JAFP-98-0322, Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With ML20153D2591998-09-21021 September 1998 SER Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20153B5611998-09-0101 September 1998 Rev 1 to JAF-SE-98-013, RHR & Core Spray Suppression Pool Suction Strainer Replacement ML20151X6891998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Ja FitzPatrick Nuclear Power Plant ML20237E8361998-08-25025 August 1998 Rev 6 to Colr ML20237E9471998-08-0808 August 1998 Rev 6 to Colr JAFP-98-0264, Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant ML20236X5881998-07-29029 July 1998 Safety Evaluation Supporting Amend 245 to License DPR-59 ML20236V8181998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief from Implementation of Requirements of 10CFR50.55a Related to Containment Repair & Replacement Activities for James a FitzPatrick Nuclear Power Plant ML20153B5781998-07-28028 July 1998 Rev 0 to JAF-SE-98-025, HPCI & RCIC Suppression Pool Suction Strainer Replacement ML20236X3831998-07-14014 July 1998 Rev 2 to JAF-RPT-MULTI-02671, Summary of Detailed Evaluation for NRC Generic Ltr 96-06 ML20154L9201998-07-10010 July 1998 SER Accepting Rev to Reactor Vessel Surveillance Capsule Withdrawal Schedule for James a Fitzpatrick Nuclear Power Plant JAFP-98-0222, Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0193, Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant1998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0128, Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively JAFP-98-0091, Monthly Operating Rept for Feb 1998 for JAFNPP1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for JAFNPP ML20202G9081998-02-0606 February 1998 Safety Evaluation Re Amend to License DPR-59 to Revise TS Tables 3.2-2 & 4.2-2 JAFP-98-0058, Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant 1999-09-30
[Table view] |
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._ .. -__ ___________, . .
i Jamss A.FitzPctrick i
= Nuclear Powir Pl:nt ..
P.O. Box 41 Lycoming, New York 13093 j 315 342-3840 i
- > NewYo.rkPower Harry P. Salmon, Jr.
& Authority nesieeni uenege, l
June 3, 1993 i JAFP-93-0318
' l l
United States Nuclear Regulatory Commission i Document Control Desk i Mail Station P1-137 Washington, D.C. 20555 )
SUBJECT:
DOCKET NO. 50-333 LICENSEE EVENT REPORT: 91-029 Spurious Trips of Primary Containment Vent and Purge Isolation System
Dear Sir:
This updated report is submitted in accordance with 10 CFR 50.73 (a) (2) (iv) .
Questions concerning this report may be addressed to Mr. Eric Mulcahey at (315) 349-6458.
Very truly yours,
/ , f IARRY P.' SALMON, J W .
HPS. M: tid Enclosure cc: USNRC, Region i USNRC Resident Inspector INPO Records Center 9
93051'00190 930603 i PDR ADDCK 05000333 S PDR .\
NRC FORM 3t,1I U.S NUCLE AR RE GUI.ATORY COMMISSION 1,6 Sp APPROVED OMB190 3150 0104 E XPIRE S 4/30/92 ESTIMATED BURDEN 8'E R RESPONSE TO COMPL Y WTH THIS LlCENSEE EVENT REPORT (LEF SIMvENIs'UGNo'i'G fu7 o"MEsV[uAYE "%'RICO Os AND REPORTS MANAGEMENT BR ANCH IP 5308, U.S NUCLE AR HEGUL ATORY COMMIS510N. W ASHa3 TON. DC 20555. AND TO THE PAPERWORK RE DUCitON PROJECT (31500104). OFF ICE OF MANAGEMENT AND BUDGET. WASHINGTON. DC 20503 FQCtLITY NAME (1) DOCKET NUMBE R (2) F AGE 43 James A. FitzPatrick Nuclear Power Plant o l5 ; O io ; o l3i 3 } i lorlc) g TITLE tai Spurious Trips of Primary Containment Vent and Purge Isolation Systen EVENT DATE (51 LER NUMBER (6) REPORT DAT E 471 OTHE R F ACILITIES INVOLVED 18)
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Update Report - Previous Report Date, Janubry 2, 1992 EIIS Codes are in []
False primary containment [NH] high radiation isolation system [JM]
signals occurred at 1431 and 1938 on November 30, 1991, and again at 1114 on December 13, 1991, while the reactor was shutdown in the cold condition. The 12 primary containment isolation valves which are activated by these signals were already closed or went closed in response. Before two of the actuations, a two-way radio was being keyed in the vicinity of the radiation monitors and at the time of the third, a cable penetration fire seal inspection was being conducted within the monitor cabinet and a Technical Specification surveillance test was being performed on main steam line radiation monitors located in adjacent cabinets. The pathways for initiation of the monitor trips was through a filter assembly. The filters were found attached to the input of the monitors during a root cause investigation. The filters were removed from the monitor inputs before the plant was restarted in January, 1993, to eliminate monitor trips by this pathway. The root cause investigation and analysis was completed during the 1992 Refueling Outage.
NRCForm3661649i
NRC 7ORM 3600 U S. NUCL EQR REGULQTOR Y COMMISSION EmrtRES:4/30/92
-
- a LICENSEE EVENT REPORT (LER) ES'l"^4E%'d8[Epy"o'gM11' R r fo
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FAC6LITY NAME (11 Dock ET NUMBER (2) LER NUMBER (Si PAGE(3)
YEAR SIDI"' Ab -AI*"
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James A. FitzPatrick Nuclear Power Plan :
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Description While the reactor was shutdown and in a cold condition on November 30, 1991, two invalid actuations of the primary containment [NH] vent and purge valves isolation system occurred. The first actuation was initiated at 1431 by the primary containment high range radiation monitor [JM] channel A and the second initiated at 1938 by high range radiation monitor channel B. At 1114 on December 13, 1991, with the reactor still in the cold condition, high range radiation monitor channel A again initiated an invalid isolation of the primary containment [NH] vent and purge valves system.
Just before the November 30, 1991, actuations a two-way radio was being keyed in the proximity of the control room cabinets containing the high range radiation monitors. The 1431 actuation, initiated the tripping of division I (channel A) isolation logic circuity (outboard vent and purge valves) and the 1938 actuation initiated the tripping of division II (channel B) isolation logic circuity (inboard vent and purge valves). During the December 13, 1991 actuation, two work ;
activities were being conducted within the vicinity of the Primary l Containment high range radiation monitors, one was the performance of l a Technical Specification (TS) table 4.1-2 Main Steam Line Radiation '
Monitor channel A calibration surveillance and the second was a fire seal inspection of cable penetrations by craft electricians within the cabinet containing the monitors. Two attempts to repeat the actions ,
of the craft electricians failed to reproduce an actuation of the monitors and the surveillance testing was continued without further incidence of spurious actuation of the high range radiation monitors.
At tne conclusion of each actuation, the isolation logic was reset and occurrence reports (OR) initiated by the station operators.
l Cause After experiencing repeated actuation of the primary containment [NH]
vent and purge isolation systems and also other ventilation systems caused by spurious (invalid) initiation of radiation monitors, a radiation monitoring specialist was contracted to perform a field investigation and analysis of the causes. A study was conducted during the 1992 refueling outage. The specialist started a NRC Form 366A (Mt91
RC FORM 336A U.S NUCLE AR REGULATOR Y COMMISSION E xPIRES 4/30/92
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OF MAN AGEMENT AND SUDGET, W ASHtNGTON. DC 20f F ACILIT V NAME O f DOCKti NUM8t R (2) LE R NUMSIR 46) PAGE (3)
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.aem a cr- w.nm preliminary inspection of the monitors environment, circuitry configuration and interconnection relationships on December 9, 1991. -
The primary containment high range radiation monitors with a high number of random actuations were selected to be investigated first, studying the sensitivity of the monitors to external (electrical and magnetic) noise. A possible pathway for the introduction of the noise into the input of the monitors had been identified from.the preliminary investigation. In LER-91-030, it was described as a filtering network attached to the inputs of the high range radiation monitors which is believed to have been used for evaluations of Electromagnetic Interference (EMI) during field tests. In-depth analysis was performed to quantify the effect of the filter assembly on the monitors performance.
The filter was found to have a significant effect on EMI susceptibility. The assembly was poorly shielded and the assembly design was such that it would rectify (and the monitor would amplify) any EMI induced noise. This was verified by keying a hand held radio to demonstrate the EMI susceptibility of the circuit with and without the filter in place.
Analysis The activation of the primary containment vent and purge valves isolation logic is reportable under provisions of 10CFR50.73 (a) (2) (iv) as an actuation of an Engineered Safety feature [JE]. There were no system or equipment failures. The 12 isolation valves which received the close signal were already in the closed (isolated) position or went closed (isolated) when actuated by the logic circuitry. The isolation logic initiating signal was not a true high radiation signal. There was no potential for adverse safety consequences generated by this event.
Corrective Actions
- 3. Correct operation of the isolation of the primary containment vent and purge valves system was confirmed. The isolations were then reset and occurrence reports initiated.
- 2. The Control Room operators removed the two-way radios from the Control Room and posted signs on Control Room [NA] entrance doors warning against use of radios in the Control Room.
NRC Form 366A 16419)
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- 3. The attached filter to the high range radiation monitors was removed prior to restart after the 1992 Outage, also the signal input cables were shortened and rerouted to lessen adverse effects of Electromagnetic Interference (EMI).
I Additional Information Related LERs: 90-028 An electrical noise spike resulting from a l high voltage measurement on a radiation monitor caused a partial isolation of the reactor building (secondary containment) [NG]
ventilation system.91-001 An electrical noise spike resulting from a high voltage measurement on service water effluent (KG] process radiation monitor caused primary containment high range radiation monitor B to initiate an isolation of primary containment vent and purge isolation valves.91-018 A random electrical noise spike (source unknown) caused primary containment high range monitor A to initiate an isolation of primary containment vent and purge isolation logic circuitry.91-022 A spurious noise spike believed to have been generated by an isolation delay timer caused primary containment high range radiation monitor A to initiate an isolation of primary containment vent and purge isolation logic circuitry.91-030 Assemblies (fi]*ers) on the input of the primary containment high range radiation monitors have been the cause of the spurious isolations of the vent and purge valves.
Reason for Update: This LER is updated to provide the results of the j evaluation of the effects of the filter assembly found attached to the input to the primary containment high range radiation monitors. A vertical bar in the right hand margin indicates text changes (except where minor editorial or typographical errors were corrected.
NRC Form 366A 16494
.