ML19210D062
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| ML19210D062 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/16/1979 |
| From: | W. Verne Childs POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19210D057 | List: |
| References | |
| LER-79-094-03L, LER-79-94-3L, NUDOCS 7911200487 | |
| Download: ML19210D062 (2) | |
Similar Documents at FitzPatrick | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045F6631993-06-25025 June 1993
[Table view]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 Category:RO) MONTHYEARML20045F6631993-06-25025 June 1993
[Table view]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 Category:TEXT-SAFETY REPORT MONTHYEARJAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With1999-09-30030 September 1999
[Table view]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 |
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(7-77) o LICENSEE EVENT REPORT CONTROL BLOCo lllllh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo lil I Nl Yl Jl A Fl lj@bl 0- l 0 -l 0 O ! O l - l O ! 0 l 0 @l 4 l 1 l 1 l 1 l I l@l ll@7 8 9 LICENSEE CODE 1#15 LICENSE NUVBER 25 26 LICENSE TYPE JO 57 CM 58 CON'T s$n$Ll@ 015 l 0 O! 01 3 3131@l I l 0 2lSI719 @l111III6171 9@
" o i 7 8 60 61 DO2KET NUV8ER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h OI2 l SEE ATTACHMENT lo 3 i O 4 1 1 O s llll 0 l6 ll0 7l0 Hll7 8 9 80 SYSTEM CAUSE CAUSE C O'.? P.VALVE CODE CODE SU8 CODE COYPONENT CODE SU8 CODE SUBCODEl Al Bl@E @ l Fl@ lV l A L lV lE lX @ lX@ lHlh o 9 7 8 9 10 11 12 13 18 in 20 SEQUENTIAL OCCURRENCE REFORT REVISION , EVENT YE AR REPORT NO CODE TYPE NO.*O lLER ROl7l9ll-ll0l9l4ll/l 013 lLll-l[0_j Ep,0_ 21 22 23 24 26 27 28 , . 29 30 31 32 TAKE A T ON O PLANT ETH HOURS S 8 IT D FCFP [UB.SUPP LI E MAN FACTURER U@[_2_j@W@Zl@l0l0 0l0llY l@lYlh IAl@lC 2l8I5l@
33 34 35 36 3/40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i O I SEE ATTACHMENT l 1 1lli I ?l l l.1 3 1 11 141 1-7 8 9 80'ST S% POWER OTHE R STATUS OISCOV RY DISCOVERY DESCRIPTION Uh 1 0l0lh NAllBl@l SURVElLLANCE TEST j i 5 ACTIVITY CONTENT RELEASED OF RE LE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE li 161 [z_J @ l z l@
NAlNAl7 8 9 10 11 44 45 80 PERSONNEL E MPOSURES NUYBER DESCRIPTION TYPE @l[0 10 01 @ l l NA i 7'" *"" PERSONNEL,N;uWitS DESCRIPTION @
Nuv8ERl0 0l 0l@[NAli 8 7 8 9 11 12 80 LC S OF CH DAMAGE TO FACILITY f pC TYPE DESCRIPTION i NA-d @ll1 9 7 8'3 10 80 PUB L ICI T Y NRC USE ONLY ISSUED @ DESCRIPTION ll l I l I l l l l I l l *4
- [!1_jlNA 2 O i 7 8 9 10 68 69 80 &NAME OF PREPARER W. Verne ChiIds (31 342-1840{'PHCNE: 7 9112 00 i h
. e.-POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333 ATTACHMENT TO LCR 79-094/03L-0 Page 1 of 1 During normal operations while conducting Operations Surveillance Test F-ST-76J14, titled " Smoke and Heat Detector Functional Tests - North Cable Room," the master valve associated with the ten ton Cardox system did not open fully. The testing was being conducted to satisfy the requirements of Technical Specifications, Appendix A, Paragraphs 4.12.C.1 and 4.12.E. Continuous fire watch personnel, equipped with portable fire extinguishing equipment were posted for the areas served by the ten ton unit until repair and testing could be completed. The event did not represent a significant hazard to the public health and safety. Disassembly and inspection of the valve revealed that the valve packing had hardened due to age and restricted the valve travel. Follow-ing replacement of the packing, proper operation of the valve was verified by successful completion of F-ST-76J14 and the system was returned to service approximately two-hours after discovery of the problem. .$./3 e}}
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