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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18040A3491998-07-0202 July 1998
LER 98-017-00:on 980602,control Room Ventilation Sys Was Declared Inoperable.Caused by Original Design Deficiency. Mod Designed,Tested & Implemented Prior to Startup from RF06 to Correct Design deficiency.W/980702 Ltr
ML17059C1011998-06-24024 June 1998
LER 98-014-00:on 980525,noted Differences Between Actual Valve Weights & Weights Shown on Engineering Drawings.Caused by Vendor Failing to Provide Accurate Valve Weights.Revised Valve Drawings & Associated Calculation,Per 10CFR21
ML18040A3451998-06-0404 June 1998
LER 98-004-01:on 980302,TS Required LSFT of Level 8 Trip of Main Turbine Was Missed.Caused by Knowledge Deficiency of EHC Sys.Revised Applicable LSFT Procedures Prior to Refueling Outage 6.W/980604 Ltr
ML18040A2851993-12-0808 December 1993
LER 93-010-00:on 931108,HPCS Was Inoperable Due to Equipment Deficiency,Inadequate Managerial Methods & Poor Work Practices.Replaced Deficient Contactors & Restored Tap Setting.Also Reportable Per Part 21.W/931208 Ltr
ML18038A3191990-08-10010 August 1990
LER 90-006-00:on 891027,discovered Unverified Assumption in App R Safe Shutdown Analysis.Caused by Fire Protection Program Failure to Provide Detailed Procedural Instructions for Operator Actions.New Procedures developed.W/900810 Ltr
ML18038A4701989-05-15015 May 1989
LER 89-014-00:on 890413,unit Reactor Experienced Reactor Scram Which Was Result of Turbine Trip Due to Actuation of Generator Protection Circuitry.Turbine Trip Caused by Disconnected Wire.Wire relanded.W/890515 Ltr
ML18038A4131988-08-22022 August 1988
LER 88-051-01:on 870813,shutdown Cooling Sys Isolated & Tech Specs 3.4.9.2 Exceeded.Caused by Equipment Failure,Personnel Error & Procedural & Design Deficiencies.Shutdown Cooling Sys Manually restored.W/880822 Ltr
ML18038A4051988-07-0101 July 1988
LER 88-024-00:on 880605,ESF Actuation Occurred Due to Resetting of Failed Radiation Monitor Microcomputer.Caused by Lack of Personnel Training.Defective Cards & Modules in RE14B Microcomputer & DRMS Panel replaced.W/880701 Ltr
ML18038A3901988-04-12012 April 1988
LER 88-014-00:on 880313,reactor Scram & ESF Actuations Occurred.Caused by Equipment Failure Due to Design Deficiency.Transmitter Replaced W/Upgraded Model & Temporary Mod Performed to Bypass Logic for valves.W/880412 Ltr
ML18038A3891988-02-17017 February 1988
LER 88-001-00:on 880120,reactor Scram Occurred Due to Actual Low Water Level Condition.Caused by Design & Personnel Errors.Operator Disciplined & Mod Addressed Inadvertent Feedwater Control Valve lockup.W/880217 Ltr
ML18038A7591987-12-22022 December 1987
LER 87-023-00:on 870422,trip of Normal Reactor Bldg Ventilation & Initiation of Emergency Ventilation Occurred. Caused by Personnel Error.Fuse Replaced.On 871123,util Discovered LER Not Submitted for event.W/871222 Ltr
ML18038A2581987-06-15015 June 1987
LER 87-025-00:on 870519,secondary Containment Isolation Signal Generated Due to Technician Relanding Lifted Lead Prematurely.Caused by Breakdown in Communications.Gaitronics Phone &/Or Headset Jack installed.W/870615 Ltr
ML18004C0061987-04-13013 April 1987
LER 86-002-01:on 861104,procedure N2-OSP-RMC-W0002 Ran for Over 2 H Thereby Violating Tech Specs.Caused by Personnel Error & Procedure Deficiency.Temporary Change Notice Issued to procedure.W/870413 Ltr
ML20024E8331983-08-16016 August 1983
LER 83-021/03L-0:on 830720,22,26 & 28,emergency Cooling Sys Loop 11 Taken Out of Svc for Periods Up to 5 H.Caused by Attempt to Reseat Isolation Valve 39-05.Valve Seat Lapped & Loop Returned to svc.W/830819 Ltr
ML20024E6341983-08-0202 August 1983
LER 83-017/03L-0:on 830707,HPCI Feedwater Booster Pumps 11 & 13 Taken Out to Svc to Inspect Impellers Due to Similar Problem on nonsafety-related Pump.Parts of Strainer Found in Pumps But Pumps undamaged.W/830805 Ltr
ML20024E0251983-07-22022 July 1983
LER 83-019/03L-0:on 830623,two Monthly Surveillance Tests on Inadequate Core cooling-accident Level Monitor Missed Following 811231 Installation.Surveillance Procedures Generated & Added to schedule.W/830725 Ltr
ML20024B7711983-06-17017 June 1983
LER 83-010/03L-0:on 830524,core Topping Pump 121 Removed from Svc to Replace Packing.Caused by Air Leaking Due to Iltr Pressure Introduction in Pump.Packing Replaced & Pump Returned to Svc within 22 h.W/830621 Ltr
ML19277C5881983-06-16016 June 1983
LER 83-013/03L-0:on 830610,during Routine Surveillance,Lock Found Missing from Outside Inlet Valve 40-12 for Core Spray Sys.Valve & Breaker in Open Position.Lock Missing for No More than 15 Days.Lock replaced.W/830708 Ltr
ML20024B7101983-06-16016 June 1983
LER 83-011/03L-0:on 830604,electromatic Relief Valve 121 Failed to Open.Caused by Dirty Pilot Due to Oxide Buildup During Extended Outage.Pilot Cleaned & Retested & Normal Shutdown initiated.W/830628 Ltr
ML20023D9571983-05-24024 May 1983
LER 83-009/03L-0:on 830426,control Room Ventilation Sys Removed from Svc for Mods to Control Room Wall,Per LER 83-06.Temporary Flexible Ducting in Place During Mods. Mods Completed.Ventilation Sys Returned to svc.W/830526 Ltr
ML20023D2551983-05-11011 May 1983
LER 83-006/03L-0:on 830411,while Performing Design Review, Discovered That Poured Concrete North & West Walls of Control Room Would Not Meet Original Seismic Criteria. Mods Made to Improve Wall Structural Loading Capabilities
ML20023B8321983-04-18018 April 1983
LER 81-053/03L-1:on 811120,discovered That Single Failure of Electrical Power Supply Could Either Isolate Both Condenser Sys or Cause Failure to Isolate.Logic for Initiation & Isolation of Condenser Sys Reviewed
ML20028C8391983-01-0505 January 1983
LER 82-018/03L-0:on 821207,during Maint Outage,Leakage from Valves 68-05 & 68-08 Found Exceeding Tech Specs.Caused by Poor Seal Design.Mods Will Be Completed During Current Outage & Followed by Retest
ML20028C8361983-01-0505 January 1983
LER 82-017/03L-0:on 821206,during Maint Outage,Leakage from Valves 68-06 & 68-09 Found Exceeding Tech Specs.Caused by Poor Seal Design.Mods Will Be Completed During Current Outage & Followed by Retest
ML20027C9681982-10-19019 October 1982
LER 82-001 Has Been Canceled
ML17341B6651982-08-0505 August 1982
LER 82-011/03L-0:on 820802,oil Leak on Fuel Oil Supply Manifold Discovered on Diesel Fire Pump.Caused by Defective Braze Joint.Leak Repaired by Manufacturer
ML20050N6691982-04-0505 April 1982
LER 82-009/01T-0:on 820323,while Conducting Routine Reactor Vessel Hydrostatic Testing Prior to Startup,Water Observed Leaking from Insulation on Recirculation Piping.Cause Being Investigated
ML20050C3881982-03-29029 March 1982
LER 82-008/01T-0:on 820317,review of Surveillance Test N1-ST-R7 Revealed Potential for Reactor Steam to Leak to Atmosphere from Emergency Condenser Vents.Caused by Potential Sys Leaks.Sys Modified Per NUREG-0737 Item II.B.1
ML20052F8991982-03-24024 March 1982
LER 82-009:on 820323,during Routine Reactor Vessel Hydrostatic Testing Prior to Startup,Water Observed Leaking from Insulation on 11 Recirculation Piping Suction from Reactor Vessel.Cause Under Investigation
ML20042C5041982-03-23023 March 1982
LER 82-006/04L-0:on 820225,during Normal Operation,While Tempering Plant Inlet Canal,Plant Discharge Temp Exceeded 85 F.Caused by Increase in Lake Temp Due to Weather Conditions & Inability to Fully Lower Tempering Gate
ML20052F8461982-03-18018 March 1982
LER 82-008:on 820317,discovered Potential Path for Reactor Steam from Emergency Condenser Steam Line Vents to Atmosphere If Emergency Condenser Tube Leaks Occur.Caused by Mods Made to Comply w/NUREG-0737,Item II.B.1
ML20042A6891982-03-12012 March 1982
LER 82-007/04L-0:on 820222,while Reviewing Environ Radiation Fish Analysis Sample Data,Lower Limit of Detection Sensitivity Was Determined Not Met for Nov 1981.Cause Not Stated.Tech Spec Proposal Being Submitted to Update Stds
ML20049H6101982-02-19019 February 1982
LER 82-005/03L-0:on 820208,115 Kv Line Taken Out of Svc for Maint,Placing Plant in Limited Condition of Operation.Maint on Line Required Due to Open Loop.Line Repaired & Returned to Svc
ML20041C1651982-02-19019 February 1982
LER 82-004/01T-0:on 820207,during Routine 115-KV Breaker Exercising,Ground Directional Relay Caused Opening of Breaker Alternate 115-KV.Caused by Momentary Loss Offsite Power.Power Restored After Closing Oswego-NMP1 Breaker
ML20041C1171982-02-17017 February 1982
LER 82-003/01T-0:on 820204,at 100% Power,Reactor Bldg Ventilation Sys Isolated & Emergency Ventilation Sys Initiated Due to Radioactive Release.Caused by Overflow of Reactor Water Cleanup Sys Filter Sludge Tank
ML20041A7511982-02-10010 February 1982
LER 82-002/01T-0:on 820129,NRC Inspector Discovered That Primary Containment Following DBA LOCA May Not Be Vented Using Operating Procedure Due to Inaccessibility of Reactor Bldg.Combustible Gas Control Sys Will Be Installed
ML20052F8961982-02-0808 February 1982
LER 82-004:on 820207,during Steady State Operation,Momentary Loss of 115 Kv Offsite Power Caused Emergency Diesel Generators to auto-start on Low Voltage to Power Boards 102 & 103
ML20052F8981982-02-0505 February 1982
LER 82-003:on 820204,during Steady State Operation,Cleanup Sludge Tank Vent Overflowed Into Reactor Bldg Exhaust Ventilation Sys Causing Emergency Ventilation Sys to Initiate.Cause Not Stated.Decontamination in Progress
ML20052F8931982-02-0101 February 1982
LER 82-002:on 820129,during Steady State Power,Upon Review by Resident Inspector,Discovered That Operating Procedure Describing Steps to Vent Primary Containment Following DBA LOCA Required Personnel to Enter Reactor Bldg
ML20040B8621982-01-18018 January 1982
LER 81-054/03L-0:on 811221,insertion of Shallow Control Rods Resulted in Average Planar Linear Heat Generation Rate in Excess of Tech Spec Limits.Caused by Flux Coupling Between Control Rods.Extra Rods Inserted & Tech Specs Modified
ML20039E2951982-01-0202 January 1982
LER 81-025,is Cancelled
ML20039C0951981-12-14014 December 1981
LER 81-053/03L-0:on 811120,emergency Condensers 11 & 12 Were Isolated When Emergency Condenser Vent Radiation Monitor de-energized Due to Loss of Dc Motor Speed Control.Caused by Defective Silicon Controlled Rectifier.Rectifier Replaced
ML20038B4971981-11-25025 November 1981
LER 81-008/01X-1:on 810316,ultrasonic Testing Revealed Indication on Southeast Reactor Feedwater Nozzle Inside Bore.Caused by Inadequate Investigation.Dye Penetrant & Surface Exam Revealed Indication Nonreportable
ML20038B4561981-11-25025 November 1981
LER 81-050/03L-0:on 810715,reactor Bldg Ventilation Duct Radiation Monitor Showed Abnormal Spiking Which Initiated Emergency Ventilation Sys.Caused by Malfunctioning sensor-convertor Unit.Unit Replaced & Calibr
ML20038B8801981-11-24024 November 1981
LER 81-052/03L-0:on 810812,failure of One Reactor Vessel Electromatic Relief Valve Thermocouple & Two Reactor Vessel Head Safety Valve Thermocouples Noted in Testing.Cause to Be Investigated Given Drywell Access in Next Cold Shutdown
ML20038B7701981-11-24024 November 1981
LER 81-049/03L-0:on 811112,during Normal Operation,Feedwater Hydraulic Snubber 29-HS-6 Taken Out of Svc for Preventative Maint Because of Small Oil Leak.Cause Not Stated.Snubber Rebuilt & Returned to Svc
ML20038B4581981-11-20020 November 1981
LER 81-051/04L-0:on 811109,while Reviewing Environ Radiation Fish Analysis Sample Data,Lower Limit of Detection Sensitivity (LLD) Not Met.Caused by Higher LLD Values When Test Data Converted from Wet to Dry Weight Units
ML20011A4851981-09-30030 September 1981
LER 81-046/04T-0:on 810922,review of 810813 & 14 ETS Semiannual Samples of Cladophora Showed Co-60 & Nb-95 at Level of 10 Times Control Value.Probably Caused by Liquid Effluent Discharge & Oct 1980 Chinese Weapons Test
ML20010G6931981-09-10010 September 1981
LER 81-042/04T-0:on 810831,during Weekly Environ Radiation Monitor Insp,Only Six Monitors Found Functioning Due to Defective Power Supply Units.Cause Unknown.Portable Monitor Installed
ML20010G4341981-09-0404 September 1981
LER 81-040/03L-0:on 810818,chromated Water Found in Diesel Generator 102 Raw Water Due to Water Leaking Through Heat Exchangers.Cause Unknown.Raw Water Lines Drained & All Chromate Recovered
1998-07-02
[Table view]
Category:RO)
MONTHYEARML18040A3491998-07-0202 July 1998
LER 98-017-00:on 980602,control Room Ventilation Sys Was Declared Inoperable.Caused by Original Design Deficiency. Mod Designed,Tested & Implemented Prior to Startup from RF06 to Correct Design deficiency.W/980702 Ltr
ML17059C1011998-06-24024 June 1998
LER 98-014-00:on 980525,noted Differences Between Actual Valve Weights & Weights Shown on Engineering Drawings.Caused by Vendor Failing to Provide Accurate Valve Weights.Revised Valve Drawings & Associated Calculation,Per 10CFR21
ML18040A3451998-06-0404 June 1998
LER 98-004-01:on 980302,TS Required LSFT of Level 8 Trip of Main Turbine Was Missed.Caused by Knowledge Deficiency of EHC Sys.Revised Applicable LSFT Procedures Prior to Refueling Outage 6.W/980604 Ltr
ML18040A2851993-12-0808 December 1993
LER 93-010-00:on 931108,HPCS Was Inoperable Due to Equipment Deficiency,Inadequate Managerial Methods & Poor Work Practices.Replaced Deficient Contactors & Restored Tap Setting.Also Reportable Per Part 21.W/931208 Ltr
ML18038A3191990-08-10010 August 1990
LER 90-006-00:on 891027,discovered Unverified Assumption in App R Safe Shutdown Analysis.Caused by Fire Protection Program Failure to Provide Detailed Procedural Instructions for Operator Actions.New Procedures developed.W/900810 Ltr
ML18038A4701989-05-15015 May 1989
LER 89-014-00:on 890413,unit Reactor Experienced Reactor Scram Which Was Result of Turbine Trip Due to Actuation of Generator Protection Circuitry.Turbine Trip Caused by Disconnected Wire.Wire relanded.W/890515 Ltr
ML18038A4131988-08-22022 August 1988
LER 88-051-01:on 870813,shutdown Cooling Sys Isolated & Tech Specs 3.4.9.2 Exceeded.Caused by Equipment Failure,Personnel Error & Procedural & Design Deficiencies.Shutdown Cooling Sys Manually restored.W/880822 Ltr
ML18038A4051988-07-0101 July 1988
LER 88-024-00:on 880605,ESF Actuation Occurred Due to Resetting of Failed Radiation Monitor Microcomputer.Caused by Lack of Personnel Training.Defective Cards & Modules in RE14B Microcomputer & DRMS Panel replaced.W/880701 Ltr
ML18038A3901988-04-12012 April 1988
LER 88-014-00:on 880313,reactor Scram & ESF Actuations Occurred.Caused by Equipment Failure Due to Design Deficiency.Transmitter Replaced W/Upgraded Model & Temporary Mod Performed to Bypass Logic for valves.W/880412 Ltr
ML18038A3891988-02-17017 February 1988
LER 88-001-00:on 880120,reactor Scram Occurred Due to Actual Low Water Level Condition.Caused by Design & Personnel Errors.Operator Disciplined & Mod Addressed Inadvertent Feedwater Control Valve lockup.W/880217 Ltr
ML18038A7591987-12-22022 December 1987
LER 87-023-00:on 870422,trip of Normal Reactor Bldg Ventilation & Initiation of Emergency Ventilation Occurred. Caused by Personnel Error.Fuse Replaced.On 871123,util Discovered LER Not Submitted for event.W/871222 Ltr
ML18038A2581987-06-15015 June 1987
LER 87-025-00:on 870519,secondary Containment Isolation Signal Generated Due to Technician Relanding Lifted Lead Prematurely.Caused by Breakdown in Communications.Gaitronics Phone &/Or Headset Jack installed.W/870615 Ltr
ML18004C0061987-04-13013 April 1987
LER 86-002-01:on 861104,procedure N2-OSP-RMC-W0002 Ran for Over 2 H Thereby Violating Tech Specs.Caused by Personnel Error & Procedure Deficiency.Temporary Change Notice Issued to procedure.W/870413 Ltr
ML20024E8331983-08-16016 August 1983
LER 83-021/03L-0:on 830720,22,26 & 28,emergency Cooling Sys Loop 11 Taken Out of Svc for Periods Up to 5 H.Caused by Attempt to Reseat Isolation Valve 39-05.Valve Seat Lapped & Loop Returned to svc.W/830819 Ltr
ML20024E6341983-08-0202 August 1983
LER 83-017/03L-0:on 830707,HPCI Feedwater Booster Pumps 11 & 13 Taken Out to Svc to Inspect Impellers Due to Similar Problem on nonsafety-related Pump.Parts of Strainer Found in Pumps But Pumps undamaged.W/830805 Ltr
ML20024E0251983-07-22022 July 1983
LER 83-019/03L-0:on 830623,two Monthly Surveillance Tests on Inadequate Core cooling-accident Level Monitor Missed Following 811231 Installation.Surveillance Procedures Generated & Added to schedule.W/830725 Ltr
ML20024B7711983-06-17017 June 1983
LER 83-010/03L-0:on 830524,core Topping Pump 121 Removed from Svc to Replace Packing.Caused by Air Leaking Due to Iltr Pressure Introduction in Pump.Packing Replaced & Pump Returned to Svc within 22 h.W/830621 Ltr
ML19277C5881983-06-16016 June 1983
LER 83-013/03L-0:on 830610,during Routine Surveillance,Lock Found Missing from Outside Inlet Valve 40-12 for Core Spray Sys.Valve & Breaker in Open Position.Lock Missing for No More than 15 Days.Lock replaced.W/830708 Ltr
ML20024B7101983-06-16016 June 1983
LER 83-011/03L-0:on 830604,electromatic Relief Valve 121 Failed to Open.Caused by Dirty Pilot Due to Oxide Buildup During Extended Outage.Pilot Cleaned & Retested & Normal Shutdown initiated.W/830628 Ltr
ML20023D9571983-05-24024 May 1983
LER 83-009/03L-0:on 830426,control Room Ventilation Sys Removed from Svc for Mods to Control Room Wall,Per LER 83-06.Temporary Flexible Ducting in Place During Mods. Mods Completed.Ventilation Sys Returned to svc.W/830526 Ltr
ML20023D2551983-05-11011 May 1983
LER 83-006/03L-0:on 830411,while Performing Design Review, Discovered That Poured Concrete North & West Walls of Control Room Would Not Meet Original Seismic Criteria. Mods Made to Improve Wall Structural Loading Capabilities
ML20023B8321983-04-18018 April 1983
LER 81-053/03L-1:on 811120,discovered That Single Failure of Electrical Power Supply Could Either Isolate Both Condenser Sys or Cause Failure to Isolate.Logic for Initiation & Isolation of Condenser Sys Reviewed
ML20028C8391983-01-0505 January 1983
LER 82-018/03L-0:on 821207,during Maint Outage,Leakage from Valves 68-05 & 68-08 Found Exceeding Tech Specs.Caused by Poor Seal Design.Mods Will Be Completed During Current Outage & Followed by Retest
ML20028C8361983-01-0505 January 1983
LER 82-017/03L-0:on 821206,during Maint Outage,Leakage from Valves 68-06 & 68-09 Found Exceeding Tech Specs.Caused by Poor Seal Design.Mods Will Be Completed During Current Outage & Followed by Retest
ML20027C9681982-10-19019 October 1982
LER 82-001 Has Been Canceled
ML17341B6651982-08-0505 August 1982
LER 82-011/03L-0:on 820802,oil Leak on Fuel Oil Supply Manifold Discovered on Diesel Fire Pump.Caused by Defective Braze Joint.Leak Repaired by Manufacturer
ML20050N6691982-04-0505 April 1982
LER 82-009/01T-0:on 820323,while Conducting Routine Reactor Vessel Hydrostatic Testing Prior to Startup,Water Observed Leaking from Insulation on Recirculation Piping.Cause Being Investigated
ML20050C3881982-03-29029 March 1982
LER 82-008/01T-0:on 820317,review of Surveillance Test N1-ST-R7 Revealed Potential for Reactor Steam to Leak to Atmosphere from Emergency Condenser Vents.Caused by Potential Sys Leaks.Sys Modified Per NUREG-0737 Item II.B.1
ML20052F8991982-03-24024 March 1982
LER 82-009:on 820323,during Routine Reactor Vessel Hydrostatic Testing Prior to Startup,Water Observed Leaking from Insulation on 11 Recirculation Piping Suction from Reactor Vessel.Cause Under Investigation
ML20042C5041982-03-23023 March 1982
LER 82-006/04L-0:on 820225,during Normal Operation,While Tempering Plant Inlet Canal,Plant Discharge Temp Exceeded 85 F.Caused by Increase in Lake Temp Due to Weather Conditions & Inability to Fully Lower Tempering Gate
ML20052F8461982-03-18018 March 1982
LER 82-008:on 820317,discovered Potential Path for Reactor Steam from Emergency Condenser Steam Line Vents to Atmosphere If Emergency Condenser Tube Leaks Occur.Caused by Mods Made to Comply w/NUREG-0737,Item II.B.1
ML20042A6891982-03-12012 March 1982
LER 82-007/04L-0:on 820222,while Reviewing Environ Radiation Fish Analysis Sample Data,Lower Limit of Detection Sensitivity Was Determined Not Met for Nov 1981.Cause Not Stated.Tech Spec Proposal Being Submitted to Update Stds
ML20049H6101982-02-19019 February 1982
LER 82-005/03L-0:on 820208,115 Kv Line Taken Out of Svc for Maint,Placing Plant in Limited Condition of Operation.Maint on Line Required Due to Open Loop.Line Repaired & Returned to Svc
ML20041C1651982-02-19019 February 1982
LER 82-004/01T-0:on 820207,during Routine 115-KV Breaker Exercising,Ground Directional Relay Caused Opening of Breaker Alternate 115-KV.Caused by Momentary Loss Offsite Power.Power Restored After Closing Oswego-NMP1 Breaker
ML20041C1171982-02-17017 February 1982
LER 82-003/01T-0:on 820204,at 100% Power,Reactor Bldg Ventilation Sys Isolated & Emergency Ventilation Sys Initiated Due to Radioactive Release.Caused by Overflow of Reactor Water Cleanup Sys Filter Sludge Tank
ML20041A7511982-02-10010 February 1982
LER 82-002/01T-0:on 820129,NRC Inspector Discovered That Primary Containment Following DBA LOCA May Not Be Vented Using Operating Procedure Due to Inaccessibility of Reactor Bldg.Combustible Gas Control Sys Will Be Installed
ML20052F8961982-02-0808 February 1982
LER 82-004:on 820207,during Steady State Operation,Momentary Loss of 115 Kv Offsite Power Caused Emergency Diesel Generators to auto-start on Low Voltage to Power Boards 102 & 103
ML20052F8981982-02-0505 February 1982
LER 82-003:on 820204,during Steady State Operation,Cleanup Sludge Tank Vent Overflowed Into Reactor Bldg Exhaust Ventilation Sys Causing Emergency Ventilation Sys to Initiate.Cause Not Stated.Decontamination in Progress
ML20052F8931982-02-0101 February 1982
LER 82-002:on 820129,during Steady State Power,Upon Review by Resident Inspector,Discovered That Operating Procedure Describing Steps to Vent Primary Containment Following DBA LOCA Required Personnel to Enter Reactor Bldg
ML20040B8621982-01-18018 January 1982
LER 81-054/03L-0:on 811221,insertion of Shallow Control Rods Resulted in Average Planar Linear Heat Generation Rate in Excess of Tech Spec Limits.Caused by Flux Coupling Between Control Rods.Extra Rods Inserted & Tech Specs Modified
ML20039E2951982-01-0202 January 1982
LER 81-025,is Cancelled
ML20039C0951981-12-14014 December 1981
LER 81-053/03L-0:on 811120,emergency Condensers 11 & 12 Were Isolated When Emergency Condenser Vent Radiation Monitor de-energized Due to Loss of Dc Motor Speed Control.Caused by Defective Silicon Controlled Rectifier.Rectifier Replaced
ML20038B4971981-11-25025 November 1981
LER 81-008/01X-1:on 810316,ultrasonic Testing Revealed Indication on Southeast Reactor Feedwater Nozzle Inside Bore.Caused by Inadequate Investigation.Dye Penetrant & Surface Exam Revealed Indication Nonreportable
ML20038B4561981-11-25025 November 1981
LER 81-050/03L-0:on 810715,reactor Bldg Ventilation Duct Radiation Monitor Showed Abnormal Spiking Which Initiated Emergency Ventilation Sys.Caused by Malfunctioning sensor-convertor Unit.Unit Replaced & Calibr
ML20038B8801981-11-24024 November 1981
LER 81-052/03L-0:on 810812,failure of One Reactor Vessel Electromatic Relief Valve Thermocouple & Two Reactor Vessel Head Safety Valve Thermocouples Noted in Testing.Cause to Be Investigated Given Drywell Access in Next Cold Shutdown
ML20038B7701981-11-24024 November 1981
LER 81-049/03L-0:on 811112,during Normal Operation,Feedwater Hydraulic Snubber 29-HS-6 Taken Out of Svc for Preventative Maint Because of Small Oil Leak.Cause Not Stated.Snubber Rebuilt & Returned to Svc
ML20038B4581981-11-20020 November 1981
LER 81-051/04L-0:on 811109,while Reviewing Environ Radiation Fish Analysis Sample Data,Lower Limit of Detection Sensitivity (LLD) Not Met.Caused by Higher LLD Values When Test Data Converted from Wet to Dry Weight Units
ML20011A4851981-09-30030 September 1981
LER 81-046/04T-0:on 810922,review of 810813 & 14 ETS Semiannual Samples of Cladophora Showed Co-60 & Nb-95 at Level of 10 Times Control Value.Probably Caused by Liquid Effluent Discharge & Oct 1980 Chinese Weapons Test
ML20010G6931981-09-10010 September 1981
LER 81-042/04T-0:on 810831,during Weekly Environ Radiation Monitor Insp,Only Six Monitors Found Functioning Due to Defective Power Supply Units.Cause Unknown.Portable Monitor Installed
ML20010G4341981-09-0404 September 1981
LER 81-040/03L-0:on 810818,chromated Water Found in Diesel Generator 102 Raw Water Due to Water Leaking Through Heat Exchangers.Cause Unknown.Raw Water Lines Drained & All Chromate Recovered
1998-07-02
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217G2161999-10-15015 October 1999
Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend
ML20217K4631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With
ML20216J9251999-09-30030 September 1999
Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced
ML20212F7301999-09-21021 September 1999
Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs
ML20212B9081999-09-14014 September 1999
Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced
ML20212C4601999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With
ML20216F5141999-08-31031 August 1999
Rept on Status of Public Petitions Under 10CFR2.206
ML20210U4591999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With
ML20209D0291999-07-0202 July 1999
Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709
ML20210B9081999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With
ML20209F8811999-06-0808 June 1999
Rev 1 to NMP Unit 1 COLR for Cycle 14
ML20207G2261999-06-0707 June 1999
SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1
ML20196E2111999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Nmp,Unit 1.With
ML20207B0241999-05-18018 May 1999
Safety Evaluation of Topical Rept TR-107285, BWR Vessel & Intervals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996.Rept Acceptable
ML20206U5351999-05-17017 May 1999
SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2
ML20196L2301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Nmp,Unit 1.With
ML20205L0541999-04-0101 April 1999
Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis
ML20205S5701999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for NMP Unit 1.With
ML20207M9231999-03-12012 March 1999
Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results
ML20207G2671999-03-0101 March 1999
Special Rept:On 990315,Nine Mile Point,Unit 1 Declared Number 12 Containment Hydrogen Monitoring Sys Inoperable. Caused by Degraded Encapsulated Reed Switch within Flow Switch FS-201.2-1495.Technicians Replaced Flow Switch
ML20204C9971999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Nine Mile Point,Unit 1.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
ML17059C5501999-01-31031 January 1999
Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept.
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
ML20199K9331998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With
ML20210R8441998-12-31031 December 1998
1998 Annual Rept for Energy East
ML20206P2391998-12-31031 December 1998
Special Rept:On 981222,operators Removed non-TS Channel 12 Drywell Pressure Recorder & Associated TS Pressure Indicator from Svc.Caused by Intermittent Measuring Cable Connection in non-TS Recorder Circuitry.Replaced Cable
ML20206P2421998-12-30030 December 1998
Special Rept:On 981219,number 12 Hydrogen Monitoring Sys (Hms) Was Declared Inoperable When Operators Closed Valve 201.2-601.Caused by Indeterminate Failure of Valve 201.2-71. Supplemental Rept Will Be Submitted After Valve Is Repaired
ML20198M3571998-12-23023 December 1998
Special Rept:On 981210,operators Declared Number 11 Inoperable,Due to Failure of CR Chart Recorder.Caused by Inverter Board in Power Supply Circuitry of Recorder Due to Component Aging.Maint Personnel Replaced Failed Inverter
ML20198D9361998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With
ML20155E2001998-11-0202 November 1998
Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation
ML20195J4141998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Nine Mile Point Nuclear Station,Unit 1.With
ML20154D8401998-10-0505 October 1998
Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs
ML20154P1821998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Nine Mile Point Nuclear Station,Unit 1.With
ML20153B2001998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Nmpns,Unit 1.With
ML20237C6351998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Nine Mile Point Nuclear Station,Unit 1
ML20236T5911998-07-20020 July 1998
LER 98-S01-00:on 980618,security Force Member Left Nine Mile Point,Unit 2 Vehicle Gate Unattended Without Ensuring,Gate Alarm Had Been Reactivated.Caused by Inadequate Work Practice.Vehicle Gate Alarm Was Activated
ML18040A3491998-07-0202 July 1998
LER 98-017-00:on 980602,control Room Ventilation Sys Was Declared Inoperable.Caused by Original Design Deficiency. Mod Designed,Tested & Implemented Prior to Startup from RF06 to Correct Design deficiency.W/980702 Ltr
ML20236Q1701998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Nine Mile Point Nuclear Station,Unit 1
ML17059C1011998-06-24024 June 1998
LER 98-014-00:on 980525,noted Differences Between Actual Valve Weights & Weights Shown on Engineering Drawings.Caused by Vendor Failing to Provide Accurate Valve Weights.Revised Valve Drawings & Associated Calculation,Per 10CFR21
ML20151P1751998-06-16016 June 1998
Rev 0 to SIR-98-067, Evaluation of NMP Unit 2 Feedwater Nozzle-to-Safe End Weld Butter Indication (Weld 2RPV-KB20, N4D)
ML18040A3451998-06-0404 June 1998
LER 98-004-01:on 980302,TS Required LSFT of Level 8 Trip of Main Turbine Was Missed.Caused by Knowledge Deficiency of EHC Sys.Revised Applicable LSFT Procedures Prior to Refueling Outage 6.W/980604 Ltr
ML20249B4971998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Nine Mile Point Nuclear Station,Unit 1
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
ML20198B4991998-05-15015 May 1998
Non-proprietary Replacement Pages for Attachment F to Which Proposed to Change TS 5.5, Storage of Unirradiated & Sf
ML20247R1141998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Nine Mile Point Nuclear Station,Unit 1
ML20217B0621998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Nine Mile Point Nuclear Station,Unit 1
ML17059C1681998-03-19019 March 1998
Revised Niagara Mohawk Powerchoice Settlement Document for NMPC PSC Case Numbers 94-E-0098 & 94-E-0099, Vols 1 & 2
ML20217F4341998-03-19019 March 1998
SER Related to Proposed Restructuring New York State Electric & Gas Corp,Nine Mile Point Nuclear Station,Unit 2
ML17059B9051998-02-28028 February 1998
NMP Unit 1 Boat Samples Analyses Part Iii:Tension Tests, RDD:98:55863-004-000:01
1999-09-30
[Table view] |
Text
NIAGARAMOHAWKGENERATIONBUSINESSGROUPNINEMILEPOINTNUCLEARSTATION/lAKE ROAD,P.O.BOX63,LYCOMING, NEWYORK13093dune4,1998'NNP2L1788UnitedStatesNuclearRegulatory Commission Attn:DocumentControlDeskWashington, DC20555RE:DocketNo.50-410LER98-04,Supplement 1Gentlemen:
Inaccordance with10CFR50.73 (a)(2)(i)(B),
wearesubmitting LER98-04,Supplement 1,"MissedTechnical Specification RequiredLSFTofLevel8TripofMainTurbine."
Thissupplement istoclarifyactionstakentocorrectthecauseofknowledge deficiency.
Verytrulyyours,KimA.Dahlberg, PlantManager-NhG?2KAD/GJG/kap Attachment xc:Mr.H.J.Miller,RegionalAdministrator, RegionIMr.B.S.Norris,SeniorResidentInspector RecordsManagement 9806ihoi40 50004iePDRADQCK0S 0
REGULATORY COMMISSION LICENSEEEVENTREPORT(LER)ROVEDOMBNO;3!500lclEXPIRES:ESfJMATKD BURDENPERRESPONSETOCOMPLYWmlTlBSINFORMATION COLLECIION REQUESfc50AJHRS.FORWARDCOMMENISREGARDOIO BURDENESAMATKTOTIESRECORDSANDREPORTSMANAGEMENfBRANCJI(M30),U.S.NUCLEARREGULATORY COMMlSSION,WAS)BNGION,DC3M55,ANDTOTHEPAPERWORK REDUCIION PROJECTO1500104),
OFF)CHOPMANAGEMENf ANDBUDGBI;WASHINGION, DC30503FACK1IYNAME(I)NineMilePointUnit2DOCXEfNUMBER(D05000410PAGEO)1OF4TIILE(4)MissedTechnical Specification RequiredLSFTofLevel8TripofMainTurbineEVENI'ATE (5)MONIHDAY*YEARgagREVISIONNUMBERREPORTDATEG)MONBlDAYYEAROTHERFACILmESINVLVED(I)FACJLIIYNAMES0302989801060498N/AN/A0500005000OPERATING MODB(9)TIESREPORTISSUBMIITIXI PURSUANTTOTHKREQUIREMENIS OFIOCFR5:(CJ>ccac>>cc>cc>>c>cc c/dscfcJJ>>wJ>>I)
(II)POWERLEVEL(lc)J>YK~>~W020.2201(b) 020.2203(a)(1) 020.2203(a)(2)Q 020.2203(a)(2)(ii) 020.2203(a)(2)(iii) 020.2203(a)(2)(iv) 020.2203(a)(2)(v) 020.2203(a)(3)
Q020.2203(a)(3)(ii) 020.2203(a)(4) 050.36(c)(1) 050.36(c)(2) 350.73(a)(2)Q 050.73(a)(2)(ii) 0$0.73(a)(2)(iii) 0$0.73(a)(2)(v) 050.73(a)(2)(v) 050.73(a)(2)(vii) 050.73(a)(2)(viii) 050.73(a)(2)(x) 073.7i0orHHtJ>CccU>I>c>Ilcc>occ aclo>>>ccc>JJ>croc,J>BCFcc>>c555UNAMEK.D.Ward-Technical SupportManagerLICENSEECONfACfFORTIESLKR(l1).TKIZPHONB NUMBER(315)349-1043COMPLEIKONBISNBFOREACHCOMPONENf FAILUREDESCRIBED INTIESREPORT(I3)REPORTABLB TONPRDSSUPPLKMKNFAL REPORTEXPECIKD0O0YESQ'ycc,co>tpkccZXFECIKDSJtul5SJOJVJMIF>J 5EXPIATEDSUBMISSION DATE(l5)MONIHDAYABSTRACTghsltco140cPc>ccc>ac>
FFccc(>>~JJcj(/Jcasc0>IJccN>cc~
JJ>>cc)06)OnMarch2,1998,NiagaraMohawkPowerCorporation (NMPC)determined thattheNineMilePointUnit2(MMP2)LogicSystemFunctional Tests(LSFT)forthemainturbinetriponhighreactorvessellevel(Level8)failedtoverifytheentirecircuit.Thisisaviolation ofTechnical Specification Surveillance Requirement (TSSR)4.3.9.2whichisrequiredtobeperformed atleastonceper18months.Thecauseofthiseventhasbeendetermined tobeanapparentknowledge deficiency oftheElectroHydraulic Control(EHC)systemcombinedwithpoorworkpractices, whichledtheLSFTprocedure developers toconcludethattheEHCpanelwastheactuateddevice.Contributing tothiseventwastheomissionofrelevantinformation whentheLSFTprocedure fortheLevel8turbinetripwasdeveloped.
ThecircuitdiagramsfortheLevel8turbinetripshowtheEHCpanelasacircuittermination.
Theapplicable LSFTprocedures willberevisedpriortorefueling outage6(RFO6).Thiseventhasbeendiscussed withpersonnel performing theGenericLetter96-01procedure reviews.
0 NRCFORM366AFACILIIYNAME(I)REGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDOMBNO.3)30010lEXPIRES:ESIIMATED BURDENPERRESPONSETOCOMPLYWmlTlIISDIFORMATION COLLECfION REQUEST:SOA)IBLS.FORWARDCOMMEÃfSREGARDBIG BURDENESIIMATETOTIIERECORDSANDREMRTSMANAGEMENI'RANCII (M30),US.NUCLEARREGULATORY COMMISSION WASIENGfON>>
DC3OSSStANDTOTHEPAPERWORK REDUCflON PROJECfOISOOIOQ, OFHCEOFMANAGEMENI'ND BUDGEf,WASIIINGTON, DC20303.PAGEO)NineMilePointUnit205000410YEAR$9804REVISIONNUMBER0102OF04TE)ffQnsarvtPttttltttyket,sr@ofdMasdNRCionaSSSI's)PDOnMarch2,1998,NiagaraMohawkPowerCorporation (NMPC)determined thattheNineMilePointUnit2(NMP2)LogicSystemFunctional Tests(LSFT)forthemainturbinetriponhighreactorvessellevel(Level8)failedtoverifytheentirecircuit.Thisisaviolation ofTechnical Specification Surveillance Requirement (TSSR)4.3.9.2whichisrequiredtobeperformed atleastonceper18months.Thisdeficiency wasidentified inresponsetoaquestionfromanotherlicenseeconcerning LSFTtestingoftheElectroHydraulic Control(EHC)system.TheEHCsystemengineerreviewedtheLSFTdrawingsanddetermined thattheEHCcircuithadbeentestedfromtheLevel8transmitter toanEHCpanelinaccordance withanLSFTprocedure whichreferences TS4.3.9.2.Thecircuitry fromthemastertripbuswithintheEHCpaneltotheturbinestopandcontrolvalveswastestedinaccordance withanInstrument andControlsurveillance procedure whichdidnotspecifically reference TS4.3.9.2.However,thecircuitry fromtheEHCpanelinputterminals tothemastertripbuswasnottestedineitheroftheLSFTprocedures.
Afterfurtherreview,itwasfoundthattheEHCpanelcircuitry fromtheinputterminals tothemastertripbushasbeentestedsinceRefueling Outage3inOctober1993,butnotbyanLSFT.Workordershavebeeninitiated withsteptexttoperformthetestingeachrefueling outagesinceRFO3.Therefore, theentirecircuithasbeentestedsinceOctober1993tomeettheLSFTrequirements.
NMPChadperformed twopreviousLSFTreviewsandaninitialreviewofthisLevel8LSFTaspartoftheoverallLSFTreviewforGenericLetter(GL)96-01.Noneofthesereviewsidentified thisdeficiency.
However,theNhP2GL96-01processhasnotbeencompleted.
Aseniorengineerisrequiredtoperformanindependent verification oftheinitialreviewer's work.Thatverification wouldlikelyhaveidentified thisdeficiency.
Thecauseofthiseventhasbeendetermined tobeanapparentknowledge deficiency oftheEHCsystemcombinedwithpoorworkpractices, whichledtheLSFTprocedure developers toconcludethattheEHCpanelwastheactuateddevice.Contributing tothisevent,was theomissionofrelevantinformation whentheLSFTprocedure fortheLevel8turbinetripwasdeveloped.
ThecircuitdiagramsfortheLevel8turbinetripshowtheEHCpanelasacircuittermination.
Thecauseoftheindividual notfindingthisduringtheinitialGL96-01reviewwasagainknowledge deficiency andpoorworkpractice.
Theindividual believedthatsincetheEHC/Turbine Systemisnon-safety related,theactualtripofthemainturbinewassimplyaneconomicissuetopreventturbinedamageandnotforreactorsafety.Basedonthis,theindividual didnotpursuehisreviewbeyondtheEHCpanelinput.
('
NRCFORM30SAREGULATORY COMMLSSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDOMBNO.31100I0(EXPIRES:ESTIMATED BURDENPERRESPONSBTOCOMPLYWIBITlBSINFORMATION COLLKCIION RE(IUESF:
SOA)HRS.FORWARDCOMMENTSREGARDB(G BURDENESIIMATETO THERECORDSANDREPORTSMANAGEMKNI'RANCH (P>>030),UA.~REGULATORY COMMISSION, WASIBNQION>>DC30SSS,ANDTOTIIEPAPERWORK REDUCIION PROJKCP(IIS00104)>>
OFFICEOPMANAGEMENI ANDBUDGET>>WASIBNGION>>
DC30S03.FACLIIYNAME(I)LKRNUMBER(6)SEQUENIIAL NUMBERREVISIONNUMBERPAGE(3)NineMilePointUnit20500041098040103OF04TEXTQ'~apace4reqafraf, meok5danafNRCF~30'~'s)(II)Thiseventisreportable inaccordance with10CFR50.73(a)(2)(i)(B),
"anyoperation orcondition prohibited bytheplant'sTechnical Specifications."
Thepurposeoftheturbinetriponhighwaterlevelistocauseareactorscramtolimittheminimumcriticalpowerratio.NMP2UpdatedSafetyAnalysisReport(USAR)Section15.1.2,Feedwater Controller Failure-MaximumDemand,Subsection 15.1.2.2.3, EffectofSingleFailuresandOperatorErrors,states"InTable15.1-3,thefirstsensedeventtoinitiatecorrective actiontothetransient isthevesselhighwaterlevel(L8)trip.MultiplelevelsensorsareusedtosenseanddetectwhenthewaterlevelreachestheL8setpoint.
Atthispointinthelogic,asinglefailurewillnotinitiateorpreventaturbinetripsignal.Turbinetripsignaltransmission, however,isnotbuilttosingle-failure criterion.
Theresultofafailureatthispointwouldhavetheeffectofdelayingthepressurization "signature."
However,highmoisturelevelsenteringtheturbinewillbedetectedbyhighlevelsintheturbinesmoistureseparators, resulting inatripoftheunit."Inaddition, excessive moistureenteringtheturbinewillcausevibration tothepointwhereittoowilltriptheunit."Basedupontheseotherturbinetripsignalsandassociated reactorscram,theimpactofnothavingthisLevel8tripisnegligible.
Therefore, thiseventdidnotposeathreattopublichealthandsafetyortoplantpersonnel.
Theapplicable LSFTprocedures willberevisedpriortonextuse.2.Thiseventhasbeenreviewedandexpectations reinforced withthepersonnel performing theGL96-01procedure reviews.Thepurposeofthisreviewwastoassurethatpersonnel clearlyunderstand thatanLSFTisrequiredtotestfrominitiating devicetotheactuateddevice.Theverification processforGL96-01willspecifically addresstheLSFTcircuitscopeaspartoftheverification review.Theverification reviewsarescheduled forcompletion bytheendofRFO6.Sincethepersonnel whooriginally developed theEHC-LSFTprocedures arenolongeremployedatNMPC,andCorrective Action2assuredathoroughreview,noadditional trainingiswarranted.
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FACLrrYNAME(I)UA.REGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDOMBNO,3I300104EXPIRES:ESrMATEDBURDENPERRESPONSETOCOMPLYWm(T)BSB(FORMATION COLLECIION REQUEST:50A)HRS.FORWARDCOMMENTSREGARDE(G BURDENESBMATEToTHERECORDSANDREPORTSMANAGEMENrBRANCH(M30),US.NUCLEARREGULATORY COMMISSION WASHINGPON>>
DC30535>>ANDToTIIBPAPERWORK REDUCIION PROJECI(3I$00104)>>OFFICEOFMANAGEMENr ANDBUDGEr>>WASKNGPON>>
DC20503PAGBO)NineMilePointUnit20500041098SEQUENfIAL NUMBER04REVISIONNUMBER0104OF04TExTQ'score4F>>>>c!4vte>>p(>>ef, areokbfaadhRcFme3!Is('sJpDV.A.Failedcomponents:
none.B.Previoussimilarevents:NMP2hashadanumberofinstances whereprocedure preparation orreviewcausedmissedorinadequately performed surveillance tests.Inaccordance withNMPC'sCorrective ActionProgram,aDeviation/Event Report(DER)wasinitiated toevaluatethistrend.Arootcauseteamwasassembled toevaluatethisoveralltrendtodetermine ifprocessproblemsorothercommonaspectscouldbeidentified.
Requiredcorrective actionswillbetakenasnecessary tocorrectanyidentified deficiencies inaccordance withthecorrective actionprogram.C.IdentiGcation ofcomponents referredtointhisLER:g>>??(?0?i',.",R>>S4>>(r0!
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