Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18038A4131988-08-22022 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 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 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 ML18037A3421981-06-0101 June 1981 LER 81-003 Has Been Cancelled ML18038A5441981-03-0404 March 1981 LER 81-007/03L-0:on 810202,during Weekly Surveillance,Diesel Fire Pump Oil Leak Was Identified.Caused by Leak in Coupling to Tubing Weld Joint.Joint Removed,Rebrazed & Returned to Svc ML18037A3281981-02-23023 February 1981 LER 81-004/01T-0:on 810209,main Steam Radiation Monitor 111 Signal Fluctuated,Causing Multiple Half Scrams.Caused by Loose detector-to-cable Connector.Connector Tightened ML18037A3211981-01-23023 January 1981 LER 80-033/03L-0:on 801224,auxiliary Power Feed Experienced Loss to Emergency Power Bus.Caused by Feeder Breaker Trip Due to Setpoint on Over Frequency Protective Relay Being Set Too Close to Nominal Frequency.Relay Recalibr ML18037A3231981-01-16016 January 1981 LER 80-032/03L-0:on 801216,one Filter Bank in Branch 11 of Emergency Ventilation Sys Found Leaking in Excess of Tech Spec.Caused by Defective Filter Sealing Gasket.New Filter Unit Installed ML18037A3141980-12-30030 December 1980 LER 80-031/01T-0:on 801216,feedwater Flow Control Valve Pneumatic Positioner Unit II Vented Excessive Amount of Air. Caused by Cracked & Worn Rubber Goods.Rubber Goods Replaced & Retested ML18037A3131980-12-29029 December 1980 LER 80-028/04T-0:on 801215,results of 801103,26 & 1201 Milk Sample Tests Showed Detectable I-131 at Three Locations. Caused by Chinese Nuclear Weapons Test During Oct.Plant Not Accountable for Detected Levels ML18037A3121980-12-26026 December 1980 LER 80-027/03L-0:on 801126,operability Tests Were Not Immediately Performed as Required.Caused by Misunderstanding of Intent of Procedure.Testing Performed ML18037A3091980-11-24024 November 1980 LER 80-025/03L-0:on 801028,stack Gas Monitoring Sys Rendered Inoperable When Inadvertently Left in Purge Operation Mode for 9.5-h.Caused by Technician Failing to Return Sys to Normal Operation.Monitor Returned to Operation ML18037A2981980-10-30030 October 1980 LER 80-024/03L-0:on 800930,during Audit,Discovered That Point Valve Was Not Recorded on 790721 Instrument Surveillance Test for Drywell High Pressure Trip Sys.Caused by Personnel oversight.Two-level Review Instituted ML18037A2961980-10-24024 October 1980 LER 80-022/03L-0:on 800927,low Power Range Monitor Detector Failed Rendering Average Power Range Monitor 18 Inoperable. Caused by Internal Shorting.Low Power Range Monitor Will Be Replaced During Next Refueling ML18037A2911980-09-29029 September 1980 LER 80-020/03L-0:on 800830,while Experiencing Electrical Storm During Normal Operation,Loss of Meteorological Data Transmission to Control Room Instruments Occurred.Caused by Transceiver Failure.Transceiver Repaired & Returned to Svc ML18037A2891980-09-0909 September 1980 LER 80-019/04T-0:on 800827,during NRC Insp at Normal Operation,Discovered Removable Bottom Door Seals of Outer Door of Reactor Bldg Track Bay Were Not Installed Properly. Caused by Personnel Error ML18037A3051980-09-0505 September 1980 LER 80-018/03L-0:on 800808,during Normal Operation, Emergency Diesel Generator 103 Fuel Oil Day Tank Low Level Alarm Was Received.Caused by Inadvertent Opening of Day Tank Drain Valve.Tank Refilled.Oil Valve Sys Locked ML18037A2831980-08-18018 August 1980 LER 80-015/04L-0:on 800804,during Steady State Operation, Offgas Monitoring Sys Inadvertently Placed in Purge Mode of Operation.Caused by Technician Error.Sys Returned to Normal Operating Mode,Restoring Sys Operability ML18037A2811980-08-0808 August 1980 LER 80-014/03L-0:on 800717,during start-up Performance for IE Bulletin 80-17 Auto Scram Test,Operability Test Attempted on Valve During Shutdown Period.Valve Failed to Open Upon Manual Initiation.Valve Removed & Disassembled ML18037A2781980-08-0101 August 1980 LER 80-012/03L-0:on 800419,during Surveillance Testing of Turbine Anticipatory Trip Bypass,Rx Scram Switch 02-13A Was Operating Outside Setpoint.Caused by Instrument Drift.Switch Readjusted & Will Be Tested Monthly ML18037A2761980-07-22022 July 1980 LER 80-011/04L-0:on 800623,recorder Review Showed Condenser Inlet/Circulating Water Discharge Delta Temp Had Exceeded Tech Spec Limit on 800620-23.Station Load Reduced,Recorder Scale Expanded & Tech Spec Change Initiated ML18037A2631980-06-0303 June 1980 LER 80-009/03L-0:on 800521,during Steady State Operation, Attempts to Stroke 122 Containment Spray Isolation Valve Failed.Caused by Isolation Valve Solenoids Being Dirty. Revising Procedures to Require Periodic Maint for Valve ML18037A2621980-06-0303 June 1980 LER 80-010/03L-0:on 800528,while Performing Valve Checks, Operator Discovered Cardox Tank Pressure Below Tech Spec Limits.Caused by Delivery of Too Low Temp Carbon Dioxide by Supplier.Low Pressure Alarm Connected ML18037A2431980-03-20020 March 1980 LER 80-007/03L-0:on 800303,while Shutdown for Maint,Attempts to Close Both Air Operated Outside Main Steam Isolation Valves Failed.Caused by Rust Buildup in Pilot Shuttle.New Instrument Air Sys Is Being Installed ML18037A2401980-02-15015 February 1980 LER 80-005/01X-0:on 800203,engineering Evaluation of GE SIL 299 Required That low-low Setpoint for Reactor Core Water Level Be Raised 20 Inches.Caused by Efforts to Precisely Measure Actual to Indicated Water Level Difference ML18037A2361980-01-21021 January 1980 LER 80-003/01T-0:on 800109,lab Analysis Not Performed on Charcoal Filter Samples from Rx Bldg & Control Room Emergency Ventilation Sys Per Tech Specs.Caused by Change in Operating Cycle Length.Will Revise Surveillance Schedule ML18037A2091979-11-19019 November 1979 LER 79-025/03L-0:on 791027,during Surveillance Testing, Personnel Unable to Zero Side Average Power Range Monitor Flow Converter 11.Caused by Component Failure.Entire Unit Replaced & Problem Eliminated ML18037A2071979-11-0202 November 1979 LER 79-023/03L-0:on 791004,cooling Water Pump of Diesel Generator 103 Tripped.Caused by Burned Contacts in Breaker. Breaker Repaired & Pump Started Manually.Preventative Maint Procedure Will Be Revised ML18037A2041979-10-0101 October 1979 LER 79-022/01T-0:on 790918,noted Failure to Install Seismic Constraint on Containment Spray Sys Outside Primary Containment Per Const Drawings.Initiated Design & Order to Install Constraint.Containment Spray Loop Inoperable ML18037A1971979-09-10010 September 1979 LER 79-019/03L-0:on 790816,during Steady State Operation, Routine Mgt Review Disclosed Failure to Complete Five Surveillance Tests on Schedule.Tests Immediately Performed & Completed.Personnel Instructed to Follow Published Schedule ML18037A1941979-09-0707 September 1979 LER 79-021/04T-0:on 790905,noted That Analysis of Excesssive Nuclide Water Sample Concentrations Was Not Completed within 30 Days.Caused by Late Rept by Contractor & High Influx of Samples.Addl Personnel Added ML18037A1881979-08-10010 August 1979 LER 79-018/03L-0 on 790726:vacuum Relief Sys Switch 68-12B Failed to Open at Proper Setpoint.No Cause Identified.Switch Adjusted to Proper Setpoint ML18037A1821979-07-0909 July 1979 LER 79-017/03L-0 on 790612:containment Spray Water Intertie Valves Leaked Causing Failure of Integrated Leak Rate Test. Valves Removed,Cleaned & re-installed ML18037A1771979-06-14014 June 1979 LER 79-011/03L-0 on 790517:during Refueling Outage, Discovered That Radiographer Received Overexposure of 3,790 Millirems for Second Quarter 1979.Cause Unknown & Under Investigation.Discussed Further in 790615 Ltr to NRC ML18037A1741979-05-31031 May 1979 LER 79-012/01T-0 on 790523:concrete Anchor Bolt Deficiencies & Missing Seismic Restraints Were Discovered on Class I Seismic Piping Sys.Caused by Incorrect Installation.Concrete Anchor Bolt Repair Program Will Be Completed by 791231 ML18037A1671979-05-0101 May 1979 LER 79-005/03L-0 on 790401:during Periodic Type C Leakage Test,Valves IV-68-06,IV-201-09,IV-201-10 & IV-58.1-02 Were Found to Be in Excess of Tech Specs.Cause Unknown.Repairs Will Be Made During Outage ML18037A1661979-04-23023 April 1979 LER 79-002/01X-1 on 790306:during Refueling Outage While Preparing Emergency Condenser Steam Nozzle 5-NB for Replacement of safe-end,discovered Inconel Weld Was Removed from Nozzle.New Safe End Installed ML18037A1411978-12-0808 December 1978 LER#78-040/03L-0 on 781113:#112 Core Spray Topping Pump Motor Breaker Closed Starting Pump But Breaker Closing Spring Motor Was Running Continuously & Not Charging Closing Spring.Caused by Misaligned Motor Assembly at Latching Pawl ML17053A2391978-11-14014 November 1978 LER#78-038/03L-0 on 781025:review of N1-ISP-RE22 Test Results Found 12 Instances Where Procedure Was Violated. Caused by Carelessness in Procedure Implementation. Re-instruction & Closer Supervision Instituted 1988-08-22
[Table view] Category:RO)
MONTHYEARML18038A4131988-08-22022 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 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 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 ML18037A3421981-06-0101 June 1981 LER 81-003 Has Been Cancelled ML18038A5441981-03-0404 March 1981 LER 81-007/03L-0:on 810202,during Weekly Surveillance,Diesel Fire Pump Oil Leak Was Identified.Caused by Leak in Coupling to Tubing Weld Joint.Joint Removed,Rebrazed & Returned to Svc ML18037A3281981-02-23023 February 1981 LER 81-004/01T-0:on 810209,main Steam Radiation Monitor 111 Signal Fluctuated,Causing Multiple Half Scrams.Caused by Loose detector-to-cable Connector.Connector Tightened ML18037A3211981-01-23023 January 1981 LER 80-033/03L-0:on 801224,auxiliary Power Feed Experienced Loss to Emergency Power Bus.Caused by Feeder Breaker Trip Due to Setpoint on Over Frequency Protective Relay Being Set Too Close to Nominal Frequency.Relay Recalibr ML18037A3231981-01-16016 January 1981 LER 80-032/03L-0:on 801216,one Filter Bank in Branch 11 of Emergency Ventilation Sys Found Leaking in Excess of Tech Spec.Caused by Defective Filter Sealing Gasket.New Filter Unit Installed ML18037A3141980-12-30030 December 1980 LER 80-031/01T-0:on 801216,feedwater Flow Control Valve Pneumatic Positioner Unit II Vented Excessive Amount of Air. Caused by Cracked & Worn Rubber Goods.Rubber Goods Replaced & Retested ML18037A3131980-12-29029 December 1980 LER 80-028/04T-0:on 801215,results of 801103,26 & 1201 Milk Sample Tests Showed Detectable I-131 at Three Locations. Caused by Chinese Nuclear Weapons Test During Oct.Plant Not Accountable for Detected Levels ML18037A3121980-12-26026 December 1980 LER 80-027/03L-0:on 801126,operability Tests Were Not Immediately Performed as Required.Caused by Misunderstanding of Intent of Procedure.Testing Performed ML18037A3091980-11-24024 November 1980 LER 80-025/03L-0:on 801028,stack Gas Monitoring Sys Rendered Inoperable When Inadvertently Left in Purge Operation Mode for 9.5-h.Caused by Technician Failing to Return Sys to Normal Operation.Monitor Returned to Operation ML18037A2981980-10-30030 October 1980 LER 80-024/03L-0:on 800930,during Audit,Discovered That Point Valve Was Not Recorded on 790721 Instrument Surveillance Test for Drywell High Pressure Trip Sys.Caused by Personnel oversight.Two-level Review Instituted ML18037A2961980-10-24024 October 1980 LER 80-022/03L-0:on 800927,low Power Range Monitor Detector Failed Rendering Average Power Range Monitor 18 Inoperable. Caused by Internal Shorting.Low Power Range Monitor Will Be Replaced During Next Refueling ML18037A2911980-09-29029 September 1980 LER 80-020/03L-0:on 800830,while Experiencing Electrical Storm During Normal Operation,Loss of Meteorological Data Transmission to Control Room Instruments Occurred.Caused by Transceiver Failure.Transceiver Repaired & Returned to Svc ML18037A2891980-09-0909 September 1980 LER 80-019/04T-0:on 800827,during NRC Insp at Normal Operation,Discovered Removable Bottom Door Seals of Outer Door of Reactor Bldg Track Bay Were Not Installed Properly. Caused by Personnel Error ML18037A3051980-09-0505 September 1980 LER 80-018/03L-0:on 800808,during Normal Operation, Emergency Diesel Generator 103 Fuel Oil Day Tank Low Level Alarm Was Received.Caused by Inadvertent Opening of Day Tank Drain Valve.Tank Refilled.Oil Valve Sys Locked ML18037A2831980-08-18018 August 1980 LER 80-015/04L-0:on 800804,during Steady State Operation, Offgas Monitoring Sys Inadvertently Placed in Purge Mode of Operation.Caused by Technician Error.Sys Returned to Normal Operating Mode,Restoring Sys Operability ML18037A2811980-08-0808 August 1980 LER 80-014/03L-0:on 800717,during start-up Performance for IE Bulletin 80-17 Auto Scram Test,Operability Test Attempted on Valve During Shutdown Period.Valve Failed to Open Upon Manual Initiation.Valve Removed & Disassembled ML18037A2781980-08-0101 August 1980 LER 80-012/03L-0:on 800419,during Surveillance Testing of Turbine Anticipatory Trip Bypass,Rx Scram Switch 02-13A Was Operating Outside Setpoint.Caused by Instrument Drift.Switch Readjusted & Will Be Tested Monthly ML18037A2761980-07-22022 July 1980 LER 80-011/04L-0:on 800623,recorder Review Showed Condenser Inlet/Circulating Water Discharge Delta Temp Had Exceeded Tech Spec Limit on 800620-23.Station Load Reduced,Recorder Scale Expanded & Tech Spec Change Initiated ML18037A2631980-06-0303 June 1980 LER 80-009/03L-0:on 800521,during Steady State Operation, Attempts to Stroke 122 Containment Spray Isolation Valve Failed.Caused by Isolation Valve Solenoids Being Dirty. Revising Procedures to Require Periodic Maint for Valve ML18037A2621980-06-0303 June 1980 LER 80-010/03L-0:on 800528,while Performing Valve Checks, Operator Discovered Cardox Tank Pressure Below Tech Spec Limits.Caused by Delivery of Too Low Temp Carbon Dioxide by Supplier.Low Pressure Alarm Connected ML18037A2431980-03-20020 March 1980 LER 80-007/03L-0:on 800303,while Shutdown for Maint,Attempts to Close Both Air Operated Outside Main Steam Isolation Valves Failed.Caused by Rust Buildup in Pilot Shuttle.New Instrument Air Sys Is Being Installed ML18037A2401980-02-15015 February 1980 LER 80-005/01X-0:on 800203,engineering Evaluation of GE SIL 299 Required That low-low Setpoint for Reactor Core Water Level Be Raised 20 Inches.Caused by Efforts to Precisely Measure Actual to Indicated Water Level Difference ML18037A2361980-01-21021 January 1980 LER 80-003/01T-0:on 800109,lab Analysis Not Performed on Charcoal Filter Samples from Rx Bldg & Control Room Emergency Ventilation Sys Per Tech Specs.Caused by Change in Operating Cycle Length.Will Revise Surveillance Schedule ML18037A2091979-11-19019 November 1979 LER 79-025/03L-0:on 791027,during Surveillance Testing, Personnel Unable to Zero Side Average Power Range Monitor Flow Converter 11.Caused by Component Failure.Entire Unit Replaced & Problem Eliminated ML18037A2071979-11-0202 November 1979 LER 79-023/03L-0:on 791004,cooling Water Pump of Diesel Generator 103 Tripped.Caused by Burned Contacts in Breaker. Breaker Repaired & Pump Started Manually.Preventative Maint Procedure Will Be Revised ML18037A2041979-10-0101 October 1979 LER 79-022/01T-0:on 790918,noted Failure to Install Seismic Constraint on Containment Spray Sys Outside Primary Containment Per Const Drawings.Initiated Design & Order to Install Constraint.Containment Spray Loop Inoperable ML18037A1971979-09-10010 September 1979 LER 79-019/03L-0:on 790816,during Steady State Operation, Routine Mgt Review Disclosed Failure to Complete Five Surveillance Tests on Schedule.Tests Immediately Performed & Completed.Personnel Instructed to Follow Published Schedule ML18037A1941979-09-0707 September 1979 LER 79-021/04T-0:on 790905,noted That Analysis of Excesssive Nuclide Water Sample Concentrations Was Not Completed within 30 Days.Caused by Late Rept by Contractor & High Influx of Samples.Addl Personnel Added ML18037A1881979-08-10010 August 1979 LER 79-018/03L-0 on 790726:vacuum Relief Sys Switch 68-12B Failed to Open at Proper Setpoint.No Cause Identified.Switch Adjusted to Proper Setpoint ML18037A1821979-07-0909 July 1979 LER 79-017/03L-0 on 790612:containment Spray Water Intertie Valves Leaked Causing Failure of Integrated Leak Rate Test. Valves Removed,Cleaned & re-installed ML18037A1771979-06-14014 June 1979 LER 79-011/03L-0 on 790517:during Refueling Outage, Discovered That Radiographer Received Overexposure of 3,790 Millirems for Second Quarter 1979.Cause Unknown & Under Investigation.Discussed Further in 790615 Ltr to NRC ML18037A1741979-05-31031 May 1979 LER 79-012/01T-0 on 790523:concrete Anchor Bolt Deficiencies & Missing Seismic Restraints Were Discovered on Class I Seismic Piping Sys.Caused by Incorrect Installation.Concrete Anchor Bolt Repair Program Will Be Completed by 791231 ML18037A1671979-05-0101 May 1979 LER 79-005/03L-0 on 790401:during Periodic Type C Leakage Test,Valves IV-68-06,IV-201-09,IV-201-10 & IV-58.1-02 Were Found to Be in Excess of Tech Specs.Cause Unknown.Repairs Will Be Made During Outage ML18037A1661979-04-23023 April 1979 LER 79-002/01X-1 on 790306:during Refueling Outage While Preparing Emergency Condenser Steam Nozzle 5-NB for Replacement of safe-end,discovered Inconel Weld Was Removed from Nozzle.New Safe End Installed ML18037A1411978-12-0808 December 1978 LER#78-040/03L-0 on 781113:#112 Core Spray Topping Pump Motor Breaker Closed Starting Pump But Breaker Closing Spring Motor Was Running Continuously & Not Charging Closing Spring.Caused by Misaligned Motor Assembly at Latching Pawl ML17053A2391978-11-14014 November 1978 LER#78-038/03L-0 on 781025:review of N1-ISP-RE22 Test Results Found 12 Instances Where Procedure Was Violated. Caused by Carelessness in Procedure Implementation. Re-instruction & Closer Supervision Instituted 1988-08-22
[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 ML20212D3611999-09-21021 September 1999 Safety Evaluation Supporting Amend 168 to License DPR-63 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 05000220/LER-1999-005-01, :on 990801,RT During Plant Startup on IRM Spiking Was Noted.Caused by electro-magnetic Interference. Inspected,Cleaned,Burnished & Tested IRM 11 Range Switch. with1999-08-30030 August 1999
- on 990801,RT During Plant Startup on IRM Spiking Was Noted.Caused by electro-magnetic Interference. Inspected,Cleaned,Burnished & Tested IRM 11 Range Switch. with
05000220/LER-1999-004-01, :on 990723,reactor Scram Was Noted.Caused by Mechanical Pressure Regulator Suppressor Valve Failure. Cleaned Pressure Suppressor Valve & Provided Guidance for Valve Disassembly & Insp.With1999-08-23023 August 1999
- on 990723,reactor Scram Was Noted.Caused by Mechanical Pressure Regulator Suppressor Valve Failure. Cleaned Pressure Suppressor Valve & Provided Guidance for Valve Disassembly & Insp.With
ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With ML20210H7851999-07-29029 July 1999 Corrected SER Supporting Amend 167 to License DPR-63, Replacing Pages 4,5 & 11.New Pages Correct SE to Be Consistent with Application for Amend 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 ML20196A3041999-06-17017 June 1999 Safety Evaluation Supporting Amend 167 to License DPR-63 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 05000220/LER-1999-003-01, :on 990320,noted That Plant Operated with Average Planear LHGR Exceeding TS Limits.Caused by Inadequate Interface Design Between Color Graphics Terminal & 3-D Monicore Sys.Lowered Reactor Power.With1999-04-22022 April 1999
- on 990320,noted That Plant Operated with Average Planear LHGR Exceeding TS Limits.Caused by Inadequate Interface Design Between Color Graphics Terminal & 3-D Monicore Sys.Lowered Reactor Power.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 05000220/LER-1999-002, :on 990217,noted That ASME Code Preservice Exams Had Not Been Performed on Emergency Condensers.Caused by Misinterpretation of ASME Code Requirements.Required Preservice Exams Were Completed on 990218.With1999-03-19019 March 1999
- on 990217,noted That ASME Code Preservice Exams Had Not Been Performed on Emergency Condensers.Caused by Misinterpretation of ASME Code Requirements.Required Preservice Exams Were Completed on 990218.With
ML20204C8001999-03-16016 March 1999 Safety Evaluation Supporting Amend 165 to License DPR-63 05000410/LER-1999-001-01, :on 990212,NMP2 Was Outside Design Basis Due to Safe SD SW Pump Bay Unit Coolers Being Oos.Caused by Inadequate Managerial Methods.Interim ACs Were Set for Safe SD Equipment.With1999-03-15015 March 1999
- on 990212,NMP2 Was Outside Design Basis Due to Safe SD SW Pump Bay Unit Coolers Being Oos.Caused by Inadequate Managerial Methods.Interim ACs Were Set for Safe SD Equipment.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 05000220/LER-1999-001, :on 990125,noted That Plant Operated Outside Design Basis Due to Failure to Revise Satellite pre-fire Plans.Satellite Copies of pre-fire Plans Were Revised & Procedure Re pre-fire Plans Was Revised.With1999-02-24024 February 1999
- on 990125,noted That Plant Operated Outside Design Basis Due to Failure to Revise Satellite pre-fire Plans.Satellite Copies of pre-fire Plans Were Revised & Procedure Re pre-fire Plans Was Revised.With
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 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 ML20210R8441998-12-31031 December 1998 1998 Annual Rept for Energy East ML20199K9331998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With 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 05000220/LER-1998-019-01, :on 981110,ASME Section XI ISI Was Missed. Caused by Cognitive Error Involving Technical Inaccuracies. Util Will Revise Second 10-yr Interval ISI Program Plan to Incorporate Visual Exam Requirements.With1998-12-10010 December 1998
- on 981110,ASME Section XI ISI Was Missed. Caused by Cognitive Error Involving Technical Inaccuracies. Util Will Revise Second 10-yr Interval ISI Program Plan to Incorporate Visual Exam Requirements.With
ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With ML17059C3821998-11-25025 November 1998 Safety Evaluation Supporting Amend 164 to License DPR-63 05000220/LER-1998-018-01, :on 981006,determined That Actual Total Crds Flow Exceeded Indicated Crds Total Flow.Caused by Degraded Crds Filter Bypass Valve.Plant Has Been Limited to 1847 Mwt & Shift Check Procedure Was Revised.With1998-11-0505 November 1998
- on 981006,determined That Actual Total Crds Flow Exceeded Indicated Crds Total Flow.Caused by Degraded Crds Filter Bypass Valve.Plant Has Been Limited to 1847 Mwt & Shift Check Procedure Was Revised.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 05000220/LER-1998-017-01, :on 980902,breach of Primary Containment Was Noted.Caused by Personnel Error in 1994.Immediately Upon Discovery,Asss Directed That CS Heat Exchanger Vent Valves Be Closed.With1998-10-0202 October 1998
- on 980902,breach of Primary Containment Was Noted.Caused by Personnel Error in 1994.Immediately Upon Discovery,Asss Directed That CS Heat Exchanger Vent Valves Be Closed.With
ML20154P1821998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Nine Mile Point Nuclear Station,Unit 1.With 05000220/LER-1998-016-01, :on 980820,determined That CS Pump Motor Bearing Cooling Flow Outside Design Basis Requirement.Caused by Error in Maint Reassembly That Crimped Cooling Coil.Cs Pump 122 Repaired.With1998-09-21021 September 1998
- on 980820,determined That CS Pump Motor Bearing Cooling Flow Outside Design Basis Requirement.Caused by Error in Maint Reassembly That Crimped Cooling Coil.Cs Pump 122 Repaired.With
05000220/LER-1998-015-01, :on 980804,breach of Primary Containment Was Noted.Caused by Personnel Error.Closed Heat Exchanger Vent Valves & Restored Torus Pressure.With1998-09-0303 September 1998
- on 980804,breach of Primary Containment Was Noted.Caused by Personnel Error.Closed Heat Exchanger Vent Valves & Restored Torus Pressure.With
1999-09-30
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