ML18037A169
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| ML18037A169 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/23/1979 |
| From: | Duda E NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML17053A699 | List: |
| References | |
| LER-79-010-03L, LER-79-10-3L, NUDOCS 7905300496 | |
| Download: ML18037A169 (2) | |
Similar Documents at Nine Mile Point | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18040A3491998-07-0202 July 1998
[Table view]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 Category:RO) MONTHYEARML18040A3491998-07-0202 July 1998
[Table view]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 Category:TEXT-SAFETY REPORT MONTHYEARML20217G2161999-10-15015 October 1999
[Table view]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 |
Text
~RM~3RM 366 (7-77)LICENSEE EVENT REPORT U.S.NUCLEAR REGULATORY COMMISSION
~0 8 CON'T~o 7 8 0;2 CONTROL BLOCK: I N Y N t4 P 9 LICENSEE CODE ,Q IPLEASE PRINT OR TYPE ALL REQUIREO INFORMATION) 1 Q20 0-0 0 0 0 0 14 15 LICENSE NUMBER 0 0 Qs 4 1 I I Q4~Os 25 26 LICENSE TYPE30 57 CAT 58 80 Qg ,",'""O'E
~QB 0 5 0 0 0 2 2 0 7 0 4 2 4 I 9 Q 60 61 DOCKET NUMBER 68 69 EVENT DATE 74'5 REPORT DATE EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES QIO ,"During refueling outage, containment vacuum relief valve (68 IV-10)~03 flange failed its leak rate test.This resulted in minimal safety implications since the unit was shutdown for refueling.
~OS~06~07~OB 7 8 g 7 8 80 SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~S0 O11~EQ12~XQI3 V A L V E X Q4~BGs~C Qls 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER RO EVENT YEAR REPORT NO.CODE TYPE NO.G7 sss0ss~79+~01 0+~~01+L+0 21 22 23 24 26 27 28 29 30 31 32 ACTION, FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDX PRIME COMP.COMPONENT TAKEN ACTION ON PI.ANT hIETHOD HOURS~22 SUBMITTED FORM SUB.SUPPLIER MANUFACTUR R QIB~Q)g~Q20~Q2 0 0 0 0~N Q23~NQ24~AQ25 A 1 8 0 Q26 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 0-rings were replaced on flange of containment vacuum relief valve (68'Y-10), which subsequently passed its leak rate test.3~14 5~N Q28~00 0 Qss NA 7 8 9 10 12 ACTIVITY CONTENT RELEASEO OF RELEASE 6~Z Q33~ZQ34 7 8 9.10 11 PERSONNFL EXPOSURES NUMBER TYPE DESCRIPTION Q3g~le~00 0 Qav~ZQss NA 7 8 9 11 12 13 PFRSQNNEL INJURIES NUMBER OESCRIPTIONQ41
~OO O 8)NA 13 44 AMOUNT OF ACTIVITY QS NA 44 7 8 9 FACILITY STATUS~~s POWER OTHER STATUS Q30 45 NA LOCATION OF RELEASE Q36 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32~B Q31 Leak Rate Test 45 46 80&0 80 80 7 8 7 8 O 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION
~ZQ42 NA 9'IO PUBLICITY ISSUED DESCRIPTION
~L>J 044 9 10 E.Duda NAME OF PREPARFR NRC USE ONLY 68 69 PHQNE(315)343-2110 Ext 1306 53 00+AC 80 80 ss 80
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