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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000220/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
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
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
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
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
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
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
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
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
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 05000410/LER-1998-019, :on 980617,determined That Fire Proofing Was Missing from Beam.Caused by Failure of Contractor Personnel. Breach Permit Initiated & Compensatory Fire Patrols Were Established1998-07-17017 July 1998
- on 980617,determined That Fire Proofing Was Missing from Beam.Caused by Failure of Contractor Personnel. Breach Permit Initiated & Compensatory Fire Patrols Were Established
05000220/LER-1998-014-01, :on 980617,control Room Staffing Was in Violation of TS Due to Unqualified SRO Assuming SRO Shift Duties.Caused by Inadequate Managerial Methods.Crew Remediated & Lessons Learned Memo Distributed1998-07-17017 July 1998
- on 980617,control Room Staffing Was in Violation of TS Due to Unqualified SRO Assuming SRO Shift Duties.Caused by Inadequate Managerial Methods.Crew Remediated & Lessons Learned Memo Distributed
05000220/LER-1998-013-01, :on 980604,valve Repositioning Caused non- Conformance W/App R Safe Shutdown Analysis. Caused by Failure to Include Valves 40-26 & 40-27 in UFSAR Description of App R.Circuit Breakers 40-30 & 40-31 Opened1998-07-0606 July 1998
- on 980604,valve Repositioning Caused non- Conformance W/App R Safe Shutdown Analysis. Caused by Failure to Include Valves 40-26 & 40-27 in UFSAR Description of App R.Circuit Breakers 40-30 & 40-31 Opened
05000410/LER-1998-017, :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 Deficiency1998-07-0202 July 1998
- 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
05000410/LER-1998-014, :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 10CFR211998-06-24024 June 1998
- 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
05000220/LER-1998-012-01, :on 980521,determined That Fire Dampers Installed in Supply & Return Ducts to Auxiliary CR Would Fail Closed as Result of Loop.Caused by Inadequate Evaluation.Modified Affected Fire Dampers1998-06-22022 June 1998
- on 980521,determined That Fire Dampers Installed in Supply & Return Ducts to Auxiliary CR Would Fail Closed as Result of Loop.Caused by Inadequate Evaluation.Modified Affected Fire Dampers
05000410/LER-1998-004, :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 61998-06-0404 June 1998
- 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
05000220/LER-1998-011-01, :on 980503,inadvertent Actuation of RPS Circuitry Occurred Due to Personnel Error.Fuse Was Replaced & SDC Was Placed Into Svc1998-06-0202 June 1998
- on 980503,inadvertent Actuation of RPS Circuitry Occurred Due to Personnel Error.Fuse Was Replaced & SDC Was Placed Into Svc
05000220/LER-1998-010-01, :on 980430,inadequate Reactor Vessel Level Instruments Were Noted.Caused by Inaccurate Input Parameter. Revised Calculations & Associated Instruments Were Recalibrated1998-06-0101 June 1998
- on 980430,inadequate Reactor Vessel Level Instruments Were Noted.Caused by Inaccurate Input Parameter. Revised Calculations & Associated Instruments Were Recalibrated
05000220/LER-1998-008-01, :on 980428,RWM TS SR Were Not Met for Previous Shutdowns.Caused by Failure to Develop Procedures Which Tested Rwm.Revised RWM Sp & Verified Adequacy of Operations Sps Which Are Performed on Conditional Basis1998-05-28028 May 1998
- on 980428,RWM TS SR Were Not Met for Previous Shutdowns.Caused by Failure to Develop Procedures Which Tested Rwm.Revised RWM Sp & Verified Adequacy of Operations Sps Which Are Performed on Conditional Basis
05000220/LER-1998-009-01, :on 980428,missing Fire Proofing Matl from Structural Steel,Was Discovered.Caused by Construction Drawing Not Followed by Contractor.Breach Permit & Compensatory Fire Patrols Initiated1998-05-28028 May 1998
- on 980428,missing Fire Proofing Matl from Structural Steel,Was Discovered.Caused by Construction Drawing Not Followed by Contractor.Breach Permit & Compensatory Fire Patrols Initiated
05000220/LER-1998-007-02, :on 980424,SRO Was Not in CR for Two Minutes. Caused by Insufficient Awareness of Assistant Station SS Role & Actions on Nuclear Safety.Counseled Assistant Station SS & Relieved Supervisor of Licensed Duties1998-05-26026 May 1998
- on 980424,SRO Was Not in CR for Two Minutes. Caused by Insufficient Awareness of Assistant Station SS Role & Actions on Nuclear Safety.Counseled Assistant Station SS & Relieved Supervisor of Licensed Duties
05000220/LER-1998-006-01, :on 980421,design Deficiency Associated W/Crevs RMs Was Noted.Caused by Engineering Personnel Not Performing Adequate Evaluations.Modified Sys Logic to Initiate CREVS Directly from MSLB & LOCA Signals1998-05-21021 May 1998
- on 980421,design Deficiency Associated W/Crevs RMs Was Noted.Caused by Engineering Personnel Not Performing Adequate Evaluations.Modified Sys Logic to Initiate CREVS Directly from MSLB & LOCA Signals
05000220/LER-1998-004-01, :on 980411,identified That Containment Spray Flow Control Valve 80-118 Had Been Left Open Since 980407. Caused by Failure by Chief Shift Operator to Properly Follow Procedure.Procedures Revised1998-05-11011 May 1998
- on 980411,identified That Containment Spray Flow Control Valve 80-118 Had Been Left Open Since 980407. Caused by Failure by Chief Shift Operator to Properly Follow Procedure.Procedures Revised
05000220/LER-1998-003-01, :on 980304,plant Exceeded 100% Rated Core Thermal Power & Exceeded Power/Flow Relationship of TS 3.1.7.d.Caused by Inadequate Managerial Methods.Implemented Conservative Interim Guidance to Ensure Correct Power Level1998-04-0303 April 1998
- on 980304,plant Exceeded 100% Rated Core Thermal Power & Exceeded Power/Flow Relationship of TS 3.1.7.d.Caused by Inadequate Managerial Methods.Implemented Conservative Interim Guidance to Ensure Correct Power Level
05000220/LER-1998-002-01, :on 980220,failure of CR Emergency Ventilation to Meet Differential Pressure Requirements Occurred.Caused by Inadequate Change Management.Engineering Supporting Analysis Was Completed to Justify Operations1998-03-23023 March 1998
- on 980220,failure of CR Emergency Ventilation to Meet Differential Pressure Requirements Occurred.Caused by Inadequate Change Management.Engineering Supporting Analysis Was Completed to Justify Operations
05000220/LER-1998-001-01, :on 980129,violation of Secondary Containment Was Noted.Caused by Knowledge Deficiency of Personnel Assessing Plant Impact of Maint Work.Plant Impact Statements in Maint Procedure Have Changed1998-03-0202 March 1998
- on 980129,violation of Secondary Containment Was Noted.Caused by Knowledge Deficiency of Personnel Assessing Plant Impact of Maint Work.Plant Impact Statements in Maint Procedure Have Changed
05000220/LER-1994-003-01, :on 940406,missed Tech Spec Surveillance Discovered.Caused by Inadequate Management.Correcting Preventive maint-surveillance Test Database1996-01-0909 January 1996
- on 940406,missed Tech Spec Surveillance Discovered.Caused by Inadequate Management.Correcting Preventive maint-surveillance Test Database
05000410/LER-1995-011, :on 951115,discovered That 100% of Rated Core Thermal Power Exceeded During Fuel Cycles 4 & 5 Due to Core Thermal Power Calculation Methodology Error.Reduced Power & Established Administrative Limit on Power1995-12-15015 December 1995
- on 951115,discovered That 100% of Rated Core Thermal Power Exceeded During Fuel Cycles 4 & 5 Due to Core Thermal Power Calculation Methodology Error.Reduced Power & Established Administrative Limit on Power
05000220/LER-1995-003-01, :on 950516,discovered That Three I&C Sps Not Performed in Compliance W/Frequency in TS SRs Due to Cognitive Personnel Error.Missed Surveillances Performed & Affected I&C Procedures Will Be Revised1995-06-15015 June 1995
- on 950516,discovered That Three I&C Sps Not Performed in Compliance W/Frequency in TS SRs Due to Cognitive Personnel Error.Missed Surveillances Performed & Affected I&C Procedures Will Be Revised
05000410/LER-1993-011, :on 931119,reactor Scram & ESF Actuation Occurred.Caused by Poor Work Organization & Planning. Work Planning Guide Revised & Procedure Changes Will Be Evaluated1993-12-20020 December 1993
- on 931119,reactor Scram & ESF Actuation Occurred.Caused by Poor Work Organization & Planning. Work Planning Guide Revised & Procedure Changes Will Be Evaluated
05000410/LER-1993-010, :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 211993-12-0808 December 1993
- 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
05000410/LER-1992-008, :on 920327,Unit 2 Experienced ESF Actuations. Caused by Personnel Error.Technician Involved Counseled, Procedure Revised & Directive to Help Minimize Risk of Relay State Verification Methods Issued1992-04-25025 April 1992
- on 920327,Unit 2 Experienced ESF Actuations. Caused by Personnel Error.Technician Involved Counseled, Procedure Revised & Directive to Help Minimize Risk of Relay State Verification Methods Issued
05000410/LER-1990-021-01, :on 901026,TS Violation Re RHR Sys Valve Tests Not Included in Inservice Test Pump/Valve Program Plan Occurred1990-11-23023 November 1990
- on 901026,TS Violation Re RHR Sys Valve Tests Not Included in Inservice Test Pump/Valve Program Plan Occurred
05000220/LER-1990-006-01, :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 Developed1990-08-10010 August 1990
- 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
05000410/LER-1989-014, :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 Relanded1989-05-15015 May 1989
- 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
05000410/LER-1987-051, :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 Restored1988-08-22022 August 1988
- 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
05000410/LER-1988-024, :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 Replaced1988-07-0101 July 1988
- 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
05000410/LER-1988-014, :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 Valves1988-04-12012 April 1988
- 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
05000410/LER-1988-001, :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 Lockup1988-02-17017 February 1988
- 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
05000220/LER-1987-023-01, :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 Event1987-12-22022 December 1987
- 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
05000410/LER-1987-045, Corrected LER 87-045-00:on 870729,two Separate ESF Actuations Occurred.Caused by Lack of Administrative Controls & Personnel Error.Surveillance Procedures Revised to Prohibit Concurrent Performance1987-08-28028 August 1987 Corrected LER 87-045-00:on 870729,two Separate ESF Actuations Occurred.Caused by Lack of Administrative Controls & Personnel Error.Surveillance Procedures Revised to Prohibit Concurrent Performance 05000410/LER-1987-025, :on 870519,secondary Containment Isolation Signal Generated Due to Technician Relanding Lifted Lead Prematurely.Caused by Breakdown in Communications.Gaitronics Phone &/Or Headset Jack Installed1987-06-15015 June 1987
- 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
05000410/LER-1986-002-01, :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 Procedure1987-04-13013 April 1987
- 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
05000410/LER-1986-012, :on 861128 & 29,series of Related Automatic Initiations of Standby Gas Treatment Sys Occurred.Caused by Clogged Filters & Personnel Error.Approx 50% of First Stage Filters Replaced & Training Mod Initiated1987-03-25025 March 1987
- on 861128 & 29,series of Related Automatic Initiations of Standby Gas Treatment Sys Occurred.Caused by Clogged Filters & Personnel Error.Approx 50% of First Stage Filters Replaced & Training Mod Initiated
05000410/LER-1987-015, :on 870222,failure to Maintain Hourly Watch Patrol in Area W/Inoperable Fire Detection Sys Occurred. Caused by Change to Fire Watch Patrol Rover Schedule W/O Notifying Fire Chief.Personnel Counseled1987-03-24024 March 1987
- on 870222,failure to Maintain Hourly Watch Patrol in Area W/Inoperable Fire Detection Sys Occurred. Caused by Change to Fire Watch Patrol Rover Schedule W/O Notifying Fire Chief.Personnel Counseled
05000410/LER-1987-016, :on 870226,abandoned Penetration in Fire Wall Between Secondary Containment & Main Steam Tunnel Found Improperly Sealed.Caused by Personnel Error.Penetrations Reviewed & Fire Watch Established1987-03-23023 March 1987
- on 870226,abandoned Penetration in Fire Wall Between Secondary Containment & Main Steam Tunnel Found Improperly Sealed.Caused by Personnel Error.Penetrations Reviewed & Fire Watch Established
05000410/LER-1986-007, :on 861120,ESF Actuation Occurred.Caused by Two Electrical Protection Assemblies (Epas) Tripping Twice in 2 H Causing Loss of Power to Circuit Bus Due to Personnel Error During MSIV Testing.Epas Reset1987-03-18018 March 1987
- on 861120,ESF Actuation Occurred.Caused by Two Electrical Protection Assemblies (Epas) Tripping Twice in 2 H Causing Loss of Power to Circuit Bus Due to Personnel Error During MSIV Testing.Epas Reset
1999-08-30
[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
[Table view] |
LER-1980-028, /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 |
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2201980028R04 - NRC Website |
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text
NRC,FORM 366
- - 77)>>,.
CONTROL BLOCK:
U. S. NUCLEAR.REGULATORYPCOMMISSION LICENSEE EVENT REPORT
,O (PLEASE PRINT OR TYPE ALLREQUIRED INFORIVIATION)
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8 CON'T
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8 QE LICENSEE CODE 14 15 LICENSE NUMBER 0 Qg.
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Qg LICENSE TYPE 30 57 CAT 58
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60 61 DOCKET NUMBER'8 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES
'IO Monthl milk sam 1
0 OB.
74 75 REPORT DATE
~03 three sam le locations.
Further sam les taken o
2 I-131 results at the nearest downwind 0
~os
~OB no significant environment effect. It is ex ected future sam le results will have no.detectable I-131.
See attachment for further details..
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~OB 80 7
8 7
8 9
SYSTEM, CAUSE
CAUSE
COMP.
VALVE CODE CODE SUBCODE CohIPONENT CODE SUBCODE SUBCODE
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~XX QII
~X Q12
~Z Qls Z
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2 Z
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10 11 12 13 18 19 20 SEOUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENTYEAR REPORT No.
CODE TYPE NO.
Q17 REPRR7 ~80
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~04
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~0 21 22 23 24 26 27 28 29 30 31 32 ACTION. FUTURE EFFECT SHUTDOWN ATTACHMENT NPR~
PRIME COMP.
'OMPONENT TAKEN ACTION ON PLANT METHOD HOURS 022 SUBhIITTED FORM SUB.
SUPPLIER MANUFACTURER LJOIRLJQ>>
LJOER LJOE LJQ>>
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CEI 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 o
The detection of 1-131 is attributed. to deposition from a nuclear. Nea'ns test conducted by the Peoples Republic of China in October.
The continued detection in a single downwind location is atributed to this farmers 3
4 extended grazing period.
Samples have been instituted weekly until, no.
further detection is present.
'Evaluation of plant release data indicates 7
8 9
p an accoun a z 3 ty or t e etecte eve s.
~ FACILITY
~3P METHOD OF STATUS 5 POWER OTHER STATUS ~
DISCOVERY DISCOVERY DESCRIPTION s
~8p- ~>>
Qog N/A'8QRI Test Results 80 NAME OF PREPARER P. Harrison 7
8 9
10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY 3
~ ~ ~
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~Z P>>
~ZP4 N/A N/A 7
8 9
10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 039 O
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8 9
11 12 13 PERSONNEL INJURIES NUMBER
'ESCRIPTIONO41 R
~OO O
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~
8 9
11 12 LOSS OF OR DAMAGETO FACILITY 43 TYPE
DESCRIPTION
g Z.
Q42 N/A 8
9 10 PUBLICITY IEERER OEECRIPEIONM 8101 070 +6 t
~NQ44 N/A 7
8 9
10 LOCATION OF RELEASE 80 80 80 80 80 NRC USE ONLY ER 68 69 80 o PHDNEI's 343-2110 Ext.
12 2 L
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~
ATTACEKNT A I.
SUMMARY Milk samples for I-131 are required to be taken monthly by NMP-1 ETS.
Samples collected on ll/3/80 demonstrated. positive I-131 detection at two off-site locations and the control location (the control location result was greater than four times the other location resu1ts).
This fact was reported to Region I (Dr. R. Bores) and was determined to be due to'the Chinese Nuclear Weapons Test in October 1980.
Samples collected for I-131 on ll/26/80 and 12/1/80 demonstrated positive I-131 results at the nearest'ownwind location only.
Region I (Cheryl Sakenas) was informed of these
,results as well (12/ll/80).
As a result of a preliminary investigation it w'as determined that the results could be'xplained by a difference in farming practices (personal communication with the farms in question).
During the beginning of November 1980, all sampling farms had cows off pasture except the farm in question with the positive I-131 result.
Sample results are included in Attachment C.
II.
General Description Deposition from a nuclear weapons test conducted by the Peoples Republic of China in October 1980 was scheduled to fall on New York State on October 21-26, 1980.
Milk samples collected from the six (6) milk sampling locations on October 27 were negative as far as I-131 detection. is concerned.
Samples collected on November 3 revealed positive I-131 detection at off-site and the control locations (this location had the highest amount of I-131; greater than 4 times the off-site locations).
See Attachment C.
This data was interpreted to mean that the effect of the weapons test fallout.was missed on October 27 sampling date but detected on the November 3 sampling date since off-site as well as.control locations had detectable I-131.
USNRC Region I was notified of this (11/26/80 - Dr. R. Bores and S. Hudson, USNRC Site Inspector).
Milk samples for I-131 were scheduled to be collected again on November 26.
Results from these samples revealed positive I-131 at the closest off-site location only (see Attachment C).
This one (1) positive result was 17.87 times the control result.
Scheduled samples on December 1 also revealed positive 1-131 at the closest off-site location.
This one (1) positive result was 31.2 times the control result.
This information was phoned to Region' on December ll
,(Cheryl Sakenas).
For purposes of investigation, weekly sampling was initiated.
next scheduled sample was December 12.
The data for I-131 for this date was negative, that is, all sampling locations did not have any detectable I-131 (all values were LLDs).
Actual data is not available to include on Attachment C since the information was acquired via telephone.
~4 Ws
Attachment A (cont'd)
III.
General Description of the Cause The cause of detectable I-131 in milk on November 26, and December 1 at the closest off-site location and not at the other off-site or control locations is due to two (2) factors.
First the I-131 detected is due to the Chinese Weapons Test of October 1980.
" November 3, I-131 results revealed detection at locations southeast and west of the site.
Wind data between October 26 and November 3 was re-viewed and resulted in southerly and northwesterly directions.
Analysis of air iodine samples and air gross beta samples around the site for both off-site and on-site locations revealed no detection of I-131 and no significant increases in gross beta counts.
A more detailed analysis. of air particulate composites (on-site and off-site) revealed positive I-131 detection as well as significant amounts of Ce-144, Hu-'103, Ba-140, Zr-95, Ce-141, Ta-140, Nd-147 (&>=10 days) and, Nb-95 (+=3.5days).
These results were not observed initially since in-dividual stations are counted separately utilizing short count times.
Ap-parently, by combining the individual samples, i.e. compositing, into on-site and off-site samples and utilizing long count times, the sensitivity of the instrumentation was increased significantly.
The presence of these nuclides
'they are associated with nuclear weapons testing) is not usually detected in air particulate composites at the site.
When considering the half life of Nd-147 and i'-95, the detection of fallout from the October Chinese Test is positive.. Further, review of NMPNPS and JAFNPP 'stack and vent release or effluent rate data did not reveal any increases that could account for the detected levels of I-131 in milk samples (these results were arrived at through dose equations using Reg.
Guide 1.109.
Finally, I-131 was detected at Salem Nuclear Power Plant, Peach Bottom Nuclear Power Plant, and Susquehanna Nuclear Power Plant.
Although -I-131 was not detected at Indian Point or Ginna Nuclear Power Plants in New York State, this fact is xplained below.
- Secondly, I-131 detection at the closest off-.site location and not the other off-site or control locations is due to. a difference in farming or in this specific, case, grazing practices.
Through personal communications with the owners of the milk sampling locations (information acquired through our biological contractor), it was determined that at all locations cows were off pasture approximately November 1, except at the closest off-site location
(¹25).
According to the owner at location ¹25. his cow (he only has one) was left to feed on pasture as long as possible for economic reasons uncoil shortly after December l.
At the other locations, cows were fed grain, hay, etc., indoors and. allowed to exercise 3-4 hours per.day.
At these locations it was determined that there was only insignificant amounts of pasture grass left, therefore pasture feeding was very limited during exercise periods.
Finally, I-131 detection at location ¹25 (closest off-site farm) was negative after December 1, since the one cow was not exposed to any I-131 deposition due to the Chinese Test fallout.
Considering the biological half-life, the presence of I-131 should be negative after 25 :.ays, as was 'demonstrated by the data.
ATTACHMENT A cont'd)
Therefore, it can be determined through observation and review of the facts that I-131 from weapons te'sting fallout was being detected on November 3.
This detection is thought to be in the initial phases of the biological buildup.
The levels increase on November 26 and December 1 but was detected. at location 825 only since this was the only location that had cows (actual only one cow) on pasture.
At the other locations, cows were not exposed to any I-131 de-
.position due to indoor feeding 'and thus milk results were nil.
ATTACHMENT B
Corrective Action
Weekly sampling at all milk locations'as initiated as per NMP-1 ETS requirements.
Sampling will continue until I-131 results are negative in milk samples or less than 2.4 pCi/liter.
An investigation was initiated covering all possible paths of contamination including plant operations.
This investigation has reviewed the pertinent data and determined the cause of I-131 in milk to be due to nuclear weapons testing.
Data from this investigation will remain on file at the plant.
As required by NMP-1 ETS, the USNRC Region 1
was notified by telephone as well as by this document and will be advised of any significant developments.
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05000220/LER-1980-001-03, /03L-0:on 800102,during Steady State Operation, Calculations Determined Planar Linear Heat Generation Rate Exceeded Tech Specs.Cause Unknown.Power Decreased. Calculation Revealed Heating Generation Rate within Limits | /03L-0:on 800102,during Steady State Operation, Calculations Determined Planar Linear Heat Generation Rate Exceeded Tech Specs.Cause Unknown.Power Decreased. Calculation Revealed Heating Generation Rate within Limits | | 05000220/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | 05000220/LER-1980-002, Forwards LER 80-002/04L-0 | Forwards LER 80-002/04L-0 | | 05000220/LER-1980-002-04, /04L-0:on 800109,during Steady State Operation, Review of Differential Recorder Revealed Condenser Inlet/ Screenwell Discharge Differential Temp Went Over Established Limits.Caused by Instrument Malfunction | /04L-0:on 800109,during Steady State Operation, Review of Differential Recorder Revealed Condenser Inlet/ Screenwell Discharge Differential Temp Went Over Established Limits.Caused by Instrument Malfunction | | 05000220/LER-1980-003-01, /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 | /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 | | 05000220/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | 05000220/LER-1980-005-01, /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 | /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 | | 05000220/LER-1980-005, Forwards LER 80-005/01X-0 | Forwards LER 80-005/01X-0 | | 05000220/LER-1980-006, Forwards LER 80-006/04L-0 | Forwards LER 80-006/04L-0 | | 05000220/LER-1980-006-04, /04L-0:on 800123-24,condensor Inlet/Circulating Water Discharge Temp Exceeded Tech Spec Limit.Following Flow Reversal,Discharge Temp Exceeded Lake Ambient by More than Tech Spec Limit.Caused by Instrument Failure | /04L-0:on 800123-24,condensor Inlet/Circulating Water Discharge Temp Exceeded Tech Spec Limit.Following Flow Reversal,Discharge Temp Exceeded Lake Ambient by More than Tech Spec Limit.Caused by Instrument Failure | | 05000220/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | 05000220/LER-1980-007-03, /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 | /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 | | 05000220/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | 05000220/LER-1980-008-03, /03L-0:on 800315,during Steady State Operation, Alarm in Control Room Signaled Loss of Flow to Stack Gas Sampling Sys.Caused by Stack Sample Flow Inlet Valve Failing Closed,Due to Arcing Relay Contacts | /03L-0:on 800315,during Steady State Operation, Alarm in Control Room Signaled Loss of Flow to Stack Gas Sampling Sys.Caused by Stack Sample Flow Inlet Valve Failing Closed,Due to Arcing Relay Contacts | | 05000220/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | 05000220/LER-1980-009-03, /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 | /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 | | 05000220/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | 05000220/LER-1980-010-03, /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 | /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 | | 05000220/LER-1980-011, Forwards LER 80-011/04L-0 | Forwards LER 80-011/04L-0 | | 05000220/LER-1980-011-04, /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 | /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 | | 05000220/LER-1980-012-03, /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 | /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 | | 05000220/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | 05000220/LER-1980-014-03, /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 | /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 | | 05000220/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | 05000220/LER-1980-015, Forwards LER 80-015/04L-0 | Forwards LER 80-015/04L-0 | | 05000220/LER-1980-015-04, /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 | /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 | | 05000220/LER-1980-018-03, /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 | /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 | | 05000220/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | 05000220/LER-1980-019, Forwards LER 80-019/04T-0 | Forwards LER 80-019/04T-0 | | 05000220/LER-1980-019-04, /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 | /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 | | 05000220/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | 05000220/LER-1980-020-03, /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 | /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 | | 05000220/LER-1980-022-03, /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 | /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 | | 05000220/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | 05000220/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | 05000220/LER-1980-023-03, /03L-0:on 800922,111 Absolute Filter Access Cover Was Found Off Housing.Caused by Residual Pressure in Containment Nitrogen Inerting Line Pressurizing Filter Housing When Torus Venting Initiated.Cover Reinstalled | /03L-0:on 800922,111 Absolute Filter Access Cover Was Found Off Housing.Caused by Residual Pressure in Containment Nitrogen Inerting Line Pressurizing Filter Housing When Torus Venting Initiated.Cover Reinstalled | | 05000220/LER-1980-024-03, /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 | /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 | | 05000220/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | 05000220/LER-1980-025, Forwards LER 80-025/03L-0 | Forwards LER 80-025/03L-0 | | 05000220/LER-1980-025-03, /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 | /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 | | 05000220/LER-1980-026-01, /01T-0:on 801118,input Error Discovered Which Resulted in Reduction in Calculated Pressure Margin to Reactor Safety Valve Setpoints During Possible Transients | /01T-0:on 801118,input Error Discovered Which Resulted in Reduction in Calculated Pressure Margin to Reactor Safety Valve Setpoints During Possible Transients | | 05000220/LER-1980-026, Forwards LER 80-026/01T-0 | Forwards LER 80-026/01T-0 | | 05000220/LER-1980-027, Forwards LER 80-027/03L-0 | Forwards LER 80-027/03L-0 | | 05000220/LER-1980-027-03, /03L-0:on 801126,operability Tests Were Not Immediately Performed as Required.Caused by Misunderstanding of Intent of Procedure.Testing Performed | /03L-0:on 801126,operability Tests Were Not Immediately Performed as Required.Caused by Misunderstanding of Intent of Procedure.Testing Performed | | 05000220/LER-1980-028, Forwards LER 80-028/04T-0 | Forwards LER 80-028/04T-0 | | 05000220/LER-1980-028-04, /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 | /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 | | 05000220/LER-1980-030, Forwards LER 80-030/04T-0 | Forwards LER 80-030/04T-0 | | 05000220/LER-1980-030-04, /04T-0:on 801204,discovered That Lower Limit of Detection for Radiological Fish Analysis Was Not within Ets. Caused by Conversion Factor.Tech Spec Changes Proposed to Update Parameter | /04T-0:on 801204,discovered That Lower Limit of Detection for Radiological Fish Analysis Was Not within Ets. Caused by Conversion Factor.Tech Spec Changes Proposed to Update Parameter | | 05000220/LER-1980-031-01, /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 | /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 | | 05000220/LER-1980-031, Forwards LER 80-031/01T-0 | Forwards LER 80-031/01T-0 | |
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