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NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 3
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RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
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RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Table of Contents Through List of Effective Pages
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IA-80-586, Study Re Potential of Licensed Sites to Cause Significant Radiation Exposure to Surrounding Populations in Event of Severe Accident
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L-88-366, Changes,Tests & Experiments Made W/O Prior Commission Approval for Jul 1987 - June 1988
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wiki page sort key: L-88-366, Changes,Tests & Experiments Made W/O Prior Commission Approval for Jul 1987 - June 1988

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AECM-84-0438, Semiannual Radioactive Effluent Release Rept, Jan-June 1984
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PY-CEI-NRR-1415, Monthly Operating Rept for Oct 1991 for Perry Nuclear Plant Unit 1
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wiki page sort key: PY-CEI-NRR-1415, Monthly Operating Rept for Oct 1991 for Perry Nuclear Plant Unit 1

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LER-1989-014, :on 890216,isolation of Refuel Floor Secondary Containment & Initiation of Standby Gas Treatment Sys,Esf Occurred.Caused by Boiler Malfunction.Auxiliary Operator at Auxiliary Boiler Encl Restored Three Boilers
type: Subject
label: 05000352/LER-1989-014, :on 890216,isolation of Refuel Floor Secondary Containment & Initiation of Standby Gas Treatment Sys,Esf Occurred.Caused by Boiler Malfunction.Auxiliary Operator at Auxiliary Boiler Encl Restored Three Boilers
page: https://kanterella.com/05000352/LER-2D1989-2D014-2C_-3Aon_890216-2Cisolation_of_Refuel_Floor_Secondary_Containment_-26_Initiation_of_Standby_Gas_Treatment_Sys-2CEsf_Occurred.Caused_by_Boiler_Malfuncti…
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wiki page sort key: 05000352/LER-1989-014, :on 890216,isolation of Refuel Floor Secondary Containment & Initiation of Standby Gas Treatment Sys,Esf Occurred.Caused by Boiler Malfunction.Auxiliary Operator at Auxiliary Boiler Encl Restored Three Boilers

LER-1986-026, :on 861011,cracks Discovered in Fire Dome Area of 12 Cylinder Heads on Emergency Diesel Generator DG-2. Cause Attributed to Cylinder Head Design.New Cylinder Heads Received & All Cracked Heads Replaced
type: Subject
label: 05000298/LER-1986-026, :on 861011,cracks Discovered in Fire Dome Area of 12 Cylinder Heads on Emergency Diesel Generator DG-2. Cause Attributed to Cylinder Head Design.New Cylinder Heads Received & All Cracked Heads Replaced
page: https://kanterella.com/05000298/LER-2D1986-2D026-2C_-3Aon_861011-2Ccracks_Discovered_in_Fire_Dome_Area_of_12_Cylinder_Heads_on_Emergency_Diesel_Generator_DG-2D2._Cause_Attributed_to_Cylinder_Head_Desi…
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wiki page sort key: 05000298/LER-1986-026, :on 861011,cracks Discovered in Fire Dome Area of 12 Cylinder Heads on Emergency Diesel Generator DG-2. Cause Attributed to Cylinder Head Design.New Cylinder Heads Received & All Cracked Heads Replaced

ML20237K653
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Closure of Incorrect Valves Counseled
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label: 05000424/LER-1987-045, :on 870702,centrifugal Charging Pumps Removed from Svc.Caused by Personnel Error.Personnel Responsible for Writing,Reviewing & Approving Clearance Associated W/Closure of Incorrect Valves Counseled
page: https://kanterella.com/05000424/LER-2D1987-2D045-2C_-3Aon_870702-2Ccentrifugal_Charging_Pumps_Removed_from_Svc.Caused_by_Personnel_Error.Personnel_Responsible_for_Writing-2CReviewing_-26_Approving_Cle…
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wiki page sort key: 05000424/LER-1987-045, :on 870702,centrifugal Charging Pumps Removed from Svc.Caused by Personnel Error.Personnel Responsible for Writing,Reviewing & Approving Clearance Associated W/Closure of Incorrect Valves Counseled

LER-1986-013, :on 861107,failure Declared on as-found Reactor Bldg Integrated Leak Rate Test.Caused by Leakage from Bldg Purge Exhaust Valve Interspace.Second Test Performed & Resultant as-left Bldg Leak Rate Acceptable
type: Subject
label: 05000289/LER-1986-013, :on 861107,failure Declared on as-found Reactor Bldg Integrated Leak Rate Test.Caused by Leakage from Bldg Purge Exhaust Valve Interspace.Second Test Performed & Resultant as-left Bldg Leak Rate Acceptable
page: https://kanterella.com/05000289/LER-2D1986-2D013-2C_-3Aon_861107-2Cfailure_Declared_on_as-2Dfound_Reactor_Bldg_Integrated_Leak_Rate_Test.Caused_by_Leakage_from_Bldg_Purge_Exhaust_Valve_Interspace.Seco…
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wiki page sort key: 05000289/LER-1986-013, :on 861107,failure Declared on as-found Reactor Bldg Integrated Leak Rate Test.Caused by Leakage from Bldg Purge Exhaust Valve Interspace.Second Test Performed & Resultant as-left Bldg Leak Rate Acceptable

ML20236N855
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05000366/LER-1986-020-01, :on 860924,primary Containment Penetrations Failed Local Leak Rate Tests.Full Description of Causes & Corrective Actions Will Be Provided
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wiki page sort key: 05000366/LER-1986-020-01, :on 860924,primary Containment Penetrations Failed Local Leak Rate Tests.Full Description of Causes & Corrective Actions Will Be Provided

05000529/LER-1986-041-01, :on 860701,unidentified Leakage Greater than 1 Gpm Detected in Rcs.Caused by Seal Leakage Due to Strainer Flushing Techniques Previously Employed.Flushing Procedure Modified
type: Subject
page: https://kanterella.com/05000529/LER-2D1986-2D041-2D01-2C_-3Aon_860701-2Cunidentified_Leakage_Greater_than_1_Gpm_Detected_in_Rcs.Caused_by_Seal_Leakage_Due_to_Strainer_Flushing_Techniques_Previously_Em…
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wiki page sort key: 05000529/LER-1986-041-01, :on 860701,unidentified Leakage Greater than 1 Gpm Detected in Rcs.Caused by Seal Leakage Due to Strainer Flushing Techniques Previously Employed.Flushing Procedure Modified

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LER-1985-065, :on 850905,main Turbine Trip Caused Reactor Trip,Feedwater Isolation,Auxiliary Feedwater Actuation,Steam Generator Blowdown & Sample Isolation.Caused by Faulty Control Pump Discharge Relief Valve
type: Subject
label: 05000482/LER-1985-065, :on 850905,main Turbine Trip Caused Reactor Trip,Feedwater Isolation,Auxiliary Feedwater Actuation,Steam Generator Blowdown & Sample Isolation.Caused by Faulty Control Pump Discharge Relief Valve
page: https://kanterella.com/05000482/LER-2D1985-2D065-2C_-3Aon_850905-2Cmain_Turbine_Trip_Caused_Reactor_Trip-2CFeedwater_Isolation-2CAuxiliary_Feedwater_Actuation-2CSteam_Generator_Blowdown_-26_Sample_Iso…
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wiki page sort key: 05000482/LER-1985-065, :on 850905,main Turbine Trip Caused Reactor Trip,Feedwater Isolation,Auxiliary Feedwater Actuation,Steam Generator Blowdown & Sample Isolation.Caused by Faulty Control Pump Discharge Relief Valve

ML20127D532
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LER-1992-009, :on 920508,reactor Tripped.Caused by Personnel Error During Testing.Appropriate Level of Positive Discipline Program Implemented for Individuals Involved & Cabinet Locking Scheme Modified
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label: 05000445/LER-1992-009, :on 920508,reactor Tripped.Caused by Personnel Error During Testing.Appropriate Level of Positive Discipline Program Implemented for Individuals Involved & Cabinet Locking Scheme Modified
page: https://kanterella.com/05000445/LER-2D1992-2D009-2C_-3Aon_920508-2Creactor_Tripped.Caused_by_Personnel_Error_During_Testing.Appropriate_Level_of_Positive_Discipline_Program_Implemented_for_Individuals…
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wiki page sort key: 05000445/LER-1992-009, :on 920508,reactor Tripped.Caused by Personnel Error During Testing.Appropriate Level of Positive Discipline Program Implemented for Individuals Involved & Cabinet Locking Scheme Modified

ML20093J554
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LER-1991-008, :on 910826,valve RHR-MO-M057 Exceeded TS Closure Time During Surveillance Testing.On 910917,valve Not Deactivated During Period of Inoperability.Caused by Personnel Failure.Personnel Counseled
type: Subject
label: 05000298/LER-1991-008, :on 910826,valve RHR-MO-M057 Exceeded TS Closure Time During Surveillance Testing.On 910917,valve Not Deactivated During Period of Inoperability.Caused by Personnel Failure.Personnel Counseled
page: https://kanterella.com/05000298/LER-2D1991-2D008-2C_-3Aon_910826-2Cvalve_RHR-2DMO-2DM057_Exceeded_TS_Closure_Time_During_Surveillance_Testing.On_910917-2Cvalve_Not_Deactivated_During_Period_of_Inopera…
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wiki page sort key: 05000298/LER-1991-008, :on 910826,valve RHR-MO-M057 Exceeded TS Closure Time During Surveillance Testing.On 910917,valve Not Deactivated During Period of Inoperability.Caused by Personnel Failure.Personnel Counseled

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LER-1990-009, :on 900427,discovered That Moving Filter Paper in Leak Detection Sys Drywell Air Particulate Sample Panel Not Collecting on take-up Reel.Caused by Loose Set Screw on Gear Train.Set Screw Tightened
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label: 05000461/LER-1990-009, :on 900427,discovered That Moving Filter Paper in Leak Detection Sys Drywell Air Particulate Sample Panel Not Collecting on take-up Reel.Caused by Loose Set Screw on Gear Train.Set Screw Tightened
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LER-1989-019-01, :on 891206,discovered That Tech Specs Violated Due to Foreman Approving Measurements of Cell Recorded as 2.10 V on 891122.Caused by Personnel Error & Inadequate Procedure.Foreman Counseled
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label: 05000424/LER-1989-019-01, :on 891206,discovered That Tech Specs Violated Due to Foreman Approving Measurements of Cell Recorded as 2.10 V on 891122.Caused by Personnel Error & Inadequate Procedure.Foreman Counseled
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LER-1989-008-03, :on 891113,containment Integrity Not Maintained for Approx 30 S.Caused by Personnel in That Inner Door Was Left Blocked Open.Personnel Counseled & Interim Administrative Controls Established
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GO2-84-465, Semiannual Effluent Rept,Jan-June 1984
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L-82-542, Forwards Addl Info Re Small Feedwater Line Break Analysis. Info Needed to Close Confirmatory Issue Addressed in Section 15.10.2 of SER
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BYRON 2017-0038, 2016 Annual Radiological Environmental Operating Report
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LER-1986-068, :on 861220,steam Generator D Water Level Reached lo-lo Setpoint,Initiating Stated Events,Including Reactor Trip & Main Feedwater Isolation.Caused by Steam Generator Level Sensitivity
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label: 05000482/LER-1986-068, :on 861220,steam Generator D Water Level Reached lo-lo Setpoint,Initiating Stated Events,Including Reactor Trip & Main Feedwater Isolation.Caused by Steam Generator Level Sensitivity
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LER-1984-002-03, :on 840505,reactor Tripped Manually After Receiving Automatic Turbine Trip Signal & Loss of Normal Feedwater.Caused by High Water Level in Feedwater Heater 5B. Module Recalibr & Channel Returned to Svc
type: Subject
label: 05000339/LER-1984-002-03, :on 840505,reactor Tripped Manually After Receiving Automatic Turbine Trip Signal & Loss of Normal Feedwater.Caused by High Water Level in Feedwater Heater 5B. Module Recalibr & Channel Returned to Svc
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Cross cutting aspect
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