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ML20205G918
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ML20204H818
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ML20203K323
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IA-99-111, Partially Deleted Final Response to Request Re Current Public Exposure Stds Approved by DOE for Amount of Radioactivity in Metal & Pending Decisions to Lower Exposure Stds to 10 Mrems Per Year.Responsive Documentation Encl
type: Subject
page: https://kanterella.com/IA-2D99-2D111-2C_Partially_Deleted_Final_Response_to_Request_Re_Current_Public_Exposure_Stds_Approved_by_DOE_for_Amount_of_Radioactivity_in_Metal_-26_Pending_Decisions_to_Lower_…
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wiki page sort key: IA-99-111, Partially Deleted Final Response to Request Re Current Public Exposure Stds Approved by DOE for Amount of Radioactivity in Metal & Pending Decisions to Lower Exposure Stds to 10 Mrems Per Year.Responsive Documentation Encl

ML20206G228
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ML20209B183
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ML20214L980
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ML20213C839
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ML20212H949
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ML20237K067
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ML20237C545
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ML20249C381
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ML20246J263
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ML20217A479
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HBL-21-004, Annual Radioactive Effluent Release Report for 2020
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ML21133A252
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ML20211B831
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ML20211B489
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ML20210G177
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ML20209J159
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ML20209G021
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ML20205N687
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B12443, Application for Amend to License NPF-49,changing Tech Spec 3.6.1.4 to Allow Plant Operation Above Limit of Figure 3.6-1 for Containment Sys Air Partial Pressure.Safety Evaluation Encl.Fee Paid
type: Subject
page: https://kanterella.com/B12443-2C_Application_for_Amend_to_License_NPF-2D49-2Cchanging_Tech_Spec_3.6.1.4_to_Allow_Plant_Operation_Above_Limit_of_Figure_3.6-2D1_for_Containment_Sys_Air_Partial_Pressure.…
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wiki page sort key: B12443, Application for Amend to License NPF-49,changing Tech Spec 3.6.1.4 to Allow Plant Operation Above Limit of Figure 3.6-1 for Containment Sys Air Partial Pressure.Safety Evaluation Encl.Fee Paid

ML20202D097
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ML22049B558
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ML22087A478
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ML22136A084
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page: https://kanterella.com/ML22136A084
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TSTF-22-07, Transmittal of TSTF-592, Revision 0, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
type: Subject
page: https://kanterella.com/TSTF-2D22-2D07-2C_Transmittal_of_TSTF-2D592-2C_Revision_0-2C_Revise_Automatic_Depressurization_System_-28ADS-29_Instrumentation_Requirements
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wiki page sort key: TSTF-22-07, Transmittal of TSTF-592, Revision 0, Revise Automatic Depressurization System (ADS) Instrumentation Requirements

B11777, Forwards Response to Request for Addl Info Re 850724 Application to Revise Tech Specs on Spent Fuel Storage Capacity
type: Subject
page: https://kanterella.com/B11777-2C_Forwards_Response_to_Request_for_Addl_Info_Re_850724_Application_to_Revise_Tech_Specs_on_Spent_Fuel_Storage_Capacity
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wiki page sort key: B11777, Forwards Response to Request for Addl Info Re 850724 Application to Revise Tech Specs on Spent Fuel Storage Capacity

ML20133P313
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ML20119A481
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page: https://kanterella.com/ML20119A481
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HL-4781, Submits Addl Info Requested by NRC Re Recent Core Shroud Mod on Plant Unit 1
type: Subject
page: https://kanterella.com/HL-2D4781-2C_Submits_Addl_Info_Requested_by_NRC_Re_Recent_Core_Shroud_Mod_on_Plant_Unit_1
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wiki page sort key: HL-4781, Submits Addl Info Requested by NRC Re Recent Core Shroud Mod on Plant Unit 1

ML23010A259
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page: https://kanterella.com/ML23010A259
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ML21109A051
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ML23109A161
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page: https://kanterella.com/ML23109A161
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ML20062H270
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ML23137A103
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page: https://kanterella.com/ML23137A103
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ML23110A202
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page: https://kanterella.com/ML23110A202
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ML23222A227
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page: https://kanterella.com/ML23222A227
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ML21167A151
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ML23198A022
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page: https://kanterella.com/ML23198A022
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ML23321A125
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page: https://kanterella.com/ML23321A125
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ML24177A278
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page: https://kanterella.com/ML24177A278
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ML24029A148
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page: https://kanterella.com/ML24029A148
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GO2-24-051, Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
type: Subject
page: https://kanterella.com/GO2-2D24-2D051-2C_Application_to_Revise_Technical_Specifications_to_Adopt_TSTF-2D592-2C_Revise_Automatic_Depressurization_System_-28ADS-29_Instrumentation_Requirements
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wiki page sort key: GO2-24-051, Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements

ML24263A271
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page: https://kanterella.com/ML24263A271
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W3P87-1770, Responds to NRC Bulletin 87-001, Thinning of Pipe Walls in Nuclear Power Plants, Which Requested Info Re Licensee Programs for Monitoring Thickness of Pipe Walls in High Energy Single Phase & two-phase Carbon Steel Piping Sys
type: Subject
page: https://kanterella.com/W3P87-2D1770-2C_Responds_to_NRC_Bulletin_87-2D001-2C_Thinning_of_Pipe_Walls_in_Nuclear_Power_Plants-2C_Which_Requested_Info_Re_Licensee_Programs_for_Monitoring_Thickness_of_Pipe…
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wiki page sort key: W3P87-1770, Responds to NRC Bulletin 87-001, Thinning of Pipe Walls in Nuclear Power Plants, Which Requested Info Re Licensee Programs for Monitoring Thickness of Pipe Walls in High Energy Single Phase & two-phase Carbon Steel Piping Sys

ML20237H962
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page: https://kanterella.com/ML20237H962
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05000352/LER-1987-052, :on 870922,unplanned Isolation of RWCU Sys Occurred Due to Signal from Steam Leak Detection Sys.Caused by Defective Riley Co Differential Temp Switch 86VTFF.Temp Switch Replaced
type: Subject
page: https://kanterella.com/05000352/LER-2D1987-2D052-2C_-3Aon_870922-2Cunplanned_Isolation_of_RWCU_Sys_Occurred_Due_to_Signal_from_Steam_Leak_Detection_Sys.Caused_by_Defective_Riley_Co_Differential_Temp_S…
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wiki page sort key: 05000352/LER-1987-052, :on 870922,unplanned Isolation of RWCU Sys Occurred Due to Signal from Steam Leak Detection Sys.Caused by Defective Riley Co Differential Temp Switch 86VTFF.Temp Switch Replaced

LER-1986-083, :on 861101,inadvertent Actuation of Channel D LOCA Logic Occurred from Invalid Reactor Water Level Signal. Caused by Equipment Failure in That Inboard 1 Isolation Valve Leaked Through.Valve Will Be Repaired
type: Subject
label: 05000354/LER-1986-083, :on 861101,inadvertent Actuation of Channel D LOCA Logic Occurred from Invalid Reactor Water Level Signal. Caused by Equipment Failure in That Inboard 1 Isolation Valve Leaked Through.Valve Will Be Repaired
page: https://kanterella.com/05000354/LER-2D1986-2D083-2C_-3Aon_861101-2Cinadvertent_Actuation_of_Channel_D_LOCA_Logic_Occurred_from_Invalid_Reactor_Water_Level_Signal._Caused_by_Equipment_Failure_in_That_I…
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wiki page sort key: 05000354/LER-1986-083, :on 861101,inadvertent Actuation of Channel D LOCA Logic Occurred from Invalid Reactor Water Level Signal. Caused by Equipment Failure in That Inboard 1 Isolation Valve Leaked Through.Valve Will Be Repaired

ML20247E549
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page: https://kanterella.com/ML20247E549
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ML20234F090
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page: https://kanterella.com/ML20234F090
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ML20207C410
type: Subject
page: https://kanterella.com/ML20207C410
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LER-1987-002-04, :During Wk of 870127,determined That Operators May Not Be Able to Isolate Particular Letdown Flow Path. Caused by Design Deficiency.Power Removed from Breakers for Valves LP-1 & HP-2 on 870129
type: Subject
label: 05000269/LER-1987-002-04, :During Wk of 870127,determined That Operators May Not Be Able to Isolate Particular Letdown Flow Path. Caused by Design Deficiency.Power Removed from Breakers for Valves LP-1 & HP-2 on 870129
page: https://kanterella.com/05000269/LER-2D1987-2D002-2D04-2C_-3ADuring_Wk_of_870127-2Cdetermined_That_Operators_May_Not_Be_Able_to_Isolate_Particular_Letdown_Flow_Path._Caused_by_Design_Deficiency.Power_R…
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cross cutting aspect: H.3(s)
wiki page sort key: 05000269/LER-1987-002-04, :During Wk of 870127,determined That Operators May Not Be Able to Isolate Particular Letdown Flow Path. Caused by Design Deficiency.Power Removed from Breakers for Valves LP-1 & HP-2 on 870129

LER-1986-002, :on 860131,failure to Implement Portions of Inservice Testing Program Discovered.Caused by Inadequate Mgt Attention to Program Requirements.Required Testing of Valves in ASME Sections 1-10 Performed
type: Subject
label: 05000272/LER-1986-002, :on 860131,failure to Implement Portions of Inservice Testing Program Discovered.Caused by Inadequate Mgt Attention to Program Requirements.Required Testing of Valves in ASME Sections 1-10 Performed
page: https://kanterella.com/05000272/LER-2D1986-2D002-2C_-3Aon_860131-2Cfailure_to_Implement_Portions_of_Inservice_Testing_Program_Discovered.Caused_by_Inadequate_Mgt_Attention_to_Program_Requirements.Requ…
wiki namespace: 0
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cross cutting aspect: H.3(s)
wiki page sort key: 05000272/LER-1986-002, :on 860131,failure to Implement Portions of Inservice Testing Program Discovered.Caused by Inadequate Mgt Attention to Program Requirements.Required Testing of Valves in ASME Sections 1-10 Performed

LER-1988-015, :on 880805,reactor Isolation Signal Inadvertently Initiated During Intermediate Range Neutron Monitor Front Panel Surveillance.Caused by Circuit Not Configured to Facilitate Testing.Fuse Replaced
type: Subject
label: 05000219/LER-1988-015, :on 880805,reactor Isolation Signal Inadvertently Initiated During Intermediate Range Neutron Monitor Front Panel Surveillance.Caused by Circuit Not Configured to Facilitate Testing.Fuse Replaced
page: https://kanterella.com/05000219/LER-2D1988-2D015-2C_-3Aon_880805-2Creactor_Isolation_Signal_Inadvertently_Initiated_During_Intermediate_Range_Neutron_Monitor_Front_Panel_Surveillance.Caused_by_Circuit…
wiki namespace: 0
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cross cutting aspect: H.3(s)
wiki page sort key: 05000219/LER-1988-015, :on 880805,reactor Isolation Signal Inadvertently Initiated During Intermediate Range Neutron Monitor Front Panel Surveillance.Caused by Circuit Not Configured to Facilitate Testing.Fuse Replaced

LER-1988-003, :on 880204,electric Fire Pump Declared Inoperable Due to High Amperage.Caused by Physical Damage to Stuffing Box Brass Bushing in Electric Driven Fire Pump. Repairs Initiated on Pump
type: Subject
label: 05000213/LER-1988-003, :on 880204,electric Fire Pump Declared Inoperable Due to High Amperage.Caused by Physical Damage to Stuffing Box Brass Bushing in Electric Driven Fire Pump. Repairs Initiated on Pump
page: https://kanterella.com/05000213/LER-2D1988-2D003-2C_-3Aon_880204-2Celectric_Fire_Pump_Declared_Inoperable_Due_to_High_Amperage.Caused_by_Physical_Damage_to_Stuffing_Box_Brass_Bushing_in_Electric_Drive…
wiki namespace: 0
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wiki page sort key: 05000213/LER-1988-003, :on 880204,electric Fire Pump Declared Inoperable Due to High Amperage.Caused by Physical Damage to Stuffing Box Brass Bushing in Electric Driven Fire Pump. Repairs Initiated on Pump

ML20148F532
type: Subject
page: https://kanterella.com/ML20148F532
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LER-1985-009-01, :on 851106,during Routine Testing on Unit Simulator,Design Discrepancy Noted in Charging Pump B Circuitry.Caused by Design Error Which Inhibits Pump Operation.Mod to Circuit Implemented
type: Subject
label: 05000336/LER-1985-009-01, :on 851106,during Routine Testing on Unit Simulator,Design Discrepancy Noted in Charging Pump B Circuitry.Caused by Design Error Which Inhibits Pump Operation.Mod to Circuit Implemented
page: https://kanterella.com/05000336/LER-2D1985-2D009-2D01-2C_-3Aon_851106-2Cduring_Routine_Testing_on_Unit_Simulator-2CDesign_Discrepancy_Noted_in_Charging_Pump_B_Circuitry.Caused_by_Design_Error_Which_In…
wiki namespace: 0
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cross cutting aspect: H.3(s)
wiki page sort key: 05000336/LER-1985-009-01, :on 851106,during Routine Testing on Unit Simulator,Design Discrepancy Noted in Charging Pump B Circuitry.Caused by Design Error Which Inhibits Pump Operation.Mod to Circuit Implemented

LER-1985-018-03, :on 851106,potential Created to Violate Secondary Containment.Caused by Failure to Provide Positive Control of Containment During Mod of Carbon Steel Piping in Emergency Equipment Cooling Water Sys
type: Subject
label: 05000260/LER-1985-018-03, :on 851106,potential Created to Violate Secondary Containment.Caused by Failure to Provide Positive Control of Containment During Mod of Carbon Steel Piping in Emergency Equipment Cooling Water Sys
page: https://kanterella.com/05000260/LER-2D1985-2D018-2D03-2C_-3Aon_851106-2Cpotential_Created_to_Violate_Secondary_Containment.Caused_by_Failure_to_Provide_Positive_Control_of_Containment_During_Mod_of_Ca…
wiki namespace: 0
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cross cutting aspect: H.3(s)
wiki page sort key: 05000260/LER-1985-018-03, :on 851106,potential Created to Violate Secondary Containment.Caused by Failure to Provide Positive Control of Containment During Mod of Carbon Steel Piping in Emergency Equipment Cooling Water Sys

LER-1985-048, :on 850724,reactor Bldg HVAC Failed to Start After Planned Trip.Hvac Exhaust Isolation Damper Reopened When Isolation Signal Reset Despite Exhaust Fan Trip. Response Procedure Revised
type: Subject
label: 05000341/LER-1985-048, :on 850724,reactor Bldg HVAC Failed to Start After Planned Trip.Hvac Exhaust Isolation Damper Reopened When Isolation Signal Reset Despite Exhaust Fan Trip. Response Procedure Revised
page: https://kanterella.com/05000341/LER-2D1985-2D048-2C_-3Aon_850724-2Creactor_Bldg_HVAC_Failed_to_Start_After_Planned_Trip.Hvac_Exhaust_Isolation_Damper_Reopened_When_Isolation_Signal_Reset_Despite_Exhau…
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cross cutting aspect: H.3(s)
wiki page sort key: 05000341/LER-1985-048, :on 850724,reactor Bldg HVAC Failed to Start After Planned Trip.Hvac Exhaust Isolation Damper Reopened When Isolation Signal Reset Despite Exhaust Fan Trip. Response Procedure Revised

Buildup of Water in Sensing Lines.Rupture Disk Replaced
type: Subject
label: 05000322/LER-1985-032, :on 850822,HPCI Turbine Exhaust Diaphragm High Pressure Side B Signal Initiated Causing HPCI Sys Isolation. Caused by Leak in Diaphragm W/Buildup of Water in Sensing Lines.Rupture Disk Replaced
page: https://kanterella.com/05000322/LER-2D1985-2D032-2C_-3Aon_850822-2CHPCI_Turbine_Exhaust_Diaphragm_High_Pressure_Side_B_Signal_Initiated_Causing_HPCI_Sys_Isolation._Caused_by_Leak_in_Diaphragm_W/Buildu…
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wiki page sort key: 05000322/LER-1985-032, :on 850822,HPCI Turbine Exhaust Diaphragm High Pressure Side B Signal Initiated Causing HPCI Sys Isolation. Caused by Leak in Diaphragm W/Buildup of Water in Sensing Lines.Rupture Disk Replaced

ML20196J544
type: Subject
page: https://kanterella.com/ML20196J544
wiki namespace: 0
wiki page content language: en
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wiki page sort key: ML20196J544

05000286/LER-1984-014-01, :on 841013,trip Signal Received While Unit Subcritical.Caused by Blown Control Power Fuse on Channel 35 Intermediate Range Monitor.Fuse Replaced
type: Subject
page: https://kanterella.com/05000286/LER-2D1984-2D014-2D01-2C_-3Aon_841013-2Ctrip_Signal_Received_While_Unit_Subcritical.Caused_by_Blown_Control_Power_Fuse_on_Channel_35_Intermediate_Range_Monitor.Fuse_Rep…
wiki namespace: 0
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cross cutting aspect: H.3(s)
wiki page sort key: 05000286/LER-1984-014-01, :on 841013,trip Signal Received While Unit Subcritical.Caused by Blown Control Power Fuse on Channel 35 Intermediate Range Monitor.Fuse Replaced

LER-1985-013-01, :on 850212,while Finishing Precoating of Filter Demineralizer,Reactor Water Cleanup Sys Isolated on High Differential Flow.Caused by Internal Accumulated Sys Leakage & Flow Perturbations
type: Subject
label: 05000373/LER-1985-013-01, :on 850212,while Finishing Precoating of Filter Demineralizer,Reactor Water Cleanup Sys Isolated on High Differential Flow.Caused by Internal Accumulated Sys Leakage & Flow Perturbations
page: https://kanterella.com/05000373/LER-2D1985-2D013-2D01-2C_-3Aon_850212-2Cwhile_Finishing_Precoating_of_Filter_Demineralizer-2CReactor_Water_Cleanup_Sys_Isolated_on_High_Differential_Flow.Caused_by_Inte…
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PNP 2024-008, Annual Radioactive Effluent Release Report
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RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station
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RAIO-0319-64959, LLC Supplemental Response to NRC Request for Additional Information No. 356 (Erai No. 9253) on the NuScale Design Certification Application
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L-96-111, Forwards Response to NRC Request for Addl Info Re Proposed License Amends Relocation of Radiological Effluent Ts,Using Guidance of GL 89-01
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GO2-90-144, Washington Nuclear Plant 2 Semiannual Effluent Release Rept,Jan-June 1990
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L-82-459, Forwards Final Response to NRC Question 220.37 Re Masonry Walls.W/Two Oversize Drawings Encl.Aperture Cards Are Available in PDR
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RAIO-0818-61468, LLC Response to NRC Request for Additional Information No. 356 (Erai No. 9253) on the NuScale Design Certification Application
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AEP-NRC-2010-38, Annual Radioactive Effluent Release Report, January 1, 2009, Through December 31, 2009
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L-2008-170, Re-Submittal of the 2007 Annual Radiological Environmental Operating Report, Required by Technical Specification 6.9.1.3
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2002 Meetings Re Saxton Nuclear Experimental (SNEC) License Termination Plan, Dose Modeling & Characterization Issues Addressed in NRC RAIs
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NG-21-0008, Attachment 3: Defueled Offsite Dose Assessment Manual (Dodam)
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PNP 2025-015, Annual Radioactive Effluent Release Report
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IR 05000336/1997211
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JAFP-23-0060, Emergency Plan Document Revisions
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TSTF-23-07, TSTF Response to NRC Request for Additional Information on TSTF-592, Revision 1, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
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