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SCH16-003, Discharge Monitoring Report December 2015
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PLA-2756, Forwards Postulated Pipe Rupture Calculations M-MSS-010 & M-MSS-006,per NRC 861112 Telcon Request
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L-PI-14-043, Independent Spent Fuel Storage Installation, 2013 Annual Radiological Environmental Monitoring Program (REMP) Report
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L-12-399, Submittal of Contractor Root Cause Assessment Report
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NL-11-2032, D. R. Madison Ltr. Edwin I. Hatch, Appeal to the Executive Director of Operations: Backfit and Applicability of Compliance Backfit Exception
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NL-11-0449, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(f)(1))
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NL-11-0255, Outage Inservice Inspection Summary Report
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ULNRC-05893, Callaway, Unit 1, Enclosure 21 to ULNRC-05893 - Callaway 2008 Air Emission Report
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L-2009-227, Request to Renew Industrial Wastewater Facility Permit
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ULNRC-06455, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00334
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SCH07-004, New Jersey Pollutant Discharge Elimination System Discharge Monitoring Report
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BVY 07-003, Email: (PA-LR) Vermont Yankee Nuclear Power Station License Renewal Commitment List, Rev. 5
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L-PI-06-037, Annual Radiological Environment Environmental Monitoring Program (REMP) Report
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NSD-NRC-97-5285, Forwards W Revised Response to NRC RAI Re AP600 Shutdown PRA & Surge Line Flooding
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B12002, Forwards Probabilistic risk-based Fire Analysis of internally-initiated Events.Fire Analysis Documented as Chapter 6 of Probabilistic Safety Study.W/Nine Oversize Encls
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page: https://kanterella.com/B12002-2C_Forwards_Probabilistic_risk-2Dbased_Fire_Analysis_of_internally-2Dinitiated_Events.Fire_Analysis_Documented_as_Chapter_6_of_Probabilistic_Safety_Study.W/Nine_Oversize_…
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2CAN039204, Application for Amend to License NPF-6,revising TS 4.4.5 to Allow Installation of Tube Sleeves as Alternative to Plugging Defective SG Tubes.Encl Rept 51-1212539-00 Withheld
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page: https://kanterella.com/2CAN039204-2C_Application_for_Amend_to_License_NPF-2D6-2Crevising_TS_4.4.5_to_Allow_Installation_of_Tube_Sleeves_as_Alternative_to_Plugging_Defective_SG_Tubes.Encl_Rept_51-2D121…
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BYRON 2023-0002, Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements
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IR 05000293/1989001
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CY-98-044, Provides Info on Beyond Design Basis Event of Loss of Water from Spent Fuel Pool at Plant Per NRC RAI
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NG-98-0531, Forwards Comments on NRC Draft SE for DAEC Conversion to Improved TS Based Upon NUREG-1433.Draft SE Contains Util Markups & Typed Inserts
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ML20217F801
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05000295/LER-1986-041, :on 861118,portable Particulate/Iodine Continuous Air Sampler Found Inoperable.Caused by Personnel Error.Sampler Relocated to Locked Caged Area in Turbine Bldg
type: Subject
page: https://kanterella.com/05000295/LER-2D1986-2D041-2C_-3Aon_861118-2Cportable_Particulate/Iodine_Continuous_Air_Sampler_Found_Inoperable.Caused_by_Personnel_Error.Sampler_Relocated_to_Locked_Caged_Area_…
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LER-1986-036-01, :on 860521,snubber Functional Tests Confirmed 104 safety-related Snubbers Failed to Meet Test Acceptance Limits.Cause of Each Failure Determined & Listed.Corrective Actions Implemented from 860521-0829
type: Subject
label: 05000373/LER-1986-036-01, :on 860521,snubber Functional Tests Confirmed 104 safety-related Snubbers Failed to Meet Test Acceptance Limits.Cause of Each Failure Determined & Listed.Corrective Actions Implemented from 860521-0829
page: https://kanterella.com/05000373/LER-2D1986-2D036-2D01-2C_-3Aon_860521-2Csnubber_Functional_Tests_Confirmed_104_safety-2Drelated_Snubbers_Failed_to_Meet_Test_Acceptance_Limits.Cause_of_Each_Failure_Det…
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wiki page sort key: 05000373/LER-1986-036-01, :on 860521,snubber Functional Tests Confirmed 104 safety-related Snubbers Failed to Meet Test Acceptance Limits.Cause of Each Failure Determined & Listed.Corrective Actions Implemented from 860521-0829

ML20236Y112
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ML20236F218
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Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS
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label: NRC-89-3448, Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS
page: https://kanterella.com/NRC-2D89-2D3448-2C_Forwards_Westinghouse_SP/90_Position_on_Selected_Severe_Accident_Issues_to_Be_Discussed_During_890714_Meeting_W/Nrc_in_Rockville-2CMd.Issue_Topics_Include_Fir…
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wiki page sort key: NRC-89-3448, Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS

ML20236D559
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ML20216C033
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LER-1987-002-04, :on 870112,eddy Current Field Rept Revealed That Steam Generator 1D Classified as Category C-3 in Tech Spec Due to 38 Tubes Being Defective.Caused by Intergranular Attack & Antivibration Bar Wear.Tubes Sleeved
type: Subject
label: 05000295/LER-1987-002-04, :on 870112,eddy Current Field Rept Revealed That Steam Generator 1D Classified as Category C-3 in Tech Spec Due to 38 Tubes Being Defective.Caused by Intergranular Attack & Antivibration Bar Wear.Tubes Sleeved
page: https://kanterella.com/05000295/LER-2D1987-2D002-2D04-2C_-3Aon_870112-2Ceddy_Current_Field_Rept_Revealed_That_Steam_Generator_1D_Classified_as_Category_C-2D3_in_Tech_Spec_Due_to_38_Tubes_Being_Defecti…
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ML20211F448
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ML20202G005
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ML20206Q999
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ML20154B463
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LER-1988-010-01, :on 880203,during NRC Equipment Qualification Insp,Damaged RHR Sys Rotork Electric Motor Operated Valve Actuator Discovered.Caused by Improper Installation of Motor to Actuator on Valve 2ND2A.Valve Repaired
type: Subject
label: 05000414/LER-1988-010-01, :on 880203,during NRC Equipment Qualification Insp,Damaged RHR Sys Rotork Electric Motor Operated Valve Actuator Discovered.Caused by Improper Installation of Motor to Actuator on Valve 2ND2A.Valve Repaired
page: https://kanterella.com/05000414/LER-2D1988-2D010-2D01-2C_-3Aon_880203-2Cduring_NRC_Equipment_Qualification_Insp-2CDamaged_RHR_Sys_Rotork_Electric_Motor_Operated_Valve_Actuator_Discovered.Caused_by_Imp…
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wiki page sort key: 05000414/LER-1988-010-01, :on 880203,during NRC Equipment Qualification Insp,Damaged RHR Sys Rotork Electric Motor Operated Valve Actuator Discovered.Caused by Improper Installation of Motor to Actuator on Valve 2ND2A.Valve Repaired

LER-1985-019-02, :on 851116,RWCU Sys Isolated on Unexpected High Temp Signal.Caused by Instrument Technicians Troubleshooting Wrong Temp Element on RWCU sys.TE-3-12-98 Leads Reconnected & RWCU Reset
type: Subject
label: 05000278/LER-1985-019-02, :on 851116,RWCU Sys Isolated on Unexpected High Temp Signal.Caused by Instrument Technicians Troubleshooting Wrong Temp Element on RWCU sys.TE-3-12-98 Leads Reconnected & RWCU Reset
page: https://kanterella.com/05000278/LER-2D1985-2D019-2D02-2C_-3Aon_851116-2CRWCU_Sys_Isolated_on_Unexpected_High_Temp_Signal.Caused_by_Instrument_Technicians_Troubleshooting_Wrong_Temp_Element_on_RWCU_sys…
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wiki page sort key: 05000278/LER-1985-019-02, :on 851116,RWCU Sys Isolated on Unexpected High Temp Signal.Caused by Instrument Technicians Troubleshooting Wrong Temp Element on RWCU sys.TE-3-12-98 Leads Reconnected & RWCU Reset

NSD-NRC-97-5079, Forwards AP600 SSAR Markups That Identify Changes Required to Implement Isolation Requirements for Normal Residual Heat Removal Sys
type: Subject
page: https://kanterella.com/NSD-2DNRC-2D97-2D5079-2C_Forwards_AP600_SSAR_Markups_That_Identify_Changes_Required_to_Implement_Isolation_Requirements_for_Normal_Residual_Heat_Removal_Sys
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wiki page sort key: NSD-NRC-97-5079, Forwards AP600 SSAR Markups That Identify Changes Required to Implement Isolation Requirements for Normal Residual Heat Removal Sys

LER-1985-007, :on 850423,24 & 25,Tech Spec 3.3.7.11.b Violated Due to Grab Samples Not Taken within Required 8 H Period When Radiation Monitor Inoperable.Caused by Personnel Error.Personnel Counseled.Procedure Written
type: Subject
label: 05000341/LER-1985-007, :on 850423,24 & 25,Tech Spec 3.3.7.11.b Violated Due to Grab Samples Not Taken within Required 8 H Period When Radiation Monitor Inoperable.Caused by Personnel Error.Personnel Counseled.Procedure Written
page: https://kanterella.com/05000341/LER-2D1985-2D007-2C_-3Aon_850423-2C24_-26_25-2CTech_Spec_3.3.7.11.b_Violated_Due_to_Grab_Samples_Not_Taken_within_Required_8_H_Period_When_Radiation_Monitor_Inoperable.…
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wiki page sort key: 05000341/LER-1985-007, :on 850423,24 & 25,Tech Spec 3.3.7.11.b Violated Due to Grab Samples Not Taken within Required 8 H Period When Radiation Monitor Inoperable.Caused by Personnel Error.Personnel Counseled.Procedure Written

ML20147E822
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LER-1984-006-01, :on 840519,diesel Generator 2B Tripped on High Jacket Water Temp.Review Revealed Generator Output Breaker Would Not Open If Trip Followed Nonemergency Test Start. Design Implemented to Correct Condition
type: Subject
label: 05000364/LER-1984-006-01, :on 840519,diesel Generator 2B Tripped on High Jacket Water Temp.Review Revealed Generator Output Breaker Would Not Open If Trip Followed Nonemergency Test Start. Design Implemented to Correct Condition
page: https://kanterella.com/05000364/LER-2D1984-2D006-2D01-2C_-3Aon_840519-2Cdiesel_Generator_2B_Tripped_on_High_Jacket_Water_Temp.Review_Revealed_Generator_Output_Breaker_Would_Not_Open_If_Trip_Followed_N…
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wiki page sort key: 05000364/LER-1984-006-01, :on 840519,diesel Generator 2B Tripped on High Jacket Water Temp.Review Revealed Generator Output Breaker Would Not Open If Trip Followed Nonemergency Test Start. Design Implemented to Correct Condition

ML20154B653
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ML20087M568
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ML20080K742
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05000366/LER-1983-062-03, /03L-0:on 830720 & 25,core Max Fraction of Limiting Power Density Exceeded Fraction of Rated Thermal Power.Caused by Peaks in Core Flux.Average Power Range Monitor Adjusted
type: Subject
page: https://kanterella.com/05000366/LER-2D1983-2D062-2D03-2C_/03L-2D0-3Aon_830720_-26_25-2Ccore_Max_Fraction_of_Limiting_Power_Density_Exceeded_Fraction_of_Rated_Thermal_Power.Caused_by_Peaks_in_Core_Flux…
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wiki page sort key: 05000366/LER-1983-062-03, /03L-0:on 830720 & 25,core Max Fraction of Limiting Power Density Exceeded Fraction of Rated Thermal Power.Caused by Peaks in Core Flux.Average Power Range Monitor Adjusted

ML20071P799
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ML20082Q611
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ML20069D490
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page: https://kanterella.com/ML20069D490
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03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled
type: Subject
label: 05000280/LER-1978-028-03, /03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled
page: https://kanterella.com/05000280/LER-2D1978-2D028-2D03-2C_/03L-2D0_on_780916-3Asnubber_Not_Meeting_Inspec_Criteria_Caused_by_Low_Oil_Level_Due_to_Leakage_at_Mating_Surface_Between_Body_-26_End_Plate.Ho…
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wiki page sort key: 05000280/LER-1978-028-03, /03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled

03L-0:on 820716,core Max Fraction of Limiting Powder Density Found Greater than Fraction of Rated Thermal Power.Caused by Rod Withdrawals in Areas of Low Xenon Concentration.Average Power Range Monitor Adjusted
type: Subject
label: 05000366/LER-1982-073-03, /03L-0:on 820716,core Max Fraction of Limiting Powder Density Found Greater than Fraction of Rated Thermal Power.Caused by Rod Withdrawals in Areas of Low Xenon Concentration.Average Power Range Monitor Adjusted
page: https://kanterella.com/05000366/LER-2D1982-2D073-2D03-2C_/03L-2D0-3Aon_820716-2Ccore_Max_Fraction_of_Limiting_Powder_Density_Found_Greater_than_Fraction_of_Rated_Thermal_Power.Caused_by_Rod_Withdrawal…
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wiki page sort key: 05000366/LER-1982-073-03, /03L-0:on 820716,core Max Fraction of Limiting Powder Density Found Greater than Fraction of Rated Thermal Power.Caused by Rod Withdrawals in Areas of Low Xenon Concentration.Average Power Range Monitor Adjusted

O Benefit of OD-1 (Low Power Range monitor).P-1 Indicated Frtp of 0.627 & Core Max Fraction of Limiting Power Density of 0.653
type: Subject
label: 05000366/LER-1982-111-03, /03L-0:on 820918,shift Technical Advisor Ran P-1 (Periodic Core Performance Log) W/O Benefit of OD-1 (Low Power Range monitor).P-1 Indicated Frtp of 0.627 & Core Max Fraction of Limiting Power Density of 0.653
page: https://kanterella.com/05000366/LER-2D1982-2D111-2D03-2C_/03L-2D0-3Aon_820918-2Cshift_Technical_Advisor_Ran_P-2D1_-28Periodic_Core_Performance_Log-29_W/O_Benefit_of_OD-2D1_-28Low_Power_Range_monitor-2…
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wiki page sort key: 05000366/LER-1982-111-03, /03L-0:on 820918,shift Technical Advisor Ran P-1 (Periodic Core Performance Log) W/O Benefit of OD-1 (Low Power Range monitor).P-1 Indicated Frtp of 0.627 & Core Max Fraction of Limiting Power Density of 0.653

Sys Failure in Offgas Recombiner Condensate Sys. Design of Sys Will Be Evaluated for Root Cause
type: Subject
label: 05000278/LER-1990-008-02, :on 900727,offgas Recombiner Isolation Occurred Causing Main Condenser Vacuum to Begin Decreasing.Caused by Component/Sys Failure in Offgas Recombiner Condensate Sys. Design of Sys Will Be Evaluated for Root Cause
page: https://kanterella.com/05000278/LER-2D1990-2D008-2D02-2C_-3Aon_900727-2Coffgas_Recombiner_Isolation_Occurred_Causing_Main_Condenser_Vacuum_to_Begin_Decreasing.Caused_by_Component/Sys_Failure_in_Offgas…
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wiki page sort key: 05000278/LER-1990-008-02, :on 900727,offgas Recombiner Isolation Occurred Causing Main Condenser Vacuum to Begin Decreasing.Caused by Component/Sys Failure in Offgas Recombiner Condensate Sys. Design of Sys Will Be Evaluated for Root Cause

05000413/LER-1989-027, :on 891120,Tech Spec Required Unit Shutdown Due to Inoperable Chemical & Vol Control Centrifugal Pump.W/
type: Subject
page: https://kanterella.com/05000413/LER-2D1989-2D027-2C_-3Aon_891120-2CTech_Spec_Required_Unit_Shutdown_Due_to_Inoperable_Chemical_-26_Vol_Control_Centrifugal_Pump.W/
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wiki page sort key: 05000413/LER-1989-027, :on 891120,Tech Spec Required Unit Shutdown Due to Inoperable Chemical & Vol Control Centrifugal Pump.W/

ML20064E138
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ML20085H302
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ML20092C762
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page: https://kanterella.com/ML20092C762
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PLA-1082, Forwards Amend 46 to OL Application,Including Revision K to Security Plan.Plan Revision Withheld (Ref 10CFR2.790)
type: Subject
page: https://kanterella.com/PLA-2D1082-2C_Forwards_Amend_46_to_OL_Application-2CIncluding_Revision_K_to_Security_Plan.Plan_Revision_Withheld_-28Ref_10CFR2.790-29
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wiki page sort key: PLA-1082, Forwards Amend 46 to OL Application,Including Revision K to Security Plan.Plan Revision Withheld (Ref 10CFR2.790)

ML20097F081
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page: https://kanterella.com/ML20097F081
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03L-0:on 820112,RCS Leak Rate Calculation Indicated Leak Rate of 1.433 Gpm from Flange for Vent Line for Reactor Coolant Pump P32C Seal Cavity Pressure Sensing Line.Caused by Loose Flange Bolts
type: Subject
label: 05000313/LER-1982-001-03, /03L-0:on 820112,RCS Leak Rate Calculation Indicated Leak Rate of 1.433 Gpm from Flange for Vent Line for Reactor Coolant Pump P32C Seal Cavity Pressure Sensing Line.Caused by Loose Flange Bolts
page: https://kanterella.com/05000313/LER-2D1982-2D001-2D03-2C_/03L-2D0-3Aon_820112-2CRCS_Leak_Rate_Calculation_Indicated_Leak_Rate_of_1.433_Gpm_from_Flange_for_Vent_Line_for_Reactor_Coolant_Pump_P32C_Seal_…
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wiki page sort key: 05000313/LER-1982-001-03, /03L-0:on 820112,RCS Leak Rate Calculation Indicated Leak Rate of 1.433 Gpm from Flange for Vent Line for Reactor Coolant Pump P32C Seal Cavity Pressure Sensing Line.Caused by Loose Flange Bolts

05000335/LER-1981-055-03, /03L-0:on 811219,during Normal Reactor Startup, Surveillance Requirement to Manually Trip Rx Trip Breakers Not Performed Per Tech Spec Limits.Caused by Personnel Error
type: Subject
page: https://kanterella.com/05000335/LER-2D1981-2D055-2D03-2C_/03L-2D0-3Aon_811219-2Cduring_Normal_Reactor_Startup-2C_Surveillance_Requirement_to_Manually_Trip_Rx_Trip_Breakers_Not_Performed_Per_Tech_Spec_…
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wiki page sort key: 05000335/LER-1981-055-03, /03L-0:on 811219,during Normal Reactor Startup, Surveillance Requirement to Manually Trip Rx Trip Breakers Not Performed Per Tech Spec Limits.Caused by Personnel Error

ML20044D323
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ML20042C413
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ML20042C170
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page: https://kanterella.com/ML20042C170
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05000335/LER-1981-043-03, /03L-0:on 810918,1A Battery Charger Shut Down on High Voltage During Battery Charging Surveillance.Caused by Defective Shutdown Device.Device Replaced
type: Subject
page: https://kanterella.com/05000335/LER-2D1981-2D043-2D03-2C_/03L-2D0-3Aon_810918-2C1A_Battery_Charger_Shut_Down_on_High_Voltage_During_Battery_Charging_Surveillance.Caused_by_Defective_Shutdown_Device.De…
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wiki page sort key: 05000335/LER-1981-043-03, /03L-0:on 810918,1A Battery Charger Shut Down on High Voltage During Battery Charging Surveillance.Caused by Defective Shutdown Device.Device Replaced

03L-0:on 820814,following Control Rod Pattern Adjustment,Core Max Fraction of Limiting Power Density Found Greater than Tech Spec Limit.Caused by Reduction in Xenon Concentration Due to Increased Burnup
type: Subject
label: 05000366/LER-1982-086-03, /03L-0:on 820814,following Control Rod Pattern Adjustment,Core Max Fraction of Limiting Power Density Found Greater than Tech Spec Limit.Caused by Reduction in Xenon Concentration Due to Increased Burnup
page: https://kanterella.com/05000366/LER-2D1982-2D086-2D03-2C_/03L-2D0-3Aon_820814-2Cfollowing_Control_Rod_Pattern_Adjustment-2CCore_Max_Fraction_of_Limiting_Power_Density_Found_Greater_than_Tech_Spec_Limi…
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wiki page sort key: 05000366/LER-1982-086-03, /03L-0:on 820814,following Control Rod Pattern Adjustment,Core Max Fraction of Limiting Power Density Found Greater than Tech Spec Limit.Caused by Reduction in Xenon Concentration Due to Increased Burnup

IR 05000277/1990001
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ML20009F200
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ML20052F448
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ML20024C437
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ML20066G447
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ML20031C097
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ML20054H634
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ML20038A000
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ML19347F071
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ML19341A307
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ML19343D576
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ST-HL-AE-4035, 2RE02 ISI Summary Rept for Repairs & Replacements at South Texas Project Electric Generating Station Unit 2
type: Subject
page: https://kanterella.com/ST-2DHL-2DAE-2D4035-2C_2RE02_ISI_Summary_Rept_for_Repairs_-26_Replacements_at_South_Texas_Project_Electric_Generating_Station_Unit_2
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ML20136C686
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ML20198L522
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ML20011E013
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ML20024C791
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ML20079M983
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ML20079S020
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ML20003F730
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Access to Protected Area in Both Units 1 & 2 Currently Subj to Unit 1 fitness-for-duty Program Since Const of Unit 2 on Hold
type: Subject
label: PY-CEI-NRR-1382, Forwards Semiannual fitness-for-duty Rept for Jan-June 1991. Personnel W/Access to Protected Area in Both Units 1 & 2 Currently Subj to Unit 1 fitness-for-duty Program Since Const of Unit 2 on Hold
page: https://kanterella.com/PY-2DCEI-2DNRR-2D1382-2C_Forwards_Semiannual_fitness-2Dfor-2Dduty_Rept_for_Jan-2DJune_1991._Personnel_W/Access_to_Protected_Area_in_Both_Units_1_-26_2_Currently_Subj_to_Unit_1_f…
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wiki page sort key: PY-CEI-NRR-1382, Forwards Semiannual fitness-for-duty Rept for Jan-June 1991. Personnel W/Access to Protected Area in Both Units 1 & 2 Currently Subj to Unit 1 fitness-for-duty Program Since Const of Unit 2 on Hold

ML20059E524
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ML20153F607
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ML20054J339
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ML20153C259
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ML20027B992
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ML20046B504
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ML20101J587
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ML19339A685
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ML20133M767
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ML20153H648
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ML19331C522
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ML19329E905
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ML19321A167
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03L-0:on 800526,during Mode 4 Operation,Boron Concentration in RWST Measured 2124 Ppm.Caused by Boron Concentration Makeup Being Too High.Boron Diluted to Proper Concentration
type: Subject
label: 05000327/LER-1980-078-03, /03L-0:on 800526,during Mode 4 Operation,Boron Concentration in RWST Measured 2124 Ppm.Caused by Boron Concentration Makeup Being Too High.Boron Diluted to Proper Concentration
page: https://kanterella.com/05000327/LER-2D1980-2D078-2D03-2C_/03L-2D0-3Aon_800526-2Cduring_Mode_4_Operation-2CBoron_Concentration_in_RWST_Measured_2124_Ppm.Caused_by_Boron_Concentration_Makeup_Being_Too_H…
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wiki page sort key: 05000327/LER-1980-078-03, /03L-0:on 800526,during Mode 4 Operation,Boron Concentration in RWST Measured 2124 Ppm.Caused by Boron Concentration Makeup Being Too High.Boron Diluted to Proper Concentration

ML19294A706
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05000245/LER-1979-006, Forwards LER 79-006/03L-0
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Fuel Assembly Loaded Grapple.Caused by Worn Track Limit Switch. Switch Replaced & Surveillance Procedure Changed
type: Subject
label: 05000245/LER-1979-015-03, /03L-0 on 790528:during Refueling,No Control Rod out-block Occurred When Refuel Bridge Was Over Core W/Fuel Assembly Loaded Grapple.Caused by Worn Track Limit Switch. Switch Replaced & Surveillance Procedure Changed
page: https://kanterella.com/05000245/LER-2D1979-2D015-2D03-2C_/03L-2D0_on_790528-3Aduring_Refueling-2CNo_Control_Rod_out-2Dblock_Occurred_When_Refuel_Bridge_Was_Over_Core_W/Fuel_Assembly_Loaded_Grapple.Cau…
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wiki page sort key: 05000245/LER-1979-015-03, /03L-0 on 790528:during Refueling,No Control Rod out-block Occurred When Refuel Bridge Was Over Core W/Fuel Assembly Loaded Grapple.Caused by Worn Track Limit Switch. Switch Replaced & Surveillance Procedure Changed

ML19262A881
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ML19261D533
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ML19241B130
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05000335/LER-2078-011, For St. Lucie Unit 1, When Upper Guide Structure Was Removed (Refueling Shutdown), 3 (of 45) Incore Instrument Thimbles Remained in the Core
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Foremen & Supervisors to Ensure Awareness of Work Order Guidelines
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L-86-388, Responds to Generic Ltr 86-14 Re Plans for Operator Licensing & Requalification Exams During FY87-90.Schedules Encl
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W3F1-2016-0064, Mitigating Strategies Assessment (MSA) Report for Flooding Hazard
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L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2
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RS-13-002, Response to Request for Additional Information Related to License Amendment Request to Technical Specification 3.7.3, Ultimate Heat Sink
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BYRON 2009-0003, Steam Generator Inservice Inspection Summary Report for Refueling Outage 14
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HNP-04-076, One Year Special Report, Steam Generator Tube Inspection Results
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L-05-101, Discharge Monitoring Report (NPDES) Permit No. PA0025615
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HL-5579, Forwards Proprietary & non-proprietary Response to 980210 RAI Re License Amend Request to Increase Authorized Max Power Level to 2,763 Mwt.Topical Rept NEDO-32749 Encl. Proprietary Info Withheld
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