Pages that link to "10 CFR 50.73(a)(2)(v)(A)"
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The following pages link to 10 CFR 50.73(a)(2)(v)(A):
Displaying 50 items.
- 05000266/LER-2021-001, Main Feedwater Pump Trip Results in Manual Reactor Trip (← links)
- 05000416/LER-2020-006-02, Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram (← links)
- 05000416/LER-2020-005-02, Primarv Water Svstem Flow Lowered Causinc Turbine Trio and Subseauent Reactor Scram (← links)
- 05000416/LER-2020-003-01, Manual Reactor Scram Due to Turbine High Pressure Control Valve Malfunction and Automatic Reactor Water Level Scram (← links)
- 05000416/LER-2020-002-02, Reactor Scram Due to Main Turbine Trip (← links)
- 05000327/LER-2021-001, Sequoya Nuclear Plant, Unit 1, Reactor Trip on High Neutron Flux Rate Due to Dropped Control Rods (← links)
- 05000277/LER-2021-001, High Pressure Coolant Injection System Declared Inoperable Due to Instrument Power Inverter Failure (← links)
- 05000456/LER-2021-001, Train a and B Source Range Neutron Flux Trip Functions Bypassed During Plant Startup (← links)
- 05000440/LER-2020-002-01, Standby Liquid Control System Rendered Inoperable Due to Valve Misposition (← links)
- 05000318/LER-2021-001, Calvert Cliff Nuclear Power Plant Unit No. 2, Pressure Heater Sleeve Weld Pressure Boundary Leakage Caused by Primary Water Stress Corrosion Cracking (← links)
- 05000483/LER-2021-001, Manual Actuation of Essential Service Water System (← links)
- 05000389/LER-2021-001, Automatic Reactor Trip Due to a Breaker Failure on the 2B2 480V Motor Control Center (← links)
- 05000317/LER-2020-001, Regarding Undervoltage Condition on 4.16kV Electrical Bus 11 Resulted in Actuation of Emergency Diesel Generator 1 a (← links)
- 05000298/LER-2020-004, Secondary Containment Differential Pressure Perturbation Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000266/LER-2020-001, Re Reactor Coolant System Pressure Boundary Leak on Steam Generator Bowl Drain Line Results in Operation Prohibited by Technical Specifications (← links)
- 05000334/LER-2020-001, Intake Structure Interconnecting Flood Door Found Open Resulting in a Loss of Train Separation for the Reactor Plant River Water System (← links)
- 05000316/LER-2020-003, Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve (← links)
- 05000410/LER-2020-002-01, Failure to Meet Technical Specification MSIV Stroke Times (← links)
- 05000267/LER-1989-019, :on 890906,steam Entered Instrument Air Header a During Startup of Outside Auxiliary Boiler.Caused by Failure of Check Valve Which Allowed Steam to Flow Into Svc Air Line.Air Header Blown Down & Dried Out (← links)
- 05000267/LER-1989-015, :on 890817,Region 19 CRD Pair Failed to Properly Insert During Weekly Partial Scram Test.Caused by Failed Clevis Bolt Head That Became Logged Between Control Rod Absorber Strings & Guide Tube (← links)
- 05000352/LER-1989-023, :on 890405,determined That in Event of Fire, Lack of Protected Suppression Pool Level & Temp Indication to Support Safe Shutdown of Plant Could Have Adversely Impacted Operator to Assess Conditions (← links)
- 05000352/LER-1989-047, :on 890720,identified That Svc Water Sys Unavailable to Provide Cooling Water to ECCS & RCIC Sys Due to Valve Position.Caused by Inadequate Emergency Procedures. Valve Reopened & Procedure T-103 Revised (← links)
- 05000317/LER-1989-009, :on 890515,preliminary Evaluation Concluded That Util May Not Have Adequate Assurance to Bring Down Unit to Cold Shutdown Condition,Per App R Requirements. Caused by Inadequate Procedure (← links)
- 05000312/LER-1988-021, :on 880615,potential Loss of Equipment Necessary to Mitigate Consequences of Accident Due to Postulated Implosion of Junction Boxed Noted.Caused by Failure to Apply Changes.Weepholes Installed (← links)
- 05000245/LER-1987-032-01, :on 870811,first Stage Bypass Switches Failed to Meet Tech Spec Requirements.Caused by Setpoint Drift from Extended Periods of Depressurization.Switches Recalibrated to Conform to Tech Specs (← links)
- 05000352/LER-1989-012, :on 890215,identified That Fire in Certain Areas of Plant Could Result in Unavailability of RCIC Sys Due to Insufficient Protection of Control Cables.Evaluation Underway.Procedure GP-2 Will Be Revised (← links)
- 05000312/LER-1987-042, :on 870912,technician Detected Electrical Problems W/Amphenol Blue Ribbon Connectors.Caused by Coating of Residue from Solder Flux,Organic Matls & Plasticizers. Nonconforming Rept Procedure Revised (← links)
- 05000272/LER-1986-018-01, :on 860806,Limitorque Motor Valve Operators W/O Environ Qualified Wires Discovered.Caused by Insufficient Control of Wiring During Operator Assembly. Wiring Replaced.Stored Wires Will Be Inspected (← links)
- 05000339/LER-1987-001-02, :on 870203,load Limit Setting on Emergency Diesel Generator 2H Determined to Be Incorrect.On 870206, Emergency Diesel Generator 2J Load Setting Also Incorrect. Caused by Failure to Follow Procedure (← links)
- 05000413/LER-2020-002, Re Unacceptable Indication Identified During Reactor Pressure Vessel Head Nozzle Penetration Inspection (← links)
- 05000219/LER-1987-008, :on 870202,reactor Recirculation Flow Converter Scram Setpoint Found to Be Above Limiting Safety Sys Setpoint Listed in Tech Specs.Caused by Instrument Drift. Flow Converter Scram Setpoint Adjusted (← links)
- 05000266/LER-1997-020-01, Forwards LER 97-020-01,describing Plant Conditions in Which Ability to Achieve & Maintain Safe Shutdown in Event of Postulated Fire May Have Been Adversely Affected (← links)
- 05000461/LER-1997-018, :on 970823,inadequate Preventive Maint Led to Possible Failure of Westinghouse Dhp Circuit Breakers to Open on Demand.Performed Corrective Maint Tasks on Dhp Circuit Breakers (← links)
- 05000219/LER-1986-020, :on 860811,during Insp of Discs in Control Rod Hydraulic Control Unit (HCU) Manual Inlet & Outlet Isolation Valves,Valve V-102 for HCU 18-15 Found W/One Ear Broken from Wedge on Disc.Disc Replaced (← links)
- 05000443/LER-2020-001, Manual Reactor Trips Due to Control Rod Bank Unexpectedly Inserting (← links)
- 05000369/LER-1987-005-02, :on 870224,battery Charger Room Fire Walls Declared Inoperable Due to Walls Not Meeting NRC Commitment Re Boundary Specs.Caused by Improper Const of Walls.Const & QA Requirements Established (← links)
- 05000338/LER-1997-008, :on 971027,both EDGs Inoperable During Testing. Caused by TS Surveillance Requirement to Demonstrate Operability of Remaining EDG When One Inoperable.Required TS Actions Cleared Following 1J EDG Testing (← links)
- 05000391/LER-2020-001, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open (← links)
- 05000390/LER-2020-002, Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 1B-B Shutdown Board (← links)
- 05000321/LER-1988-015-02, :on 881026,informed That Automatic Depressurization Sys Design Was Such That Single Failure (Battery) Could Cause Sys to Be Unable to Perform Safety Function.Caused by Inadequate Design Review (← links)
- 05000413/LER-2020-002-01, Unacceptable Indication Identified During Reactor Pressure Vessel Head Nozzle Penetration Inspection (← links)
- 05000220/LER-2020-001, Control Room Air Treatment System Inoperable (← links)
- 05000296/LER-2020-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000482/LER-2020-001-01, Plant Shutdown Due to Inoperable Containment Purge Isolation Valves (← links)
- 05000316/LER-2020-002, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Leakage (← links)
- 05000272/LER-2020-002, Unit 2 RHR Availability for Emergency Core Cooling in Mode 4 (← links)
- 05000400/LER-2020-001-01, Automatic Reactor Trip During Turbine Control System Digital Electro-Hydraulic System Maintenance (← links)
- 05000250/LER-2020-001, Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrument Channel Functional Units (← links)
- 05000346/LER-2020-002, Manual Reactor Trip on Trip of Reactor Coolant Pumps Due to Loss of 13.8 Kv Bus Potential Transformer Fuse (← links)
- 05000483/LER-2020-002, Reactor Trip and AFW Actuation Following Spurious MFRV Closure (← links)