Pages that link to "05000388/LER-2017-001"
Jump to navigation
Jump to search
The following pages link to 05000388/LER-2017-001:
Displayed 50 items.
- 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material (← links)
- 05000388/LER-2014-001 (← links)
- 05000388/LER-2015-001 (← links)
- 05000388/LER-2015-002 (← links)
- 05000388/LER-2015-006 (← links)
- 05000388/LER-2016-006 (← links)
- 05000388/LER-2016-004 (← links)
- 05000388/LER-2016-003 (← links)
- 05000388/LER-2016-002 (← links)
- 05000388/LER-2016-001 (← links)
- 05000388/LER-2001-005 (← links)
- 05000388/LER-2001-004 (← links)
- 05000388/LER-2001-003 (← links)
- 05000388/LER-2001-002 (← links)
- 05000388/LER-2001-001 (← links)
- 05000388/LER-2017-009 (← links)
- 05000388/LER-2017-007 (← links)
- 05000388/LER-2017-006 (← links)
- 05000388/LER-2017-005 (← links)
- 05000388/LER-2017-004 (← links)
- 05000388/LER-2017-003 (← links)
- 05000388/LER-1984-013, Attachments to LER 84-013-00 (← links)
- 05000388/LER-2023-001, Secondary Containment Bypass Leakage Limit Exceeded Due Inadequate Procedure Guidance Resulting in Failure of the Inboard Containment Isolation Valve to Close and Pressurize (← links)
- 05000388/LER-2022-001, Re Inadequate Performance of Loss of Safety Determination Resulting in Both Divisions of Core Spray Being Inoperable (← links)
- 05000388/LER-2021-004-01, From Susquehanna Steam Electric Station, Unit 2 Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications Due to Inadequate Valve Modification (← links)
- 05000388/LER-2021-005-01, Condition Prohibited by Technical Specification Due to Setpoint Drift Attributed to Age Related Degradation (← links)
- 05000388/LER-2021-003-01, Automatic Reactor Scram Due to Main Turbine Trip Caused by Inadvertent Trip of the Main Generator Output Breakers (← links)
- 05000388/LER-2021-001-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch (← links)
- 05000388/LER-2021-005, Condition Prohibited by Technical Specification Due to Setpoint Drift (← links)
- 05000388/LER-2021-002-01, Loss of Secondary Containment Due to Failed Differential Pressure Transmitter (← links)
- 05000388/LER-2021-002, Re Loss of Secondary Containment (← links)
- 05000388/LER-2021-001, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch (← links)
- 05000388/LER-2020-002-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch Caused by Lack of Requirements for Acclimation of the Instrument to the Operating Environment (← links)
- 05000388/LER-2020-001-01, Manual Scram Due to Rising Main Condenser Backpressure Caused by Failure of an Offgas Recombiner Inlet Valve (← links)
- 05000388/LER-1986-034, :on 860927-30,sampling of RHR Svc Water Not Completed.Caused by Communication Problems During Period When RHR Svc Water Monitors Out of Svc.Administrative Controls Will Be Implemented (← links)
- 05000388/LER-1986-013-01, :on 860919,full Reactor Protection Sys Scram Occurred When Intermediate Range Monitors C & G Spiked Upscale.Caused by Noise Due to Faulty Primary Containment Penetration Connectors.Cables Rebuilt (← links)
- 05000388/LER-1986-017-01, :on 861101,unplanned ESF Actuation Occurred & RWCU Sys Isolated in High Sys Flow.Caused by Instantaneous Flow Spike Induced by Cracking Open Bypass Valve.Design Changes Initiated.Sys Returned to Svc (← links)
- 05000388/LER-1986-011-01, :on 860717,limiting Condition for Operation Not Entered When Primary Containment Isolation Valve Inoperable. Caused by Smoking Electrical Components from Transversing in-core Probe Machine C (← links)
- 05000388/LER-1986-016-01, :on 861024,DX Unit Valve a Discovered Mispositioned.Caused by Procedure Incorrectly Stating That Valve a Be Placed at Zero Position.Procedure Revised to Reflect Correct Repositioning (← links)
- 05000388/LER-1986-015-01, :on 861012,valve F008 Isolated Twice,Due to Spurious High Flow Signal & Water Hammer,Respectively. Water Hammer Caused by Partial Draindown of Sys.Personnel Will Review Event (← links)
- 05000388/LER-1986-019-01, :on 861218,22 & 25,facility Entered Limiting Condition for Operation 3.0.3 Three Times to Sample Wetwell. Caused by Off Normal Valve Lineup of Containment Radiation Monitoring Sys.Operating Strategy Reviewed (← links)
- 05000388/LER-1986-009-01, :on 860708,Limiting Condition for Operation 3.0.3 Entered Twice.Caused by Surveillance Procedure SI-280-305 Being Performed While RCIC Sys Inoperable.W/ (← links)
- 05000388/LER-1985-018, :on 850529,circuit Breaker 8B in Reactor Protection Sys Distribution Panel 2Y201B Tripped.Caused by Loose Load Side Connection Leading to Overheating of Terminal Lug.Breaker Replaced (← links)
- 05000388/LER-1987-001, :on 870110,Limiting Condition for Operation 3.6.3.a Entered When Reactor Bldg Chilled Water Sys Inboard Isolation Valve Failed.Possibly Caused by Valve Failing to Stroke.Solenoid Valve Replaced (← links)
- 05000388/LER-1986-014, :on 860927-30,sampling of RHR Svc Water Effluent Not Completed as Required by Tech Specs.Caused by Communication Problems.Administrative Controls Implemented to Correct Communication Deficiencies (← links)
- 05000388/LER-1987-002-01, :on 870214,HPCI Sys Isolated.Caused by Cognitive Error Made by Technician.Test Signal Removed & Containment Isolation Valve Reopened.Mod Will Install States Links (← links)
- 05000388/LER-1986-018-01, :on 861219,125-volt Dc Battery Charger 1D613 Inoperable.Unit 1 Supervisor Failed to Inform Unit 2 Supervisor of Equipment Failure,Resulting in Violation of Tech Spec.Battery Replaced (← links)
- 05000388/LER-1986-015, :on 861012,primary Containment Isolation Valve Closed Twice Due to Spurious High Flow Signal.Caused by Waterhammer Due to Opening of Valve F008.Operations Personnel Will Review Event (← links)
- 05000388/LER-1986-003, :on 860124,Tech Spec Motherhood Clause Entered Due to Malfunctioning Which Provides ECCS Initiation Signals.Caused by Broken Adjustment Locking Screw Replaced (← links)
- 05000388/LER-1986-001-01, :on 860121,during Startup,Reactor Scrammed When Vessel Water Level Dropped to Plus 13 Inches.Caused by Operator Failing to Notice Turbine Bypass Valves Opened. Procedures Revised.Alarms Will Be Installed (← links)