Pages that link to "10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat"
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The following pages link to 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat:
Displayed 50 items.
- 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release (← links)
- 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor (← links)
- 10 CFR 20.2201(a)(1)(i) (← links)
- 10 CFR 73.71(b)(1), Safeguards Event (← links)
- 10 CFR 35.3045(a)(3) (← links)
- 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation (← links)
- 10 CFR 35.3045(a)(1) (← links)
- 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat (← links)
- 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident (← links)
- 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition (← links)
- 10 CFR 50.72(a)(1)(i), Emergency Class Declaration (← links)
- 10 CFR 50.72(b)(3)(iv)(A), System Actuation (← links)
- 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown (← links)
- 10 CFR 30.50(b)(2) (← links)
- 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness (← links)
- 10 CFR 20.2201(a)(1)(ii) (← links)
- 10 CFR 50.73(a)(1), Submit an LER (← links)
- 10 CFR 20.2202(b)(1) (← links)
- 10 CFR 40.35(f) (← links)
- 10 CFR 50.72(b)(3)(xii), Transport of a Contaminated Person Offsite (← links)
- 10 CFR 30.50(b)(1) (← links)
- 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge (← links)
- 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded (← links)
- 10 CFR 20.1906(d)(2) (← links)
- 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material (← links)
- 10 CFR 76.120(c)(2) (← links)
- 10 CFR 40.60(b)(2) (← links)
- 10 CFR 40.60(b)(3) (← links)
- 10 CFR 26.719, FFD Reporting requirements (← links)
- 10 CFR 21.21(d)(3)(i), Failure to Comply or Defect (← links)
- Agreement State (← links)
- NUREG-1022, Event Reporting Guidelines for 10 CFR 50.72 and 10 CFR 50.73 (← links)
- 05000263/LER-2015-001, Operations With A Potential To Drain The Reactor Vessel (OPDRV) Without Secondary Containment Operable (← links)
- 10 CFR 50.73(a)(2)(iv)(A), System Actuation (← links)
- 05000266/LER-2015-001, Inadequately Sealed Pipe Penetrations Result in Unanalyzed Condition for Internal Flooding (← links)
- 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition (← links)
- 10 CFR 50.72(b)(3)(v), Loss of Safety Function (← links)
- 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor (← links)
- 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material (← links)
- 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident (← links)
- 10 CFR 50.73(a)(2)(v)(B) (redirect page) (← links)
- 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat (← links)
- 05000266/LER-2015-001, Inadequately Sealed Pipe Penetrations Result in Unanalyzed Condition for Internal Flooding (← links)
- Loss of Safety Function (← links)
- 05000296/LER-2015-001, High Pressure Coolant Injection and Reactor Core Isolation Cooling Inoperable Due To No Suction Source Aligned (← links)
- 05000499/LER-2015-001, Technical Specification Action Statement Time Exceeded Due to Turbine-Driven Auxiliary Feedwater Pump Test Failure Not Recognized (← links)
- 05000482/LER-2015-001, Personnel Error Causes Two Inoperable Residual Heat Removal Trains (← links)
- 05000382/LER-2014-003 (← links)
- 05000483/LER-2001-002 (← links)
- 05000263/LER-2001-005 (← links)
- 05000390/LER-2017-009 (← links)
- 05000254/LER-1997-011, Forwards LER 97-011-00 Re an Event or Condition That Alone Could Have Prevented Fulfillment of Safety Function of Structures or Sys That Are Needed to Remove Residual Heat. Commitments Made by Ltr,Submitted (← links)
- 05000254/LER-1997-003, Forwards LER 97-003-00 IAW 10CFR50.73(a)(2)(v)(B)(D). Procedure Qcap 0307-02, ASME Section XI Repair & Replacement Program Preparation, Attachment a, Section XI Repair/Replacement Program Will Be Revised Re VT-2 (← links)
- 05000265/LER-1998-006, Forwards LER 98-006-00,IAW 10CFR50.73(a)(2)(v)(B). Commitments Made by Util Are Listed (← links)
- 05000304/LER-1997-007, Forwards LER 97-007-00 Per 10CFR50.73(a)(2)(v)(B) Which Requires Written Rept for Any Event or Condition That Could Prevent Fulfillment of Safety Function of Structures or Sys Needed to Remove Residual Heat.W/Commitments Attach (← links)
- 05000304/LER-1997-002, Forwards LER 97-002-00,per 10CFR50.73(a)(2)(v)(B),which Requires 30 Day Written Rept.Commitments Associated W/Correspondence,Encl (← links)
- 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure (← links)
- 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications (← links)
- 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function (← links)
- 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal (← links)
- 05000341/LER-2024-001, Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-22 (← links)
- 05000412/LER-2023-003-01, Missile Barrier Door Left Open Resulting in a Loss of Safety Function (← links)
- 05000443/LER-2023-005, Auxiliary Feedwater System Inoperable (← links)
- 05000458/LER-2023-001-01, Ultimate Heat Sink Inoperable Due to Boundary Valve Leakage (← links)
- 05000412/LER-2023-003, Missile Barrier Door Left Open Resulting in a Loss of Safety Function (← links)
- 05000443/LER-2023-001, Automatic Actuation of B Emergency Diesel Generator Emergency Power Sequencer (← links)
- 05000374/LER-2021-002-02, Supplement to Reactor Protection System Half Scram Due to Motor Generator Set Output Breaker Trip (← links)
- 05000458/LER-2023-001, Ultimate Heat Sink Inoperable Due to Boundary Valve Leakage (← links)
- 05000382/LER-2022-001-01, On Non-Compliance with Technical Specifications Due to Incorrect Procedural Guidance for Radiation Monitors (← links)
- 05000373/LER-2022-004, Both Trains of Main Control Room and Auxiliary Electric Room HVAC Declared Inoperable Due to Compressor Trips (← links)
- 05000483/LER-2022-003, Submittal of Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications (← links)
- 05000410/LER-2022-002, Reactor Protection System Actuation While Shutdown (← links)
- 05000382/LER-2022-006, Non-Compliance with Technical Specifications Due to Incorrect Conversion Factors in Plant Stack and Fuel Handling Building Radiation Monitors (← links)
- 05000237/LER-2022-002-01, Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation (← links)
- 05000335/LER-2022-002, Condition Prohibited by Technical Specifications (← links)
- 05000237/LER-2022-002, Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation (← links)
- 05000416/LER-2022-001, For Grand Gulf Nuclear Station, Unit 1, Manual Reactor Trip Due to the Loss of Balance of Plant Transformer 23 (← links)
- 05000254/LER-2022-002, Low Pressure Coolant Injection Manually Isolated Due to Valve Test Equipment Issue (← links)
- 05000287/LER-2022-002, Automatic Actuation of Emergency Feedwater System Due to Malfunctioning Startup Feedwater Control Valve (← links)
- 05000410/LER-2022-001, Regarding Automatic Reactor Scram Due to Low Reactor Water Level During Maintenance (← links)
- 05000374/LER-2022-002, Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation (← links)
- 05000270/LER-2022-003, Manual Reactor Trip Due to Main Feedwater Control Valve Positioner Malfunction (← links)
- 05000270/LER-2022-001, Regarding Automatic Reactor Trip Due to Loss of Power to Reactor Coolant Pumps (← links)
- 05000287/LER-2022-001, Response Actions Resulted in Brief Inoperability of Both Onsite and Offsite Emergency AC Power Paths (← links)
- 05000387/LER-2021-004-01, Loss of 1B RHRSW Pump Due to Cable Damage During Excavation Activities (← links)
- 05000389/LER-2022-001, Reactor Shutdown Required by Technical Specifications Due to a Misaligned Control Element Assembly (← links)
- 05000270/LER-2021-005, Automatic Reactor Trip Due to Spurious Trip Signal Concurrent with System Testing (← links)
- 05000270/LER-2021-004, More than One Axial Power Shaping Rod Not Aligned within Technical Specification Limits (← links)
- 05000270/LER-2021-003, Conditions Prohibited by Technical Specifications Due to Ssf and Psw Inoperability (← links)
- 05000335/LER-2021-001, Manual Reactor Trip Due to Insufficient Feed Flow to Steam Generators (← links)
- 05000270/LER-2021-002, Actuation of the Keowee Hydroelectric Station Due to Loss of AC Power to the Unit 2 Main Feeder Buses (← links)
- 05000387/LER-2021-004, Loss of 1B RHRSW Pump Due to Cable Damage During Excavation Activities (← links)
- 05000220/LER-2021-002, Isolation of Both Emergency Condensers Due to Loss of UPS 162A (← links)
- 05000389/LER-2021-002, Foreign Material Exclusion Device Found in Containment Spray System (← links)
- 05000266/LER-2021-001, Main Feedwater Pump Trip Results in Manual Reactor Trip (← links)
- 05000416/LER-2020-005-02, Primarv Water Svstem Flow Lowered Causinc Turbine Trio and Subseauent Reactor 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)
- 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)
- 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)
- 05000213/LER-1989-014, :on 890904,svc Water Pumps a & B Flow Determined Less than Design Basis for Modes 1,2,3 & 4 During Inservice Insp Test.Caused by Failure to Predict Pump Performance.Performance Restored (← links)
- 05000254/LER-1989-001-03, :on 890106,RCIC Pump Discharge Inboard Isolation Valve Failed to Open from Full Closed Position. Caused by Binding of Torque Switch on Valve Operator.Switch Replaced.Reportability Per Part 21 Possible (← links)
- 05000312/LER-1989-002, :on 890228,DHR Sys Dropline Isolation Valve Closed Automatically on High RCS Pressure Signal,Resulting in Temporary Loss of DHR Capability.Caused by Pressure Transmitter Out of Calibr.Loop Recalibr (← links)
- 05000382/LER-1998-008, :on 980414,potential Concurrent Degraded Ecw Sys Trains a & B Was Noted.Cause Was Indeterminate. Affected Circuits Have Been Corrected (within Design Parameters) to Address Condition (← links)
- 05000338/LER-1989-010-01, :on 890416,normal Power Supply to 4,160-volt Emergency Buses 1H & 2J Lost When Lifted Wire Inadvertently Grounded During Removal for Switchyard Mods.Caused by Personnel Error.Rhr Pump B Restored (← links)
- 05000254/LER-1989-005-08, 5:on 890522,RCIC Declared Inoperable Due to Differential Pressure Indicating Switch Failure to Calibr Properly.Caused by Worn Trip Setpoint Locking Mechanism. Switch Replaced & New Switch Calibr (← links)
- 05000213/LER-1987-015, :on 870814,temporary Loss of Power to Spent Fuel Pit Cooling Sys & Bldg Crane Occurred.Caused by Personnel Error.Corrective Measures Include Better Training & Increased Supervisory Involvement (← links)
- 05000312/LER-1987-045, :on 871105,surveillance Procedure for Weekly Battery Testing Not Performed by Tech Spec Required Date. Caused by Personnel Error.Manual Tracking Schedule for Surveillance Procedures Instituted (← links)
- 05000346/LER-1998-005, :on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations (← links)
- 05000333/LER-1999-008-01, :on 990910,HPCI Sys Was Declared Inoperable Due to Apparent Failure of Master Trip Unit (MTU) within HPCI Sys Automatice Isolation Logic.Subject MTU Was Replaced & HPCI Sys Was Returned to Operable Status.With (← links)
- 05000254/LER-1986-034-02, On 861117,discovered Severe Packing Leak on HPCI Sys Steam Supply Valve.Caused by Normal Wear on Packing Ring.Old Packing Removed & Replaced w/17 Rings of New Packing (← links)
- 05000269/LER-1986-010-04, :on 860828,potential for Lack of Pump Runout Protection During Certain Design Basis Transients Found. Caused by Failure to Analyze Emergency Feedwater Sys for All Design Basis Transients (← links)
- 05000413/LER-2020-002, Re Unacceptable Indication Identified During Reactor Pressure Vessel Head Nozzle Penetration Inspection (← links)
- 05000456/LER-1987-011, :on 870121,while Preparing to Drain Component Cooling Water Shellside of Hx,Rhr Lost Svc.Caused by Leaking Component Cooling Inlet Isolation Valve.Leaking Valve Repaired & Surge Tank Refilled (← links)
- 05000382/LER-1999-010-01, :on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity (← links)
- 05000266/LER-1997-035, :on 970516,discovered Inadequate Seismic Support for Reactor Coolant Pump Rotor Stand.Caused by Rotor Stand Being Stored Since Initial Plant Construction.Moved Rotor Stand & Verified as Seismically Adequate (← links)
- 05000443/LER-2020-001, Manual Reactor Trips Due to Control Rod Bank Unexpectedly Inserting (← links)
- 05000324/LER-1999-001-02, :on 990317,RCIC Sys Declared Inoperable.Caused by Inadequate Packing Compression on live-load Packing.Valve 2-E51-F008 Repacked & Tested in Accordance with Plant Procedures.With (← links)
- 05000304/LER-1997-007-06, :on 971030,failure to Maintain Required Number of Svc Water Pumps Operable Was Identified.Caused by Failure of Mgt Personnel to Adhere to Requirements for Reviewers to Use Applicable Drawings.Procedure Rev to Provide Guidanc (← links)
- 05000333/LER-1997-013-01, :on 971216,high Pressure Coolant Sys Was Declared Inoperable.Caused by Instrument Malfunction During Surveillance Testing.Completed Repair Activities to Correct Adjustments to Master Trip Unit (← links)
- 05000213/LER-1988-013, :on 880502,vol Control Tank Isolation Valve Failed to Close During Surveillance Testing.Caused by Binding of Mechanical Interlock within Reversing Starter Assembly.Starter Replaced W/New Model (← 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)
- 05000213/LER-1997-010, :on 970410,SFP Cooling Pump Net Positive Suction Head Was Declared Inadequate.Caused by Deficiency in Original (Pre 1975) Design Basis.Confirmed That Existing Design Is Adequate (← 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)
- 05000336/LER-1996-018, :on 960316,gaps Discovered in Encls Door Seals for Motor Control Ctrs B51 & B61.Caused by Weakness in Existing Program to Inspect & Verify Integrity of Environ Protective Barriers.Doors for MCC B51 & MCC B61 Replaced (← links)
- 05000265/LER-2020-002, Electromatic Relief Valve 3D Did Not Actuate Due to Out of Specification Plunger (← links)
- 05000423/LER-2020-002, 3, Automatic Reactor Trip Due to Main Generator Ground Fault (← links)
- 05000254/LER-1987-032-03, :on 871223,discovered That RCIC Pump Would Not Inject Water Into Reactor Vessel.Caused by RCIC Pump Discharge Check Valve Failing to Open.Check Valve Disassembled,Repaired,Reassembled & Tested (← links)
- 05000265/LER-1988-003-04, :on 880301,RCIC Declared Inoperable.Caused by Failed Remote Hydraulic Servo on Turbine Govenor Valve.Servo Replaced & RCIC Successfully Tested (← links)
- 05000272/LER-2020-001, Station, Unit 1, Manual Reactor Trip and Auxiliary Feed Water System Actuation (← links)
- 05000498/LER-2020-001, Automatic Actuation of Emergency Diesel Generators Due to Lockout of Switchyard Electrical Bus (← links)
- 05000400/LER-2020-001, Automatic Reactor Trip During Turbine Control System Digital Electro-Hydraulic System Maintenance (← links)
- 05000325/LER-2020-001, Manual Reactor Scram During Startup Due to All Bypass Valves Fully Opening (← links)
- 05000323/LER-1986-002, :on 860117,RHR Valve 8702 Closed & RHR Pump 2-1 Secured in Response to Ensuing loss-of-flow Alarm.Caused by Unlicensed Operator Error.Valve Reopened.Pump Restarted, Observed for Seal Damage & Declared Operable (← links)
- 05000265/LER-2020-001, Loss of Both Divisions of Residual Heat Removal Low Pressure Coolant Injection Due to Swing Bus Failure to Transfer (← links)
- 05000325/LER-2020-002, Technical Specification Required Shutdown Due to Unidentified Leakage (← links)
- 05000213/LER-1996-026, :on 961009,found Weld Flaws in Svc Water Piping for Spent Fuel Cooling.Caused by Microbiologically Influenced Corrosion (Mic).Will Revise MIC Program to Treat Safety Related Portion of Service Water Sys (← links)
- 05000219/LER-1985-023, :on 851211 Re Emergency Svc Water Sys Seismic Concerns.Caused by Original Design Error.Procedures Used to Determine Pump Operability Revised to Change Min Acceptable Flow Rate & Engineering Evaluation Performed (← links)
- 05000373/LER-1996-018-02, :on 961104,determined That RHR Pump Seal Coolers Do Not Meet Design Pressure Requirements.Caused by Inadequate Design Info from Vendor.Replaced Casings (Shell Side) W/Casings W/Design Pressure of 15 Psig (← links)
- 05000423/LER-1996-040-01, :on 961024,potential Component Cooling Sys Overcooling Noted Due to Loss of Instrument Air Sys Concurrent W/Low Svc Water Inlet Temp.Ccp Heat Exchanger Outlet Temp Control Valve Will Be Modified (← links)
- 05000213/LER-1996-029, :on 961024,primary Auxiliary Bldg Flood Protection Design Deficiencies Were Noted Due to Inadequate Design Review.Flood Watch Responsible for Notifying CR Will Be Established (← links)
- 05000423/LER-1996-007-02, Forwards LER 96-007-02 Which Supplements Rept Submitted on 960502,per 10CFR50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D), 10CFR50.73(a)(2)(vii)(B&D).Commitments in Response to Event, Encl (← links)
- 05000346/LER-2020-001, Three Main Steam Safety Valves Failed Inservice Test Program As-Found Lift Acceptance Criteria (← links)
- 05000410/LER-2020-001, Manual Scram Due to an Electro Hydraulic Control Fluid Leak on the Turbine Control System (← links)
- 05000410/LER-2020-002, Failure to Meet Technical Specification MSIV Stroke Times (← links)
- 05000338/LER-1996-008, :on 960926,identified Component Cooling Water Surge Tank Not Seismically Qualified When Tank Level Full. Caused by Personnel Error.Issued Justification for Continued Operation & Completed Design Mods (← links)
- 05000382/LER-2020-001, (Waterford 3), Violation of Technical Specification 3.3.3.7.3.a (Broad Range Gas Detection) Due to Operators and Maintenance Technicians Not Performing Procedure Step as Intended (← links)
- 05000254/LER-1992-026-02, :on 921027,discovered That RCIC Flow Transmitter Out of Calibr,Resulting in Pump Flow Below TS Requirements.Caused by Setpoint Drift.Calibr of Flow Transmitter Verified (← links)
- 05000333/LER-1992-013, :on 920226,determined That Actual Design & Design Described in FSAR Differ for Air Conditioning Sys for Environ Encls.Caused by Incomplete Understanding of Design & Operation of Equipment.Load Ctrs Qualified (← links)
- 05000296/LER-2020-001, Automatic Actuation of Emergency Diesel Generators Due to an Offsite Lightning Strike (← links)
- 05000338/LER-2020-001-01, For North Anna Power Station, Unit 1, Degraded Upper Cylinder Piston Pin Bushing Discovered During Maintenance Activities on Emergency Diesel Generator (← links)
- 05000530/LER-2020-001, Condition Prohibited by Technical Specifications Due to Inoperable Spray Pond Pump (← links)
- 05000327/LER-2019-003-01, 1 for Sequoyah Nuclear Plant, Unit 1, Automatic Reactor Trio Due to Negative Rate Trip as a Result of a Dropped Control Rod (← links)
- 05000336/LER-1996-027-01, :on 960426,turbine Bldg Crane Not Included in NUREG-0612 Evaluation for Heavy Loads.Turbine Bldg Crane Procedures Revised (← links)
- 05000423/LER-1996-007-01, :on 960403,CRS & Qs Sys Found Outside Design Basis Due to Design Errors.Restored Sys to Appropriate Design Basis Requirements Prior to Declaring Sys Inoperable (← links)
- 05000423/LER-1996-017-02, :on 960621,determined Design Deficiency Existed in Tornado Protection Ventilation Dampers,Could Have Affected EDGs Following Tornado.Caused by Inadequate Original Plant Const Design.Procedure Revised (← links)
- 05000254/LER-1992-023-01, :on 920920,determined That Heat Transfer Capability of 1B & 2B HX Did Not Meet Design Requirements. Caused by Fouling & Silt Accumulation on Rhrsw.Routine Two Pump Flushing Will Be Performed (← links)
- 05000341/LER-2020-001, Secondary Containment Inoperable Due to Both Airlock Doors Open (← links)
- 05000389/LER-2020-001, Turbine Loss of Load Trip Found Outside Technical Specification Allowable Range Due to Unspecified Legacy M&TE or Calibration Deficiencies (← links)
- 05000272/LER-1985-001-01, :on 850205,discovered Low Suction Pressure Trip Circuits for Auxiliary Feedwater Pumps Did Not Meet Single Failure Criteria.Caused by Design Error.Safety Evaluation Done.Circuits to Be Redesigned (← links)
- 05000346/LER-1984-019, :on 841108,blank Flange Found on Outlet of Component Cooling Water Surge Tank Relief Valve CC3602.On 841130,util Determined Tank Not Protected Against Overpressurization W/Blank Flange (← links)
- 05000483/LER-2020-001, Emergency Exhaust Train Inoperable Due to Fan Belt Degradation and Failure (← links)
- 05000390/LER-2020-001, Manual Reactor Trip Due to Lowering Steam Generator Level Caused by a Hand Station Failure (← links)
- 05000269/LER-1996-003, :on 960214,RC Makeup Sys Technically Inoperable for App R Scenario Due to Design Analysis,Sys Functional Design Deficiency.Compensatory Actions Taken to Limit Leakage & DBD Will Be Revised (← links)
- 05000331/LER-1992-010, :on 920617,RW Pump Circuit Failure Caused Fire to Break Out in 1B20 Load Center.Caused by Inadequate Review of Breaker Disconnect Compatability W/Load Ctr Cubicle Stabs in Design.Procedural Revisions Re Design Made (← links)
- 05000333/LER-1992-031, :on 920605,false High Area Temp Signal Caused Automatic HPCI Isolation Logic Signal.Caused by Bowing of Supports Bars.Support Bars Straightened & Printed Circuit Card Fully Inserted (← links)
- 05000336/LER-1996-006-01, :on 960207,service Water Pump Motor Flood Protection Not Provided.Caused by Inadequate Administrative Controls.Administrative Controls Established (← links)
- 05000354/LER-1995-016, :on 950708-09,SDC Bypass Event Occurred, Rendering SDC Mode of RHR Sys Inoperable Due to Procedural non-compliance & Inadequate Operator Knowledge,Skills & Training.Special Training on Event Conducted (← links)
- 05000336/LER-1995-003-02, :on 960205,failed to Enter TS LCO 3.0.3 After Discovering Svc Water Strainers Inoperable.Caused by Failure to Recognize Ice Plug Formation in Strainer Backwash Line. Implement Comprehensive Operability Process (← links)
- 05000254/LER-1991-039-01, :on 910424,RCIC 1301-49 Pump Discharge Valve Failed to Open.Cause Is Unknown.Valve Disk Manually Cracked Off Seat & Valve Stroked Afterwards (← links)
- 05000382/LER-2019-005-01, Automatic Reactor Scram Due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback Due to Failed Diode Modules with the Main Exciter (← links)
- 05000336/LER-1996-002, :on 960108,determined That Ice Plug in Common Line Resulted in Inability to Backwash Svc Water Strainers. Caused by Mod to Backwash Line Piping.Ice Plug Removed, Restoring Ability to Backwash (← links)
- 05000285/LER-1992-015, :on 920412,480-volt Bus Feeder Breaker Tripped, Resulting in Loss of Power to Shutdown Cooling Flow Control Valve Controller.Caused by Failure to Have Policy to Address Event.Policy Developed (← links)
- 05000333/LER-1992-015, :on 920317,reanalysis of 10CFR50 App R Analyses Revealed Seven Deficiencies W/Potential to Effect Safe Shutdown Capability During Postulated Fires.Caused by Lack of Mgt Commitments.Deficiences Corrected (← links)
- 05000272/LER-1984-013-01, :on 840602,power Interrupted Between 500 Kv Yard & 13 Kv Bus,Resulting in Loss of Onsite Power to 4 Kv Group & Vital Busses.Caused by Operator Error.Individual Counseled & Reprimanded for Actions (← links)
- 05000482/LER-2020-001, Shutdown Due to Inoperable Containment Purge Isolation Valves (← links)
- 05000338/LER-1992-003, :on 920121,determined That RHR Sys Suction Relief Valve Discharge Piping Arrangement May Not Pass Design Flowrate.Caused by Design Deficiency.Ts Change Package Developed to Raise RHR Temp (← links)
- 05000333/LER-1992-002, :on 920107,15,17,18,22 & 24,calculations Indicated That Valve Operator Design for motor-operated Valves Would Not Provide Adequate Valve Stem Thrust,Per Generic Ltr 89-10.Operator Declared Inoperable (← links)
- 05000285/LER-1991-016, :on 910711,roll Pin for Diesel Generator Exhaust Damper Linkage Failed.On 910718,crack Discovered in Roll Pin for DG-1 Linkage.On 910802,util Notified That Crack Due to Mfg Defect.Also Reported Per Part 21 (← links)
- 05000373/LER-1995-007, :on 950216,noted That Quarterly TS Surveillances for Fourth Quarter 1994 Had Not Been Performed.Caused by Personnel Error.Surveillances Performed (← links)
- 05000333/LER-1993-021, :on 930722,motor for 10MOV-25A RHR a Side LPCI Inboard Isolation Valve Failed Due to Inadequate Brake Design Test.Mod M1-90-174 Completed on Motor Actuators for 10MOV-25A & B (← links)
- 05000285/LER-1994-008, :on 941108,potential for Raw Water Pump Room Flooding Heavy Load Drop Occurred.Caused by Lack of Depth in Evaluation/Review Associated W/Original Load Drop Analysis. Danger Tag Placed to Restrict Use of HE-5 (← links)
- 05000423/LER-2020-001, Technical Specification Allowed Outage Time Exceeded by Accident Monitoring Instrument (← links)
- 05000446/LER-2020-001, Manual Reactor Trip Due to Trip of Both Main Feedwater Pumps (← links)
- 05000354/LER-1994-001-02, :on 940305,ESF Sys Actuation,Isolation & Loss of Shutdowm Cooling Occurred.Caused by Personnel Error.Lead Technician Counseled on Event (← links)
- 05000382/LER-1993-005-01, :on 931007,discovered That Motor Pinion Gear Keys SDC Valves Not Staked Due to Inadequate Procedure.Two Motor Pinion Gear Keys Staked.Appropriate Procedures Will Be Revised (← links)
- 05000333/LER-1993-021-01, :on 930722,motor Operator Valve Failed.Caused by Design Deficiency in Selection of Motor Brake.Mod to Motor Thermal Overloads Implemented to Minimize Failure Potential (← links)
- 05000213/LER-1993-016, :on 930920,determined That Potential Existed to Divert Inventory from Dwst.Issue of Thoroughness in Engineering Analyses & Evaluations Will Be Addressed by Reviewing Event W/Engineering Personnel (← links)
- 05000423/LER-2019-001, Regarding Plant Shutdown Required by Technical Specifications, Emergency Diesel Generator Exceeded Allowed Outage Time (← links)
- 05000280/LER-2019-002, Items Non-Conforming to Design for Tornado Missile Protection (← links)
- 05000247/LER-2018-003-01, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap (← links)
- 05000341/LER-2019-006, Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Damper Malfunction (← links)
- 05000333/LER-1992-015-01, :on 920317,deficiencies W/Potential to Effect Safe Shutdown During Postulated Fires Identified Due to Lack of Commitment to Fire Protection Implementation by Mgt.Plant Mods Scheduled (← links)
- 05000440/LER-1993-011, :on 930419,identified That Excessive Strainer Differential Pressure Across RHR Suction Strainers Could Have Compromised Long Term Cooling During LOCA Operation. Caused by Inadequate Program Requirements (← links)
- 05000298/LER-2019-003, Division 2 Service Water Discharge Blockage Resulting in Unplanned Service Water Inoperability (← links)
- 05000352/LER-1990-012, :on 900426,inoperability of RHR Sys Modes Occurred Due to Physical Separation Deficiencies.Caused by Drawing Deficiency Resulting in Installation Error During Original Const.Nonclass 1E Cable Sleeved (← links)
- 05000483/LER-2019-005-01, Violation of Technical Specification 3.7.10 Due to Control Room Emergency Ventilation System Train B Inoperability (← links)
- 05000328/LER-2019-002, Loss of Heater Drain Tank Flow Causes Turbine Runback and Manual Reactor Trip (← links)
- 05000461/LER-2019-004-01, Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications (← links)
- 05000245/LER-1994-015, :on 940410,during Surveillance Test,Inadvertent Decrease of RPV Water Level Occurred.Caused by Failure to Recognize Interactions.Corrective Action:Restored RPV Water Level & Isolated Leakage (← links)
- 05000281/LER-2019-002, Auxiliary Feedwater System Loss of Safety Function Due to Check Valve Failure to Close (← links)
- 05000395/LER-2019-004, 4-00 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Condition Prohibited by Technical Specification 3.6.1.1 (← links)
- 05000390/LER-2019-004, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open (← links)
- 05000354/LER-2019-002, Safety Relief Valve (SRV) As-found Set-point Failures (← links)
- 05000395/LER-2019-003, Completion of a Technical Specification Required Plant Shutdown (← links)
- 05000334/LER-2019-001, Low Head Safety Injection Discharge Relief Valve Did Not Reseat During Surveillance Test (← links)
- 05000334/LER-2019-002, Manual Reactor Trip at 15% Power Due to Lifting of the 1A Main Steam Safety Valve (← links)
- 05000458/LER-2019-004, For River Bend Station, Unit 1, Potential Loss of Safety Function for All ADS, (Automatic Depressurization System) Valves (← links)
- 05000278/LER-2019-001, Failure of Reactor Mode Switch Results in Condition Prohibited by Technical Specifications (← links)
- 05000499/LER-2019-002, 0 for South Texas Project Unit 2, Incorrect Sequencer Part Replacement Leads to Undervoltage Signal and Valid Actuation of Emergency Diesel Generator (← links)
- 05000260/LER-2019-001-01, Traversing In-core Probe Purge Header Check Valve Leak Rate in Excess of Technical Specifications Limits (← links)
- 05000400/LER-2019-003, Both Source Range Nuclear Instruments Inoperable (← links)
- 05000348/LER-2019-001, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift (← links)
- 05000260/LER-2019-003, Automatic Reactor Scram During Startup Due to Intermediate Range Monitor Noise (← links)
- 05000333/LER-1989-021, :on 891031,circuit Breaker for RCIC Inboard Injection Valve to Feedwater Sys Tripped During Required Valve Testing.Caused by Fault in Motor Winding Insulation. New Motor Installed (← links)
- 05000341/LER-2019-005, Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Damper Malfunction (← links)
- 05000265/LER-1988-003-03, :on 880301,while Performing RCIC Monthly Test, RCIC Pump Could Only Achieve 400 Gpm Against Discharge Pressure of 500 Psig.Caused by Failed Hydraulic Actuator on Turbine Governor Valve.Actuator Replaced (← links)
- 05000328/LER-2019-001, Component Cooling Water System Train a Inoperable Longer than Allowed by Technical Specifications (← links)
- 05000483/LER-2019-001-01, Unplanned Loss of Switchyard Bus B Results in System Actuation (← links)
- 05000346/LER-2019-003, Anticipatory Reactor Trip System Actuated During Turbine Stop Valve Testing Due to the Closure of a Main Turbine Stop Valve (← links)
- 05000259/LER-2019-001-01, High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation (← links)
- 05000499/LER-2019-001, Equipment Clearance Order Error Leads to Loss of Primary Containment Integrity (← links)
- 05000335/LER-2019-003, Inoperability of Emergency Diesel Generator Due to Cracked Crankshaft (← links)
- 05000416/LER-2019-004, Loss of High Pressure Core Spray Due to Instrument Inverter Failure (← links)
- 05000254/LER-2019-002, Phase to Ground Fault in Isolated Phase Bus Duct Led to Generator Trip and an Automatic Scram (← links)
- 05000346/LER-2019-002, Auxiliary Feedwater Trains Inoperable Due to Loss of Train Separation from Door Being Left Open (← links)
- 05000390/LER-2019-003, Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed (← links)
- 05000414/LER-2019-004, Condition Prohibited by Technical Specification and Loss of Safety Function Due to Refueling Water Storage Tank Volume Below the Minimum Requirement (← links)
- 05000395/LER-2019-002, Regarding Condition Prohibited by Technical Specification 3.6.4 (← links)
- 05000346/LER-2019-001, Emergency Ventilation System Train Inoperable Due to Non-specific Test Description of Damper Operation (← links)
- 05000446/LER-2018-001-01, For Comanche Peak Nuclear Power Plant, Unit 2, Automatic Reactor Trip Due to Turbine Trip (← links)
- 05000482/LER-2019-001, Re Valid Actuation of One of the Emergency Diesel Generators (← links)
- 05000220/LER-2019-004, Average Power Range Monitors Declared Inoperable (← links)
- 05000440/LER-2019-004, Loss of Feedwater Heating Results in Loss of Safety Function (← links)
- 05000354/LER-2019-001, Manual Scram and Manual Actuation of Reactor Core Isolation Cooling (← links)
- 05000498/LER-2019-002, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Inoperable Reactor Head Vent Throttle Valves (← links)
- 05000280/LER-2019-001, Failure to Align Angle Drive to Pump Results in Inoperable Emergency Service Water Pump (← links)
- 05000382/LER-2019-007, (Waterford 3), Plant Shutdown Required by Technical Specifications Due to Charging Pump Suction Line Flaw (← links)
- 05000353/LER-2019-002, Emergency Diesel Generator Lube Oil Pressure Sensing Line Leak Resulting in a Condition Prohibited by Technical Specifications (← links)
- 05000400/LER-2019-002, B Train Chiller for the Essential Services Chilled Water System Tripped on High Compressor Oil Temperature (← links)
- 05000400/LER-2019-001-01, Turbine Control System Auto-Stop Trip Solenoid Operated Valves Response Times Impacted (← links)
- 05000483/LER-2019-005, Inoperability of CREVS B Train (← links)
- 05000413/LER-2019-002-01, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Auxiliary Feedwater Sump Pump Conditions (← links)
- 05000259/LER-2019-001, High Pressure Coolant Injection System Declared Inoperable Due to Steam Supply Isolation (← links)
- 05000414/LER-2019-003, Component Cooling Water System Alignment Led to Both Trains of Component Cooling Water Inoperable (← links)
- 05000313/LER-2018-004-01, Reactor Trip Due to the Loss of a Non-Vital 4160 Volt Bus (← links)
- 05000382/LER-2019-006, (Waterford 3), Unplanned Loss of Both Trains of Broad Range Gas Monitors Results in a Condition That Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000416/LER-2019-001-01, Automatic Reactor Shutdown Due to Activation of Generator Lockout (← links)
- 05000391/LER-2019-002, Breach Due to Penetration Boot Seal Separation Results in Shield Building Inoperability (← links)
- 05000269/LER-2019-001, Standby Shutdown Facility Reactor Coolant Makeup Pump Oil Suction Tubing Failure (← links)
- 05000220/LER-2019-003-01, Manual Reactor Scram Due to Pressure and-Power Oscillations (← links)
- 05000353/LER-2019-001, Regarding Valid Actuation of the Reactor Protection System Due to a Trip of D214-24 Load Center (← links)
- 05000324/LER-2019-003, High Pressure Coolant Injection (HPCI) Inoperable (← links)
- 05000220/LER-2019-001-01, Automatic Reactor Scram Due to High Reactor Pressure (← links)
- 05000458/LER-2019-003, Manual Reactor Scram Initiated in Response to Loss of Feedwater Due to Abnormal Plant Configuration (← links)
- 05000255/LER-2018-003-01, Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations (← links)
- 05000341/LER-2019-003, Secondary Containment Declared Inoperable Due to Opening Both Airlock Doors (← links)
- 05000220/LER-2019-003, Manual Reactor Scram Due to Pressure and Power Oscillations (← links)
- 05000461/LER-2019-001, Main Feed Breaker Failed to Close During Bus Shift (← links)
- 05000220/LER-2019-002, Condition Prohibited by Technical Specification Due to Vacuum Breaker Not Locked Closed (← links)
- 05000260/LER-2019-002, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000440/LER-2019-002, Loss of Safety Function Due to Low Pressure Core Spray Inoperability (← links)
- 05000391/LER-2019-001, Regarding Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed (← links)
- 05000483/LER-2019-004, Security Force Positions Evacuated Due to Severe Weather Announcement (← links)
- 05000382/LER-2019-005, Automatic Reactor Scram Due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback Due to Failed Diode Modules within the the Main Exciter (← links)
- 05000483/LER-2019-003, Reactor Trip Due to Source Range Hi-Flux (← links)
- 05000483/LER-2019-002, Mode 4 Entry with Inoperable Auxiliary Building Pressure Boundary (← links)
- 05000237/LER-2019-002, Scram Due to Main Turbine Low Oil Pressure Trip (← links)
- 05000364/LER-2019-002, Manual Reactor Trip Due to Misaligned Rod During Low Power Physics Testing (← links)
- 05000373/LER-2019-002, Turbine Stop Valve Limit Switch Failure Due to Insufficient Lubrication (← links)
- 05000335/LER-2019-001, Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load (← links)
- 05000455/LER-2019-001, Manual Actuation of Auxiliary Feedwater Due to High Inboard Motor Bearing Temperature on Startup Feedwater Pump (← links)
- 05000220/LER-2019-001, Automatic Reactor Scram Due to High Reactor Pressure (← links)
- 05000400/LER-2019-001, Turbine Control System Auto-Stop Trip Solenoid Operated Valves Response Times Impacted (← links)
- 05000293/LER-2019-004, Manual Reactor Scram Due to Degrading Condenser Vacuum (← links)
- 05000413/LER-2019-002, Condition Prohibited by Technical Specifications Due to Auxiliary Feedwater Sump Pump Conditions (← links)
- 05000364/LER-2019-001, Inoperable Containment Isolation Valve Due to Design Control Error (← links)
- 05000483/LER-2019-001, Unplanned Loss of Switchyard Bus B Results in System Actuation (← links)
- 05000458/LER-2019-001, Initiation of Standby Service Water Due to Inadequate Monitoring of System Parameters During Maintenance Activities (← links)
- 05000498/LER-2019-001-01, Condition Prohibited by Technical Specifications Due to Inoperable Essential Cooling Water Pump (← links)
- 05000324/LER-2019-002, Manual Reactor Protection System Actuation and Specified System Actuation (← links)
- 05000425/LER-2019-001, Spurious Closure of Main Steam Isolation Valve Results in Manual Reactor Trip (← links)
- 05000339/LER-2019-001, Manual Reactor Trip on Degrading Condenser Vacuum Due to a Failed Weld (← links)
- 05000315/LER-2019-001, Two Main Steam Safety Valve Setpoints Found Outside Technical Specification Limits (← links)
- 05000324/LER-2019-001, Automatic Actuation of the Primary Containment Isolation System (← links)
- 05000498/LER-2019-001, Condition Prohibited by Technical Specifications Due to Inoperable Essential Cooling Water Pump (← links)
- 05000374/LER-2019-001, Safety Related Electrical Bus Undervoltage Results in Valid Actuation of the Common Emergency Diesel Generator (← links)
- 05000461/LER-2018-005-02, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux (← links)
- 05000265/LER-2018-001-01, Two Main Steam Isolation Valves (Msivs) Closure Times Exceeded (← links)
- 05000341/LER-2019-002, Secondary Containment Airlock Doors Opened at the Same Time Resulting in a Condition Prohibited by Technical Specifications (← links)
- 05000277/LER-2019-001, Regarding Emergency Bus Breaker Relay Failure Results in Loss of Safety Function (← links)
- 05000395/LER-2019-001, Condition Prohibited by Technical Specification 3.4.6.1 (← links)
- 05000311/LER-2019-001, Manual Reactor Trip Due to Circulating Water Intake Frazil Ice Blockage (← links)
- 05000237/LER-2019-001, Secondary Containment Differential Pressure Exceeded Technical Specification Due to Excess Ventilation Supply Flow (← links)
- 05000461/LER-2018-005-01, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux (← links)
- 05000293/LER-2019-002, Failure of Main Steam Isolation Valve Limit Switch Results in a Condition Prohibited by Technical Specifications (← links)
- 05000482/LER-2018-002, Modification Activities Affected Control Room Envelope Boundary Causing a Condition Prohibited by Technical Specifications (← links)
- 05000277/LER-2018-002-01, Emergency Diesel Generator Air Inlet Check Valve Failure Results in a Condition Prohibited by Technical Specifications (← links)
- 05000293/LER-2019-001, Reactor Core Isolation Cooling System Declared Inoperable During Surveillance Testing (← links)
- 05000341/LER-2019-001, Unplanned Loss of Safety Function of Gland Seal Exhauster Trip During Planned Maintenance Due to Inadequate Procedure (← links)
- 05000254/LER-2018-004-01, Reactor Scram Due to Turbine-Generator Load Reject (← links)
- 05000346/LER-2018-001, Borated Water Storage Tank Level Transmitter Out of Tolerance Due to Reaching End of Expected Life (← links)
- 05000313/LER-2018-004, Reactor Trip Due to the Loss of a Non-Vital 4160 Volt Bus (← links)
- 05000317/LER-2018-001-01, Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due to Damaged Internals (← links)
- 05000382/LER-2019-001, Past Inoperability of Effluent Accident Monitor Exceeds Allowed Outage Time Resulting in Condition Prohibited by Technical Specifications (← links)
- 05000259/LER-2018-007, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000461/LER-2018-003-01, Load Driver Card Failure Resulting in High Pressure Core Spray Inoperability (← links)
- 05000341/LER-2018-007, Reactor Building to Suppression Chamber Vacuum Breaker Condition Prohibited by Technical Specifications (← links)
- 05000397/LER-2018-001-01, Automatic Reactor Scram Due to Main Transformer Trip (← links)
- 05000446/LER-2018-002, Automatic Actuation of Auxiliary Feedwater System (← links)
- 05000483/LER-2018-006, Inoperability of SSCs Due to Improper Environmental Qualification Classification (← links)
- 05000336/LER-2018-001, Regarding Loss of Both Trains of Control Room Emergency Ventilation Resulting in the Loss of Safety Function (← links)
- 05000280/LER-2018-003, Regarding Auto-Start of Emergency Diesel Generators Due to Pilot Wire Lockout on C Reserve Station Service Transformer (← links)
- 05000373/LER-2019-001, Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation (← links)
- 05000259/LER-2018-004-01, Hiqh Pressure Coolant Injection Declared Inoperable Due to Steam Supply Valve Isolation (← links)
- 05000374/LER-2018-001-01, Manual Reactor Scram Due to Main Condenser Vacuum Degradation (← links)
- 05000278/LER-2018-002-01, Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown (← links)
- 05000458/LER-2018-010, Reactor Scram Due to Turbine Control Valve Failure (← links)
- 05000255/LER-2018-003, Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations (← links)
- 05000269/LER-2018-002, Loss. of Condenser Vacuum Results in a Main Turbine Trip and a Manual Reactor Trip (← links)
- 05000461/LER-2018-005, Unplanned Reactor Scram During Maintenance Outage Due to High Intermediate Range Monitor Flux (← links)
- 05000247/LER-2018-003, For Indian Point Nuclear Generating Unit 2, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap (← links)
- 05000335/LER-2018-001, Feedwater Heater Level Control Malfunctions Resulted in Lowering Steam Generator Water Level and Manual Reactor Trip (← links)
- 05000331/LER-2018-004, Regarding Automatic Reactor Scram Due to Feedwater Regulating Valve Failure (← links)
- 05000254/LER-2018-005, Loss of Safety Bus and Automatic Actuation of a Safety System During Undervoltage Relay Surveillance (← links)
- 05000298/LER-2018-003, Safety Valve Failure Results in Loss of Safety Function (← links)
- 05000389/LER-2018-001-01, Pressurizer Instrument Nozzle Leak Due to Primary Water Stress Corrosion Cracking (← links)
- 05000341/LER-2018-006, Emergency Diesel Generator Load Sequencer Inhibits Automatic Start of Residual Heat Removal Pumps Under Certain Scenarios Due to Unrecognized Original Design Defect (← links)
- 05000317/LER-2018-001, For Calvert Cliffs Nuclear Power Plant, Units No. 1 and 2, Both Unit 2 Emergency Diesel Generators Inoperable Due to Depressurization in Common Air Start Headers (← links)
- 05000389/LER-2018-002, Automatic Reactor Trip Due to a Breaker Failure on the 2A1 6.9kV Bus (← links)
- 05000412/LER-2018-002, Inadvertent Automatic Actuation Signal to the Unit 2 Standby Service Water System (← links)
- 05000259/LER-2018-006, Standby Gas Treatment System Train C Inoperable Longer than Allowed by Tech (← links)
- 05000457/LER-2018-001, Reactor Coolant System Pressure Boundary Leak on a Steam Generator Bowl Drain Line Due to High Cycle Fatigue Cracking Initiated from Small Welding Defects (← links)
- 05000498/LER-2018-001, Main Steam Safety Valve as Left Settings Outside of Required Range Contrary to Technical Specifications Due to Inadequate Procedure (← links)
- 05000293/LER-2018-006, Automatic Reactor Scram Due to Feedwater Regulating Valve Malfunction (← links)
- 05000424/LER-2018-002, Manual Reactor Trip Due to Receiving Rod Control Urgent Failure Alarm During Low Power Physics Testing (← links)
- 05000440/LER-2018-003, Unanalyzed Condition Resulting from Unfused Alternating Current Control Circuits (← links)
- 05000461/LER-2018-004, Undervoltage Condition Caused by an Offsite Ameren Transformer Bushing Failure Initiates an Automatic Start of an Emergency Diesel Generator (← links)
- 05000254/LER-2018-004, For Quad Cities Nuclear Power Station, Unit 1, Reactor Scram Due to Turbine-Generator Load Reject (← links)
- 05000341/LER-2018-004, Re Inoperability of Reactor Water Cleanup System Isolation Differential Flow-High Function (← links)
- 05000416/LER-2018-009, Reactor Manual Shutdown Due to Feedwater Level Control Changes (← links)
- 05000311/LER-2018-002, Automatic Reactor Trip Due to High 23 Steam Generator Water Level (← links)
- 05000286/LER-2018-002, Manual Reactor Shutdown Due to Weld Leak in Safety Injection System Tank (← links)
- 05000254/LER-2018-003-01, Two Reactor Protection System Channels Impacted by Single Main Stop Valve Limit Switch Failure (← links)
- 05000389/LER-2018-001, Pressurizer Instrument Nozzle Leak Due to Primary Water Stress Corrosion Cracking (← links)
- 05000287/LER-2018-002-01, Actuation of the Keowee Hydroelectric Station Due to Loss of AC Power to the Unit 3 Main Feeder Buses (← links)
- 05000410/LER-2018-002, Turbine Trip and Scram Due to Unit Differential Relay Trip (← links)
- 05000458/LER-2018-007, Manual Reactor Scram Due to Reactor Recirculation Pump Trip Caused by Transformer Failure (← links)
- 05000331/LER-2018-003, Regarding Combined Maximum Main Steam Line Pathway Leakage Exceeded Technical Specification Limit (← links)
- 05000338/LER-2018-002, 1J Emergency Diesel Generator Auto-Start (← links)
- 05000374/LER-2018-001, For LaSalle County Station, Unit 2, Manual Reactor Scram Due to Main Condenser Vacuum Degradation (← links)
- 05000446/LER-2018-001, Automatic Reactor Trip Due to Turbine Trip (← links)
- 05000391/LER-2018-005, For Watts Bar Nuclear Plant, Unit 2, Automatic Reactor Trip Due to Turbine Control System Card Failure and Throttle Valve Closure (← links)
- 05000482/LER-2018-001, Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications (← links)
- 05000354/LER-2018-002-01, Safety Relief Valve L (SRV) As-Found Setpoint Failure (← links)
- 05000412/LER-2018-001, Technical Specification Required Shutdown Due to Loss of 2P 480 Volt Emergency Bus (← links)
- 05000341/LER-2018-005, Non-Functional Mechanical Draft Cooling Tower Fan Brakes Leads to HPCI Being Declared Inoperable and Loss of Safety Function (← links)
- 05000400/LER-2018-004, Independent Trains of the Emergency Core Cooling System Inoperable During Testing (← links)
- 05000306/LER-2018-001-01, Automatic Actuation of Emergency Diesel Generator D5 (← links)
- 05000293/LER-2018-005, Condition Prohibited by Technical Specifications Involving Standby Gas Treatment System Pneumatic Leakage Rate (← links)
- 05000259/LER-2018-005, Inoperability of Unit 1 and 2 Emergency Diesel Generators Results in Condition Prohibited by Technical Specifications (← links)
- 05000317/LER-2018-003, Control Room Loss of Ventilation Due to Smoke Detector Failure Causing Common Supply Damper to Shut (← links)
- 05000400/LER-2018-003, Turbine Control System Auto-Stop Trip Solenoid Operated Valves Response Times Impacted (← links)
- 05000455/LER-2018-001, Automatic Safety System Actuation Following a Trip of a Station Auxiliary Transformer and Subsequent Loss of Offsite Power (← links)
- 05000530/LER-2018-001, Reactor Trip on Low Steam Generator Level (← links)
- 05000528/LER-2018-004-01, Engineered Safety Feature Pump Room Exhaust Air Cleanup System Failure Resulting in a Condition Prohibited by Technical Specifications (← links)
- 05000461/LER-2018-003, Load Driver Card Failure Resulting in High Pressure Core Spray Lnoperability (← links)
- 05000331/LER-2018-002, Both Doors in Secondary Containment Airlock Opened Concurrently (← links)
- 05000277/LER-2018-002, Unit 3, Emergency Diesel Generator Air Inlet Check Valve Failure Results in a Condition Prohibited by Technical Specifications (← links)
- 05000325/LER-2018-003, Setpoint Drift in Main Steam Line Safety/Relief Valves Results in Two Valves Inoperable (← links)
- 05000353/LER-2017-004-01, Degraded Condition Due to RPV Instrument Nozzle Leakage (← links)
- 05000219/LER-2018-001, EMRV Pressure Sensor As-Found Setting Exceeded Limiting Safety System Settings (← links)
- 05000254/LER-2018-003, For Quad Cities Nuclear Power Station, Unit 1, Two Reactor Protection System Channels Impacted by Single Main Stop Valve Limit Switch Failure (← links)
- 05000272/LER-2018-001, Inadequate Protection from Tornado Missiles Due to Nonconforming Design Conditions (← links)
- 05000373/LER-2018-003-01, For LaSalle County Station, Unit 1, Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test (← links)
- 05000306/LER-2018-002, RHR Flood Barriers Compensatory Measures (← links)
- 05000461/LER-2018-002, Division 2 Diesel Generator Inoperability Due to Air Receiver Remaining Isolated Following Clearance Removal Resulting in Unplanned Shutdown Risk Change (← links)
- 05000397/LER-2018-001, Automatic Reactor Scram Due to Main Transformer Trip (← links)
- 05000306/LER-2018-001, For Prairie Island Nuclear Generating Plant, Unit 2, Automatic Actuation of Emergency Diesel Generator D5 (← links)
- 05000296/LER-2018-004, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints (← links)
- 05000313/LER-2018-001, Automatic Reactor Trip Due to Loss of Main Feedwater Pump (← links)
- 05000410/LER-2018-001, For Nine Mile Point Unit 2, Auto Start of Division II Emergency Diesel Generator Due to Loss of Line 6 (← links)
- 05000416/LER-2018-008, Unplanned System Actuation (Diesel Generator) Caused by Inadvertently Opening the Wrong Fuse Drawer (← links)
- 05000311/LER-2018-001, For Salem Nuclear Generating Station Unit 2, Manual Reactor Trip Due to Elevated 21 Reactor Coolant Pump Motor Winding Temperature (← links)
- 05000316/LER-2018-003, Regarding Manual Reactor Trip Due to High-High Moisture Separator Drain Tank Level (← links)
- 05000483/LER-2018-002, Inadequate EOP Guidance for Asymmetric Natural Circulation Cooldown (← links)
- 05000416/LER-2018-007, Potential Loss of Safety Function (Residual Heat Removal) and System Actuation Caused by Inadvertent Valve Opening (← links)
- 05000499/LER-2018-001-01, Supplement to Unit 2 Condition Prohibited by Technical Specifications That Could Have Prevented the Fulfillment of a Safety Function Due to Two Inoperable Extended Range Monitors (← links)
- 05000247/LER-2018-002, Manual Reactor Trip Due to Trip of Both Main Boiler Feedwater Pumps (← links)
- 05000278/LER-2018-001, Reactor Core Isolation Cooling System Pressure Switch Failure Results in Condition Prohibited by TS (← links)
- 05000456/LER-2018-004, A Emergency Diesel Generator Output Breaker Opened During a Surveillance Which Resulted in Unplanned Actuations of Bus 141 Undervoltage Relay (← links)
- 05000456/LER-2018-001, A Emergency Diesel Generator Lost Voltage During a Surveillance Due to a Failed Exciter Diode, Which Resulted in an Unplanned Actuation of Bus 141 Undervoltage Relay (← links)
- 05000352/LER-2018-003, High Pressure Coolant Injection (HPCI) Inoperability Due to Main Pump Inboard Seal Leak (← links)
- 05000354/LER-2018-001, Operations with a Potential to Drain the Reactor Vessel Without Secondary Containment (← links)
- 05000456/LER-2018-003, Indications on Top Head to Upper Center Disc Weld of Reactor Head Identified Due to New Inspection Standards (← links)
- 05000269/LER-2018-001, Manual Reactor Trip Due to Main Feedwater Flow Control Valve E/P Converter Failures (← links)
- 05000458/LER-2018-001, Potential Loss of Safety Function of Control Building HVAC Due to Legacy Design Flaw (← links)
- 05000341/LER-2018-002, Loss of Division 1 Offsite Power Causes Partial Loss of Feedwater Leading to ECCS Injection and Reactor Scram (← links)
- 05000317/LER-2018-002, Items Non-Conforming to Design for Tornado Missile Protection (← links)
- 05000316/LER-1918-002, Component Cooling Water System Inoperable Longer than Allowed by Technical Specifications (← links)
- 05000400/LER-2018-002, Reactor Pressure Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking (← links)
- 05000316/LER-2018-001, Valid Actuation of the Unit 2 Cd Emergency Diesel Generator During Testing (← links)
- 05000325/LER-2018-002, Automatic Reactor Trip During Stator Coolant System Realignment (← links)
- 05000400/LER-2018-001, Automatic Actuation of Auxiliary Feedwater System (← links)
- 05000315/LER-2018-001, East Essential Service Water Pump Inoperable Longer than Allowed by Technical Specifications (← links)
- 05000352/LER-2018-002, Primary Containment Isolation Valve Failed to Fully Close Resulting in Condition Prohibited by Technical Specifications (← links)
- 05000293/LER-2018-004, Automatic Emergency Diesel Generator System Actuation Caused by Loss of Offsite Power (← links)
- 05000461/LER-2018-001, Degraded Personnel Airlock Interlock Results in Loss of Primary Containment (← links)
- 05000247/LER-2018-001, Re Penetration Indications Discovered During Reactor Pressure Vessel Head Inspection (← links)
- 05000416/LER-2018-005, Secondary Containment Door Misaligned, Due to 1nadequate Criteria, Could Have Prevented Fulfillment of a Safety Function (← links)
- 05000416/LER-2018-006, Secondary Containment Roof Hatch Left Open Due to Inadequate Corrective Actions (← links)
- 05000499/LER-2018-001, Condition Prohibited by Technical Specifications That Could Have Prevented the Fulfillment of a Safety Function Due to Two Inoperable Extended Range Monitors (← links)
- 05000373/LER-2018-004, Technical Specification Required Shutdown Due to Reactor Pressure Boundary Leakage (← links)
- 05000414/LER-2018-001, Auxiliary Feedwater System Auto-Start Due to a Loss of Both Feedwater Pumps Signal (← links)
- 05000265/LER-2018-001, Two Main Steam Isolation Valves (Msivs) Closure Times Exceeded (← links)
- 05000259/LER-2018-002, Automatic Reactor Scram Due to an Unanticipated Electro-Hydraulic Control Logic Condition (← links)
- 05000338/LER-2018-001, SW-P-1B Failed to Trip During the 1J Blackout Test (← links)
- 05000277/LER-2018-001, Fire Safe Shutdown Requirements Not Met for Spurious Operation of Valves at a High-Low Pressure Interface (← links)
- 05000331/LER-2018-001, Regarding Loss of RPS Function During MSIV and TSV Channel Functional Testing Due to Use of a Test Box (← links)
- 05000395/LER-2018-001-01, Tor Virgil C. Summer, Unit 1, Valid Actuation of Emergency Diesel Generator (← links)
- 05000325/LER-2018-001, Implementation of Enforcement Guidance Memorandum (Egm) 11-003, Revision 3 (← links)
- 05000296/LER-2018-002, Inoperable 250V Shutdown Board Battery Charger Results in Condition Prohibited by Technical Specifications (← links)
- 05000416/LER-2018-003, Inoperable Reactor Protection Functions During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Box (← links)
- 05000395/LER-2016-001-02, (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors (← links)
- 05000296/LER-2018-003, Misadjusted Switch Results in Condition Prohibited by Technical Specifications (← links)
- 05000528/LER-2018-001, Unit, Automatic Actuation of the Reactor Protection System Resulting from a Loss of Reactor Coolant Pumps (← links)
- 05000373/LER-2018-002, Damaged Bus Bar Identified Potentially Affecting High Pressure Core Spray System (← links)
- 05000373/LER-2018-001, Unanalyzed Condition Affecting Accident Mitigation for Tornado Generated Missile Protection Non-Conformances (← links)
- 05000443/LER-2018-001, Re Pressurizer Safety Valve Outside of Technical Specification Limits Discovered During As-Found Set Point Testing (← links)
- 05000272/LER-2016-006-01, Technical Specification for Containment Integrity Not Met (← links)
- 05000293/LER-2018-003, Target Rock Relief Valve Pilot Assembly Failed As-Found Lift Test, a Condition Prohibited by Plant Technical Specifications (← links)
- 05000387/LER-2017-008, Core Spray Inoperable Due to Not Meeting Seismic Requirements as a Result of a Human Performance Error (← links)
- 05000254/LER-2018-001, Secondary Containment Differential Pressure Momentarily Lost Due to Fuel Pool Radiation Monitor Spike (← links)
- 05000333/LER-2017-004-01, Regarding Safety Relief Valves Out of Tolerance (← links)
- 05000440/LER-2018-001, Regarding Loss of Safety Function and Violation of Technical Specifications Due to Diode Failure (← links)
- 05000280/LER-2018-001, Loss of 4160 Volt Emergency Bus and Start of Emergency Diesel Generator Due to Opening Emergency Bus Potential Transformer Drawer (← links)
- 05000321/LER-2018-002, Regarding Operations with the Potential to Drain the Reactor Vessel (Opdrvs) Without Secondary Containment (← links)
- 05000321/LER-2018-001, Regarding Condition Prohibited by Tech Specs Due to Secondary Containment Inoperability (← links)
- 05000293/LER-2018-001, Regarding Manual Reactor Scram Due to Loss of One Offsite Transmission Line (← links)
- 05000293/LER-2018-002, Diesel Generator a Inoperable, a Condition Prohibited by the Plant Technical Specifications (← links)
- 05000395/LER-2018-001, Valid Actuation of Emergency Diesel Generator (← links)
- 05000483/LER-2018-001, Violation of Technical Specification 3.6.3 Containment Isolation Manual Found in Open Position (← links)
- 05000282/LER-2018-001, Motor Driven Cooling Water Pump Auto Start Due to Smoking Packing on 11 Cooling Water Pump (← links)
- 05000341/LER-2018-001, Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC System Manipulation (← links)
- 05000315/LER-2017-001, For Donald C. Cook Unit 1 Regarding Unit 1 Turbine Driven Auxiliary Feedwater Pump Inoperable Longer than Allowed by Technical Specifications (← links)
- 05000353/LER-2017-008-01, Eog Inoperable for Greater than 30 Days Resulting in Condition Prohibited by TS (← links)
- 05000237/LER-2017-002-01, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage (← links)
- 05000382/LER-2018-001, For Waterford Unit 3 Regarding Failure to Enter Limiting Condition of Operation Action Statement Due to Lack of Procedure Guidance Results in a Condition Prohibited by Technical Specifications (← links)
- 05000387/LER-2017-009-01, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Equipment Exhaust Fan (← links)
- 05000440/LER-2017-007, For Perry Nuclear Power Plant Regarding High Pressure Core Spray Inoperability Due to System Leak (← links)
- 05000461/LER-1917-010, Regarding Division 1 Transformer Failure Leads to Instrument Air Isolation to Containment Requiring a Manual Reactor Scram (← links)
- 05000260/LER-1994-012-01, :on 941113,RHR Shutdown Cooling Valve Inadvertently Closed.Caused by Personnel Failure to Follow Procedure During Surveillance Instruction.Personnel Involved in Event Counseled (← links)
- 05000353/LER-1918-001, HPCI Inoperability Due to Discharge Check Valve Failure to Close (← links)
- 05000289/LER-1917-004, Regarding Items Nonconforming to Design for Tornado Missile Protection (← links)
- 05000352/LER-1918-001, Regarding D12 EDG Inoperable for Greater than 30 Days Resulting in Condition Prohibited by TS (← links)
- 05000446/LER-1917-003, Regarding Manual Reactor Trip Due to Trip of Both Main Feedwater Pumps (← links)
- 05000293/LER-1917-013, Regarding Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment Lnoperability Not Reported During the Previous Three Years (← links)
- 05000388/LER-1917-010, Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches (← links)
- 05000498/LER-1917-002, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil (← links)
- 05000263/LER-1917-006, Regarding Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Fixture (← links)
- 05000364/LER-1917-005, Regarding Power Range Nuclear Instrument Inoperable Due to Poor Connection of High Voltage Cable Connector (← links)
- 05000272/LER-1916-006, Regarding Technical Specification (TS) for Containment Integrity Not Met (← links)
- 05000306/LER-1917-003, Regarding Both Containment Spray Pump Control Switches in Pull-Out in Mode 4 (← links)
- 05000219/LER-1917-005, Regarding Failure of the Emergency Diesel Generator 2 During Surveillance Testing Due to a Broken Electrical Connector (← links)
- 05000390/LER-1917-015, Regarding Failure to Enter Limiting Condition of Operation Action Statement Results in a Condition Prohibited by Technical Specifications (← links)
- 05000272/LER-1917-001, Regarding Containment Integrity Inoperable for Longer than Allowed by Technical Specifications (← links)
- 05000334/LER-1917-003, Regarding Reactor Trip Due to Turbine Trip and Automatic Initiation of the Auxiliary Feedwater System (← links)
- 05000461/LER-1917-009, Regarding Trip of Emergency Reserve Auxiliary Transformer Static Var Compensator Causes Positive Secondary Containment Pressure Following Voltage Transient on 138 Kv Offsite Source (← links)
- 05000254/LER-1917-004, For Quad Cities Nuclear Power Station, Unit 1 Unit 1 HPCI Did Not Trip Due to Wear Debris in the Turbine Stop Valve Oil Resetting Solenoid (← links)
- 05000237/LER-1917-002, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage Limits (← links)
- 05000296/LER-1917-002, Regarding 4kV Shutdown Board Potential Transformer Primary Fuses Do Not Coordinate with Secondary Fuses (← links)
- 05000286/LER-1917-004, Regarding Reactor Trip Due to Main Generator Loss of Field (← links)
- 05000395/LER-1917-005, V.C Summer, Unit 1, Regarding Automatic Reactor Trip Due to Main Turbine Trip (← links)
- 05000483/LER-1917-003, Regarding Violation of Technical Specification 3.6.3, Containment Isolation Check Valve Found in Open Position (← links)
- 05000278/LER-1917-001, Regarding Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line (← links)
- 05000364/LER-1917-003, Regarding Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits (← links)
- 05000364/LER-1917-002, Regarding Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits (← links)
- 05000389/LER-1917-004, Regarding Automatic Reactor Trip Due to Turbine Control System Malfunction (← links)
- 05000389/LER-1917-003, Regarding Improper System Realignment Resulted in Loss of Steam Driven Auxiliary Feedwater Pump Flow Indication (← links)
- 05000395/LER-1917-006, Regarding Technical Specification Action Not Met for Inoperable Oxygen Monitor (← links)
- 05000266/LER-1917-003, Regarding Degraded Condition (← links)
- 05000266/LER-1917-002, Regarding Operation or Condition Prohibited by Technical Specifications (← links)
- 05000410/LER-1917-002, Regarding Secondary Containment Inoperable Due to Wind Conditions (← links)
- 05000306/LER-1917-002, Regarding Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect (← links)
- 05000353/LER-1917-008, Regarding Eog Inoperable for Greater than 30 Days Resulting in Condition Prohibited by Technical Specifications (← links)
- 05000352/LER-1917-004, Regarding Core Spray Pump Failed to Start Resulting in Condition Prohibited by TS (← links)
- 05000440/LER-1917-006, Regarding Loss of Safety Function Due to the Inoperability of Both Trains of Motor Control Center Ventilation (← links)
- 05000397/LER-1917-007, Regarding Valve Closure Results in Momentary Increase in Secondary Containment Pressure (← links)
- 05000306/LER-1917-001, Regarding 23 Containment Fan Coil Unit Operability (← links)
- 05000346/LER-1917-002, For Davis-Besse Nuclear Power Station, Unit 1, Regarding Auxiliary Feed Water Pump Turbine Bearing Damaged Due to Improperly Marked Lubricating Oil Sight Glass (← links)
- 05000353/LER-1917-007, Regarding Reactor Mode Switch Change During RCIC Testing (← links)
- 05000458/LER-1917-009, Regarding Potential Loss of Safety Function of Secondary Containment Due to Unsecured Personnel Door (← links)
- 05000220/LER-1917-003, Regarding Automatic Reactor Scram Due to Reactor Vessel Low Water Level (← links)
- 05000293/LER-1917-012, Regarding Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit (← links)
- 05000254/LER-1917-003, Regarding Control Room Emergency Ventilation Air Conditioning Piping Refrigerant Leak Due to High Cycle Fatigue (← links)
- 05000266/LER-1917-001, Regarding Control Room Barrier Inadvertently Disabled (← links)
- 05000324/LER-1917-004, Regarding Emergency Diesel Generator and Primary Containment Isolation System Actuations (← links)
- 05000249/LER-1917-001, Regarding Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak (← links)
- 05000387/LER-1917-009, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Equipment Exhaust Fan (← links)
- 05000335/LER-1917-003, Regarding Inadequate Reactor Protection System Trip Process for Inoperable Channel Results in Operation in a Condition Prohibited by Technical Specifications (← links)
- 05000482/LER-1917-003, Regarding ARV and MSSV Tornado Missile Vulnerabilities Result in Unanalyzed Condition (← links)
- 05000395/LER-1917-004, Regarding Actuation of a Emergency Diesel Generator (← links)
- 05000397/LER-1917-006, For Condition Prohibited by Technical Specifications Due to Incomplete Action Statement (← links)
- 05000259/LER-1917-004, Regarding Safety System Functional Failures Due to the Lnoperability of Both Unit 1 and 2 Control Bay Chillers (← links)
- 05000397/LER-1917-005, Regarding Valve Closure Results in Momentary Increase in Secondary Containment Pressure (← links)
- 05000251/LER-1917-001, Regarding Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control (← links)
- 05000341/LER-1917-005, Regarding Non-Functional Mechanical Draft Cooling Tower Fan Brakes Leads to HPCI Being Declared Inoperable and Loss of Safety Function (← links)
- 05000296/LER-1917-001, Regarding Inoperable Residual Heat Removal Pump Results in Condition Prohibited by Technical Specifications (← links)
- 05000395/LER-1917-003, For Virgil C. Summer Nuclear Station, Unit 1, Regarding Failed Lightning Arrester on Main Transformer Causes Reactor Trip (← links)
- 05000280/LER-1917-001, Regarding Shutdown Due to an Unisolable Leak in Reactor Coolant Pressure Boundary (← links)
- 05000390/LER-1917-011, Regarding Failure to Enter Technical Specification 3.6.3 for Containment Lsolation Valve (← links)
- 05000410/LER-1917-001, Regarding Automatic Reactor Scram Due to High Reactor Pressure (← links)
- 05000397/LER-1917-004, Regarding Manual Reactor Scram Due to High Main Condenser Back Pressure (← links)
- 05000397/LER-1993-001, :on 930213,determined That Both Trains of SPC of RHR System Were Inoperable Due to LOP Coincident W/Lpci Safety Function.Reviews & Safety Evaluations Has Been Enhanced (← links)
- 05000446/LER-1917-001, Regarding Auxiliary Feedwater System Actuation During Unit 2 Turbine Trip (← links)
- 05000397/LER-1992-017, :on 920508,personnel Determined That Heat Removal Capability of Train a RHR Heat Exchanger Less than Design Allowable.Caused by Insufficient Monitoring of Plant Components.Corrective Actions Not Required (← links)
- 05000397/LER-1992-012, :on 920318,determined That Removal of Access Plugs Over RHR Pump Rooms a & B Exposed Both Rooms to Potential Flooding from Common Source.Caused by Faulty Mgt Methods.Interim Guidance Provided (← links)
- 05000483/LER-1917-002, Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design (← links)
- 05000387/LER-1917-007, Regarding Secondary Containment Declared Inoperable Due to Supply Air Flow (← links)
- 05000341/LER-1917-004, Regarding Inadequate Procedural Guidance for Residual Heat Removal Complex Ventilation Systems Leads to Condition Prohibited by Technical Specifications and Loss of Safety Function (← links)
- 05000440/LER-1917-005, Regarding Controller Malfunction Results in Momentary Degradation of Secondary Containment Pressure (← links)
- 05000440/LER-1917-004, Re Loss of Safety Function for High Pressure Core Spray Suppression Pool Level Instrumentation (← links)
- 05000323/LER-1917-001, Regarding Relief Valve Leakage Resulting in Inoperable Pressurizer Power Operated Relief Valve (← links)
- 05000335/LER-1917-002, Regarding Inadequate Hot Leg Injection Procedure Results in Unanalyzed Condition (← links)
- 05000353/LER-1917-006, Regarding HPCI Lnoperability During Post Maintenance Testing (← links)
- 10 CFR 50.73(a)(2)(v), Loss of Safety Function (← links)
- 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability (← links)
- Licensee Event Report (← links)
- 05000296/LER-2015-001, High Pressure Coolant Injection and Reactor Core Isolation Cooling Inoperable Due To No Suction Source Aligned (← links)
- 10 CFR 50.73(a)(2)(iv), System Actuation (← links)
- 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications (← links)
- 05000499/LER-2015-001, Technical Specification Action Statement Time Exceeded Due to Turbine-Driven Auxiliary Feedwater Pump Test Failure Not Recognized (← links)
- 05000482/LER-2015-001, Personnel Error Causes Two Inoperable Residual Heat Removal Trains (← links)
- 05000482/LER-2015-002, Two Control Room Air Conditioning Trains Inoperable Due to Failure to Meet Surveillance Requirement (← links)