NL-17-107, LER 15-001-02 for Indian Point, Unit 2, Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable Containment Caused by a Service Water Pipe Leak with a Flaw Size That Results in Exceeding the Allowed Leakage Rate fo
05000445/LER-2024-001, Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning
05000483/LER-2020-008, Reactor Trip Due to Main Generator Electrical Fault
05000325/LER-1988-025, :on 881115,failure to Meet Tech Specs 3.61.2b & 3.6.1.2c Revealed Through Local Leak Rate Testing.Caused by Manpower Constraints.Valves Listed in Table 1 Are on Separate Containment Penetrations
05000346/LER-1998-006, :on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources
05000374/LER-1987-002-01, :on 870117,containment Leakage Limit of 0.6 La Exceeded on Local Leak Rate Testing of Feedwater Check Valves.List of Failed Valves,Causes & Corrective Actions Provided
05000374/LER-1987-004-08, :on 870401,53 Safety Related Snubbers Failed to Meet Functional Test Acceptance Limits During Tech Spec Surveillance.Causes & Corrective Actions for Each Snubber Listed
05000278/LER-1985-015, :on 850930,total Leakage of Type B & C Test Exceeded Leak Rate Limit.Caused by Several Valves Tested W/ Excessive Rates Contributing to Total.Valve Repaired & Retested Prior to Returning Unit to Operation
05000293/LER-1993-006, :on 930315,indications of Actuation of Reactor bldg-to-torus Train B Vacuum Relief Sys Discovered While Shut Down.Caused by Negative Differential Pressure.Nitrogen Added to Torus Atmosphere
05000388/LER-1917-010, Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches
05000387/LER-2018-005-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches
05000416/LER-2019-006, Failure to Meet Technical Specification 5.5.7 for Division II Standby Gas Charcoal Filter Media Efficiency
05000416/LER-2019-005, Primary Containment Personnel Airlock Potential Loss of Safety Function Due to Inadequate Door Closure
05000416/LER-2019-004, Loss of High Pressure Core Spray Due to Instrument Inverter Failure
05000263/LER-2019-002, Two Manual Primary Containment Isolation Valves Found Open Resulting in a Condition Prohibited by Technical Specification
05000416/LER-2019-002, Manual Reactor Shutdown Due to Loss of Service Water
05000266/LER-2019-002, Operation Not Maintained within Pressure and Temperature Limit Report (PTLR) as Required by Technical Specification 3.4.3
05000255/LER-2019-002, Automatic Reactor Trip and AFW System Actuation Due to the Loss of Power to the RPS Bd Matrix
07200041/LER-2018-002, 0 for San Onofre Nuclear Generating Station ISFSI Re Spent Nuclear Fuel Transport Conveyance Vehicle Operated Outside Obstacle Clearance Limit
05000416/LER-2018-010, Reactor Manual Scram Due to Main Turbine Bypass Valve Drifting Open
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
05000331/LER-2018-004, Regarding Automatic Reactor Scram Due to Feedwater Regulating Valve Failure
05000301/LER-2018-001, Operation or Condition Prohibited by Technical Specifications, Less than Minimum Refueling Cavity Water Level
05000354/LER-2018-002-01, Safety Relief Valve L (SRV) As-Found Setpoint Failure
05000416/LER-2017-003-02, Reactor Shutdown Because of Condensate System Inventory Depletion and a Manual Reactor Core Isolation Cooling (RCIC) Initiation Because of a Feedwater System Shutdown
05000354/LER-2018-003-01, Feedwater Isolation Valve Leakage Exceeded Technical Specification Limit
05000387/LER-2018-005, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches
05000306/LER-2018-001, For Prairie Island Nuclear Generating Plant, Unit 2, Automatic Actuation of Emergency Diesel Generator D5
05000483/LER-2018-002, Inadequate EOP Guidance for Asymmetric Natural Circulation Cooldown
LR-N18-0065, Safety Relief Valve (SRV) As-Found Setpoint Failure
05000354/LER-2018-003, Feedwater Isolation Valve Leakage Exceeded Technical Specification Limit
05000387/LER-2018-003, Main Steam Isolation Valve Leakage Due to Pilot Poppet and Pilot Poppet Seat Wear/Degradation
05000416/LER-2018-006, Secondary Containment Roof Hatch Left Open Due to Inadequate Corrective Actions
05000416/LER-2018-005, Secondary Containment Door Misaligned, Due to 1nadequate Criteria, Could Have Prevented Fulfillment of a Safety Function
05000272/LER-2016-006-01, Technical Specification for Containment Integrity Not Met
05000387/LER-2017-008, Core Spray Inoperable Due to Not Meeting Seismic Requirements as a Result of a Human Performance Error
05000282/LER-2018-001, Motor Driven Cooling Water Pump Auto Start Due to Smoking Packing on 11 Cooling Water Pump
05000387/LER-2017-009-01, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Equipment Exhaust Fan
05000306/LER-1917-003, Regarding Both Containment Spray Pump Control Switches in Pull-Out in Mode 4
05000387/LER-1917-006, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Exhaust Fan
05000425/LER-1917-002, Regarding Valid Undervoltage Condition Results in Automatic Actuation of a Safety System
05000387/LER-1917-009, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Equipment Exhaust Fan
05000387/LER-1917-007, Regarding Secondary Containment Declared Inoperable Due to Supply Air Flow
05000388/LER-1917-008, Regarding Condition Prohibited by Technical Specifications Due to a Loose Terminal Block Associated with a Primary Containment Isolation Valve
05000293/LER-1917-008, Re 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure
05000293/LER-1917-004, Regarding Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System
05000424/LER-1917-002, Regarding Wiring Error Results in Automatic Actuation of a Safety System
05000425/LER-1917-001, Regarding Power Supply Failure Results in Operation in a Condition Prohibited by Technical Specifications
05000458/LER-2007-002, Regarding Unplanned Manual Reactor Scram Due to Loss of Cooling on No. 2 Main Transformer
05000388/LER-2007-001, Regarding U2 Secondary Containment Bypass Leakage Exceeded
05000255/LER-2007-002, Re Inoperable Containment Due to Containment Air Cooler Through-Wall Flaw
05000458/LER-2006-004, Regarding Automatic Reactor Scram Following Recirculation Pump Downshift Due to Failed Optical Isolator Card
05000458/LER-2004-005, Regarding Unplanned Automatic Scram Due to Loss of Non-vital 120 Volt Instrument Bus
05000458/LER-2004-004, Regarding Unplanned Automatic Start of Standby Diesel Generator Due to Loss of Division 2 Switchgear
05000440/LER-2003-004-02, Regarding Emergency Service Water Pump Upper Shaft Coupling Sleeve Failure
05000302/LER-2001-005-01, Regarding Loss of Steam to the Operating Main Feedwater Pump Results in Actuation of the Emergency Feedwater System
05000373/LER-1988-002-03, :on 880316,Type B & Type C Total Leakage Exceeded 0.6 La During Leak Rate Testing.Caused by Excessive Leakages.Corrective Actions Include Installment of New Disc Listed in Table 1