| | | Reporting criterion |
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| 05000245/LER-1988-001-01, :on 880120,discharge Valve Inadvertently Opened to Unsampled Floor Drain Sample Tank B.Caused by Personnel Failure to Follow Operating Procedure.Operator Disciplined & Procedure Controls Implemented |
- on 880120,discharge Valve Inadvertently Opened to Unsampled Floor Drain Sample Tank B.Caused by Personnel Failure to Follow Operating Procedure.Operator Disciplined & Procedure Controls Implemented
| 10 CFR 50.73(a)(2)(i) |
| 05000336/LER-1988-001, :on 880108,three Steam Generator Tube Ends Found Unplugged During Cold Shutdown.Caused by Equipment Operator Error.Tube Ends Plugged |
- on 880108,three Steam Generator Tube Ends Found Unplugged During Cold Shutdown.Caused by Equipment Operator Error.Tube Ends Plugged
| 10 CFR 50.73(a)(2)(1) |
| 05000245/LER-1988-002-02, :on 880310,discovered That Sp 1060, Inservice Insp Program Pump Vibration & Hydraulic Test for Svc Water Pump C Missed.Caused by Personnel Error.Methods for Surveillance Scheduling Changed |
- on 880310,discovered That Sp 1060, Inservice Insp Program Pump Vibration & Hydraulic Test for Svc Water Pump C Missed.Caused by Personnel Error.Methods for Surveillance Scheduling Changed
| 10 CFR 50.73(a)(2)(1) |
| 05000336/LER-1988-002-01, :on 880119,loss of Normal Power Occurred on Vital 4160-volt Power Electrical Bus 24D.Caused by Failure of Dc Input Capacitor in Supply Inverter INV-1.Normal Power Restored to Bus & Capacitor Replaced |
- on 880119,loss of Normal Power Occurred on Vital 4160-volt Power Electrical Bus 24D.Caused by Failure of Dc Input Capacitor in Supply Inverter INV-1.Normal Power Restored to Bus & Capacitor Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1988-003, :on 880130,inadvertent Automatic loss-of-normal Power Actuation Occurred on Two of Engineered Safeguards Actuation Sys.Immediate Cause Not Apparent.Wiring Error Identified & Corrected |
- on 880130,inadvertent Automatic loss-of-normal Power Actuation Occurred on Two of Engineered Safeguards Actuation Sys.Immediate Cause Not Apparent.Wiring Error Identified & Corrected
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(b)(2)(ii) |
| 05000245/LER-1988-003-02, :on 880312,reactor Scram on Low Water Level Occurred.Caused by Feed Pump Trip.Feedwater Pump a Low Suction Pressure Switch Replaced,Recalibr & Tested Satisfactorily |
- on 880312,reactor Scram on Low Water Level Occurred.Caused by Feed Pump Trip.Feedwater Pump a Low Suction Pressure Switch Replaced,Recalibr & Tested Satisfactorily
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1988-003, :on 880116,emergency Diesel Generator Train B Started Due to Bumped Relay Allowing Test Signal to Commence Emergency Load Sequencing.Caused by Relay Failure.Procedures Changed to Remove Dependency on Relay |
- on 880116,emergency Diesel Generator Train B Started Due to Bumped Relay Allowing Test Signal to Commence Emergency Load Sequencing.Caused by Relay Failure.Procedures Changed to Remove Dependency on Relay
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000245/LER-1988-004-02, :on 880318,discovered Potential for ECCS Pump Suction Strainers to Foul W/Fibrous Insulation Debris.Caused by Insufficient Area of Existing Strainers.Strainers Replaced |
- on 880318,discovered Potential for ECCS Pump Suction Strainers to Foul W/Fibrous Insulation Debris.Caused by Insufficient Area of Existing Strainers.Strainers Replaced
| 10 CFR 50.73(a)(2)(vi) |
| 05000245/LER-1988-004, :on 880318,determined Potential Fouling of ECCS Suction Strainers.Caused by Insufficient Area of Existing Strainers.Project Assignment Initiated to Replace ECCS Suction Strainers |
- on 880318,determined Potential Fouling of ECCS Suction Strainers.Caused by Insufficient Area of Existing Strainers.Project Assignment Initiated to Replace ECCS Suction Strainers
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vi) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) |
| 05000336/LER-1988-004-01, :0n 880126,inadvertent ESF Actuation Occurred. Caused by Personnel Error.Testing Suspended & Equipment Disconnected & Retest Procedure Revised to Provide Step by Step Details on Checking Isolation Transformer |
- 0n 880126,inadvertent ESF Actuation Occurred. Caused by Personnel Error.Testing Suspended & Equipment Disconnected & Retest Procedure Revised to Provide Step by Step Details on Checking Isolation Transformer
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1988-004, :on 880118,control Bldg Isolation Signal Occurred from Train B Control Bldg Ventilation Sys Supply Air Duct Chlorine Detector.Caused by Failed Chlorine Detector.Sensing Element Replaced |
- on 880118,control Bldg Isolation Signal Occurred from Train B Control Bldg Ventilation Sys Supply Air Duct Chlorine Detector.Caused by Failed Chlorine Detector.Sensing Element Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000245/LER-1988-005, :on 880527,insufficient Containment Interlock Setpoint to Ensure That ECCS Pump Caviation Would Not Occur. Caused by Single Failure That Exceeds Margin of Safety. ECCS Suction Strainers Replaced |
- on 880527,insufficient Containment Interlock Setpoint to Ensure That ECCS Pump Caviation Would Not Occur. Caused by Single Failure That Exceeds Margin of Safety. ECCS Suction Strainers Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(n)(2)(v) |
| 05000423/LER-1988-005, :on 880119,cold Overpressure Protection Sys Failed to Operate During Pressure Transient.Caused by Closure of RHR Valves Due to Misuse of Design Drawings. Procedure to Use Sys Being Prepared |
- on 880119,cold Overpressure Protection Sys Failed to Operate During Pressure Transient.Caused by Closure of RHR Valves Due to Misuse of Design Drawings. Procedure to Use Sys Being Prepared
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 05000336/LER-1988-005-01, :on 880204,loss of Normal Power Occurred on Facility 1 Vital 4160 Volt Electrical Bus.Caused by Operator Error.Facility 1 Reactor Bldg Closed Cooling Water,Svc Water & Low Pressure Safety Injection Pumps Started |
- on 880204,loss of Normal Power Occurred on Facility 1 Vital 4160 Volt Electrical Bus.Caused by Operator Error.Facility 1 Reactor Bldg Closed Cooling Water,Svc Water & Low Pressure Safety Injection Pumps Started
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000245/LER-1988-005-02, :on 880527,containment Spray Interlock Setpoint Insufficient to Ensure ECCS Pump Cavitation Would Not Occur.Emergency Operating Procedures Revised to Ensure Sufficient Pressure Maintained |
- on 880527,containment Spray Interlock Setpoint Insufficient to Ensure ECCS Pump Cavitation Would Not Occur.Emergency Operating Procedures Revised to Ensure Sufficient Pressure Maintained
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000336/LER-1988-006-01, :on 880218,combined Bypass Leakage Rate Exceeded Tech Spec 3.6.1.2.C Limit.Caused by Debris Lodged in Caged Area of Valve Preventing Plug from Entering Seat. Debris Removed & Seating Surface Cleaned |
- on 880218,combined Bypass Leakage Rate Exceeded Tech Spec 3.6.1.2.C Limit.Caused by Debris Lodged in Caged Area of Valve Preventing Plug from Entering Seat. Debris Removed & Seating Surface Cleaned
| 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(n)(2)(1) |
| 05000423/LER-1988-006, :on 880130,determined That Only One Centrifugal Charging Pump Operable,In Violation of Tech Spec 3.5.2. Caused by Procedural Inadequacy,Compounded by Poor Communications.Heatup Procedure Revised |
- on 880130,determined That Only One Centrifugal Charging Pump Operable,In Violation of Tech Spec 3.5.2. Caused by Procedural Inadequacy,Compounded by Poor Communications.Heatup Procedure Revised
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000245/LER-1988-006-02, :on 880806,standby Gas Treatment Sys Initiated Automatically & Reactor Bldg Ventilation Sys Isolated Due to Spurious High Radiation Signal.Caused by Electronic Equipment Failure.Relays & Capacitors Tested |
- on 880806,standby Gas Treatment Sys Initiated Automatically & Reactor Bldg Ventilation Sys Isolated Due to Spurious High Radiation Signal.Caused by Electronic Equipment Failure.Relays & Capacitors Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1988-006, :on 880218,local Leak Rate Testing Determined Combined Bypass Leakage Exceeded Tech Spec 3.6.1.2.C Limit. Caused by Debris Being Lodged in Seat Area of Valve.Duplex Strainer Installed in Piping Sys |
- on 880218,local Leak Rate Testing Determined Combined Bypass Leakage Exceeded Tech Spec 3.6.1.2.C Limit. Caused by Debris Being Lodged in Seat Area of Valve.Duplex Strainer Installed in Piping Sys
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000245/LER-1988-007-01, :on 880908,discovered Emergency Svc Water self- Cleaning Strainer Drive Motor B 480-volt Breaker in Tripped Position.Caused by Failure of Packing Gland Follower Bolting on Strainer.Level Switch Installed |
- on 880908,discovered Emergency Svc Water self- Cleaning Strainer Drive Motor B 480-volt Breaker in Tripped Position.Caused by Failure of Packing Gland Follower Bolting on Strainer.Level Switch Installed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) |
| 05000423/LER-1988-007, :on 880203,manual Reactor Trip Initiated Due to Inoperable Digital Rpi.Caused by Equipment Failure.Display Card for Rod N-11 Warped Resulting in Pins on Card to Contact Adjacent Card.Display Card Replaced |
- on 880203,manual Reactor Trip Initiated Due to Inoperable Digital Rpi.Caused by Equipment Failure.Display Card for Rod N-11 Warped Resulting in Pins on Card to Contact Adjacent Card.Display Card Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1988-007, :on 880216,plant Entered Mode 3 W/Only One of Two Diesel Generators Operable,Violating Tech Spec Section 3.04.Caused by Personnel Error.Addl Attention Directed to Tech Spec Actions Statements & Mode Changes |
- on 880216,plant Entered Mode 3 W/Only One of Two Diesel Generators Operable,Violating Tech Spec Section 3.04.Caused by Personnel Error.Addl Attention Directed to Tech Spec Actions Statements & Mode Changes
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000336/LER-1988-008, :on 880408,control Element Assembly (CEA) 22 Dropped Into Core & on 890409,CEA 4 Dropped Into Core.Caused by Overheating of Upper Gripper Coil Due to Air Flow Blockage of Hx.Coils & Loose Wire Replaced |
- on 880408,control Element Assembly (CEA) 22 Dropped Into Core & on 890409,CEA 4 Dropped Into Core.Caused by Overheating of Upper Gripper Coil Due to Air Flow Blockage of Hx.Coils & Loose Wire Replaced
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000336/LER-1988-008-01, :on 880408,control Element Assembly (CEA) Dropped Into Core & Declared Inoperable.Caused by Overheating of Upper Gripper Coil.Control Element Drive Sys Coils for CEA Replaced |
- on 880408,control Element Assembly (CEA) Dropped Into Core & Declared Inoperable.Caused by Overheating of Upper Gripper Coil.Control Element Drive Sys Coils for CEA Replaced
| 10 CFR 50.73(a)(2)(1) |
| 05000423/LER-1988-009, :on 880210,automatic Reactor Trip Occurred. Caused by Inability of Assigned Operator to Control Feedwater to All Steam Generators Simultaneously Due to Insufficient Job Planning by Shift Supervisor |
- on 880210,automatic Reactor Trip Occurred. Caused by Inability of Assigned Operator to Control Feedwater to All Steam Generators Simultaneously Due to Insufficient Job Planning by Shift Supervisor
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1988-009-01, :on 880607,CEA Dropped Into Core.Caused by Upper Gripper Coil Failure from Overheating Condition Resulting in Degraded Coil Insulation.Total of 60 Coils Either Replaced or New Coil Stack Installed |
- on 880607,CEA Dropped Into Core.Caused by Upper Gripper Coil Failure from Overheating Condition Resulting in Degraded Coil Insulation.Total of 60 Coils Either Replaced or New Coil Stack Installed
| 10 CFR 50.73(a)(2)(1) |
| 05000336/LER-1988-010-01, :on 880921,observed That Test/Operate Switch for Each of Containment Atmosphere Gaseous Radiation Monitors Was in Test Position.Caused by Operator Error. Switch Placed in Operate Position |
- on 880921,observed That Test/Operate Switch for Each of Containment Atmosphere Gaseous Radiation Monitors Was in Test Position.Caused by Operator Error. Switch Placed in Operate Position
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000423/LER-1988-010, :on 880209,discovered That Nuclear Instrumentation Negative & Positive Rate Reactor Trips Set Nonconservatively.Caused by Personnel Failing to Properly Account for Leakage on Excore Instrumentation |
- on 880209,discovered That Nuclear Instrumentation Negative & Positive Rate Reactor Trips Set Nonconservatively.Caused by Personnel Failing to Properly Account for Leakage on Excore Instrumentation
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 05000245/LER-1988-010, :on 881115,noticed That One of Hydraulic Snubbers Had No Visible Signs of Fluid in Reservoir.Caused by Small Crack at Base of Plastic Reservoir.Visual Insp of All Snubbers in Containment Performed |
- on 881115,noticed That One of Hydraulic Snubbers Had No Visible Signs of Fluid in Reservoir.Caused by Small Crack at Base of Plastic Reservoir.Visual Insp of All Snubbers in Containment Performed
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 05000336/LER-1988-010, :on 880921,w/plant Operating in Mode 1 at 100% Power,Two Unit Process Radiation Monitors Inoperable.Caused by Personnel Error.Procedures for Radiation Monitors Functions Testing Reviewed |
- on 880921,w/plant Operating in Mode 1 at 100% Power,Two Unit Process Radiation Monitors Inoperable.Caused by Personnel Error.Procedures for Radiation Monitors Functions Testing Reviewed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) |
| 05000336/LER-1988-011, :on 881025,loss of Normal Power on Both 4160-volt Vital Ac Buses Caused Reactor Trip & ESF Actuation.Caused by Personnel Error.Procedure Rewritten to Assure Proper Use of Ground & Test Devices |
- on 881025,loss of Normal Power on Both 4160-volt Vital Ac Buses Caused Reactor Trip & ESF Actuation.Caused by Personnel Error.Procedure Rewritten to Assure Proper Use of Ground & Test Devices
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1988-011, :on 880222 & 29,containment Leakage Detection Sys Surveillances Missed.Caused by Personnel Error Re Transfer of Incorrect Surveillance Frequencies During Procedural Rev.Memo Distributed |
- on 880222 & 29,containment Leakage Detection Sys Surveillances Missed.Caused by Personnel Error Re Transfer of Incorrect Surveillance Frequencies During Procedural Rev.Memo Distributed
| 10 CFR 50.73(a)(2)(1) |
| 05000336/LER-1988-011-01, :on 881025,loss of Normal Power Due to Improper Connection of Grounding Device to Bus Side of 4,160 Volt Breaker.Caused by Personnel Error.Verification That All Equipment Responding as Required Done |
- on 881025,loss of Normal Power Due to Improper Connection of Grounding Device to Bus Side of 4,160 Volt Breaker.Caused by Personnel Error.Verification That All Equipment Responding as Required Done
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1988-012, :on 880318,fire Boundary Door Found Blocked Open by Temporary Air Hose W/O Hourly Fire Watch Patrols. Caused by Procedural Deficiency.Hose Removed & Door Closed to Reestablish Fire Barrier |
- on 880318,fire Boundary Door Found Blocked Open by Temporary Air Hose W/O Hourly Fire Watch Patrols. Caused by Procedural Deficiency.Hose Removed & Door Closed to Reestablish Fire Barrier
| 10 CFR 50.73(a)(2)(1) |
| 05000423/LER-1988-013, :on 880328,incomplete Installation to Circuits in Hydrogen Recombiner Sys Determined.Caused by Circuits Not Being Installed in Accordance W/Last Design Document.Work Completed as Described in Design Document |
- on 880328,incomplete Installation to Circuits in Hydrogen Recombiner Sys Determined.Caused by Circuits Not Being Installed in Accordance W/Last Design Document.Work Completed as Described in Design Document
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000423/LER-1988-014, :on 880413,reactor Trip Occurred Resulting from Turbine Trip.Caused by Leaking Isolation Valves on Screen Wash Duplex Strainers.Operational Procedures Updated to Provide Screen Wash Strainer Cleaning Guidance |
- on 880413,reactor Trip Occurred Resulting from Turbine Trip.Caused by Leaking Isolation Valves on Screen Wash Duplex Strainers.Operational Procedures Updated to Provide Screen Wash Strainer Cleaning Guidance
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1988-015, :on 880415,determined That Action Taken to Terminate Previously Documented Unidentified Leakage Event Improperly Performed.Caused by Personnel Error.Operations Dept Personnel Sent Internal Memo Re Event |
- on 880415,determined That Action Taken to Terminate Previously Documented Unidentified Leakage Event Improperly Performed.Caused by Personnel Error.Operations Dept Personnel Sent Internal Memo Re Event
| 10 CFR 50.73(a)(2)(1) |
| 05000423/LER-1988-016, :on 880425,control Switches for Both Trains of Motor Driven Auxiliary Feedwater Pumps & Train a Fan Left in pull-to-lock During Change Mode.Caused by Personnel Error. Tech Spec Reviewed to Ensure Operability |
- on 880425,control Switches for Both Trains of Motor Driven Auxiliary Feedwater Pumps & Train a Fan Left in pull-to-lock During Change Mode.Caused by Personnel Error. Tech Spec Reviewed to Ensure Operability
| 10 CFR 50.73(a)(2)(1) |
| 05000423/LER-1988-017, :on 880425,4 H Sample Flow Rate Estimate Not Performed Per Tech Spec 3.3.3.10.Caused by Personnel Error. Written Communications Between Depts Required When Directing Another Dept to Comply W/Tech Spec Action |
- on 880425,4 H Sample Flow Rate Estimate Not Performed Per Tech Spec 3.3.3.10.Caused by Personnel Error. Written Communications Between Depts Required When Directing Another Dept to Comply W/Tech Spec Action
| 10 CFR 50.73(a)(2)(1) |
| 05000423/LER-1988-018, :on 880519,two Reportable Events Re Control Bldg Inlet Ventilation High Radiation Control Bldg Isolation Trip Setpoint Discovered.Caused by Administrative Error. Default Values Changed to Comply W/Tech Specs |
- on 880519,two Reportable Events Re Control Bldg Inlet Ventilation High Radiation Control Bldg Isolation Trip Setpoint Discovered.Caused by Administrative Error. Default Values Changed to Comply W/Tech Specs
| 10 CFR 50.73(a)(2)(1) |
| 05000423/LER-1988-019, :on 880611,automatic Control Bldg Isolation Occurred.Caused by Personnel Error.Control Bldg Ventilation Immediately Placed in Filtered Recirculation & Correct Radiation Engineering Calibr Factor Installed |
- on 880611,automatic Control Bldg Isolation Occurred.Caused by Personnel Error.Control Bldg Ventilation Immediately Placed in Filtered Recirculation & Correct Radiation Engineering Calibr Factor Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1988-020, :on 880718,improper Bypass Breaker Surveillance Identified.Caused by Inadequate Administrative Review of Trip Actuating Device Operational Test Frequency Portion of Tech Specs.Review of Tech Specs Implemented |
- on 880718,improper Bypass Breaker Surveillance Identified.Caused by Inadequate Administrative Review of Trip Actuating Device Operational Test Frequency Portion of Tech Specs.Review of Tech Specs Implemented
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000423/LER-1988-021, :on 880819,area Temp for Environ Zone AB-06 Not Taken within Required 12 H Surveillance Interval.Caused by Personnel Error.Manual Area Temp Data Retrieval in Zone AB-06 Reinitiated |
- on 880819,area Temp for Environ Zone AB-06 Not Taken within Required 12 H Surveillance Interval.Caused by Personnel Error.Manual Area Temp Data Retrieval in Zone AB-06 Reinitiated
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) |
| 05000423/LER-1988-022, :on 880913 & 14,discovered That Hourly Fire Watch Patrol Initiated for Wrong Fire Door.Caused by Inadequate Identification of Fire Boundary Doors.Hourly Fire Watch Patrol Initiated on Subj Fire Door |
- on 880913 & 14,discovered That Hourly Fire Watch Patrol Initiated for Wrong Fire Door.Caused by Inadequate Identification of Fire Boundary Doors.Hourly Fire Watch Patrol Initiated on Subj Fire Door
| 10 CFR 50.73(a)(2)(i) |
| 05000423/LER-1988-023, :on 881006,MSIV Closed During Performance of Partial Stroke Surveillance Test,Resulting in Reactor Trip Due to Low Level in Steam Generator.Caused by Procedural Inadequacy.Surveillance Procedure Changed |
- on 881006,MSIV Closed During Performance of Partial Stroke Surveillance Test,Resulting in Reactor Trip Due to Low Level in Steam Generator.Caused by Procedural Inadequacy.Surveillance Procedure Changed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1988-024, :on 881022,manual Reactor Trip Due to Imminent Turbine Trip Due to Low Condenser Vacuum.Caused by Environ Conditions.Mods to Travelling Screen Sys Trash Trough to Increase Debris Removal Capability Implemented |
- on 881022,manual Reactor Trip Due to Imminent Turbine Trip Due to Low Condenser Vacuum.Caused by Environ Conditions.Mods to Travelling Screen Sys Trash Trough to Increase Debris Removal Capability Implemented
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1988-026, :on 881118,discovered That Certain Circumstances Could Lead to Facility Becoming Isolated from Plant Switchyard While on-line.Caused by Inadequate Plant Design.Mod Planned for Next Refueling Outage |
- on 881118,discovered That Certain Circumstances Could Lead to Facility Becoming Isolated from Plant Switchyard While on-line.Caused by Inadequate Plant Design.Mod Planned for Next Refueling Outage
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) |