| | | Reporting criterion |
|---|
| 05000245/LER-1990-001-02, :on 900126,determined That 1 H Roving Fire Patrol Established on 900125 for Two Nonfunctional Fire Barriers Penetrations Not Consistent W/Requirements of Tech Spec 3.12.F.2.Caused by Personnel Error |
- on 900126,determined That 1 H Roving Fire Patrol Established on 900125 for Two Nonfunctional Fire Barriers Penetrations Not Consistent W/Requirements of Tech Spec 3.12.F.2.Caused by Personnel Error
| 10 CFR 50.73(a)(2)(i) |
| 05000423/LER-1990-001, :on 910108,inoperable Fire Hose Stations Due to Insufficient Fire Hose Inventory.Cause Unknown for Fuel Bldg Fire Hose Rack & Procedural Inadequacy for Auxiliary Bldg Fuel Racks.Station Restored to Operable Status |
- on 910108,inoperable Fire Hose Stations Due to Insufficient Fire Hose Inventory.Cause Unknown for Fuel Bldg Fire Hose Rack & Procedural Inadequacy for Auxiliary Bldg Fuel Racks.Station Restored to Operable Status
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000336/LER-1990-001, :on 900110,discovered That Surveillances in Tech Specs for New Smoke Detectors & Suppression Sys Not Performed.Caused by Personnel Error.Fire Protection Sections of Tech Specs Updated |
- on 900110,discovered That Surveillances in Tech Specs for New Smoke Detectors & Suppression Sys Not Performed.Caused by Personnel Error.Fire Protection Sections of Tech Specs Updated
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000423/LER-1990-001-01, :on 900108,discovered That Fire Hose Racks in Fuel & Auxiliary Blgs Had Insufficient Fire Lengths to Fulfill Tech Spec Operability Requirements.Caused by Procedural Inadequacy.Caution Signs Posted |
- on 900108,discovered That Fire Hose Racks in Fuel & Auxiliary Blgs Had Insufficient Fire Lengths to Fulfill Tech Spec Operability Requirements.Caused by Procedural Inadequacy.Caution Signs Posted
| 10 CFR 50.73(a)(2)(i) |
| 05000245/LER-1990-002-01, :on 900305,main Steam Line High Flow Setpoint Determined to Be Incorrect & Nonconservative.Caused by Use of Incorrect Assumptions Based on Original Plant Design Conditions.Setpoint Corrected |
- on 900305,main Steam Line High Flow Setpoint Determined to Be Incorrect & Nonconservative.Caused by Use of Incorrect Assumptions Based on Original Plant Design Conditions.Setpoint Corrected
| 10 CFR 50.73(a)(2)(i) |
| 05000336/LER-1990-002-02, :on 900322,Tech Spec Action Statement 3.3.3.10 Not Entered for Out of Svc Stack Gas & Particulate Radiation Monitor.No Particulate Radiation Increases Detected.Caused by Personnel Error |
- on 900322,Tech Spec Action Statement 3.3.3.10 Not Entered for Out of Svc Stack Gas & Particulate Radiation Monitor.No Particulate Radiation Increases Detected.Caused by Personnel Error
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000423/LER-1990-002, :on 900109,partial Train a Containment Depressurization Actuation Signal Generated.Caused by Personnel Error.Warnings Added to Production Maint Mgt Sys for Recirculation Spray Sys Pump Breakers |
- on 900109,partial Train a Containment Depressurization Actuation Signal Generated.Caused by Personnel Error.Warnings Added to Production Maint Mgt Sys for Recirculation Spray Sys Pump Breakers
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000245/LER-1990-003, :on 900302,determined That 4-day Limiting Condition for Operation for One Emergency Power Sources, Gas Turbine Generator Exceeded.Caused by Lack of Verification of Load Requirement |
- on 900302,determined That 4-day Limiting Condition for Operation for One Emergency Power Sources, Gas Turbine Generator Exceeded.Caused by Lack of Verification of Load Requirement
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(0)(i) |
| 05000423/LER-1990-003, :on 900115,discovered That Fire Watches Not Established Prior to Removing Deluge Sys for Trains a & B Reserve Station Svc Transformers from Svc.Caused by Personnel Error.Personnel Counseled |
- on 900115,discovered That Fire Watches Not Established Prior to Removing Deluge Sys for Trains a & B Reserve Station Svc Transformers from Svc.Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(i) |
| 05000336/LER-1990-004-01, :on 900228,control Room Ventilation Sys Operated Outside Tech Specs.Caused by Inconsistency in Tech Specs.Proposed Tech Spec Change Request Submitted Re Emergency Diesel Generator Operability |
- on 900228,control Room Ventilation Sys Operated Outside Tech Specs.Caused by Inconsistency in Tech Specs.Proposed Tech Spec Change Request Submitted Re Emergency Diesel Generator Operability
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000423/LER-1990-004, :on 900115,nuclear Instrument Power Range Channel N43 Became Inoperable Due to Power Supply Failure. Caused by Computer Program 3R5 Design Inadequacy.Night Order Issued to Enter Tech Spec 4.2.1.1.1.b |
- on 900115,nuclear Instrument Power Range Channel N43 Became Inoperable Due to Power Supply Failure. Caused by Computer Program 3R5 Design Inadequacy.Night Order Issued to Enter Tech Spec 4.2.1.1.1.b
| 10 CFR 50.73(a)(2)(i) |
| 05000245/LER-1990-004-02, :on 900406,calculation Which Was Performed to Verify Reactor High Pressure Scram Setpoint Demonstrated That Existing Head Correction Nonconservative.Caused by Lack of Independent Verification of Setpoint |
- on 900406,calculation Which Was Performed to Verify Reactor High Pressure Scram Setpoint Demonstrated That Existing Head Correction Nonconservative.Caused by Lack of Independent Verification of Setpoint
| 10 CFR 50.73(a)(2)(i) |
| 05000336/LER-1990-004, :on 900228,Unit Operated Outside of Tech Specs for Control Room Air Conditioning Sys.Caused by Inconsistency in Tech Specs.Tech Spec Change Request Approved |
- on 900228,Unit Operated Outside of Tech Specs for Control Room Air Conditioning Sys.Caused by Inconsistency in Tech Specs.Tech Spec Change Request Approved
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) |
| 05000336/LER-1990-005, :on 900503,notified of Potential High Energy Line Break Via as Sys in Safety Related Areas.Caused by Inaccurate Conclusions Drawn from 1973 Rept.As Sys Removed from Svc & Plant Mods Initiated |
- on 900503,notified of Potential High Energy Line Break Via as Sys in Safety Related Areas.Caused by Inaccurate Conclusions Drawn from 1973 Rept.As Sys Removed from Svc & Plant Mods Initiated
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000336/LER-1990-005-02, :on 900503,identified Potential for High Energy Line Break in Auxiliary Steam Sys That Could Degrade Plant Areas Determined as Mild Environs.Probably Caused by Incorrect Conclusions from Analysis in 1973 |
- on 900503,identified Potential for High Energy Line Break in Auxiliary Steam Sys That Could Degrade Plant Areas Determined as Mild Environs.Probably Caused by Incorrect Conclusions from Analysis in 1973
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vi) |
| 05000423/LER-1990-005, :on 900118,manual Plant Trip Initiated in Anticipation of Automatic Trip on lo-lo Level in All Four Steam Generators.Caused by Loss of Preload on Coupling Blocks from Personnel Error.Procedure Revised |
- on 900118,manual Plant Trip Initiated in Anticipation of Automatic Trip on lo-lo Level in All Four Steam Generators.Caused by Loss of Preload on Coupling Blocks from Personnel Error.Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000245/LER-1990-005-01, :on 900411,determined That Daily Surveillance Greater than 6 H from Previous Days Surveillance.Caused by Combination of Factors Including Administrative Deficiency. Operations Dept Logs Revised |
- on 900411,determined That Daily Surveillance Greater than 6 H from Previous Days Surveillance.Caused by Combination of Factors Including Administrative Deficiency. Operations Dept Logs Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000245/LER-1990-006-01, :on 900424,determined That Gas Turbine Encl Not Included in Monthly Surveillance for Nonsupervised Circuits. Caused by Personnel Error.Gas Turbine Fire Detection Surveillance Changed to Monthly |
- on 900424,determined That Gas Turbine Encl Not Included in Monthly Surveillance for Nonsupervised Circuits. Caused by Personnel Error.Gas Turbine Fire Detection Surveillance Changed to Monthly
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000423/LER-1990-006, :on 900118,chemistry Dept Determined 6-month Interval Tech Spec for Average Disintegration Energy Determination Not Met.Caused by Inappropriate Appliance of Surveillance Interval.Addl Controls Placed |
- on 900118,chemistry Dept Determined 6-month Interval Tech Spec for Average Disintegration Energy Determination Not Met.Caused by Inappropriate Appliance of Surveillance Interval.Addl Controls Placed
| 10 CFR 50.73(a)(2)(i) |
| 05000336/LER-1990-006-02, :on 900508,reactor Manually Tripped When Decreasing Levels Noted in Steam Generator 1 & Feedwater Regulating Valve Indicated Full Open.Caused by Valve Stem Separating from Plug.Feedwater Flow Restored |
- on 900508,reactor Manually Tripped When Decreasing Levels Noted in Steam Generator 1 & Feedwater Regulating Valve Indicated Full Open.Caused by Valve Stem Separating from Plug.Feedwater Flow Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) |
| 05000245/LER-1990-007-01, :on 900512,determined That One Emergency Power Source Did Not Have Sufficient Capacity for Accident Loading Conditions.Gas Turbine Generator Declared Inoperable & Orderly Reactor Shutdown Initiated |
- on 900512,determined That One Emergency Power Source Did Not Have Sufficient Capacity for Accident Loading Conditions.Gas Turbine Generator Declared Inoperable & Orderly Reactor Shutdown Initiated
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) |
| 05000336/LER-1990-007, :on 900611,discovered Missed Surveillance Prior to Entering Mode 4 |
- on 900611,discovered Missed Surveillance Prior to Entering Mode 4
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000336/LER-1990-007-02, :on 900611,discovered That Surveillance Procedure 2609E Re Encl Bldg Filtration Sys Testing - Refueling Not Performed Prior to Entering Mode 4.Caused by Personnel Error.Missed Surveillance Performed |
- on 900611,discovered That Surveillance Procedure 2609E Re Encl Bldg Filtration Sys Testing - Refueling Not Performed Prior to Entering Mode 4.Caused by Personnel Error.Missed Surveillance Performed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000423/LER-1990-007, :on 900125,discovered That Tech Spec Surveillance Did Not Verify Load Shedding of Five Compressors.Caused by Procedural Inadequacy & Personnel Error.Surveillance Procedure Revised |
- on 900125,discovered That Tech Spec Surveillance Did Not Verify Load Shedding of Five Compressors.Caused by Procedural Inadequacy & Personnel Error.Surveillance Procedure Revised
| 10 CFR 50.73(a)(2)(i) |
| 05000245/LER-1990-008-01, :on 900531,determined That Fuel Thermal Limit Exceeded Tech Spec Limit.Caused by Underestimation of Xenon Transient That Resulted from Power Reduction.Refresher Course Planned for Personnel |
- on 900531,determined That Fuel Thermal Limit Exceeded Tech Spec Limit.Caused by Underestimation of Xenon Transient That Resulted from Power Reduction.Refresher Course Planned for Personnel
| 10 CFR 50.73(a)(2)(i) |
| 05000336/LER-1990-008-02, :on 900620,determined That Grab Sample of Unit Stack Gas Not Taken.Caused by Lack of Communication Between Personnel.Grab Sample Obtained & Analyzed |
- on 900620,determined That Grab Sample of Unit Stack Gas Not Taken.Caused by Lack of Communication Between Personnel.Grab Sample Obtained & Analyzed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000245/LER-1990-009-01, :on 900511,determined That House Heating Steam Sys Could Potentially Degrade Environ Classified, Eeq Mild Environs. Caused by Incorrect Conclusion Drawn from 1973 Study.Plant Mods Implemented |
- on 900511,determined That House Heating Steam Sys Could Potentially Degrade Environ Classified, Eeq Mild Environs. Caused by Incorrect Conclusion Drawn from 1973 Study.Plant Mods Implemented
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000336/LER-1990-009-02, :on 900617,inadvertent Partial Actuation of Train B of Enclosure Bldg Filtration Sys Occurred.Root Cause Not Determined.No Corrective Actions Recommended Until Further Testing & Troubleshooting Performed |
- on 900617,inadvertent Partial Actuation of Train B of Enclosure Bldg Filtration Sys Occurred.Root Cause Not Determined.No Corrective Actions Recommended Until Further Testing & Troubleshooting Performed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1990-009-01, :on 900617,facility Experienced Inadvertent Partial Actuation of Train B of Auxiliary Exhaust Actuation Sys.Cause Undetermined.Two Addl Actuations Occurred on 900711 |
- on 900617,facility Experienced Inadvertent Partial Actuation of Train B of Auxiliary Exhaust Actuation Sys.Cause Undetermined.Two Addl Actuations Occurred on 900711
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1990-009, :on 900309,automatic Turbine Trip W/Subsequent Reactor Trip Occurred Due to High Stator Cooling Water Temp. Caused by Failure of Mechanical Linkage on Fisher & Portor Controller.Controller Replaced W/Spare |
- on 900309,automatic Turbine Trip W/Subsequent Reactor Trip Occurred Due to High Stator Cooling Water Temp. Caused by Failure of Mechanical Linkage on Fisher & Portor Controller.Controller Replaced W/Spare
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(viii)(B) |
| 05000245/LER-1990-010-01, :on 891223,EEQ Barriers Violated W/Switchgear Area & Heating & Ventilation Room Mild Environ & Turbine Deck Had Potential Harsh Environ.Caused by Lack of Formal guidance.Long-term Program Developed |
- on 891223,EEQ Barriers Violated W/Switchgear Area & Heating & Ventilation Room Mild Environ & Turbine Deck Had Potential Harsh Environ.Caused by Lack of Formal guidance.Long-term Program Developed
| |
| 05000423/LER-1990-010, :on 900319,both Trains of Auxiliary Bldg Filters Became Inoperable When Train B Circuit Breaker Motor Failed & Train a Filter Removed from Svc.Caused by Fatigue Failure in Breaker Spring.Filter Work Stopped |
- on 900319,both Trains of Auxiliary Bldg Filters Became Inoperable When Train B Circuit Breaker Motor Failed & Train a Filter Removed from Svc.Caused by Fatigue Failure in Breaker Spring.Filter Work Stopped
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000336/LER-1990-010-02, :on 900621,door Identified in Configuration Not Consistent W/Bechtel Design Drawings During High Energy Line Review.Caused by Lack of Knowledge of Requirements.Double Door Reinforced |
- on 900621,door Identified in Configuration Not Consistent W/Bechtel Design Drawings During High Energy Line Review.Caused by Lack of Knowledge of Requirements.Double Door Reinforced
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000336/LER-1990-010-01, :on 900621,door Identified as Being in Configuration Not Consistent W/Bechtel Design Drawings Due to Lack of Knowledge of HELB Requirements for Area |
- on 900621,door Identified as Being in Configuration Not Consistent W/Bechtel Design Drawings Due to Lack of Knowledge of HELB Requirements for Area
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000245/LER-1990-011-01, :on 900720,Tech Spec Fire Door Found Blocked Open & Unguarded by Fire Watch.Caused by Personnel Error. Personnel Cautioned to Be Aware of Potential for Impacting Tech Spec Barrier Requirements |
- on 900720,Tech Spec Fire Door Found Blocked Open & Unguarded by Fire Watch.Caused by Personnel Error. Personnel Cautioned to Be Aware of Potential for Impacting Tech Spec Barrier Requirements
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) |
| 05000423/LER-1990-011, :on 900330,manual Reactor Trip Initiated Due to Anticipated Turbine Trip from Loss of Condenser Vacuum. Caused by Failure to Collect Debris from Manual Screen Washing.Elbow Replaced & Screen Wash Restored |
- on 900330,manual Reactor Trip Initiated Due to Anticipated Turbine Trip from Loss of Condenser Vacuum. Caused by Failure to Collect Debris from Manual Screen Washing.Elbow Replaced & Screen Wash Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1990-012-02, :on 900827,automatic Reactor Trip Occurred During Bypass Switch Operations.Caused by Operator Error. Procedure Sp 2601D Revised to Incorporate Separate Section on Performing Calibrs |
- on 900827,automatic Reactor Trip Occurred During Bypass Switch Operations.Caused by Operator Error. Procedure Sp 2601D Revised to Incorporate Separate Section on Performing Calibrs
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000245/LER-1990-012-01, :on 900813,determined That hi-hi Trip Settings on Both Offgas Instrument Drawers Set in Nonconservative Direction & Exceeded Tech Spec 3.8.B.1.Caused by Failure to Recognize Significance of Response Factor |
- on 900813,determined That hi-hi Trip Settings on Both Offgas Instrument Drawers Set in Nonconservative Direction & Exceeded Tech Spec 3.8.B.1.Caused by Failure to Recognize Significance of Response Factor
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |
| 05000423/LER-1990-012, :on 900406,review of Steam Generator Blowdown Monitor High Radiation Alarm Setpoint Revealed That Setpoint Was Nonconservative.Caused by Administrative Deficiency. Correct Setpoint Installed |
- on 900406,review of Steam Generator Blowdown Monitor High Radiation Alarm Setpoint Revealed That Setpoint Was Nonconservative.Caused by Administrative Deficiency. Correct Setpoint Installed
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000245/LER-1990-013, :on 900806,standby Gas Treatment Sys Initiation Occurred Due to Inadvertent de-energization of Power Supply to Channel 2 Process Radiation Monitoring Sys.Power Restored to Channel 2 & Initiation Trip Logic Reset |
- on 900806,standby Gas Treatment Sys Initiation Occurred Due to Inadvertent de-energization of Power Supply to Channel 2 Process Radiation Monitoring Sys.Power Restored to Channel 2 & Initiation Trip Logic Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1990-013, :on 900416,manual Reactor Trip Occurred Due to Imminent Loss of Condenser Vacuum.Caused by Inadequate Administrative Guidance.Personnel Instructed to Closely Monitor Trash Rack Water Levels |
- on 900416,manual Reactor Trip Occurred Due to Imminent Loss of Condenser Vacuum.Caused by Inadequate Administrative Guidance.Personnel Instructed to Closely Monitor Trash Rack Water Levels
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1990-014-02, :on 901010,main Steam Safety Valve Setpoint Drift Discovered During as-found Simmer Test |
- on 901010,main Steam Safety Valve Setpoint Drift Discovered During as-found Simmer Test
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000245/LER-1990-014-01, :on 900907,inconsistency Between Procedural & Design Parameters Associated W/Lpci HX Flow Rates Identified.Caused by Inadequate Evaluation of Original Plant Design Documentation |
- on 900907,inconsistency Between Procedural & Design Parameters Associated W/Lpci HX Flow Rates Identified.Caused by Inadequate Evaluation of Original Plant Design Documentation
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000423/LER-1990-014, :on 900519,manual Reactor Trip Initiated as Result of Anticipated Turbine Trip Due to Condenser Vacuum. Caused by Design Deficiency in That Traveling Screen Capacity Inadequate.Traveling Screen Modified |
- on 900519,manual Reactor Trip Initiated as Result of Anticipated Turbine Trip Due to Condenser Vacuum. Caused by Design Deficiency in That Traveling Screen Capacity Inadequate.Traveling Screen Modified
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1990-015, :on 900512,feedwater Isolation Occurred While Opening Msivs.Caused by MSIV 2 Opening Faster than Other Msivs,Resulting in Swell in Steam Generator 2.Steam Generator Level Restored to Normal |
- on 900512,feedwater Isolation Occurred While Opening Msivs.Caused by MSIV 2 Opening Faster than Other Msivs,Resulting in Swell in Steam Generator 2.Steam Generator Level Restored to Normal
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1990-015, :on 900919,unit Experienced Inadvertent Isolation of Containment Purge Valves.On 900920,unit Experienced Actuation of SI Actuation Sys.Caused by Operator Error.Technician Counseled |
- on 900919,unit Experienced Inadvertent Isolation of Containment Purge Valves.On 900920,unit Experienced Actuation of SI Actuation Sys.Caused by Operator Error.Technician Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1990-015-02, :on 900919,containment Purge Valves 2-AC-4, 2-AC-5,2-AC-6 & 2-AC-7 Inadvertently Isolated |
- on 900919,containment Purge Valves 2-AC-4, 2-AC-5,2-AC-6 & 2-AC-7 Inadvertently Isolated
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) |
| 05000245/LER-1990-015-01, :on 900914,reactor Scram Occurred on Low Reactor Water Level After Feedwater Regulating Valves Began to Close |
- on 900914,reactor Scram Occurred on Low Reactor Water Level After Feedwater Regulating Valves Began to Close
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1990-016, :on 901009,inadvertent ESAS Actuation of Containment Purge Isolation Sys Occurred.Caused by Loose Ground Wire in Control Room Cabinet S14D.Ground Wire Termination Tightened |
- on 901009,inadvertent ESAS Actuation of Containment Purge Isolation Sys Occurred.Caused by Loose Ground Wire in Control Room Cabinet S14D.Ground Wire Termination Tightened
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000336/LER-1990-016-02, :on 901009,inadvertent ESAS Actuation Occurred in Violation of Tech Specs |
- on 901009,inadvertent ESAS Actuation Occurred in Violation of Tech Specs
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |