| | | Reporting criterion |
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| 05000272/LER-1988-001, :on 880211,improper Anchoring of Three Diesel Generator Day Tanks to Supporting Steel Beam Foundation Identified.Caused by Inadequate Design & Design Review. Tanks Weld Anchored to Steel Beam Foundation |
- on 880211,improper Anchoring of Three Diesel Generator Day Tanks to Supporting Steel Beam Foundation Identified.Caused by Inadequate Design & Design Review. Tanks Weld Anchored to Steel Beam Foundation
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000311/LER-1988-001, :on 880112,chemistry Sample Not Taken on Time, Per Tech Spec Action Statement 3.3.3.8.Caused by Inadequate Administrative Controls.New Form to Help Track Sampling Requirements Issued & Procedures Reviewed |
- on 880112,chemistry Sample Not Taken on Time, Per Tech Spec Action Statement 3.3.3.8.Caused by Inadequate Administrative Controls.New Form to Help Track Sampling Requirements Issued & Procedures Reviewed
| |
| 05000272/LER-1988-001-02, :on 880211,diesel Generator Day Tanks Found Not Properly Anchored to Supporting Steel Foundation.Cause Not Determined.Tanks Weld Anchored to Wide Flange Steel Beam Foundation on 880212 |
- on 880211,diesel Generator Day Tanks Found Not Properly Anchored to Supporting Steel Foundation.Cause Not Determined.Tanks Weld Anchored to Wide Flange Steel Beam Foundation on 880212
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) |
| 05000311/LER-1988-002, :on 880113,during Routine Tour of Svc Water Intake Structure,Operator Observed Excessive Leakage from Pump 22.Caused by Equipment Malfunction.Pump Replaced W/Spare Pump |
- on 880113,during Routine Tour of Svc Water Intake Structure,Operator Observed Excessive Leakage from Pump 22.Caused by Equipment Malfunction.Pump Replaced W/Spare Pump
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000272/LER-1988-002-03, :on 880218,control Room Indication Identified to Register Approx 5 F Above Wide Range RCS Indication. Caused by Mfg Not Identifying Component Design Mod in Specs |
- on 880218,control Room Indication Identified to Register Approx 5 F Above Wide Range RCS Indication. Caused by Mfg Not Identifying Component Design Mod in Specs
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000272/LER-1988-003-02, :on 880224,reactor Trip Occurred on False intermediate-range High Flux Signal.Caused by Personnel Error.Maint Mgt Completed Review of Circumstances Surrounding Event.Individual Counseled |
- on 880224,reactor Trip Occurred on False intermediate-range High Flux Signal.Caused by Personnel Error.Maint Mgt Completed Review of Circumstances Surrounding Event.Individual Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) |
| 05000311/LER-1988-003, :on 880208,Tech Spec Table 3.3-12 Action 27 Not Complied With.Caused by Personnel Error Associated W/ Inadequate Communications & Training.Operations Dept Mgt Reviewed Event & Procedures Will Be Modified |
- on 880208,Tech Spec Table 3.3-12 Action 27 Not Complied With.Caused by Personnel Error Associated W/ Inadequate Communications & Training.Operations Dept Mgt Reviewed Event & Procedures Will Be Modified
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-004, :on 870312,generator Turbine/Reactor Trip Occurred.Caused by Loss of Generator Excitation Due to Bumped Transfer.Relays Responsible for Subj Occurrence Checked & New Operating Curves Issued |
- on 870312,generator Turbine/Reactor Trip Occurred.Caused by Loss of Generator Excitation Due to Bumped Transfer.Relays Responsible for Subj Occurrence Checked & New Operating Curves Issued
| |
| 05000272/LER-1988-004-01, :on 880222,change from Mode 3 to Mode 2 Conducted W/Containment Hydrogen Analyzer Technically Inoperable Due to Missed Environ Qualification Surveillance. Caused by Ineffective Administrative Control |
- on 880222,change from Mode 3 to Mode 2 Conducted W/Containment Hydrogen Analyzer Technically Inoperable Due to Missed Environ Qualification Surveillance. Caused by Ineffective Administrative Control
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |
| 05000272/LER-1988-005-01, :on 880307,identified Tech Spec Surveillance 4.7.8.1.2.a,sealed Source Leak Check Not Performed within 6 Months from Prior Surveillance.Caused by Inadequate Administrative Controls Associated W/Computer Sys |
- on 880307,identified Tech Spec Surveillance 4.7.8.1.2.a,sealed Source Leak Check Not Performed within 6 Months from Prior Surveillance.Caused by Inadequate Administrative Controls Associated W/Computer Sys
| |
| 05000272/LER-1988-005, Forwards LER 88-005-00 | Forwards LER 88-005-00 | 10 CFR 50.73(a)(2) |
| 05000311/LER-1988-005-02, :on 880404,discovered That Hourly Roving Fire Watch Was 23 Minutes Late for 122 Ft Auxiliary Bldg Area. Caused by Personnel Error.Performance of Hourly Fire Watch Surveillances Stressed |
- on 880404,discovered That Hourly Roving Fire Watch Was 23 Minutes Late for 122 Ft Auxiliary Bldg Area. Caused by Personnel Error.Performance of Hourly Fire Watch Surveillances Stressed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000272/LER-1988-006, :on 880318,10CFR50 App R Cable Design Deficiency Identified.Caused by Design Error.Cable Will Be re-routed During Next Refueling Outage.Roving Fire Watch Will Be Continued Until Completion of Repair |
- on 880318,10CFR50 App R Cable Design Deficiency Identified.Caused by Design Error.Cable Will Be re-routed During Next Refueling Outage.Roving Fire Watch Will Be Continued Until Completion of Repair
| 10 CFR 50.73(a)(2)(vi) 10 CFR 50.73(a)(2) |
| 05000311/LER-1988-006-02, :on 880421,reactor Trip Occurred.Caused by Maint Technician Not Using Proper Procedure When Repairing Leak on Low Pressure Side of Reactor Coolant Loop 23 Flow Channel II Transmitter.Event Reviewed |
- on 880421,reactor Trip Occurred.Caused by Maint Technician Not Using Proper Procedure When Repairing Leak on Low Pressure Side of Reactor Coolant Loop 23 Flow Channel II Transmitter.Event Reviewed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000272/LER-1988-007, :on 880323,several Fire Dampers Identified as Not Fire Rated & Duct Sections Penetrating Barriers Found W/O Approved Fire Barrier Coating.Caused by Personnel Error in Engineering Review of Procurement Documents |
- on 880323,several Fire Dampers Identified as Not Fire Rated & Duct Sections Penetrating Barriers Found W/O Approved Fire Barrier Coating.Caused by Personnel Error in Engineering Review of Procurement Documents
| |
| 05000311/LER-1988-007-02, :on 880422,reactor Trip Occurred Due to Turbine Trip as Result of Steam Generator hi-hi Level.Caused by electro-hydraulic Control (EHC) Equipment Problems.Ehc Rate Amplifier Card Replaced & Successfully Tested |
- on 880422,reactor Trip Occurred Due to Turbine Trip as Result of Steam Generator hi-hi Level.Caused by electro-hydraulic Control (EHC) Equipment Problems.Ehc Rate Amplifier Card Replaced & Successfully Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000272/LER-1988-008, :on 880324,0404 & 15,discovered That Hourly Roving Fire Watches Were Late Between 10 & 32 Minutes for Four Areas.Caused by Personnel Error.Time Period Between Roving Fire Watches Reduced |
- on 880324,0404 & 15,discovered That Hourly Roving Fire Watches Were Late Between 10 & 32 Minutes for Four Areas.Caused by Personnel Error.Time Period Between Roving Fire Watches Reduced
| 10 CFR 50.73(a)(2)(i) |
| 05000311/LER-1988-008-02, :on 880426,discovered That Valve 2FP147 Not Surveilled.Caused by Personnel Error.Procedure Revised to Address Requirement to Surveill the 2FP147 Valve & 2FP148 Check Valve at Same Time |
- on 880426,discovered That Valve 2FP147 Not Surveilled.Caused by Personnel Error.Procedure Revised to Address Requirement to Surveill the 2FP147 Valve & 2FP148 Check Valve at Same Time
| 10 CFR 50.73(a)(2) |
| 05000272/LER-1988-009, :on 880330,electro-hydraulic (Eh) Pumps 11 & 12 Failed to Automatically Start.Caused by lo-lo Condition in Eh Control Oil Reservoir.Mechanical Level Indicator Replaced W/Dipstick to Provide Local Level Indication |
- on 880330,electro-hydraulic (Eh) Pumps 11 & 12 Failed to Automatically Start.Caused by lo-lo Condition in Eh Control Oil Reservoir.Mechanical Level Indicator Replaced W/Dipstick to Provide Local Level Indication
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000311/LER-1988-009-02, :on 880513,reactor Trip Occurred.Caused by Control Rod 1D3 Drop Resulting in Negative Rate Trip.Testing for Probable Causes of Control Rod Drop Completed |
- on 880513,reactor Trip Occurred.Caused by Control Rod 1D3 Drop Resulting in Negative Rate Trip.Testing for Probable Causes of Control Rod Drop Completed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000272/LER-1988-010-01, :on 880519,discovered That Diesel Generator Area Cardox Fire Suppression Sys PE Relay May Not Be Class 1E Seismically Qualified.Caused by Inadequate Design. Procedure Mods Made Re Resetting Relay |
- on 880519,discovered That Diesel Generator Area Cardox Fire Suppression Sys PE Relay May Not Be Class 1E Seismically Qualified.Caused by Inadequate Design. Procedure Mods Made Re Resetting Relay
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor |
| 05000311/LER-1988-010-02, :on 880509,identified That for 37 Electrical Circuits Penetrating Containment,Backup Overcurrent Protection Device Would Not Operate.Caused by Inadequate Design Review.Detailed Calculation Prepared |
- on 880509,identified That for 37 Electrical Circuits Penetrating Containment,Backup Overcurrent Protection Device Would Not Operate.Caused by Inadequate Design Review.Detailed Calculation Prepared
| |
| 05000272/LER-1988-011-02, :on 880517,monthly Tech Spec Surveillance 4.0.5 for Apr Not Performed for Valve 12SW39.Caused by Personnel Error.Programmatic Review Conducted to Determine Progammatic Improvements Needed |
- on 880517,monthly Tech Spec Surveillance 4.0.5 for Apr Not Performed for Valve 12SW39.Caused by Personnel Error.Programmatic Review Conducted to Determine Progammatic Improvements Needed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-011-01, :on 880523,Tech Spec Surveillance 4.7.10.1.1.c Late Due to Inadequate Communications Between Nuclear Fire Dept Supervision & Station Mgt.Ltr Issued to Station Supervision Addressing Adequate Communications |
- on 880523,Tech Spec Surveillance 4.7.10.1.1.c Late Due to Inadequate Communications Between Nuclear Fire Dept Supervision & Station Mgt.Ltr Issued to Station Supervision Addressing Adequate Communications
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000272/LER-1988-012-02, :on 880712,Tech Spec 3.7.9 Noncompliance Involving Missing Snubber Downstream from 1SJ13 Valve Occurred.Caused by Inadequate Administrative Control Over Design Change Work.New Snubber Installed |
- on 880712,Tech Spec 3.7.9 Noncompliance Involving Missing Snubber Downstream from 1SJ13 Valve Occurred.Caused by Inadequate Administrative Control Over Design Change Work.New Snubber Installed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-012-01, :on 880618,Tech Spec Action 3.5.2 Entered W/ Both Centrifugal Charging Pumps (CCP) Declared Inoperable. Caused by Individaul CCP Equipment Problems.Ccp Breaker Replaced |
- on 880618,Tech Spec Action 3.5.2 Entered W/ Both Centrifugal Charging Pumps (CCP) Declared Inoperable. Caused by Individaul CCP Equipment Problems.Ccp Breaker Replaced
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-013-01, :on 880615,control Room Overhead Annunciator, Sec Trouble Alarm,Annunciated & on 880616,Tech Spec 3.3.2.1.b,Action 13 Entered in Support of 2B Sec Chassis Replacement.Caused by Circuit Boards Failure |
- on 880615,control Room Overhead Annunciator, Sec Trouble Alarm,Annunciated & on 880616,Tech Spec 3.3.2.1.b,Action 13 Entered in Support of 2B Sec Chassis Replacement.Caused by Circuit Boards Failure
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000272/LER-1988-013-02, :on 880812,several Penetration Seals Did Not Conform to Correct Color or Cell Structure as Recommended by Silicone Foam Mfg to Provide Necessary Fire Protection. Caused by Inadequate Procedural Guidance |
- on 880812,several Penetration Seals Did Not Conform to Correct Color or Cell Structure as Recommended by Silicone Foam Mfg to Provide Necessary Fire Protection. Caused by Inadequate Procedural Guidance
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-014, :on 880622,reactor Trip & Safety Injection Occurred.Caused by Failure of C Vital Instrument Bus Inverter.Inverter Repaired.Design Change Initiated to Delete Reactor Trip Logic & to Replace Inverters |
- on 880622,reactor Trip & Safety Injection Occurred.Caused by Failure of C Vital Instrument Bus Inverter.Inverter Repaired.Design Change Initiated to Delete Reactor Trip Logic & to Replace Inverters
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000272/LER-1988-014-01, :on 880830,QA Review Identified Several Missed Fire Barrier Penetration Surveillances.Caused by Inadequate Administrative Controls.Work Schedule Reviewed Monthly by Site Protection Supervisor |
- on 880830,QA Review Identified Several Missed Fire Barrier Penetration Surveillances.Caused by Inadequate Administrative Controls.Work Schedule Reviewed Monthly by Site Protection Supervisor
| 10 CFR 50.73(a)(2)(i) |
| 05000272/LER-1988-015-02, :on 880831,reactor/turbine Trip Occurred Due to Low Auto Stop Oil Sys Pressure.Caused by Equipment Problem. Functional Testing of Various Turbine Trip Mechanisms Completed Satisfactorily |
- on 880831,reactor/turbine Trip Occurred Due to Low Auto Stop Oil Sys Pressure.Caused by Equipment Problem. Functional Testing of Various Turbine Trip Mechanisms Completed Satisfactorily
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000311/LER-1988-015-01, :on 880726,component Cooling HX 21 Declared Inoperable Due to Svc Water Leakage from Downstream Piping Resulting in Inoperability of HX 22.Caused by Equipment Problems.Leakage Repaired |
- on 880726,component Cooling HX 21 Declared Inoperable Due to Svc Water Leakage from Downstream Piping Resulting in Inoperability of HX 22.Caused by Equipment Problems.Leakage Repaired
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-016-01, :on 880730,reactor Trip Occurred.Caused by Equipment Problems Associated W/Vital Instrument Bus C Inverter.Design Change to Delete Specified Reactor Trip Logic Initiated |
- on 880730,reactor Trip Occurred.Caused by Equipment Problems Associated W/Vital Instrument Bus C Inverter.Design Change to Delete Specified Reactor Trip Logic Initiated
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000272/LER-1988-016-02, :on 880909,twenty-nine Air Balance Model 119 Dampers in Units 1 & 2 Fire Areas Not Surveilled as Required by Tech Spec.Caused by Inadequate Administrative Controls. Engineers Counseled & Requirements Reviewed |
- on 880909,twenty-nine Air Balance Model 119 Dampers in Units 1 & 2 Fire Areas Not Surveilled as Required by Tech Spec.Caused by Inadequate Administrative Controls. Engineers Counseled & Requirements Reviewed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000272/LER-1988-017, :880919,steam Flow Channels I & II for Steam Generators 12 & 14 & Channel II for Steam Generator 13 Declared Inoperable Due to Low Reading.Cause Not Determined. Steam Flow Channel Recalibr |
- 880919,steam Flow Channels I & II for Steam Generators 12 & 14 & Channel II for Steam Generator 13 Declared Inoperable Due to Low Reading.Cause Not Determined. Steam Flow Channel Recalibr
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-017-01, :on 880831,reactor Trip Occurred After Turbine Trip as Result of Steam Generator hi-hi Level.Caused by Design/Equipment Problem Associated w/23BF19 Valve.Maint Requirements Will Be Modified |
- on 880831,reactor Trip Occurred After Turbine Trip as Result of Steam Generator hi-hi Level.Caused by Design/Equipment Problem Associated w/23BF19 Valve.Maint Requirements Will Be Modified
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000272/LER-1988-017-02, :on 880919,Steam Flow Channels I & II for 12 & 14 Steam Generators Declared Inoperable.Channels Were Reading -5% Low.Investigation of Root Cause Continuing.Steam Flow Channels Recalibr |
- on 880919,Steam Flow Channels I & II for 12 & 14 Steam Generators Declared Inoperable.Channels Were Reading -5% Low.Investigation of Root Cause Continuing.Steam Flow Channels Recalibr
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-018-01, :on 880914,discovered That Plant Vent Tritium Grab Samples Not Taken Between 880913-15.Refueling Canal Flooded on 880913 in Support of Refueling Efforts.Caused by Inadequate Administrative Controls |
- on 880914,discovered That Plant Vent Tritium Grab Samples Not Taken Between 880913-15.Refueling Canal Flooded on 880913 in Support of Refueling Efforts.Caused by Inadequate Administrative Controls
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000272/LER-1988-018-02, :on 881001,hourly Roving Fire Watch Patrol for Several Areas Not Completed within 1 H (Between 22 & 82 Minutes Late).Caused by Equipment Problem Associated W/ Security Sys Computer.Fire Watch Posted |
- on 881001,hourly Roving Fire Watch Patrol for Several Areas Not Completed within 1 H (Between 22 & 82 Minutes Late).Caused by Equipment Problem Associated W/ Security Sys Computer.Fire Watch Posted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000272/LER-1988-018, :on 871209,personnel Determined That Lead/Lag & Derivative Amplifiers in Process & Protection Control Sys Incorrectly Calibr.Caused by Procedural Inadequacy. Procedures Revised |
- on 871209,personnel Determined That Lead/Lag & Derivative Amplifiers in Process & Protection Control Sys Incorrectly Calibr.Caused by Procedural Inadequacy. Procedures Revised
| 10 CFR 50.73(a)(2) |
| 05000272/LER-1988-019-02, :on 880926,discovered That Hourly Roving Fire Watch Patrol for Several Areas Not Completed within H.Caused by Personnel Error.Corrective Disciplinary Action Taken Against Personnel Involved |
- on 880926,discovered That Hourly Roving Fire Watch Patrol for Several Areas Not Completed within H.Caused by Personnel Error.Corrective Disciplinary Action Taken Against Personnel Involved
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-019-01, :on 881005,several Tubes Found Degraded in Steam Generator Tubes 22 & 24.Caused by Steam Generator Design.Emergency License Amend Issued to Modify Steam Generator Tube Sampling Method |
- on 881005,several Tubes Found Degraded in Steam Generator Tubes 22 & 24.Caused by Steam Generator Design.Emergency License Amend Issued to Modify Steam Generator Tube Sampling Method
| |
| 05000272/LER-1988-020-02, :on 881117,two Trains of Engineering Safety Sys Made Inoperable by Common Mode Following Annunciation of Air Particulate Detector Trouble Alarm.Root Cause Attributed to Partially Clogged Bypass Line |
- on 881117,two Trains of Engineering Safety Sys Made Inoperable by Common Mode Following Annunciation of Air Particulate Detector Trouble Alarm.Root Cause Attributed to Partially Clogged Bypass Line
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000272/LER-1988-020, :on 861108,Tech Spec Surveillance 4.7.7.1.a Not Completed within Specified Time.Caused by Personnel Error.Supervisors Counseled About Failure to Take Necessary Steps to Ensure Performance of Surveillance |
- on 861108,Tech Spec Surveillance 4.7.7.1.a Not Completed within Specified Time.Caused by Personnel Error.Supervisors Counseled About Failure to Take Necessary Steps to Ensure Performance of Surveillance
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-020-01, :on 881001,fuel Assembly Insert Changeouts in Fuel Handling Building (Fhb) Conducted W/Fhb Exhaust Fan 21 Inoperable.Caused by Personnel Error.Std Tagout of Fhb Ventilation Sys Will Be Prepared |
- on 881001,fuel Assembly Insert Changeouts in Fuel Handling Building (Fhb) Conducted W/Fhb Exhaust Fan 21 Inoperable.Caused by Personnel Error.Std Tagout of Fhb Ventilation Sys Will Be Prepared
| |
| 05000311/LER-1988-021-01, :on 881031,hourly Roving Fire Watch Patrol for Several Areas Not Completed within 1h.Caused by Personnel Error.Personnel Given Medical Fitness for Duty Exam & Site Protection Dept Mgt Reviewed Event |
- on 881031,hourly Roving Fire Watch Patrol for Several Areas Not Completed within 1h.Caused by Personnel Error.Personnel Given Medical Fitness for Duty Exam & Site Protection Dept Mgt Reviewed Event
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000311/LER-1988-022-01, :on 881022 & 23,visual Exam of Containment Spray Valves 21 & 22CS6 Revealed Cracks in Valve Casting. Cause Attributed to Transgranular Stress Corrosion Cracking. Valves Temporarily Replaced W/Piping Spools |
- on 881022 & 23,visual Exam of Containment Spray Valves 21 & 22CS6 Revealed Cracks in Valve Casting. Cause Attributed to Transgranular Stress Corrosion Cracking. Valves Temporarily Replaced W/Piping Spools
| |
| 05000311/LER-1988-023-01, :on 880912,discovered That Several Radiation Monitoring Sys Monitors Were Calibr Low Due to Use of Incorrect Calibr Source Response Info.Caused by Inadequate Administrative Controls.Monitors Calibr |
- on 880912,discovered That Several Radiation Monitoring Sys Monitors Were Calibr Low Due to Use of Incorrect Calibr Source Response Info.Caused by Inadequate Administrative Controls.Monitors Calibr
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000311/LER-1988-024-01, :on 881128,reactor Tripped Due to Inadequate Procedural Guidance Resulting in Equipment Problem. Positioner 23BF19 Repaired & Valve Successfully Stroke Tested |
- on 881128,reactor Tripped Due to Inadequate Procedural Guidance Resulting in Equipment Problem. Positioner 23BF19 Repaired & Valve Successfully Stroke Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000311/LER-1988-025-01, :on 881201,failure to Perform Item from Tech Spec 4.3.2.1.1 as Required Discovered.Caused by Inadequate Administrative Control.Procedure for Changing Modes from Mode 4 to Mode 3 Revised |
- on 881201,failure to Perform Item from Tech Spec 4.3.2.1.1 as Required Discovered.Caused by Inadequate Administrative Control.Procedure for Changing Modes from Mode 4 to Mode 3 Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |