| | | Reporting criterion |
|---|
| 05000412/LER-1997-001-01, :on 970106,reactor Trip Occurred Due to Main Transformer Ground Protection.Caused by Inadequate Design Implementation.Procedure 10M-35.3C & Elementary Diagram Was Revised |
- on 970106,reactor Trip Occurred Due to Main Transformer Ground Protection.Caused by Inadequate Design Implementation.Procedure 10M-35.3C & Elementary Diagram Was Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000412/LER-1997-001, :on 970106,reactor Trip Occurred Due to Main Transformer Ground Protection Relay.Caused by Inadequate Design Implementation.Procedures 2OM-35.3C & 2OM-35.4L Revised |
- on 970106,reactor Trip Occurred Due to Main Transformer Ground Protection Relay.Caused by Inadequate Design Implementation.Procedures 2OM-35.3C & 2OM-35.4L Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000334/LER-1997-001-01, Forwards LER 97-001-01 Re Inadequate Surveillance Testing of Auxiliary Feedwater Pump Auto Start Circuitry,Per GL 96-01. Encl LER Suppl Provides Addl Info Re Issues Identified as Result of Reviews Performed in Response to GL | Forwards LER 97-001-01 Re Inadequate Surveillance Testing of Auxiliary Feedwater Pump Auto Start Circuitry,Per GL 96-01. Encl LER Suppl Provides Addl Info Re Issues Identified as Result of Reviews Performed in Response to GL 96-01 | 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-002-01, :on 970219,declared EDGs Inoperable Due to Inaccuracies of Watt Meter Instrument Loop.Restored EDG Operability Via Performance of Revised Operating Surveillance Tests |
- on 970219,declared EDGs Inoperable Due to Inaccuracies of Watt Meter Instrument Loop.Restored EDG Operability Via Performance of Revised Operating Surveillance Tests
| 10 CFR 50.73(a)(2)(i) |
| 05000412/LER-1997-002, :on 970111,while in Mode 3 at 0% Reactor Power Plant Entered TS 3.0.3 for Cooldown to Mode 5.Caused by Incomplete Construction Contractor Documentation & Lack of Overall Knowledge of Flood Protection by Crew |
- on 970111,while in Mode 3 at 0% Reactor Power Plant Entered TS 3.0.3 for Cooldown to Mode 5.Caused by Incomplete Construction Contractor Documentation & Lack of Overall Knowledge of Flood Protection by Crew
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
| 05000334/LER-1997-003, :on 970220,identified RCS Pressure Isolation Valves Were Not Tested.Caused by Operator Error.Affected Valves Declared Inoperable & Verified to Be Closed & Deenergized & Procedures Revised |
- on 970220,identified RCS Pressure Isolation Valves Were Not Tested.Caused by Operator Error.Affected Valves Declared Inoperable & Verified to Be Closed & Deenergized & Procedures Revised
| 10 CFR 50.73(a)(2)(i) |
| 05000412/LER-1997-003, :on 970521,entry of TS 3.0.3 Occurred Due to Inoperability of Both Trains of Suppl Leak Collection & Release Sys.Caused by Failure to Recognize That Operating in Condition Is Prohibited by Ts.Reviewed Rept 971141 |
- on 970521,entry of TS 3.0.3 Occurred Due to Inoperability of Both Trains of Suppl Leak Collection & Release Sys.Caused by Failure to Recognize That Operating in Condition Is Prohibited by Ts.Reviewed Rept 971141
| 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000412/LER-1997-004, :on 970911,four CIVs Were Not Tested IAW Tss. Caused by Inadequate Change Mgt.Ufsar Table 6.2-60 Revised to Remove Any Credit for Four (4) CIVs in Containment Penetrations 14 & 15.With |
- on 970911,four CIVs Were Not Tested IAW Tss. Caused by Inadequate Change Mgt.Ufsar Table 6.2-60 Revised to Remove Any Credit for Four (4) CIVs in Containment Penetrations 14 & 15.With
| 10 CFR 50.73(a)(2)(i) |
| 05000412/LER-1997-004-01, :on 970911,discovered That Four Containment Isolation Valves Were Not Tested IAW Ts.Caused by Inadequate Mgt Change.Will Revise Licensing Requirements Manual Table 5.1-1 & UFSAR Table 6.2-60 |
- on 970911,discovered That Four Containment Isolation Valves Were Not Tested IAW Ts.Caused by Inadequate Mgt Change.Will Revise Licensing Requirements Manual Table 5.1-1 & UFSAR Table 6.2-60
| 10 CFR 50.73(a)(2)(i) |
| 05000412/LER-1997-005-01, :on 971015,conditions Prohibited by TS During Routine 4.16kV & 480 Volt Emergency Bus Surveillance Testing,Was Determined.Caused by Inadequate Design.Testing Performed Using Other Existing Procedures |
- on 971015,conditions Prohibited by TS During Routine 4.16kV & 480 Volt Emergency Bus Surveillance Testing,Was Determined.Caused by Inadequate Design.Testing Performed Using Other Existing Procedures
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-006, :on 970322,failure to Test Solid State Protection Sys Logic IAW TS Caused by Procedural Deficiencies.Performed Surveillance Testing on 970324 |
- on 970322,failure to Test Solid State Protection Sys Logic IAW TS Caused by Procedural Deficiencies.Performed Surveillance Testing on 970324
| 10 CFR 50.73(a)(2)(i) |
| 05000412/LER-1997-006-01, :on 971201,TS Requirements for 4.16 Kv Bus Undervoltage Trip Feeder Breaker Function ESF Response Time Were Not Met.Caused by Inadequate Relay Calibr Procedures. Recalibrated Time Delays |
- on 971201,TS Requirements for 4.16 Kv Bus Undervoltage Trip Feeder Breaker Function ESF Response Time Were Not Met.Caused by Inadequate Relay Calibr Procedures. Recalibrated Time Delays
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-007, :on 970322,failure to Test Control Room Emergency Bottled Air Pressurization Subsystem IAW TS Was Caused by Inadequate Coordination,Communication & Procedures.Discharge Trip Valves Tested |
- on 970322,failure to Test Control Room Emergency Bottled Air Pressurization Subsystem IAW TS Was Caused by Inadequate Coordination,Communication & Procedures.Discharge Trip Valves Tested
| 10 CFR 50.73(a)(2)(i) |
| 05000412/LER-1997-007-01, :on 971205,routine Surveillance Testing of Pr Neutron Flux High Positive Rate RT Function Was Inadequate. Caused by Lack of Awareness During Procedural Development to Ensure Adequate Overlap.Procedure Revised |
- on 971205,routine Surveillance Testing of Pr Neutron Flux High Positive Rate RT Function Was Inadequate. Caused by Lack of Awareness During Procedural Development to Ensure Adequate Overlap.Procedure Revised
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000334/LER-1997-008-01, Informs of Change in Scheduled Completion Date for LER 97-008-01 Commitment from 981130 to 990830 | Informs of Change in Scheduled Completion Date for LER 97-008-01 Commitment from 981130 to 990830 | |
| 05000412/LER-1997-009-01, :on 971218,surveillance of Gaseous Waste Storage Tank Radioactive Matl Quantity Determination Was Missed.Caused by Personnel Error.Operating Manual Procedure 2OM-19.4.G Was Implemented |
- on 971218,surveillance of Gaseous Waste Storage Tank Radioactive Matl Quantity Determination Was Missed.Caused by Personnel Error.Operating Manual Procedure 2OM-19.4.G Was Implemented
| 10 CFR 50.73(a)(2)(i) |
| 05000412/LER-1997-010-01, :on 971219,lack of Electrical Isolation in Unit 2 EDG Room Ventilation Sys Temperature Control Circuits Was Noted.Caused by Inadequate Design.Temporary Mods 2-97-22 & 2-97-23 Were Completed on 971220 |
- on 971219,lack of Electrical Isolation in Unit 2 EDG Room Ventilation Sys Temperature Control Circuits Was Noted.Caused by Inadequate Design.Temporary Mods 2-97-22 & 2-97-23 Were Completed on 971220
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000412/LER-1997-011-02, On 971229,determined That Inadequate Electrical Isolation in Secondary Process Rack Circuitry Occurred Due to Design Error.Technical Evaluation Rept 1162 Was Developed | On 971229,determined That Inadequate Electrical Isolation in Secondary Process Rack Circuitry Occurred Due to Design Error.Technical Evaluation Rept 1162 Was Developed | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000334/LER-1997-011, :on 970509,determined Inadequate Testing Was Performed on Solid State Protection Sys Relays K630A & K630B.Caused by Inadequate Procedure.Subject Relays Tested & Verified Operable & Revised Procedures |
- on 970509,determined Inadequate Testing Was Performed on Solid State Protection Sys Relays K630A & K630B.Caused by Inadequate Procedure.Subject Relays Tested & Verified Operable & Revised Procedures
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-015, :on 970501,voluntary Entry Was Proceduralized Into TS 3.0.3 by Allowing Bypass of Source Range Channels Input to High Flux Trip.Caused by Misinterpretation of TS 3.3.1.1,Table 3.3-1,Item 6.Changed Procedure |
- on 970501,voluntary Entry Was Proceduralized Into TS 3.0.3 by Allowing Bypass of Source Range Channels Input to High Flux Trip.Caused by Misinterpretation of TS 3.3.1.1,Table 3.3-1,Item 6.Changed Procedure
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-017, :on 970701,ESFA of P-12 Interlock Occurred Due to Decreasing Reactor Water Temperature.Caused by Human Performance Problems.Provided Training for All Planners |
- on 970701,ESFA of P-12 Interlock Occurred Due to Decreasing Reactor Water Temperature.Caused by Human Performance Problems.Provided Training for All Planners
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000334/LER-1997-018, :on 970705,potential for Spurious Seismically Induced FPS Sys Activation Affecting EDG Was Noted.Caused by Deficiency in Original Design.Established Fire Watch |
- on 970705,potential for Spurious Seismically Induced FPS Sys Activation Affecting EDG Was Noted.Caused by Deficiency in Original Design.Established Fire Watch
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000334/LER-1997-019, :on 970710,containment Penetration Check Valves Not IAW Design Bases Was Revealed.Caused by Inadequate Design Reviews.Temporary Mod Was Performed to Install Blank Flange Downstream of Check Valve 1SA-15 |
- on 970710,containment Penetration Check Valves Not IAW Design Bases Was Revealed.Caused by Inadequate Design Reviews.Temporary Mod Was Performed to Install Blank Flange Downstream of Check Valve 1SA-15
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2) |
| 05000334/LER-1997-020, :on 970724,identified Pressure Switch Contact, Installed in Control Circuit,Had Unqualified Level Category. Caused by Deficiency in Original Design of Ventilation Sys. Installed Qualified Replacement Switches |
- on 970724,identified Pressure Switch Contact, Installed in Control Circuit,Had Unqualified Level Category. Caused by Deficiency in Original Design of Ventilation Sys. Installed Qualified Replacement Switches
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000334/LER-1997-022, :on 970730,ESFA of P-12 Interlock Occurred Due to Decreased Reactor Water Temp.Caused by Operator Unfamiliarity W/Level Controller Response in All Situations. Controller Windup Will Be Demonstrated |
- on 970730,ESFA of P-12 Interlock Occurred Due to Decreased Reactor Water Temp.Caused by Operator Unfamiliarity W/Level Controller Response in All Situations. Controller Windup Will Be Demonstrated
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000334/LER-1997-023, :on 970801,determined Two Analog Rod Position Indicators (Arpi) Channels Inoperable.Caused by Calibr Drift of Arpi Sys.Will Complete Mod to Upgrade Arpi Sys During Upcoming Unit 1 Refueling Outage |
- on 970801,determined Two Analog Rod Position Indicators (Arpi) Channels Inoperable.Caused by Calibr Drift of Arpi Sys.Will Complete Mod to Upgrade Arpi Sys During Upcoming Unit 1 Refueling Outage
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-024, :on 970805,TS 3.0.3 Was Entered as Result of Failure of RWST Level Transmitter.Caused by Crack in Ferrite Block for Level Transmitter LT-QS-100B.Replaced Transmitter W/Foxboro Model 827DF-IS1SHSA1 |
- on 970805,TS 3.0.3 Was Entered as Result of Failure of RWST Level Transmitter.Caused by Crack in Ferrite Block for Level Transmitter LT-QS-100B.Replaced Transmitter W/Foxboro Model 827DF-IS1SHSA1
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-025, :on 970807,ground in Feedwater Flow Controller Resulted in High SG Level & Subsequent Turbine Trip/Reactor Trip.Caused by Mfg Defect on Circuit Card.Formed Event Response Team |
- on 970807,ground in Feedwater Flow Controller Resulted in High SG Level & Subsequent Turbine Trip/Reactor Trip.Caused by Mfg Defect on Circuit Card.Formed Event Response Team
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000334/LER-1997-026, :on 970814,CR Ventilation Isolation Dampers & Containment Isolation Valves Did Not Meet TS ESF Response Time Srs.Caused by Inadequate Surveillance Test Procedures. Reviewed Surveillance Test Data |
- on 970814,CR Ventilation Isolation Dampers & Containment Isolation Valves Did Not Meet TS ESF Response Time Srs.Caused by Inadequate Surveillance Test Procedures. Reviewed Surveillance Test Data
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-027, :on 970817,surveillance of Refueling Water Storage Tank Boron Concentration Was Missed.Caused by Inattention to Detail & Lack of Self Checking by Daylight Chemistry Specialist.Counseled Personnel |
- on 970817,surveillance of Refueling Water Storage Tank Boron Concentration Was Missed.Caused by Inattention to Detail & Lack of Self Checking by Daylight Chemistry Specialist.Counseled Personnel
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-028, :on 970825,SFP Crane Interlocks & Physical Stops Were Not Tested Prior to Use IAW Ts.Caused by Procedures,Program/Process/Equipment Labeling & Training/ Qualification.Performed Surveillance Test |
- on 970825,SFP Crane Interlocks & Physical Stops Were Not Tested Prior to Use IAW Ts.Caused by Procedures,Program/Process/Equipment Labeling & Training/ Qualification.Performed Surveillance Test
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-029, :on 970907,discovery of de-energized Chart Recorder Leads to Missed RWST Level Check Surveillance. Caused by Operator error.Re-energized Level Recorder & Performed RWST Level Channel Operability Check |
- on 970907,discovery of de-energized Chart Recorder Leads to Missed RWST Level Check Surveillance. Caused by Operator error.Re-energized Level Recorder & Performed RWST Level Channel Operability Check
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-030, :on 970908,failure to Comply W/Edg TS Action Statement Was Identified.Caused by Inadequate Interpretation of Ts.Revised Procedure 3.4, Clearance Procedure to Agree W/Ts Action Statement 3.8.1.1.b |
- on 970908,failure to Comply W/Edg TS Action Statement Was Identified.Caused by Inadequate Interpretation of Ts.Revised Procedure 3.4, Clearance Procedure to Agree W/Ts Action Statement 3.8.1.1.b
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-031, :on 970919,identified That Routine Testing of Surveillance Procedures for ESF Were Inadequate.Caused by Inadequate Development of Procedures.Will Develop Addl Routine Surveillance Testing |
- on 970919,identified That Routine Testing of Surveillance Procedures for ESF Were Inadequate.Caused by Inadequate Development of Procedures.Will Develop Addl Routine Surveillance Testing
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-032, :on 970927,automatic Start of EDG Occurred During Bus Transfer from Unit to Sys Station Transformer. Caused by Conservative Setpoints for Starting EDGs at Unit 1.Restored CR Ventilation |
- on 970927,automatic Start of EDG Occurred During Bus Transfer from Unit to Sys Station Transformer. Caused by Conservative Setpoints for Starting EDGs at Unit 1.Restored CR Ventilation
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000334/LER-1997-033, :on 971008,identified Potential for Nis Supply Voltages to Be Outside of Design Requirements.Caused by Inadequate Design Change During Original Construction of Plant.Developed & Implemented Design Change |
- on 971008,identified Potential for Nis Supply Voltages to Be Outside of Design Requirements.Caused by Inadequate Design Change During Original Construction of Plant.Developed & Implemented Design Change
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000334/LER-1997-034, :on 971008,identified That Rhrs TS Requirements Were Not Satisfied During Refueling Cavity Draining.Caused by Inadequate Procedures.Revised Procedure 1OM-20.4.E, Draining Refueling Cavity, to Satisfy TS |
- on 971008,identified That Rhrs TS Requirements Were Not Satisfied During Refueling Cavity Draining.Caused by Inadequate Procedures.Revised Procedure 1OM-20.4.E, Draining Refueling Cavity, to Satisfy TS
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-035, :on 971017,small Bore Piping Support Design Deficiencies Were Identified.Caused by Inadequate Original Design.Comprehensive Evaluation Performed |
- on 971017,small Bore Piping Support Design Deficiencies Were Identified.Caused by Inadequate Original Design.Comprehensive Evaluation Performed
| |
| 05000334/LER-1997-036, :on 971113,inadequate Channel Check for Meteorological Monitoring Instrumentation Was Noted.Caused by Inadequate Change Mgt.Hp Was Requested to Perform Channel Checks & Rept Results to CR |
- on 971113,inadequate Channel Check for Meteorological Monitoring Instrumentation Was Noted.Caused by Inadequate Change Mgt.Hp Was Requested to Perform Channel Checks & Rept Results to CR
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-037, :on 971120,inadequate Ssps Automatic Logic Functions Testing Noted.Caused by Procedural Deficiencies. Revised Applicable Procedures & Completed Addl Surveillance Testing to Adequately Verify Two Functions |
- on 971120,inadequate Ssps Automatic Logic Functions Testing Noted.Caused by Procedural Deficiencies. Revised Applicable Procedures & Completed Addl Surveillance Testing to Adequately Verify Two Functions
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-039, :on 971208,gas Accumulated in Charging/High Safety Injection Pump Piping.Caused by HHSI Pump Minimum Flow Recirculation Line Orifices.Flow Orifices Are Being Replaced at Unit 1 & 2,to Reduce Generation of Gas Bubbles |
- on 971208,gas Accumulated in Charging/High Safety Injection Pump Piping.Caused by HHSI Pump Minimum Flow Recirculation Line Orifices.Flow Orifices Are Being Replaced at Unit 1 & 2,to Reduce Generation of Gas Bubbles
| |
| 05000334/LER-1997-040, :on 971210,inadequate Testing of Reactor Protection Sys P-8 Interlock,Was Identified.Caused by Vendor Design Error.Applicable Surveillance Test Procedures Were Revised to Include Manual Test |
- on 971210,inadequate Testing of Reactor Protection Sys P-8 Interlock,Was Identified.Caused by Vendor Design Error.Applicable Surveillance Test Procedures Were Revised to Include Manual Test
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) |
| 05000334/LER-1997-041, :on 971215,failed to Remove Power from Isolated RCS Loop Isolation Valve Operators within One Hour as Required by Ts.Caused by Inadequate Actions Taken to Control & Implement Change.Revised Procedures |
- on 971215,failed to Remove Power from Isolated RCS Loop Isolation Valve Operators within One Hour as Required by Ts.Caused by Inadequate Actions Taken to Control & Implement Change.Revised Procedures
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-042, :on 971215,failure to Perform Axial Flux Difference Monitor Surveillance as Required by TS Noted. Caused by Misunderstood Instructions.Revised Procedures & Reviewed TS Interpretations |
- on 971215,failure to Perform Axial Flux Difference Monitor Surveillance as Required by TS Noted. Caused by Misunderstood Instructions.Revised Procedures & Reviewed TS Interpretations
| 10 CFR 50.73(a)(2)(i) |
| 05000334/LER-1997-043, :on 971231,inadequate Surveillance Testing of Solid State Protection Sys Resulted in Entry Into TS 3.0.3. Caused by Misinterpretation of TSs During Procedure Development.Test Specified Will Be Deleted |
- on 971231,inadequate Surveillance Testing of Solid State Protection Sys Resulted in Entry Into TS 3.0.3. Caused by Misinterpretation of TSs During Procedure Development.Test Specified Will Be Deleted
| 10 CFR 50.73(a)(2)(i) |