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| 05000499/LER-1994-001-01, :on 940301,SDG 21 Experienced Inadvertent Start.Caused by Weakened Transistor in non-1E Fiber Optic Start Circuits & Faulty Power Supply (PS-2).Fiber Optic Boards G,C & J & PS-2 Power Supply Replaced |
- on 940301,SDG 21 Experienced Inadvertent Start.Caused by Weakened Transistor in non-1E Fiber Optic Start Circuits & Faulty Power Supply (PS-2).Fiber Optic Boards G,C & J & PS-2 Power Supply Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000498/LER-1994-001, :on 940105,discovered Small Gaps in Reactor Containment Bldg Emergency Sumps Screens.Caused by Less than Adequate Attention to Detail.Repair Dispositions Initiated to Correct Noted Deficiencies in Sump |
- on 940105,discovered Small Gaps in Reactor Containment Bldg Emergency Sumps Screens.Caused by Less than Adequate Attention to Detail.Repair Dispositions Initiated to Correct Noted Deficiencies in Sump
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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) |
| 05000498/LER-1994-002, :on 940115,identified Centrifugal Charging Pump 1A Discharge Bypass Valve CV-MOV-8348 Opened.Caused by Hydropneumatic Transient.Mov Data Base Searched to Identify Other Valves Susceptible to Event |
- on 940115,identified Centrifugal Charging Pump 1A Discharge Bypass Valve CV-MOV-8348 Opened.Caused by Hydropneumatic Transient.Mov Data Base Searched to Identify Other Valves Susceptible to Event
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) |
| 05000499/LER-1994-002-02, :on 940302,Piston 4R Was Discovered Damaged During Insp Due to Piston Failure Foreign Material or Trapped Wear Particles Between Piston & Liner.Piston & Cylinder Liner for Cylinder 4R Were Replaced |
- on 940302,Piston 4R Was Discovered Damaged During Insp Due to Piston Failure Foreign Material or Trapped Wear Particles Between Piston & Liner.Piston & Cylinder Liner for Cylinder 4R Were Replaced
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 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) |
| 05000498/LER-1994-002-01, :on 940115,centifugal Charging Pump 1A Discharge Bypass Valve Found in Open Position Contrary to TS 3.1.2.3 Requirements.Caused by hydro-pneumatic Transient. MOV Database Searched |
- on 940115,centifugal Charging Pump 1A Discharge Bypass Valve Found in Open Position Contrary to TS 3.1.2.3 Requirements.Caused by hydro-pneumatic Transient. MOV Database Searched
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000498/LER-1994-003, :on 940118,discovered Interference Between Plant Exhaust Vent Tornado Damper Linkage & Gusset.Caused by Undetected Const Interference.Interference Between Damper & Gusset Removed by Notching Gusset |
- on 940118,discovered Interference Between Plant Exhaust Vent Tornado Damper Linkage & Gusset.Caused by Undetected Const Interference.Interference Between Damper & Gusset Removed by Notching Gusset
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000499/LER-1994-003-01, :on 940429,inadvertent Test Mode Start of Standby DG 21 & 22 Occurred Due to fiber-optic Board Susceptibility to Noise in Conjunction W/Transient DC Spikes.Maint for Boards Initiated |
- on 940429,inadvertent Test Mode Start of Standby DG 21 & 22 Occurred Due to fiber-optic Board Susceptibility to Noise in Conjunction W/Transient DC Spikes.Maint for Boards Initiated
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000498/LER-1994-004, :on 940119,determined Surveillance Performed to Comply W/Sr 4.4.4.1.b for Rvs Needed to Be Enhanced Because PORVs Not Tested from Mcb.Procedure 1(2)PSP03-RC-0010 Replaced w/OPSP03-RC-0010 |
- on 940119,determined Surveillance Performed to Comply W/Sr 4.4.4.1.b for Rvs Needed to Be Enhanced Because PORVs Not Tested from Mcb.Procedure 1(2)PSP03-RC-0010 Replaced w/OPSP03-RC-0010
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000499/LER-1994-004-01, :on 940512,SG hi-hi Level (P-14) Signal Generated While Performing RTD Cross Calibrs Due to Filling SG to Approx 90% Full.Crew Briefings Discussing Event Conducted |
- on 940512,SG hi-hi Level (P-14) Signal Generated While Performing RTD Cross Calibrs Due to Filling SG to Approx 90% Full.Crew Briefings Discussing Event Conducted
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) |
| 05000499/LER-1994-005-02, :on 940607,standby Diesel Generator 22 Had Received Unexpected Test Mode Start Signal.Caused by Voltage Spike Generated by Emergency Fuel Oil Solenoid Deenergizing. Replaced Parts Found to Be Weak |
- on 940607,standby Diesel Generator 22 Had Received Unexpected Test Mode Start Signal.Caused by Voltage Spike Generated by Emergency Fuel Oil Solenoid Deenergizing. Replaced Parts Found to Be Weak
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000498/LER-1994-006, :on 940214,reactor Manually Tripped Following Unanticipated Test Results.Caused by Failed post-mod Testing.Test Terminated & Solid State Rod Control Sys Returned to Original Design Configuration |
- on 940214,reactor Manually Tripped Following Unanticipated Test Results.Caused by Failed post-mod Testing.Test Terminated & Solid State Rod Control Sys Returned to Original Design Configuration
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000499/LER-1994-006-01, :on 940711,discovered That Sp Used to Verify Operability of Accident Monitoring Instrumentation & Remote Shutdown Monitoring Instrumentation Inadequate.Sp Revised.W/ |
- on 940711,discovered That Sp Used to Verify Operability of Accident Monitoring Instrumentation & Remote Shutdown Monitoring Instrumentation Inadequate.Sp Revised.W/
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) |
| 05000499/LER-1994-007-02, :on 940625,main Transformer Lockout Relay Actuated.Caused by Failure of Capacitor within Pilot Wire Relay.Annunciator Response Procedures Have Been Revised & Faulty Pilot Wire Relay Was Replaced |
- on 940625,main Transformer Lockout Relay Actuated.Caused by Failure of Capacitor within Pilot Wire Relay.Annunciator Response Procedures Have Been Revised & Faulty Pilot Wire Relay Was Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000498/LER-1994-007, :on 940224,Reactor Trip Bypass Breaker Did Not Properly Satisfy Ts.Caused by Inadequate Procedure Preparation & Review.Surveillance Procedure Enhancement Program & Basis Document Developed |
- on 940224,Reactor Trip Bypass Breaker Did Not Properly Satisfy Ts.Caused by Inadequate Procedure Preparation & Review.Surveillance Procedure Enhancement Program & Basis Document Developed
| 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) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000498/LER-1994-007-01, :on 940224,station Procedure for Testing Reactor Trip Bypass Breakers Did Not Satisfy Ts.Caused by Inadequate Procedure Preparation & Review.Surveillance Procedure Enhancement Program Underway |
- on 940224,station Procedure for Testing Reactor Trip Bypass Breakers Did Not Satisfy Ts.Caused by Inadequate Procedure Preparation & Review.Surveillance Procedure Enhancement Program Underway
| |
| 05000498/LER-1994-010, :on 940719,Unit 1 Failed to Fully Meet Surveillance Requirements of TS 4.7.4, Essential Cooling Water Sys. Caused by Misuse of Equipment Procedures. Revised Procedure Was re-performed for Unit 1 |
- on 940719,Unit 1 Failed to Fully Meet Surveillance Requirements of TS 4.7.4, Essential Cooling Water Sys. Caused by Misuse of Equipment Procedures. Revised Procedure Was re-performed for Unit 1
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000498/LER-1994-011, :on 940310,safety Injection Actuation Was Received on Trains A,B & C.Cause Was Failure to Adhere to Procedure.Corrective Actions:Restored Cooling Shutdown & Removed Personnel from Watchbill |
- on 940310,safety Injection Actuation Was Received on Trains A,B & C.Cause Was Failure to Adhere to Procedure.Corrective Actions:Restored Cooling Shutdown & Removed Personnel from Watchbill
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000498/LER-1994-013, :on 940804,identified Two Cases of NUMARC 87-00 Criterion Not Being Satisfied.Caused by Failure to Confirm Validity of Blackout Program.Severe Weather Guidelines Revised |
- on 940804,identified Two Cases of NUMARC 87-00 Criterion Not Being Satisfied.Caused by Failure to Confirm Validity of Blackout Program.Severe Weather Guidelines Revised
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) |
| 05000498/LER-1994-015, :on 940920,unit 1 Experienced Reactor Trip on low-low Steam Generator Level for Approx Four Minutes After Loss of Steam Generator Feedwater Pump.Caused by Expected Response Instead of Actual Conditions |
- on 940920,unit 1 Experienced Reactor Trip on low-low Steam Generator Level for Approx Four Minutes After Loss of Steam Generator Feedwater Pump.Caused by Expected Response Instead of Actual Conditions
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) |
| 05000498/LER-1994-016, :on 940923,failure to Fully Meet Requirements of TS Due to Not Placing CR Envelope HVAC Sys in Required Mode.Toxic Gas Analyzers Repaired & Mod Implemented |
- on 940923,failure to Fully Meet Requirements of TS Due to Not Placing CR Envelope HVAC Sys in Required Mode.Toxic Gas Analyzers Repaired & Mod Implemented
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) |
| 05000498/LER-1994-017, :on 941011,gaseous Effluent Monitor Setpoints Had Not Been Calculated in Accordance W/Offsite Dose Calculation Methodology.Caused by Failure to Revise Related Change Documents.Monitors Verified Operable |
- on 941011,gaseous Effluent Monitor Setpoints Had Not Been Calculated in Accordance W/Offsite Dose Calculation Methodology.Caused by Failure to Revise Related Change Documents.Monitors Verified Operable
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000498/LER-1994-018-01, :on 941102,failure to Fully Meet Requirements of TS Re CR Envelope HVAC Sys Boundary.Caused by Less than Adequate Surveillance Test Procedure.Development of Detailed Testing Method Initiated |
- on 941102,failure to Fully Meet Requirements of TS Re CR Envelope HVAC Sys Boundary.Caused by Less than Adequate Surveillance Test Procedure.Development of Detailed Testing Method Initiated
| 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)(x) 10 CFR 50.73(a)(2) |
| 05000498/LER-1994-018, :on 941102,required 0.125 Inches Water Gauge Could Not Be Demonstrated on Trains of CR Envelope HVAC Due to Less than Adequate Surveillance Test Procedure.Electrical Auxiliary Bldg HVAC Airflows Adjusted |
- on 941102,required 0.125 Inches Water Gauge Could Not Be Demonstrated on Trains of CR Envelope HVAC Due to Less than Adequate Surveillance Test Procedure.Electrical Auxiliary Bldg HVAC Airflows Adjusted
| 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000498/LER-1994-019-01, Forwards LER 94-019-01,removing Commitment to Revise SI Actuation & Response Time Test Surveillance Procedure to Include spin-up Time for Fuel Handling Bldg HVAC Sys | Forwards LER 94-019-01,removing Commitment to Revise SI Actuation & Response Time Test Surveillance Procedure to Include spin-up Time for Fuel Handling Bldg HVAC Sys | |
| 05000498/LER-1994-020, :on 941209,determination Made That Combined Total of 66 Breakers Potentially Out of Tolerance.Caused by Misinterpretation of Acceptance Criteria.Molded Case Circuit Breaker Tests Procedure Revised |
- on 941209,determination Made That Combined Total of 66 Breakers Potentially Out of Tolerance.Caused by Misinterpretation of Acceptance Criteria.Molded Case Circuit Breaker Tests Procedure Revised
| 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) |