| | | Reporting criterion |
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| 05000368/LER-1984-001, :on 840128,unit Tripped During Low Power Physics Testing.Caused by One Pin Peaking Factor Limit Being Exceeded Due to Control Element Assembly Position During Testing.Procedures Modified |
- on 840128,unit Tripped During Low Power Physics Testing.Caused by One Pin Peaking Factor Limit Being Exceeded Due to Control Element Assembly Position During Testing.Procedures Modified
| 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) |
| 05000313/LER-1984-001-01, :on 840321,during Scheduled mid-cycle Outage, Pressurizer Spray Line Snubber Failed to Meet Lock Up Test Acceptance Criteria.Cause Undetermined.Equipment Refurbished,Retested & Returned to Svc |
- on 840321,during Scheduled mid-cycle Outage, Pressurizer Spray Line Snubber Failed to Meet Lock Up Test Acceptance Criteria.Cause Undetermined.Equipment Refurbished,Retested & Returned to Svc
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-002, :on 840129,during Routine Surveillances of Core Protection Calculator Sys,Operations Personnel Observed That Valves of Addressable Constants Did Not Agree W/Valves for Cycle 4.Caused by Reactor Trip on 840128 |
- on 840129,during Routine Surveillances of Core Protection Calculator Sys,Operations Personnel Observed That Valves of Addressable Constants Did Not Agree W/Valves for Cycle 4.Caused by Reactor Trip on 840128
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000313/LER-1984-002-01, :on 840316,reactor Tripped During Reactor Protective Sys Anticipatory Trip,Resulting in Loss of Both Main Feedwater Pumps.Possibly Caused by Clogged Oil Filters. Filters Changed |
- on 840316,reactor Tripped During Reactor Protective Sys Anticipatory Trip,Resulting in Loss of Both Main Feedwater Pumps.Possibly Caused by Clogged Oil Filters. Filters Changed
| 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)(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)(1) |
| 05000368/LER-1984-003, :on 840130,unit Tripped on Low Steam Generator Pressure W/Concurrent Main Steam Isolation Sys Actuation. Caused by Leaking Boric Acid Addition Flow Control Valve 2CV-4926.Valve Repaired |
- on 840130,unit Tripped on Low Steam Generator Pressure W/Concurrent Main Steam Isolation Sys Actuation. Caused by Leaking Boric Acid Addition Flow Control Valve 2CV-4926.Valve Repaired
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000313/LER-1984-003-01, :on 840328,three RCS Pressure Transmitters Found Out of Tolerance in Nonconservative Direction.Caused by Transmitter Drift.Instruments Calibr within Acceptable Tolerances |
- on 840328,three RCS Pressure Transmitters Found Out of Tolerance in Nonconservative Direction.Caused by Transmitter Drift.Instruments Calibr within Acceptable Tolerances
| 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)(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)(1) 10 CFR 50.73(a)(2)(viii)(8) |
| 05000313/LER-1984-004-01, :on 840421,alarm Came in for Thrust Bearing Wear on Main Feedwater Pump Turbine K-2A.Caused by Personnel Error.Alarm/Trip Circuitry & Instrumentation Calibr & Associated Circuitry Returned to Svc |
- on 840421,alarm Came in for Thrust Bearing Wear on Main Feedwater Pump Turbine K-2A.Caused by Personnel Error.Alarm/Trip Circuitry & Instrumentation Calibr & Associated Circuitry Returned to Svc
| 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 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-004, :on 840131,reactor Tripped from Approx 10% Full Power.Caused by Low Steam Generator Level in Steam Generator B Due to Manual Level Control Difficulties |
- on 840131,reactor Tripped from Approx 10% Full Power.Caused by Low Steam Generator Level in Steam Generator B Due to Manual Level Control Difficulties
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000313/LER-1984-005-01, :on 841005,automatic Reactor Trip Occurred Due to Loss of Power to Two Reactor Coolant Pumps.Caused by Janitor Accidentally Bumping Handswitch on Feeder Breaker from Unit Auxiliary Transformer |
- on 841005,automatic Reactor Trip Occurred Due to Loss of Power to Two Reactor Coolant Pumps.Caused by Janitor Accidentally Bumping Handswitch on Feeder Breaker from Unit Auxiliary Transformer
| 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)(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)(1) |
| 05000368/LER-1984-005, :on 840210,output of Channel a ex-core Detector Subchannels Appeared to Saturate at 50.7% Power.Preamp Assembly & Filter Replaced.Testing Confirmed Proper Functioning of Subchannels |
- on 840210,output of Channel a ex-core Detector Subchannels Appeared to Saturate at 50.7% Power.Preamp Assembly & Filter Replaced.Testing Confirmed Proper Functioning of Subchannels
| 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)(A) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-006, :on 840221,operations Personnel Recognized That Addressable Constant Updated for Core Protection Calculator Channel C Still in Progress When Channel D Prepared for Monthly Surveillance Testing.Procedure Changed |
- on 840221,operations Personnel Recognized That Addressable Constant Updated for Core Protection Calculator Channel C Still in Progress When Channel D Prepared for Monthly Surveillance Testing.Procedure Changed
| 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)(A) |
| 05000313/LER-1984-006-01, :on 841029,engineering Evaluation of Hydrogen Purge Sys Using LOCA Conditions Revealed Potential for Degradation of Reactor Bldg Liner Plate.Cause Not Stated. Piping Supports Will Be Modified |
- on 841029,engineering Evaluation of Hydrogen Purge Sys Using LOCA Conditions Revealed Potential for Degradation of Reactor Bldg Liner Plate.Cause Not Stated. Piping Supports Will Be Modified
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-007, :on 840310,unit Tripped from Approx .01% Full Power During Controlled Shutdown.Core Protection Calculators Generated Low DNBR Trip When Out of Range Value of Local Heat Flux,Resulting in Min DNBR Value of Zero |
- on 840310,unit Tripped from Approx .01% Full Power During Controlled Shutdown.Core Protection Calculators Generated Low DNBR Trip When Out of Range Value of Local Heat Flux,Resulting in Min DNBR Value of Zero
| 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)(1) 10 CFR 50.73(a)(2)(viii)(8) |
| 05000368/LER-1984-008, :on 840312,reactor Tripped Due to Low Steam Generator Level in Steam Generator A.Caused by Normal Level Control Difficulties at Low Steam Demand Conditions. Corrective Actions Under Consideration |
- on 840312,reactor Tripped Due to Low Steam Generator Level in Steam Generator A.Caused by Normal Level Control Difficulties at Low Steam Demand Conditions. Corrective Actions Under Consideration
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-009, :on 840319,response Time of Resistance Temp Detector on Channels a & D Beyond Tech Spec Limits.Caused by Inadequate Thermal Coupling.No Corrective Actions Taken |
- on 840319,response Time of Resistance Temp Detector on Channels a & D Beyond Tech Spec Limits.Caused by Inadequate Thermal Coupling.No Corrective Actions Taken
| 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)(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) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-011, :on 840507,reactor Turbine Trip Occurred Due to High Level on Steam Generator B.Caused by Master Controller Settings Not Being Set at Optimum Setpoints for Maneuvering at Reduced Power Levels |
- on 840507,reactor Turbine Trip Occurred Due to High Level on Steam Generator B.Caused by Master Controller Settings Not Being Set at Optimum Setpoints for Maneuvering at Reduced Power Levels
| 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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000368/LER-1984-012, :on 780905,unit Entered Mode 4 W/Apparent Error in Vendor Electrical Drawing for RCS Sampling Cabinet 2C116. Caused by Design Const Error.Jumpers Removed on 840518, Restoring Fuse Protection |
- on 780905,unit Entered Mode 4 W/Apparent Error in Vendor Electrical Drawing for RCS Sampling Cabinet 2C116. Caused by Design Const Error.Jumpers Removed on 840518, Restoring Fuse Protection
| 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)(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)(1) |
| 05000368/LER-1984-013, :on 840617,reactor Tripped from Full Power on Low DNBR Due to Penalty Factors Generated by Core Protection Calculators.Caused by Dropped Control Element Assembly |
- on 840617,reactor Tripped from Full Power on Low DNBR Due to Penalty Factors Generated by Core Protection Calculators.Caused by Dropped Control Element Assembly
| 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)(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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-014, :on 840618,reactor Turbine Trip Occurred at Approx 8% Full Power Due to High Level in Steam Generator A.Caused by Main Feedwater Bypass Regulating Valve E/P Converter Malfunction |
- on 840618,reactor Turbine Trip Occurred at Approx 8% Full Power Due to High Level in Steam Generator A.Caused by Main Feedwater Bypass Regulating Valve E/P Converter Malfunction
| 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000368/LER-1984-015, :on 840302,discrepancy in Fire Barrier Penetration 2099-0002,which Previously Evaluated Acceptable, Identified as Nonfunctional.Caused by Lack of Definitive Guidelines in Walkdown Program |
- on 840302,discrepancy in Fire Barrier Penetration 2099-0002,which Previously Evaluated Acceptable, Identified as Nonfunctional.Caused by Lack of Definitive Guidelines in Walkdown Program
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-016, :on 840621,penetration Fire Barrier Damper Mfg by American Warming & Ventilating,Inc,Failed to Completely Close Upon Fusible Link Removal.Caused by Metal Shaving on Pivot Section of Damper Blades |
- on 840621,penetration Fire Barrier Damper Mfg by American Warming & Ventilating,Inc,Failed to Completely Close Upon Fusible Link Removal.Caused by Metal Shaving on Pivot Section of Damper Blades
| 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 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(viii)(8) |
| 05000368/LER-1984-017, :on 840713,fire Barrier Penetration 2124-0004 Identified as Degraded During HVAC Mods.Fire Watch Established within 1 H of Discovery.Penetration Repaired by Replacing Plastic Tubing W/Copper Tubing |
- on 840713,fire Barrier Penetration 2124-0004 Identified as Degraded During HVAC Mods.Fire Watch Established within 1 H of Discovery.Penetration Repaired by Replacing Plastic Tubing W/Copper Tubing
| 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)(1) 10 CFR 50.73(a)(2)(viii)(3) |
| 05000368/LER-1984-018, :on 840618,Train B of Sodium Hydroxide Addition Sys Discovered Inoperable During Monthly Surveillance Test. Caused by Personnel Error.Administrative Procedure Revised to Provide Clarification |
- on 840618,Train B of Sodium Hydroxide Addition Sys Discovered Inoperable During Monthly Surveillance Test. Caused by Personnel Error.Administrative Procedure Revised to Provide Clarification
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-019, :840720,manual Reactor Trip Initiated from 100% Full Power Following Spurious half-leg Trip.Caused by Operator Inadvertently Pressing Alternate Source to Load Button Instead of Reset Button |
- 840720,manual Reactor Trip Initiated from 100% Full Power Following Spurious half-leg Trip.Caused by Operator Inadvertently Pressing Alternate Source to Load Button Instead of Reset Button
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-020, :on 840726,automatic Reactor Trip Occurred Due to High Level in Steam Generator B.Caused by Swell in Steam Generator Levels When MSIVs Opened During Startup |
- on 840726,automatic Reactor Trip Occurred Due to High Level in Steam Generator B.Caused by Swell in Steam Generator Levels When MSIVs Opened During Startup
| 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-021, :on 840728,automatic Reactor Trip Occurred Due to High Level on Steam Generator B.Main Feedwater Flow Increased in Response to Decreasing Steam Generator Level.No post-trip Anomalies Noted |
- on 840728,automatic Reactor Trip Occurred Due to High Level on Steam Generator B.Main Feedwater Flow Increased in Response to Decreasing Steam Generator Level.No post-trip Anomalies Noted
| 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)(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)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-023, :on 840829,while RCS Being Vented Via Upper Vessel Head Vent,Nitrogen Flow Exceeded Vent Flow Capacity, Causing RCS to Slightly Pressurize Resulting in Inaccurate Level Indication |
- on 840829,while RCS Being Vented Via Upper Vessel Head Vent,Nitrogen Flow Exceeded Vent Flow Capacity, Causing RCS to Slightly Pressurize Resulting in Inaccurate Level Indication
| 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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-024, :on 840828,reactor Trip Occurred.Caused by Dropped Control Element Assembly (Cea).Silicon Controlled Rectifiers Replaced for Cea.Power Supply fuses,opto-isolator Cards & Coil Driver Cards Replaced |
- on 840828,reactor Trip Occurred.Caused by Dropped Control Element Assembly (Cea).Silicon Controlled Rectifiers Replaced for Cea.Power Supply fuses,opto-isolator Cards & Coil Driver Cards 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) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-025, :on 840727,discovered That Incorrect Data Used to Calibr Resistance Temp Detector (RTD) 2TE-4711-4 Which Provides Cold Leg Temp Input to Channel D Core Protection Calculator.Caused by Manufacturer Error |
- on 840727,discovered That Incorrect Data Used to Calibr Resistance Temp Detector (RTD) 2TE-4711-4 Which Provides Cold Leg Temp Input to Channel D Core Protection Calculator.Caused by Manufacturer Error
| 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) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-026, :on 841026,automatic Reactor Trip Occurred as Result of Dropped Control Element Assembly.Caused by Shorted Upper Gripper Coil for Control Element Assembly 7. Coil Replaced |
- on 841026,automatic Reactor Trip Occurred as Result of Dropped Control Element Assembly.Caused by Shorted Upper Gripper Coil for Control Element Assembly 7. Coil 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 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(8) |
| 05000368/LER-1984-027, :on 841031,automatic Reactor Trip Occurred. Caused by out-of-range Axial Shape Index.Plant Startup Procedures Modified to Include Guidance for Axial Shape Index Control Considering Core Life |
- on 841031,automatic Reactor Trip Occurred. Caused by out-of-range Axial Shape Index.Plant Startup Procedures Modified to Include Guidance for Axial Shape Index Control Considering Core Life
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-028, :on 841103,reactor Tripped.Caused by Low Water Level in Steam Generator a During Turbine Stop Valve Testing Due to Possible Malfunction of mercury-wetted Relay.Initial Operation Restored Mercury to Reservoir |
- on 841103,reactor Tripped.Caused by Low Water Level in Steam Generator a During Turbine Stop Valve Testing Due to Possible Malfunction of mercury-wetted Relay.Initial Operation Restored Mercury to Reservoir
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000368/LER-1984-029, :on 841129,fire Door self-closing Mechanism Found Out of Adjustment.Caused by High Usage,Oil Cylinders & Worn seals.Self-closing Mechanism Replaced |
- on 841129,fire Door self-closing Mechanism Found Out of Adjustment.Caused by High Usage,Oil Cylinders & Worn seals.Self-closing Mechanism 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) |