| | | Reporting criterion |
|---|
| 05000237/LER-1985-001-03, :on 850104,4-kV Breaker 2329 Failed to Trip Open During Breaker Differential Relay Testing.Caused by Cut Wires in Tripping Logic.Wires Reconnected |
- on 850104,4-kV Breaker 2329 Failed to Trip Open During Breaker Differential Relay Testing.Caused by Cut Wires in Tripping Logic.Wires Reconnected
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000237/LER-1985-001, :on 850104,4-kV Breaker 2329 Failed to Trip Open During Relay Testing.Caused by Four Disconnected Wires in Trip Logic.Wires Reconnected |
- on 850104,4-kV Breaker 2329 Failed to Trip Open During Relay Testing.Caused by Four Disconnected Wires in Trip Logic.Wires Reconnected
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000249/LER-1985-001-04, :on 850112,during Turbine Checks Surveillance, Reactor Scrammed from Turbine Trip.Caused by Oil Trip Solenoid Valve Malfunction.Solenoid Valve Replaced.Group I Isolation Caused by Switch Vibration |
- on 850112,during Turbine Checks Surveillance, Reactor Scrammed from Turbine Trip.Caused by Oil Trip Solenoid Valve Malfunction.Solenoid Valve Replaced.Group I Isolation Caused by Switch Vibration
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000249/LER-1985-002-05, :on 850201,reactor Scrammed on Low Water Level W/O Cause.Caused by Vibration from Inservice Insp Std Which Inadvertently Hit Floor Near Instrument Rack 2203-6.Low Water Level Switches Replaced |
- on 850201,reactor Scrammed on Low Water Level W/O Cause.Caused by Vibration from Inservice Insp Std Which Inadvertently Hit Floor Near Instrument Rack 2203-6.Low Water Level Switches Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000237/LER-1985-002-02, :850103,interlock Doors Simultaneously Opened. Caused by Doors Closing Too Quickly & Bouncing Back.Closure Arms for Interlock Doors Adjusted to Allow Slower Closing |
- 850103,interlock Doors Simultaneously Opened. Caused by Doors Closing Too Quickly & Bouncing Back.Closure Arms for Interlock Doors Adjusted to Allow Slower Closing
| 10 CFR 50.73(a)(2)(1) |
| 05000237/LER-1985-002, :on 850103,reactor/turbine 517 Ft Interlock Alarm Received,Indicating Interlock Doors Opened Simultaneously.Caused by Doors Closing Too Quickly.Door Closures Adjusted W/Bldg Pressures |
- on 850103,reactor/turbine 517 Ft Interlock Alarm Received,Indicating Interlock Doors Opened Simultaneously.Caused by Doors Closing Too Quickly.Door Closures Adjusted W/Bldg Pressures
| 10 CFR 50.73(a)(2)(1) |
| 05000237/LER-1985-003-06, :on 850129,level Transmitters 2-263-57A,58A & 58B Taken Out of Svc Causing Group 2 Isolation.Caused by Operator Error.Operator Counseled |
- on 850129,level Transmitters 2-263-57A,58A & 58B Taken Out of Svc Causing Group 2 Isolation.Caused by Operator Error.Operator Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000249/LER-1985-003-07, :on 850206,HPCI Room Cooler Fan Belts Fell Off, Rendering Sys Inoperable.Cause Not Stated.Belts Replaced & Cooler Fans Ran Properly |
- on 850206,HPCI Room Cooler Fan Belts Fell Off, Rendering Sys Inoperable.Cause Not Stated.Belts Replaced & Cooler Fans Ran Properly
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000237/LER-1985-004-04, :on 850206,reactor Protection Sys Power Supply Switched from Reserve to Normal,Causing Channel B to Become Deenergized,Resulting in Full Scram.Procedure Will Be Created to Prevent Recurrence |
- on 850206,reactor Protection Sys Power Supply Switched from Reserve to Normal,Causing Channel B to Become Deenergized,Resulting in Full Scram.Procedure Will Be Created to Prevent Recurrence
| |
| 05000249/LER-1985-004-06, :on 850215,level Indicating Switch 3-263-58B Found to Trip at 116.5 Inches Water & Switch 3-263-57B Found to Trip at 127 Inches Water (Differential Pressure).Caused by Setpoint Drift.Switches Adjusted & Recalibr |
- on 850215,level Indicating Switch 3-263-58B Found to Trip at 116.5 Inches Water & Switch 3-263-57B Found to Trip at 127 Inches Water (Differential Pressure).Caused by Setpoint Drift.Switches Adjusted & Recalibr
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000237/LER-1985-005-04, :on 850130,Group II Isolation Occurred While Returning Level Transmitter 2-263-S8B to Svc.Cause Under Investigation.Supplemental Rept Will Be Issued When Root Cause Determined |
- on 850130,Group II Isolation Occurred While Returning Level Transmitter 2-263-S8B to Svc.Cause Under Investigation.Supplemental Rept Will Be Issued When Root Cause Determined
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000249/LER-1985-005, :on 850216-17,caution Cards Inadvertently Hung on Unit 3 Diesel Generator Knife Switches Rather than Unit 2 Switches & Corresponding Unit 3 Switches Opened.Caused by Communications & Operator Error |
- on 850216-17,caution Cards Inadvertently Hung on Unit 3 Diesel Generator Knife Switches Rather than Unit 2 Switches & Corresponding Unit 3 Switches Opened.Caused by Communications & Operator Error
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) |
| 05000237/LER-1985-005-02, :on 850130,during Outage,Full Group II Isolation Occurred When Operator Error Caused Isolation Signal Generated from Transmitter While Valving Transmitter Back Into Svc.Operator Training Revised |
- on 850130,during Outage,Full Group II Isolation Occurred When Operator Error Caused Isolation Signal Generated from Transmitter While Valving Transmitter Back Into Svc.Operator Training Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000249/LER-1985-005-05, :on 850216,undervoltage Protection on Bus 34-1 Lost.Caused by A-man Hanging Caution Cards on Wrong Knife Switches.Event Reviewed W/Operating Personnel.New Procedures for ECCS Undervoltage Test Created |
- on 850216,undervoltage Protection on Bus 34-1 Lost.Caused by A-man Hanging Caution Cards on Wrong Knife Switches.Event Reviewed W/Operating Personnel.New Procedures for ECCS Undervoltage Test Created
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) |
| 05000237/LER-1985-006-04, :on 850217,reactor Scram Occurred During Undervoltage Tests.Caused by Misunderstanding of Ae Re Power Supply Divisionalization.Power Supplies Will Be Redesigned, Rewired & Tested |
- on 850217,reactor Scram Occurred During Undervoltage Tests.Caused by Misunderstanding of Ae Re Power Supply Divisionalization.Power Supplies Will Be Redesigned, Rewired & Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000249/LER-1985-006-05, :on 850222,HPCI Sys Inoperable Due to Valved Out Svc Water.Caused by Personnel Error.Valves Opened & Sys Operability Restored.All Svc Water Supply Valves to HPCI Locked Open to Prevent Recurrence |
- on 850222,HPCI Sys Inoperable Due to Valved Out Svc Water.Caused by Personnel Error.Valves Opened & Sys Operability Restored.All Svc Water Supply Valves to HPCI Locked Open to Prevent Recurrence
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000249/LER-1985-006, :on 850222,svc Water Leading to HPCI Room Cooler Discovered Valved Out,Causing Svc Water & HPCI Sys to Be Inoperable.Caused by Personnel Error.Valves Immediately Opened & Sys Restored |
- on 850222,svc Water Leading to HPCI Room Cooler Discovered Valved Out,Causing Svc Water & HPCI Sys to Be Inoperable.Caused by Personnel Error.Valves Immediately Opened & Sys Restored
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000237/LER-1985-006-01, :on 850217,while Shut Down for Refueling,Full Scram Occurred.Caused by Improper Design & Lack of Extensive Design Review.Power Supplies Will Be Redesigned,Rewired & Functionally Tested |
- on 850217,while Shut Down for Refueling,Full Scram Occurred.Caused by Improper Design & Lack of Extensive Design Review.Power Supplies Will Be Redesigned,Rewired & Functionally Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000249/LER-1985-007-05, :on 850302,during Normal Operation,Two Normally Closed Torus Water Sample Valves Discovered Open W/Water Draining to Sump.Caused by Personnel Error.Valves Locked. Procedures Revised |
- on 850302,during Normal Operation,Two Normally Closed Torus Water Sample Valves Discovered Open W/Water Draining to Sump.Caused by Personnel Error.Valves Locked. Procedures Revised
| 10 CFR 50.73(a)(2)(1) |
| 05000237/LER-1985-007-03, :on 850215,weekly Operating Surveillances Not Completed.Caused by Operator Overlooking Surveillances on Weekly Schedule Due to Another Operator Incorrectly Recording Surveillances |
- on 850215,weekly Operating Surveillances Not Completed.Caused by Operator Overlooking Surveillances on Weekly Schedule Due to Another Operator Incorrectly Recording Surveillances
| 10 CFR 50.73(a)(2)(1) |
| 05000237/LER-1985-008-05, :on 850222,reactor Scram Occurred Due to Reactor Protection Sys (RPS) Motor Generator Set B Tripping Resulting in Loss of Power to Channel A.Caused by Early Trip of Thermal Overload Relays.Relays Replaced |
- on 850222,reactor Scram Occurred Due to Reactor Protection Sys (RPS) Motor Generator Set B Tripping Resulting in Loss of Power to Channel A.Caused by Early Trip of Thermal Overload Relays.Relays Replaced
| |
| 05000249/LER-1985-008-04, :on 850311,diesel Generator 2/3 Automatically Started W/No Actuation Signal Present.Caused by Vibration to Auto Start Relay During Mod.Following Auto Start,Engine Loaded & Operated for 88 Minutes |
- on 850311,diesel Generator 2/3 Automatically Started W/No Actuation Signal Present.Caused by Vibration to Auto Start Relay During Mod.Following Auto Start,Engine Loaded & Operated for 88 Minutes
| |
| 05000249/LER-1985-009-03, :on 850205,manual Isolation Valve 3-1699-15 to Torus Sight Glass Discovered Locked in Open Position.Caused by Personnel Error.Dos 1600-2 Changed to Include Second Signature Verifying Locked Closed Position |
- on 850205,manual Isolation Valve 3-1699-15 to Torus Sight Glass Discovered Locked in Open Position.Caused by Personnel Error.Dos 1600-2 Changed to Include Second Signature Verifying Locked Closed Position
| |
| 05000237/LER-1985-009-04, :on 850221,standby Liquid Control Pump Taken Out of Svc & Required Operability Test for Redundant Pump 2B Not Performed Until 850223.Caused by Inadvertent Dept Oversight.Event Discussed W/Shift Personnel |
- on 850221,standby Liquid Control Pump Taken Out of Svc & Required Operability Test for Redundant Pump 2B Not Performed Until 850223.Caused by Inadvertent Dept Oversight.Event Discussed W/Shift Personnel
| 10 CFR 50.73(a)(2)(vi) 10 CFR 50.73(a)(2)(1) |
| 05000237/LER-1985-010-03, :on 850305,fire Door for 125-volt Battery Room Encl Found Open W/O Fire Watch Established within 1 H Per Tech Spec 3.12.F.2.Cause Under Investigation.Suppl Will Be Issued on 850410 W/Results of Investigation |
- on 850305,fire Door for 125-volt Battery Room Encl Found Open W/O Fire Watch Established within 1 H Per Tech Spec 3.12.F.2.Cause Under Investigation.Suppl Will Be Issued on 850410 W/Results of Investigation
| 10 CFR 50.73(a)(2)(1) |
| 05000249/LER-1985-010-07, :on 850427,full Reactor Scram Initiated from Low Water Level W/Subsequent Group II & III Isolation.Cause Undetermined.Level Sensors 263-58 a & B to Be Replaced W/Analog Trip Units |
- on 850427,full Reactor Scram Initiated from Low Water Level W/Subsequent Group II & III Isolation.Cause Undetermined.Level Sensors 263-58 a & B to Be Replaced W/Analog Trip Units
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000237/LER-1985-010, :on 850305,fire Watch Not Established within 1 H of Opening Fire Door for 125-volt Dc Battery Room for Maint on Fire Header Valve Located Outside Room.Caused by Personnel Oversight.Door Closed |
- on 850305,fire Watch Not Established within 1 H of Opening Fire Door for 125-volt Dc Battery Room for Maint on Fire Header Valve Located Outside Room.Caused by Personnel Oversight.Door Closed
| 10 CFR 50.73(a)(2)(1) |
| 05000249/LER-1985-010-01, :on 850427,full Reactor Scram Initiated from Low Water Level.Probably Caused by Vibration Near Sensor Rack Due to Improper Filling & Venting of Shutdown Cooling Sys.Equipment Attendants Retrained |
- on 850427,full Reactor Scram Initiated from Low Water Level.Probably Caused by Vibration Near Sensor Rack Due to Improper Filling & Venting of Shutdown Cooling Sys.Equipment Attendants Retrained
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000237/LER-1985-011-03, :on 850306,reactor Vessel Not Vented at Less than 149 F.Caused by Lack of Procedural Steps to Ensure Vent Path Exists Prior to Completion of Head Vent Piping Replacement.Procedures Changed |
- on 850306,reactor Vessel Not Vented at Less than 149 F.Caused by Lack of Procedural Steps to Ensure Vent Path Exists Prior to Completion of Head Vent Piping Replacement.Procedures Changed
| 10 CFR 50.73(a)(2)(1) |
| 05000249/LER-1985-011-05, :on 850416,reactor Bldg Vent Trip & Isolation Occurred W/Standby Gas Treatment Sys B Automatically Started.Caused by Fuel Handlers Removing Machinery from Fuel Pool.Machinery Washed to Reduce Dose Levels |
- on 850416,reactor Bldg Vent Trip & Isolation Occurred W/Standby Gas Treatment Sys B Automatically Started.Caused by Fuel Handlers Removing Machinery from Fuel Pool.Machinery Washed to Reduce Dose Levels
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000249/LER-1985-011, :on 850416,high Radiation Signal from Refueling Floor Radiation Monitors Caused Reactor Bldg Ventilation Sys Trip & Isolation W/Standby Gas Treatment Sys B Automatically Starting |
- on 850416,high Radiation Signal from Refueling Floor Radiation Monitors Caused Reactor Bldg Ventilation Sys Trip & Isolation W/Standby Gas Treatment Sys B Automatically Starting
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000237/LER-1985-012-02, :on 850309,full Scram Occurred During Reactor Protection Sys Operating Procedure.Caused by Misaligned Styrofoam Block.Relay Calibr Procedures Revised to Require Physical Jumper on Contact |
- on 850309,full Scram Occurred During Reactor Protection Sys Operating Procedure.Caused by Misaligned Styrofoam Block.Relay Calibr Procedures Revised to Require Physical Jumper on Contact
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000249/LER-1985-012-05, :on 850429,feedwater Check Valve 3-220-62A Observed to Leak 587.04 Scfh.W/Previous as Left Leakage, Total Leakage Exceeds Tech Spec Limit.Caused by Worn Pressure Seal Ring.Seal Ring Replaced |
- on 850429,feedwater Check Valve 3-220-62A Observed to Leak 587.04 Scfh.W/Previous as Left Leakage, Total Leakage Exceeds Tech Spec Limit.Caused by Worn Pressure Seal Ring.Seal Ring Replaced
| 10 CFR 50.73(a)(2)(1) |
| 05000249/LER-1985-013-06, :on 850516,discovered That Both Channels of ARM 3-1705-16 Set to Trip at 120 Mr/H in Excess of Tech Spec Limit of 100 Mr/H.Caused by Personnel Error.Individual Instructed Re Usage of Dip 2100-9 |
- on 850516,discovered That Both Channels of ARM 3-1705-16 Set to Trip at 120 Mr/H in Excess of Tech Spec Limit of 100 Mr/H.Caused by Personnel Error.Individual Instructed Re Usage of Dip 2100-9
| |
| 05000237/LER-1985-013-02, :on 850310,ATWS Alternate Rod Insertion Initiated.Caused by Leaking Isolation Valve Which Allowed Hydrostatic Pressure to Bleed Into One Side of Level Diaphragm Causing Low Level Condition |
- on 850310,ATWS Alternate Rod Insertion Initiated.Caused by Leaking Isolation Valve Which Allowed Hydrostatic Pressure to Bleed Into One Side of Level Diaphragm Causing Low Level Condition
| |
| 05000237/LER-1985-014-02, :on 850315,during Reactor Refueling,W/Mode Switch in Shutdown,Reactor Protection Sys Switched from Reserve to Normal Power,Resulting in Full Scram.Caused by Personnel Error.Engineer Responsible Counseled |
- on 850315,during Reactor Refueling,W/Mode Switch in Shutdown,Reactor Protection Sys Switched from Reserve to Normal Power,Resulting in Full Scram.Caused by Personnel Error.Engineer Responsible Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000249/LER-1985-014-07, :on 850520,delay Experienced in Returning Wet Pipe Sprinkler Sys to Svc Following Mod Initiated to Reroute Wet Pipe Sprinkler Sys Piping & Supply Header.Caused by Testing Delays |
- on 850520,delay Experienced in Returning Wet Pipe Sprinkler Sys to Svc Following Mod Initiated to Reroute Wet Pipe Sprinkler Sys Piping & Supply Header.Caused by Testing Delays
| |
| 05000237/LER-1985-015-02, :on 850325,three Main Steam Line Low Pressure Isolation Switches Tripped Below Tech Spec Min Trip Point. Caused by Instrument Setpoint Drift.Switches Recalibr to Meet Tech Spec Limit & Successfully Tested |
- on 850325,three Main Steam Line Low Pressure Isolation Switches Tripped Below Tech Spec Min Trip Point. Caused by Instrument Setpoint Drift.Switches Recalibr to Meet Tech Spec Limit & Successfully Tested
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 05000237/LER-1985-015, :on 850325,three Main Steam Line Low Pressure Switches Tripped Below Tech Spec Min Trip Point.Caused by Instrument Setpoint Drift.Switches Immediately Recalibr & Tested |
- on 850325,three Main Steam Line Low Pressure Switches Tripped Below Tech Spec Min Trip Point.Caused by Instrument Setpoint Drift.Switches Immediately Recalibr & Tested
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 05000249/LER-1985-015-07, :on 850820,during Functional Test,Reactor Bldg Vent Sys Inadvertently Tripped & Isolated.Caused by Procedural Violation Due to Instrument Mechanic Error. Tailgate Presented.Mechanic Counseled |
- on 850820,during Functional Test,Reactor Bldg Vent Sys Inadvertently Tripped & Isolated.Caused by Procedural Violation Due to Instrument Mechanic Error. Tailgate Presented.Mechanic Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000237/LER-1985-016-03, :on 850411,during Startup Following Refueling outage,0000 H Pumpdown of Drywell Floor & Equipment Sumps Not Performed.Cause Not Stated.Operator Briefed as to Importance of Sump Pumping at Proper Time |
- on 850411,during Startup Following Refueling outage,0000 H Pumpdown of Drywell Floor & Equipment Sumps Not Performed.Cause Not Stated.Operator Briefed as to Importance of Sump Pumping at Proper Time
| 10 CFR 50.73(a)(2)(1) |
| 05000249/LER-1985-016-07, :on 850826,equipment Attendant Observed HPCI Room Cooler Fan Breaker Emitting Smoke.Caused by Shorted Motor Contactor Coil.Coil & Auxiliary Contacts Replaced & Maint Procedure DMP 7300-5 Performed |
- on 850826,equipment Attendant Observed HPCI Room Cooler Fan Breaker Emitting Smoke.Caused by Shorted Motor Contactor Coil.Coil & Auxiliary Contacts Replaced & Maint Procedure DMP 7300-5 Performed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000249/LER-1985-017-06, :on 850905,fuel Pool Channel B High Radiation Trip Occurred,Causing Ventilation Sys Trip & Starting Gas Treatment Sys.Caused by Chips in water-filled Bucket Used for Cleanup.Bucket Immersed in Fuel Pool |
- on 850905,fuel Pool Channel B High Radiation Trip Occurred,Causing Ventilation Sys Trip & Starting Gas Treatment Sys.Caused by Chips in water-filled Bucket Used for Cleanup.Bucket Immersed in Fuel Pool
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000237/LER-1985-017-03, :on 850413,during Startup,Reactor Water Samples Not Taken Every 4 H.Caused by Misunderstanding Between Personnel.Personnel Briefed on Importance of Providing & Following Specific Instructions During Startup |
- on 850413,during Startup,Reactor Water Samples Not Taken Every 4 H.Caused by Misunderstanding Between Personnel.Personnel Briefed on Importance of Providing & Following Specific Instructions During Startup
| 10 CFR 50.73(a)(2)(1) |
| 05000237/LER-1985-018-03, :on 850415,routine Svc Water Effluent Samples Taken 6 H After 12 H Tech Spec Time Limit Expired.Caused by Personnel Error.Responsible Individual Retrained.Technician Routine Checklist Updated |
- on 850415,routine Svc Water Effluent Samples Taken 6 H After 12 H Tech Spec Time Limit Expired.Caused by Personnel Error.Responsible Individual Retrained.Technician Routine Checklist Updated
| 10 CFR 50.73(a)(2)(1) |
| 05000237/LER-1985-019-03, :on 850419,diesel Generator 2/3 Automatically Started W/O Bus undervoltage,lo-lo Water Level or Drywell High Pressure.Caused by Possible Inadvertent Jarring of Auto Start Relay 1430-108A |
- on 850419,diesel Generator 2/3 Automatically Started W/O Bus undervoltage,lo-lo Water Level or Drywell High Pressure.Caused by Possible Inadvertent Jarring of Auto Start Relay 1430-108A
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000249/LER-1985-019-07, :on 850923,observed That Reactor Not Vented at Less than 149 F.Caused by Failure of Shutdown Procedure to Completely Outline Conditions to Vent Reactor.Reactor Head Vents Opened |
- on 850923,observed That Reactor Not Vented at Less than 149 F.Caused by Failure of Shutdown Procedure to Completely Outline Conditions to Vent Reactor.Reactor Head Vents Opened
| 10 CFR 50.73(a)(2)(1) |
| 05000249/LER-1985-020-05, :on 850925,no Particulate Sample for Reactor Bldg Ventilation Sys Collected for Wk.Caused by Failure to Replace Screen in Filter Holder After Last Sample.Signs to Be Posted in Future |
- on 850925,no Particulate Sample for Reactor Bldg Ventilation Sys Collected for Wk.Caused by Failure to Replace Screen in Filter Holder After Last Sample.Signs to Be Posted in Future
| 10 CFR 50.73(a)(2)(1) |
| 05000237/LER-1985-020-02, :on 850424,during HPCI Steam Line High Flow Isolation Surveillance,Hpci Valve 2301-H Failed to Close. Caused by Dirty Breaker Auxiliary Contacts.Contacts Cleaned & Later Replaced |
- on 850424,during HPCI Steam Line High Flow Isolation Surveillance,Hpci Valve 2301-H Failed to Close. Caused by Dirty Breaker Auxiliary Contacts.Contacts Cleaned & Later Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000237/LER-1985-021-02, :on 850503,during Shutdown,Two Reactor Scrams Occurred from Intermediate Range Monitors 13 & 15 hi-hi Condition.Caused by Spurious Radio Repeater Signals. Relocation of Radio Repeaters Initiated |
- on 850503,during Shutdown,Two Reactor Scrams Occurred from Intermediate Range Monitors 13 & 15 hi-hi Condition.Caused by Spurious Radio Repeater Signals. Relocation of Radio Repeaters Initiated
| 10 CFR 50.73(a)(2)(iv), System Actuation |