05000482/LER-1985-001, :on 850313,16 & 19,containment Purge Isolation & Control Room Ventilation Isolation Signals Actuated During Initial Fuel Loading.Caused by Faulty Relay in Radiation Monitor.Relay Replaced

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:on 850313,16 & 19,containment Purge Isolation & Control Room Ventilation Isolation Signals Actuated During Initial Fuel Loading.Caused by Faulty Relay in Radiation Monitor.Relay Replaced
Person / Time
ML20115G642
Site:	Wolf Creek
Issue date:	04/12/1985
From:	Koester G, Mike Williams KANSAS GAS & ELECTRIC CO.
To:	Denise R NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
KMLNRC-85-083, KMLNRC-85-83, LER-85-001, LER-85-1, NUDOCS 8504220273
Download: ML20115G642 (3)
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LER-1985-001, on 850313,16 & 19,containment Purge Isolation & Control Room Ventilation Isolation Signals Actuated During Initial Fuel Loading.Caused by Faulty Relay in Radiation Monitor.Relay Replaced

Event date:
Report date:
4821985001R00 - NRC Website
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text

Licensee Event Report

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		Reporting criterion
05000482/LER-1985-001, :on 850313,16 & 19,containment Purge Isolation & Control Room Ventilation Isolation Signals Actuated During Initial Fuel Loading.Caused by Faulty Relay in Radiation Monitor.Relay Replaced	on 850313,16 & 19,containment Purge Isolation & Control Room Ventilation Isolation Signals Actuated During Initial Fuel Loading.Caused by Faulty Relay in Radiation Monitor.Relay Replaced
05000482/LER-1985-002, :on 850313,control Room Air Intake Radiation Element in Bypass for Greater than 1 H W/O Isolating Emergency Ventilation Sys.Caused by Personnel Error. Personnel Counseled	on 850313,control Room Air Intake Radiation Element in Bypass for Greater than 1 H W/O Isolating Emergency Ventilation Sys.Caused by Personnel Error. Personnel Counseled
05000482/LER-1985-003, :on 850314,ESF Signal Initiated.Caused by Operator Deenergizing Control Room Radiation Monitor.Error Reviewed by Shift Supervisor & Personnel	on 850314,ESF Signal Initiated.Caused by Operator Deenergizing Control Room Radiation Monitor.Error Reviewed by Shift Supervisor & Personnel
05000482/LER-1985-004, :on 850319,following Initial Fuel Loading, Hourly Fire Watch Patrols for One Room in Auxiliary Bldg & One Room in Control Bldg Missed.Patrols Reestablished.W/	on 850319,following Initial Fuel Loading, Hourly Fire Watch Patrols for One Room in Auxiliary Bldg & One Room in Control Bldg Missed.Patrols Reestablished.W/	10 CFR 50.73(a)(2)(i)
05000482/LER-1985-005, :on 850311,one roll-up Fire Door in Auxiliary Bldg Not Verified Closed Every 7 Days.Caused by Revised Surveillance Procedure Approved on 850226.Procedure Change Initiated & Issued on 850411	on 850311,one roll-up Fire Door in Auxiliary Bldg Not Verified Closed Every 7 Days.Caused by Revised Surveillance Procedure Approved on 850226.Procedure Change Initiated & Issued on 850411	10 CFR 50.73(a)(2)(i)
05000482/LER-1985-006, 00:on 850407,ESF Actuation Resulted Due to Inadvertent Actuation of Fuel Bldg Ventilation & Control Room Ventilation Isolation Signals.Caused by Personnel Error.Personnel Counseled	00:on 850407,ESF Actuation Resulted Due to Inadvertent Actuation of Fuel Bldg Ventilation & Control Room Ventilation Isolation Signals.Caused by Personnel Error.Personnel Counseled	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-007, :on 850408,control Room Ventilation Isolation Signal Occurred During Surveillance Procedure in Mode 5. Caused by Personnel Error.Control Room HVAC Monitor Bypassed.Personnel Counseled	on 850408,control Room Ventilation Isolation Signal Occurred During Surveillance Procedure in Mode 5. Caused by Personnel Error.Control Room HVAC Monitor Bypassed.Personnel Counseled	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-008, :on 850409,ESF Actuation Signal Initiated While Resetting Flow on Containment Purge Gaseous Activity Monitor.Caused by Faulty Vacuum Transducer.Transducer Replaced	on 850409,ESF Actuation Signal Initiated While Resetting Flow on Containment Purge Gaseous Activity Monitor.Caused by Faulty Vacuum Transducer.Transducer Replaced	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-009, :on 850412,ESF Actuation Signal Initiated When Several Radiation Monitors Deenergized.Caused by Ground Fault Indication Tripping Power Supply Breaker.Breaker Reset & Power Restored	on 850412,ESF Actuation Signal Initiated When Several Radiation Monitors Deenergized.Caused by Ground Fault Indication Tripping Power Supply Breaker.Breaker Reset & Power Restored
05000482/LER-1985-010-01, :on 850411,preaction Sprinkler Sys for Area Containing Redundant Sys Taken Out of Svc W/O Establishing Required Continuous Fire Watch.Situation Discovered on 850413.Caused by Personnel Error	on 850411,preaction Sprinkler Sys for Area Containing Redundant Sys Taken Out of Svc W/O Establishing Required Continuous Fire Watch.Situation Discovered on 850413.Caused by Personnel Error	10 CFR 50.73(a)(2)(1)
05000482/LER-1985-010, :on 850413,preaction Sprinkler Sys for Redundant Sys or Components Discovered Taken Out of Svc on 850411 W/O Establishing Continuous Fire Watch.Caused by Personnel Error.Event Reviewed W/Personnel	on 850413,preaction Sprinkler Sys for Redundant Sys or Components Discovered Taken Out of Svc on 850411 W/O Establishing Continuous Fire Watch.Caused by Personnel Error.Event Reviewed W/Personnel	10 CFR 50.73(a)(2)(i)
05000482/LER-1985-011, :on 850412,control Room Ventilation Isolation Signal Occurred.Caused by Spurious Spike on Chlorine Monitor GK-AITS-2.Monitor Placed in Bypass & Later Returned to Svc	on 850412,control Room Ventilation Isolation Signal Occurred.Caused by Spurious Spike on Chlorine Monitor GK-AITS-2.Monitor Placed in Bypass & Later Returned to Svc	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-012, :on 850419,inadvertent Train B Safety Injection Occurred.Caused by Loose Limit Switch Tug in Valve Motor Operator.Switch Lug Repaired	on 850419,inadvertent Train B Safety Injection Occurred.Caused by Loose Limit Switch Tug in Valve Motor Operator.Switch Lug Repaired	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-013, :on 850506,15,23,26 & 30,ESF Actuation Signal Initiated by Control Room Intake Radiation Monitor Spurious Alarm,Causing Control Room Ventilation Isolation Signal. Caused by Mismatch in Microprocessing Unit	on 850506,15,23,26 & 30,ESF Actuation Signal Initiated by Control Room Intake Radiation Monitor Spurious Alarm,Causing Control Room Ventilation Isolation Signal. Caused by Mismatch in Microprocessing Unit
05000482/LER-1985-014, :on 850421,ESFAS Initiated When Control Room Chlorine Monitor Ran Out of Paper,Causing Ventilation Isolation Signal.Caused by Personnel Error.Schedule for Changing Paper Increased to Twice Weekly	on 850421,ESFAS Initiated When Control Room Chlorine Monitor Ran Out of Paper,Causing Ventilation Isolation Signal.Caused by Personnel Error.Schedule for Changing Paper Increased to Twice Weekly	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-017, :on 850424,Ruskin Mfg Co Fire Dampers Found in Violation of Tech Specs Since Issuance of OL on 850311. Caused by Insufficient Clearance Between Damper Frames & Penetration Sleeves.Fire Watches Established	on 850424,Ruskin Mfg Co Fire Dampers Found in Violation of Tech Specs Since Issuance of OL on 850311. Caused by Insufficient Clearance Between Damper Frames & Penetration Sleeves.Fire Watches Established	10 CFR 50.73(a)(2)(i)
05000482/LER-1985-019, :on 850426,auxiliary Feedwater Actuation Signal Occurred.Caused by Operator Placing Switch FC-HS-25 in Permit Position.Switch Returned to Block Position.Error Discussed W/Operating Personnel	on 850426,auxiliary Feedwater Actuation Signal Occurred.Caused by Operator Placing Switch FC-HS-25 in Permit Position.Switch Returned to Block Position.Error Discussed W/Operating Personnel
05000482/LER-1985-020, :on 850429,ESF Actuation Signal Initiated When Steam Generator C Water Level Increased to High Level Setpoint.Caused by Personnel Error.Event Considered Isolated Case.Shift Supervisor & Personnel Counseled	on 850429,ESF Actuation Signal Initiated When Steam Generator C Water Level Increased to High Level Setpoint.Caused by Personnel Error.Event Considered Isolated Case.Shift Supervisor & Personnel Counseled
05000482/LER-1985-021, :on 850428,ESF Actuation Occurred.Caused by Anticipatory Trip Generated by rate-sensitive Steam Generator Circuiting Due to Personnel Error.Setpoint Actuation Will Be Stressed During Training	on 850428,ESF Actuation Occurred.Caused by Anticipatory Trip Generated by rate-sensitive Steam Generator Circuiting Due to Personnel Error.Setpoint Actuation Will Be Stressed During Training
05000482/LER-1985-022, :on 850430,safety Injection & Main Steam Line Isolation Occurred,Causing ESF Actuation.Unusual Event Declared & Subsequently Canceled.Caused by Interference from Operator Radio.Radio Use Restricted	on 850430,safety Injection & Main Steam Line Isolation Occurred,Causing ESF Actuation.Unusual Event Declared & Subsequently Canceled.Caused by Interference from Operator Radio.Radio Use Restricted	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-023, :on 850501,reactor Protection Sys Trip Signal & ESFAS Initiated During Startup Test Procedure in Mode 3. Caused by Personnel Error.Plant Testing Temporarily Suspended.Personnel Counseled	on 850501,reactor Protection Sys Trip Signal & ESFAS Initiated During Startup Test Procedure in Mode 3. Caused by Personnel Error.Plant Testing Temporarily Suspended.Personnel Counseled	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-024, :on 850501,ESFAS Signal Initiated When Steam Generator a Level Indication Spiked Low,Resulting in Initiation of Feedwater Isolation Signal & Auxiliary Feedwater Actuation Signal	on 850501,ESFAS Signal Initiated When Steam Generator a Level Indication Spiked Low,Resulting in Initiation of Feedwater Isolation Signal & Auxiliary Feedwater Actuation Signal
05000482/LER-1985-025, :on 850501,two Main Steam Line Isolation Valves Declared Inoperable.Caused by Hydraulic Oil Pump Malfunction.Oil Pumps Replaced & Valves Tested	on 850501,two Main Steam Line Isolation Valves Declared Inoperable.Caused by Hydraulic Oil Pump Malfunction.Oil Pumps Replaced & Valves Tested	10 CFR 50.73(a)(2)(i)
05000482/LER-1985-026, :on 850506,ESFAS Signal Initiated When Two Radiation Monitors Deenergized Due to Inadvertent Loss of Power to safety-related 480-volt Ac Load Ctr.Caused by Personnel Error.Sys Restored to Normal	on 850506,ESFAS Signal Initiated When Two Radiation Monitors Deenergized Due to Inadvertent Loss of Power to safety-related 480-volt Ac Load Ctr.Caused by Personnel Error.Sys Restored to Normal
05000482/LER-1985-027, :on 850506,ESF Actuation Occurred,Resulting in Safety Injection & Main Steam Line Isolation Due to Low Steam Line Pressure Signal on Steam Generator A.Caused by Personnel Error.Personnel Counseled	on 850506,ESF Actuation Occurred,Resulting in Safety Injection & Main Steam Line Isolation Due to Low Steam Line Pressure Signal on Steam Generator A.Caused by Personnel Error.Personnel Counseled	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-028, :on 850516,auxiliary Feedwater Actuation Signal Initiated When Steam Generator D Decreased Below lo-lo Actuation Setpoint.Caused by Personnel Error.Personnel Counseled & Required to Read LER	on 850516,auxiliary Feedwater Actuation Signal Initiated When Steam Generator D Decreased Below lo-lo Actuation Setpoint.Caused by Personnel Error.Personnel Counseled & Required to Read LER	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-029, :on 850506,containment Purge Isolation Control Room Ventilation Isolation & Fuel Bldg Ventilation Isolation Signals Occurred During Recovery from Safety Injection. Caused by Procedural Deficiency	on 850506,containment Purge Isolation Control Room Ventilation Isolation & Fuel Bldg Ventilation Isolation Signals Occurred During Recovery from Safety Injection. Caused by Procedural Deficiency	10 CFR 50.73(a)(2)
05000482/LER-1985-030, :on 850518,ESFAS & Feedwater Isolation Occurred When Steam Generator Level Transmitter Sensed Erroneous High Level Condition.Caused by Pressure Perturbation in Common Sensing Line	on 850518,ESFAS & Feedwater Isolation Occurred When Steam Generator Level Transmitter Sensed Erroneous High Level Condition.Caused by Pressure Perturbation in Common Sensing Line	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-031, :on 850611,ESF Actuation Signal Initiated Due to hi-hi Water Level in Steam Generator C,Initiating Feedwater Isolation,Main Turbine Trip & Main Feedwater Pump Trip Signals	on 850611,ESF Actuation Signal Initiated Due to hi-hi Water Level in Steam Generator C,Initiating Feedwater Isolation,Main Turbine Trip & Main Feedwater Pump Trip Signals	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-032, :on 850521,containment Purge & Control Room Ventilation Isolation Signals Initiated.Caused by Inadvertent Repositioning of ESFAS Cabinet Test Switch While Performing Test Procedure STS IC-230	on 850521,containment Purge & Control Room Ventilation Isolation Signals Initiated.Caused by Inadvertent Repositioning of ESFAS Cabinet Test Switch While Performing Test Procedure STS IC-230	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-033, :on 850523,manual Control Room Ventilation Isolation Signal Initiated.Caused by Electronic Spike from Control Room Chlorine Monitor Displaying Erratic Behavior. Potential Equipment Mod Under Evaluation	on 850523,manual Control Room Ventilation Isolation Signal Initiated.Caused by Electronic Spike from Control Room Chlorine Monitor Displaying Erratic Behavior. Potential Equipment Mod Under Evaluation	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-034, :on 850524,containment Water Level Instrument LF-LI-09 Found in out-of-svc Condition.Caused by Obstruction on Slide Pole Resulting from Insulation Activity.Obstruction Removed & Instrument Returned to Svc	on 850524,containment Water Level Instrument LF-LI-09 Found in out-of-svc Condition.Caused by Obstruction on Slide Pole Resulting from Insulation Activity.Obstruction Removed & Instrument Returned to Svc	10 CFR 50.73(a)(2)(1)
05000000/LER-1985-035, Forwards LER 85-035-00 Re Physical Security Event	Forwards LER 85-035-00 Re Physical Security Event
05000482/LER-1985-036, :on 850531,when Steam Generator Level Bistable Tripped in Error During Maint,Esfas Initiated.All ESF Equipment Responded Properly.No Equipment Damage or Release of Radioactivity Noted	on 850531,when Steam Generator Level Bistable Tripped in Error During Maint,Esfas Initiated.All ESF Equipment Responded Properly.No Equipment Damage or Release of Radioactivity Noted	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-036-01, :on 850531,ESF Actuation Signal Initiated When Steam Generator Level Bistable Tripped in Error During Maint Activity.Caused by Technician Pressing Trip Button on Wrong Bistable Logic Card.Personnel Counseled	on 850531,ESF Actuation Signal Initiated When Steam Generator Level Bistable Tripped in Error During Maint Activity.Caused by Technician Pressing Trip Button on Wrong Bistable Logic Card.Personnel Counseled	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-037, :on 850602,spurious Electronic Spike in Control Room Intake Radiation Monitor (GK-RE-04) Occurred. Caused by Mismatch Between Software & Hardware in Microprocessing Unit RM-80	on 850602,spurious Electronic Spike in Control Room Intake Radiation Monitor (GK-RE-04) Occurred. Caused by Mismatch Between Software & Hardware in Microprocessing Unit RM-80	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-038, :on 850604,auxiliary Feedwater Actuation Signal & Steam Generator Blowdown & Sample Isolation Signal Initiated.Caused by Auxiliary Boiler Trip.Pumps Secured	on 850604,auxiliary Feedwater Actuation Signal & Steam Generator Blowdown & Sample Isolation Signal Initiated.Caused by Auxiliary Boiler Trip.Pumps Secured	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-039, :on 850606,during Test of Steam Dump Control Sys,Reactor Trip & Low Coolant Sys Average Temp Initiated Feedwater Isolation Signal.Caused by lo-lo Steam Generator Water Level.Water Levels Returned to Normal	on 850606,during Test of Steam Dump Control Sys,Reactor Trip & Low Coolant Sys Average Temp Initiated Feedwater Isolation Signal.Caused by lo-lo Steam Generator Water Level.Water Levels Returned to Normal	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-040, :on Seven Occasions Between 850702 & 12,ESF Actuation Initiated Control Room Intake Radiation Monitor Spurious Alarm.Caused by Mismatch Between Software & Hardware in Microprocessing Unit	on Seven Occasions Between 850702 & 12,ESF Actuation Initiated Control Room Intake Radiation Monitor Spurious Alarm.Caused by Mismatch Between Software & Hardware in Microprocessing Unit	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-041, :on 850609 & 13,auxiliary Feedwater Actuation & Steam Generator Blowdown & Sample Isolation Occurred. Caused by Main Feedwater Pump a Trips	on 850609 & 13,auxiliary Feedwater Actuation & Steam Generator Blowdown & Sample Isolation Occurred. Caused by Main Feedwater Pump a Trips	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-042, :on 850705 & 11,ESF Actuation Occurred Resulting in Feedwater Isolation,Main Turbine Trip & Main Feedwater Pump Trips.Caused by High Water Levels in Steam Generator & Overlap Between Setpoints	on 850705 & 11,ESF Actuation Occurred Resulting in Feedwater Isolation,Main Turbine Trip & Main Feedwater Pump Trips.Caused by High Water Levels in Steam Generator & Overlap Between Setpoints	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-043, :on 850609,feedwater Isolation Signal,Main Turbine Trip & Steam Generator Feed Pump Turbine Trip Signals Occurred Due to hi-hi Water Level in Steam Generator A.Caused by Leak Through Main Control Valves	on 850609,feedwater Isolation Signal,Main Turbine Trip & Steam Generator Feed Pump Turbine Trip Signals Occurred Due to hi-hi Water Level in Steam Generator A.Caused by Leak Through Main Control Valves	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-044, :on 850614,feedwater Isolation,Auxiliary Feedwater Actuation,Steam Generator Blowdown & Sample Isolation Occurred.Caused by Higher than Actual Indication of Reactor Power Level	on 850614,feedwater Isolation,Auxiliary Feedwater Actuation,Steam Generator Blowdown & Sample Isolation Occurred.Caused by Higher than Actual Indication of Reactor Power Level	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-045, :on 850623,reactor Trip Occurred During Performance of Surveillance Test STS IC-211A.Caused by Inadvertent Breaker Trip Due to Confusing Procedural Steps. Procedure Revised	on 850623,reactor Trip Occurred During Performance of Surveillance Test STS IC-211A.Caused by Inadvertent Breaker Trip Due to Confusing Procedural Steps. Procedure Revised	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-047, :on 850622,hourly Fire Watch Patrol Not Performed in Several Areas of Auxiliary Bldg.Caused by Personnel Error.Individual Dismissed & Hourly Fire Watch Patrols Performed by Permanent Personnel	on 850622,hourly Fire Watch Patrol Not Performed in Several Areas of Auxiliary Bldg.Caused by Personnel Error.Individual Dismissed & Hourly Fire Watch Patrols Performed by Permanent Personnel	10 CFR 50.73(a)(2)(i)
05000482/LER-1985-048, :on 850628,daily Calorimetric Heat Balance Test & Adjustment of ex-core Nuclear Instrumentation Channel Gains Determined Not Performed from 850615-0623.Caused by Isolated Personnel Oversight	on 850628,daily Calorimetric Heat Balance Test & Adjustment of ex-core Nuclear Instrumentation Channel Gains Determined Not Performed from 850615-0623.Caused by Isolated Personnel Oversight	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1)
05000482/LER-1985-049, :on 850709,ESF Actuation & Reactor Trip Occurred Due to lo-lo Water Level in Steam Generator C. Caused by Loss of Feedwater Flow Due to Installation & Removal of Test Equipment.Personnel Counseled	on 850709,ESF Actuation & Reactor Trip Occurred Due to lo-lo Water Level in Steam Generator C. Caused by Loss of Feedwater Flow Due to Installation & Removal of Test Equipment.Personnel Counseled
05000482/LER-1985-050, :on 850710,hi-hi Water Level in Steam Generator Initiated Feedwater Isolation,Main Turbine Trip & Feedwater Pump Trip.Caused by Excessive Leakage Through Feedwater Control Valve.Valve Connections Adjusted	on 850710,hi-hi Water Level in Steam Generator Initiated Feedwater Isolation,Main Turbine Trip & Feedwater Pump Trip.Caused by Excessive Leakage Through Feedwater Control Valve.Valve Connections Adjusted	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-051, :on 850720,standby Emergency Diesel Generator a Inadvertently Started,Causing ESF Actuation.Caused by Technician Bumping Start Relay for Generator.Technician Admonished to Exercise Caution	on 850720,standby Emergency Diesel Generator a Inadvertently Started,Causing ESF Actuation.Caused by Technician Bumping Start Relay for Generator.Technician Admonished to Exercise Caution	10 CFR 50.73(a)(2)(iv), System Actuation
05000482/LER-1985-052, :on 850712,control Room Ventilation Isolation Signal Initiated Due to Alarm on Control Room HVAC Chlorine Monitor.Caused by Broken Filter Paper Tape.Tape Replaced	on 850712,control Room Ventilation Isolation Signal Initiated Due to Alarm on Control Room HVAC Chlorine Monitor.Caused by Broken Filter Paper Tape.Tape Replaced	10 CFR 50.73(a)(2)(iv), System Actuation
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