| | | Reporting criterion |
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| 05000362/LER-1984-001, :on 840101,precautionary Penetration & Radwaste Bldgs Evacuation Initiated When Units 2 & 3 Area Radiation Monitors & Plant Vent Stack Monitors Alarmed.Caused by Routine Draining of Waste Gas Header Line |
- on 840101,precautionary Penetration & Radwaste Bldgs Evacuation Initiated When Units 2 & 3 Area Radiation Monitors & Plant Vent Stack Monitors Alarmed.Caused by Routine Draining of Waste Gas Header Line
| 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii)(A) |
| 05000361/LER-1984-001, :on 840111,preparation of Fire Hazard Analysis & Review of Fire Protection Surveillance Results Identified Deficiencies in Fire Protection Program.Review in Progress. Complete Rept Will Be Submitted by 840228 |
- on 840111,preparation of Fire Hazard Analysis & Review of Fire Protection Surveillance Results Identified Deficiencies in Fire Protection Program.Review in Progress. Complete Rept Will Be Submitted by 840228
| |
| 05000361/LER-1984-001-01, :on 840111,preparation of Updated Fire Hazards Analysis Resulted in 91 Nonconformance Repts (NCR) Re Fire Protection Program Deficiencies.Compensatory Measures Established.Ncr Dispositions Planned |
- on 840111,preparation of Updated Fire Hazards Analysis Resulted in 91 Nonconformance Repts (NCR) Re Fire Protection Program Deficiencies.Compensatory Measures Established.Ncr Dispositions Planned
| |
| 05000362/LER-1984-002, :on 840107,penetration Bldg Airborne Iodine of Noble Gas Concentrations Increased Above Precautionary Level.Cause Under Investigation.Engineering Evaluation Will Determine Corrective Actions |
- on 840107,penetration Bldg Airborne Iodine of Noble Gas Concentrations Increased Above Precautionary Level.Cause Under Investigation.Engineering Evaluation Will Determine Corrective Actions
| 10 CFR 50.73(a)(2)(1) |
| 05000362/LER-1984-003, :on 840107,while in Mode 3 at Zero Power,During Planned Reactor Shutdown,Control Element Assembly (CEA) 64 Slipped 30 Inches.Caused by Sluggish Operation of CEA Drive Mechanism.Vendor Requested to Review Event |
- on 840107,while in Mode 3 at Zero Power,During Planned Reactor Shutdown,Control Element Assembly (CEA) 64 Slipped 30 Inches.Caused by Sluggish Operation of CEA Drive Mechanism.Vendor Requested to Review Event
| |
| 05000361/LER-1984-003-01, :on 840122,containment Purge Isolation Sys Actuated When Gaseous Activity Alarm Setpoint Reached Train a Containment Airborne Monitor 2RT7804.Caused by Increase in Containment Background Radiation |
- on 840122,containment Purge Isolation Sys Actuated When Gaseous Activity Alarm Setpoint Reached Train a Containment Airborne Monitor 2RT7804.Caused by Increase in Containment Background Radiation
| |
| 05000361/LER-1984-004, :on 840116,train a Containment Purge Isolation Sys Spuriously Actuated.Caused by Subgroup Relay Actuation Voltage Transient on ESF Bus.No Corrective Action Planned as Minor Transients Expected in Test |
- on 840116,train a Containment Purge Isolation Sys Spuriously Actuated.Caused by Subgroup Relay Actuation Voltage Transient on ESF Bus.No Corrective Action Planned as Minor Transients Expected in Test
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000362/LER-1984-004-01, :on 840222,three Safety Injection Pumps Started & Injected 150 Gallons of Water Into Rcs.Caused by Dirty Contacts on Relay Hold Pushbutton.Contacts Cleaned |
- on 840222,three Safety Injection Pumps Started & Injected 150 Gallons of Water Into Rcs.Caused by Dirty Contacts on Relay Hold Pushbutton.Contacts Cleaned
| 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 50.72(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) |
| 05000362/LER-1984-005, :on 840106,following Reactor Trip for Testing, RCS Sample Analysis Indicated That RCS Specific Activity Exceeded 1.0 Uci/G Dose Equivalent.Cause Indicative of Iodine Spiking Following Power Change |
- on 840106,following Reactor Trip for Testing, RCS Sample Analysis Indicated That RCS Specific Activity Exceeded 1.0 Uci/G Dose Equivalent.Cause Indicative of Iodine Spiking Following Power Change
| |
| 05000361/LER-1984-005-01, :on 840127,while in Mode 5,w/purge/vent Stack wide-range Monitor 3RT-7865 & Flow Rate Monitor Out of Svc for Installation of Noise Suppression Circuit,Flow Rate Estimates Not Performed as Required |
- on 840127,while in Mode 5,w/purge/vent Stack wide-range Monitor 3RT-7865 & Flow Rate Monitor Out of Svc for Installation of Noise Suppression Circuit,Flow Rate Estimates Not Performed as Required
| 10 CFR 50.73(a)(2)(1) |
| 05000361/LER-1984-006, :on 840103,spurious Toxic Gas Isolation Sys Actuations Occurred.Caused by Toxic Gas Isolation Sys Setpoint Set at Threshold Level of Detection.Tech Specs Revised to Raise Setpoint Requirements |
- on 840103,spurious Toxic Gas Isolation Sys Actuations Occurred.Caused by Toxic Gas Isolation Sys Setpoint Set at Threshold Level of Detection.Tech Specs Revised to Raise Setpoint Requirements
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000362/LER-1984-006-01, :on 840226,during Surveillance,Reactor Trip Breaker 8 Undervoltage Device Did Not Actuate.Caused by Metal Filings Between Two Terminals of Control Room Pushbutton.No Corrective Action Planned |
- on 840226,during Surveillance,Reactor Trip Breaker 8 Undervoltage Device Did Not Actuate.Caused by Metal Filings Between Two Terminals of Control Room Pushbutton.No Corrective Action Planned
| 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)(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) 10 CFR 50.73(a)(2)(1) |
| 05000361/LER-1984-007, :on 840203 & 04,Train a & B Main Steam Isolation Sys Spuriously Actuated on Low Pressure Signal from E-088.Caused by Voltage Fluctuation Resulting from Electrical Realignments,Testing & Maint |
- on 840203 & 04,Train a & B Main Steam Isolation Sys Spuriously Actuated on Low Pressure Signal from E-088.Caused by Voltage Fluctuation Resulting from Electrical Realignments,Testing & Maint
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000362/LER-1984-007-01, :on 840305,spurious Reactor Protection Sys Trip Occurred.Cause Undetermined.No Restrictions Placed on Plant Operations as Result of Trip |
- on 840305,spurious Reactor Protection Sys Trip Occurred.Cause Undetermined.No Restrictions Placed on Plant Operations as Result of Trip
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000362/LER-1984-008, :on 840310,operators Received Indications of Possible Saltwater Leak in One Main Condenser Quadrant. Caused by Water in Air Removal Piping.Drain Lines Cleaned |
- on 840310,operators Received Indications of Possible Saltwater Leak in One Main Condenser Quadrant. Caused by Water in Air Removal Piping.Drain Lines Cleaned
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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) |
| 05000361/LER-1984-008-02, :on 840211,inadvertent Entry Into Mode 3 Occurred.Caused by Failure of Plant Monitoring Sys (PMS) Due to Incorrect RCS Temp Display.Pms Display Repaired & Returned to Svc |
- on 840211,inadvertent Entry Into Mode 3 Occurred.Caused by Failure of Plant Monitoring Sys (PMS) Due to Incorrect RCS Temp Display.Pms Display Repaired & Returned to Svc
| 10 CFR 50.73(a)(2)(1) |
| 05000361/LER-1984-009, :on 840214,analysis of Startup Test Data Established Calculated Thermal Power Calculated by Core Protection Calculators May Become Decalibr Relative to Secondary Calorimetric Power.Procedure Changed |
- on 840214,analysis of Startup Test Data Established Calculated Thermal Power Calculated by Core Protection Calculators May Become Decalibr Relative to Secondary Calorimetric Power.Procedure Changed
| |
| 05000362/LER-1984-009, :on 840317,during Surveillance of Sys Alignment Status,Manual Isolation Valves Found Closed,Rendering Both Trains of Containment Spray Sys Inoperable.Procedure Modified to Clarify Valve Lineup Requirements |
- on 840317,during Surveillance of Sys Alignment Status,Manual Isolation Valves Found Closed,Rendering Both Trains of Containment Spray Sys Inoperable.Procedure Modified to Clarify Valve Lineup Requirements
| 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)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000361/LER-1984-009-01, Revised LER 84-009-01:on 840214,analysis of Startup Test Data for Units 2 & 3 Established That Calculated Thermal Power May Become Decalibr Relative to Secondary Calometric Power.Procedure S023-5-1 Revised | Revised LER 84-009-01:on 840214,analysis of Startup Test Data for Units 2 & 3 Established That Calculated Thermal Power May Become Decalibr Relative to Secondary Calometric Power.Procedure S023-5-1 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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1) |
| 05000206/LER-1984-009-02, :on 841205,load Sequencer 31-day Surveillance Delinquent.Caused by Personnel Oversight.Personnel Counseled & Performance of Tech Spec Required Surveillances in Specified Manner Reemphasized |
- on 841205,load Sequencer 31-day Surveillance Delinquent.Caused by Personnel Oversight.Personnel Counseled & Performance of Tech Spec Required Surveillances in Specified Manner Reemphasized
| 10 CFR 50.73(a)(2)(1) |
| 05000362/LER-1984-009-01, Forwards LER 84-009-01 | Forwards LER 84-009-01 | |
| 05000206/LER-1984-010, :on 840930,during Mode 5 Outage,Two of Three Boric Acid Flow Paths Inoperable.Caused by Accumulated Gas from Vol Control Tank Due to Leak in Valve CV406B.Valve Diaphragms Replaced.Procedures Revised |
- on 840930,during Mode 5 Outage,Two of Three Boric Acid Flow Paths Inoperable.Caused by Accumulated Gas from Vol Control Tank Due to Leak in Valve CV406B.Valve Diaphragms Replaced.Procedures Revised
| |
| 05000361/LER-1984-010-02, :on 840223,reactor Power Surge Occurred Due to Partial Loss of Extraction Steam Feedwater Heating.Caused by Spurious Cycle of First Point Level Controller Resulting in High Levels in Point Heaters |
- on 840223,reactor Power Surge Occurred Due to Partial Loss of Extraction Steam Feedwater Heating.Caused by Spurious Cycle of First Point Level Controller Resulting in High Levels in Point Heaters
| |
| 05000362/LER-1984-010, :on 840424,train a Containment Purge Isolation Sys Spuriously Actuated by Electrical Noise Spikes from Containment Area Radiation Monitor 3RT-7804.Cause Under Investigation |
- on 840424,train a Containment Purge Isolation Sys Spuriously Actuated by Electrical Noise Spikes from Containment Area Radiation Monitor 3RT-7804.Cause Under Investigation
| |
| 05000361/LER-1984-011, :on 840225,containment Purge Isolation Sys Actuated When Containment Airborne Monitor 2RE-7804 Gaseous Channel C Failed.Caused by Water in Gaseous Detector Cell, Short Circuiting pre-amp.Water Removed |
- on 840225,containment Purge Isolation Sys Actuated When Containment Airborne Monitor 2RE-7804 Gaseous Channel C Failed.Caused by Water in Gaseous Detector Cell, Short Circuiting pre-amp.Water Removed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000362/LER-1984-011-01, :on 840227,during Investigation of Reactor Trip Breaker Pushbutton Event,One Set of Leads in Each of Four Plant Protection Sys Bays Found Disconnected.Caused by Leads Disconnected During Earlier Surveillance |
- on 840227,during Investigation of Reactor Trip Breaker Pushbutton Event,One Set of Leads in Each of Four Plant Protection Sys Bays Found Disconnected.Caused by Leads Disconnected During Earlier Surveillance
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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) |
| 05000361/LER-1984-012, :on 840301,spurious Toxic Gas Isolation Sys (Tgis) Actuation Occurred.Caused by Unnecessary Conservatisms in Tgis Setpoint.Basis for Setpoint Will Be Reanalyzed & Tech Specs Amended |
- on 840301,spurious Toxic Gas Isolation Sys (Tgis) Actuation Occurred.Caused by Unnecessary Conservatisms in Tgis Setpoint.Basis for Setpoint Will Be Reanalyzed & Tech Specs Amended
| 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) |
| 05000362/LER-1984-012-01, :on 840330,MSIVs 3HV8204 & 5 Failed to Close within Required 5 S.Caused by Cylinder Nitrogen Pressure Above Min Specified Limit W/Valves Open.Tech Spec Change Will Be Submitted to Increase Closure Time |
- on 840330,MSIVs 3HV8204 & 5 Failed to Close within Required 5 S.Caused by Cylinder Nitrogen Pressure Above Min Specified Limit W/Valves Open.Tech Spec Change Will Be Submitted to Increase Closure Time
| 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) 10 CFR 50.73(a)(2)(1) |
| 05000361/LER-1984-013, :on 840305,containment Pressure Exceeded Tech Spec Limits.Caused by Misinterpretation of Venting Procedure.Operators Interpreted Procedure to Require 2 H Venting.Operators Counseled Re Procedure |
- on 840305,containment Pressure Exceeded Tech Spec Limits.Caused by Misinterpretation of Venting Procedure.Operators Interpreted Procedure to Require 2 H Venting.Operators Counseled Re Procedure
| 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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000362/LER-1984-013-01, :on 840330 & 0401,following Reactor Shutdown for Maint,Rcs Exceeded 1.0 Uci/G Dose Equivalent I-131. Caused by Iodine Spiking Following Power Change.Purification Flow Increased & RCS Activity Reduced |
- on 840330 & 0401,following Reactor Shutdown for Maint,Rcs Exceeded 1.0 Uci/G Dose Equivalent I-131. Caused by Iodine Spiking Following Power Change.Purification Flow Increased & RCS Activity Reduced
| 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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) |
| 05000362/LER-1984-013, :on 840330 & 0401,following Reactor Shutdown for Maint,Rcs Sample Analysis Indicated That RCS Specific Activity Exceeded 1.0 Uci/G Dose Equivalent I-131.Cause Indicative of Iodine Spiking Following Power Change |
- on 840330 & 0401,following Reactor Shutdown for Maint,Rcs Sample Analysis Indicated That RCS Specific Activity Exceeded 1.0 Uci/G Dose Equivalent I-131.Cause Indicative of Iodine Spiking Following Power Change
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000361/LER-1984-015, :on 840306,fire Program Discrepancies Found During Preparation of Fire Hazard Analysis (FHA) & Review of IE Info Notice 84-09.Compensatory Measures & Rev to FHA Implemented |
- on 840306,fire Program Discrepancies Found During Preparation of Fire Hazard Analysis (FHA) & Review of IE Info Notice 84-09.Compensatory Measures & Rev to FHA Implemented
| 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) |
| 05000362/LER-1984-015-01, :on 840427,0505 & 07,analysis of RCS Sample Indicated That Specific Activity Exceeded 1.0 Uci/G Dose Equivalent I-131.Cause Not Stated.Personnel Instructed to Perform Sampling within Required 4 H Period |
- on 840427,0505 & 07,analysis of RCS Sample Indicated That Specific Activity Exceeded 1.0 Uci/G Dose Equivalent I-131.Cause Not Stated.Personnel Instructed to Perform Sampling within Required 4 H Period
| 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) |
| 05000362/LER-1984-016-01, :on 840428,undervoltage (UV) Trip Device for Reactor Trip Breaker 256A4002-656-29 Exhibited Unacceptable Response Time.Following Maint,Breaker Yielded Acceptable UV Response Time.Breaker Returned to Svc |
- on 840428,undervoltage (UV) Trip Device for Reactor Trip Breaker 256A4002-656-29 Exhibited Unacceptable Response Time.Following Maint,Breaker Yielded Acceptable UV Response Time.Breaker 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)(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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000361/LER-1984-016, :on 840309,technician Inadvertently Actuated Safety Injection,Containment Cooling & Containment Spray Activation Sys.Caused by Technician Error.Procedural Changes Implemented |
- on 840309,technician Inadvertently Actuated Safety Injection,Containment Cooling & Containment Spray Activation Sys.Caused by Technician Error.Procedural Changes Implemented
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000362/LER-1984-017-01, :on 840505 & 08,reactor Trip Occurred on High Steam Generator Water Level.Caused by Overfeeding Steam Generators W/Feedwater Control Sys in Manual Control.Design Changes Under Consideration |
- on 840505 & 08,reactor Trip Occurred on High Steam Generator Water Level.Caused by Overfeeding Steam Generators W/Feedwater Control Sys in Manual Control.Design Changes Under Consideration
| 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000361/LER-1984-017, :on 840321,shutdown Cooling HX Flow Control Valve 2HV9316 Discovered Locked Fully Open.Caused by Disengaged Handwheel Clutch.Surveillance Position Revised to Verify Handwheel Engaged |
- on 840321,shutdown Cooling HX Flow Control Valve 2HV9316 Discovered Locked Fully Open.Caused by Disengaged Handwheel Clutch.Surveillance Position Revised to Verify Handwheel Engaged
| 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) |
| 05000362/LER-1984-018-01, :on 840525,during Surveillance,Undervoltage Trip Device for Reactor Trip Breaker,Serial 256A4002-656-29, Exhibited Procedurally Unacceptable Response Time.Breaker Replaced W/Spare |
- on 840525,during Surveillance,Undervoltage Trip Device for Reactor Trip Breaker,Serial 256A4002-656-29, Exhibited Procedurally Unacceptable Response Time.Breaker Replaced W/Spare
| 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) |
| 05000361/LER-1984-018, :on 840324,remaining Control Room Isolation Sys Radiation Monitor 2/3RT-7825 Declared Inoperable.Caused by Low Flow Alarm Due to Dirty Filter.Filter Changed & Monitor Returned to Svc |
- on 840324,remaining Control Room Isolation Sys Radiation Monitor 2/3RT-7825 Declared Inoperable.Caused by Low Flow Alarm Due to Dirty Filter.Filter Changed & Monitor 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) |
| 05000361/LER-1984-019, :on 840324,while at 100% Power,False Position Indication for Control Element Assembly (CEA) 20 on CEA Calculator (Ceac) 1 Resulted in Penalty Factors,Causing Reactor Trip.Specific Cause Undetermined |
- on 840324,while at 100% Power,False Position Indication for Control Element Assembly (CEA) 20 on CEA Calculator (Ceac) 1 Resulted in Penalty Factors,Causing Reactor Trip.Specific Cause Undetermined
| 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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
| 05000362/LER-1984-019-01, :on 840505,post-maint Testing Not Performed Following Packing Adjustment to Reduce Leakage on Containment Isolation Valves 3HV9205 & 3HV9212.Caused by Personnel Error.Operations Personnel Briefed |
- on 840505,post-maint Testing Not Performed Following Packing Adjustment to Reduce Leakage on Containment Isolation Valves 3HV9205 & 3HV9212.Caused by Personnel Error.Operations Personnel Briefed
| 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000361/LER-1984-020, :on 840326,w/unit in Mode 2 at 2% Power,Reactor Trip Occurred on High Steam Generator Level.Caused by Overfeeding Steam Generators During Manual Operation of Feedwater Control Sys |
- on 840326,w/unit in Mode 2 at 2% Power,Reactor Trip Occurred on High Steam Generator Level.Caused by Overfeeding Steam Generators During Manual Operation of Feedwater Control Sys
| 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)(viii)(B) 10 CFR 50.73(a)(2)(1) |
| 05000362/LER-1984-020, :on 840527,8 H Grab Sample Due at 0800 Not Taken Until 0945.Low-range Flow at Sample Conditioning Skid Diverted from Filter a to Filter B,Causing Blown Fuse. Alternate Flow Path Established |
- on 840527,8 H Grab Sample Due at 0800 Not Taken Until 0945.Low-range Flow at Sample Conditioning Skid Diverted from Filter a to Filter B,Causing Blown Fuse. Alternate Flow Path Established
| 10 CFR 50.73(a)(2)(x) |
| 05000362/LER-1984-020-01, :on 840527,grab Sample Not Taken Per 8 H Requirement.Caused by Sample Pump Isolation.Corrective Action Will Be Reported in LER Rev by 840801 |
- on 840527,grab Sample Not Taken Per 8 H Requirement.Caused by Sample Pump Isolation.Corrective Action Will Be Reported in LER Rev by 840801
| 10 CFR 50.73(a)(2)(1) |
| 05000361/LER-1984-021, :on 840330,0405,07,10-12,15,19,22 & 23. Spurious Toxic Gas Isolation Sys Actuations Occurred.Caused by Conservative Setpoints Which Contained Unnecessary Conservatisms.Setpoints Will Be Reanalyzed |
- on 840330,0405,07,10-12,15,19,22 & 23. Spurious Toxic Gas Isolation Sys Actuations Occurred.Caused by Conservative Setpoints Which Contained Unnecessary Conservatisms.Setpoints Will Be Reanalyzed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000362/LER-1984-021-01, :on 840602,safety Relief Valve 3PSV-0245 on Nuclear Sample Sys Actuated.Caused by Setpoint on Valve Set Unnecessarily Low.Setpoint Raised & Valve Returned to Svc on 840606 |
- on 840602,safety Relief Valve 3PSV-0245 on Nuclear Sample Sys Actuated.Caused by Setpoint on Valve Set Unnecessarily Low.Setpoint Raised & Valve Returned to Svc on 840606
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000362/LER-1984-022-01, :on 840601,failure in Turbine Control Sys Caused High Pressure Turbine Stop Valves to Close,Resulting in Loss of Load Reactor Trip.Cause Undetermined.Module Replaced |
- on 840601,failure in Turbine Control Sys Caused High Pressure Turbine Stop Valves to Close,Resulting in Loss of Load Reactor Trip.Cause Undetermined.Module 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) 10 CFR 50.73(a)(2)(viii)(A) |
| 05000361/LER-1984-022, :on 840330 & 0410,control Room Isolation Sys Train Spuriously Actuated from Spike on Control Room Airborne Radiation Monitor.Caused by Spurious Electrical Spikes.No Corrective Action Planned |
- on 840330 & 0410,control Room Isolation Sys Train Spuriously Actuated from Spike on Control Room Airborne Radiation Monitor.Caused by Spurious Electrical Spikes.No Corrective Action Planned
| 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)(B) |
| 05000361/LER-1984-023, :on 840524,spurious Actuation of Control Room Isolation Sys Occurred Because of Noise Spike on Control Room Airborne Radiation Monitor.Monitor Detector Replaced & Preamplifier Properly Grounded |
- on 840524,spurious Actuation of Control Room Isolation Sys Occurred Because of Noise Spike on Control Room Airborne Radiation Monitor.Monitor Detector Replaced & Preamplifier Properly Grounded
| 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)(viii) 10 CFR 50.73(a)(2) |
| 05000362/LER-1984-023-01, :on 840601 & 11,during Turbine Overspeed Protection Test,Reactor Trip Occurred Involving RCS Specific Activity.Caused by Iodine Spiking.Primary Coolant Activity Will Be Monitored & Evaluated |
- on 840601 & 11,during Turbine Overspeed Protection Test,Reactor Trip Occurred Involving RCS Specific Activity.Caused by Iodine Spiking.Primary Coolant Activity Will Be Monitored & Evaluated
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) |