| | | Reporting criterion |
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| 05000387/LER-1984-001-01, Updated LER 84-001-01:on 840103,H2/O2 Analyzers in Containment Atmosphere Monitoring Sys Declared Inoperable Based on Vendor Info.Caused by Catalyst Inability to Withstand Iodine Concentrations | Updated LER 84-001-01:on 840103,H2/O2 Analyzers in Containment Atmosphere Monitoring Sys Declared Inoperable Based on Vendor Info.Caused by Catalyst Inability to Withstand Iodine Concentrations | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000387/LER-1984-001, :on 840103,hydrogen Dioxide Analyzers in Containment Atmosphere Monitoring Sys Inoperable.Caused by Design Deficiency.Catalyst Will Be Replaced on 840201 for Unit 1 & on 840215 for Unit 2 |
- on 840103,hydrogen Dioxide Analyzers in Containment Atmosphere Monitoring Sys Inoperable.Caused by Design Deficiency.Catalyst Will Be Replaced on 840201 for Unit 1 & on 840215 for Unit 2
| 10 CFR 50.73(a)(2)(vi) |
| 05000388/LER-1984-001-01, :on 840405,unit Experienced Reactor Protection Sys Actuation on Spurious Signal from Intermediate Range Monitor Channel D.Caused by Defective Cabinet.Channel Voltage Preamplifier Replaced |
- on 840405,unit Experienced Reactor Protection Sys Actuation on Spurious Signal from Intermediate Range Monitor Channel D.Caused by Defective Cabinet.Channel Voltage Preamplifier Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1984-003-01, :on 840409,six Scrams Occurred within Approx 1 H.No Upscale Trip Lamps for Associated Nuclear Instrumentation Channels Lit.Scrams Caused by Intermittent Fault in Inoperative Trip Circuits |
- on 840409,six Scrams Occurred within Approx 1 H.No Upscale Trip Lamps for Associated Nuclear Instrumentation Channels Lit.Scrams Caused by Intermittent Fault in Inoperative Trip Circuits
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1984-004-01, :on 840501,during Shutdown W/Nonirradiated Fuel,Esf Actuations Occurred While Installing Test Equipment in Div 11 Primary Containment Isolation Sys Circuitry.Caused by Grounded Leads |
- on 840501,during Shutdown W/Nonirradiated Fuel,Esf Actuations Occurred While Installing Test Equipment in Div 11 Primary Containment Isolation Sys Circuitry.Caused by Grounded Leads
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1984-004, :on 840113,two Level Switches on Condensate Storage Tank Found Inoperable Due to Freezing.Caused by Deenergized Heat Tracing.Heat Tracing on Affected Instrument Lines & Switches Restored |
- on 840113,two Level Switches on Condensate Storage Tank Found Inoperable Due to Freezing.Caused by Deenergized Heat Tracing.Heat Tracing on Affected Instrument Lines & Switches Restored
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000388/LER-1984-005-01, :on 840515,during Monthly Functional Test of Reactor Water Cleanup Sys Area Ventilation Differential Temp Controls Test,Personnel Caused Inadvertent Closure of Primary Containment Isolation Valve |
- on 840515,during Monthly Functional Test of Reactor Water Cleanup Sys Area Ventilation Differential Temp Controls Test,Personnel Caused Inadvertent Closure of Primary Containment Isolation Valve
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1984-005, :on 840127,svc Water Grab Sample Not Taken During Day Shift.Caused by Sample Being Missed During Turnover Between Day & Afternoon Shifts.Procedural Change Issued |
- on 840127,svc Water Grab Sample Not Taken During Day Shift.Caused by Sample Being Missed During Turnover Between Day & Afternoon Shifts.Procedural Change Issued
| |
| 05000388/LER-1984-006-01, :on 840521,LPCI Valve HV-2F015B Closed & de-energized Following Dual Indication on Testable Check Valve HV-2F05B.Reactor Shut Down on 840528.Caused by Loose Plate Connector on Valve HV-2F122B |
- on 840521,LPCI Valve HV-2F015B Closed & de-energized Following Dual Indication on Testable Check Valve HV-2F05B.Reactor Shut Down on 840528.Caused by Loose Plate Connector on Valve HV-2F122B
| |
| 05000387/LER-1984-006, :on 840125,discovered That Performance of Weekly Source & Intermediate Range Monitors W/Unit in Mode 5 Constitutes Core Alteration.Core Alterations Prohibited Per Tech Specs.Tech Spec Change in Progress |
- on 840125,discovered That Performance of Weekly Source & Intermediate Range Monitors W/Unit in Mode 5 Constitutes Core Alteration.Core Alterations Prohibited Per Tech Specs.Tech Spec Change in Progress
| 10 CFR 50.73(a)(2)(1) |
| 05000388/LER-1984-007-01, :on 840525,reactor Water Cleanup Differential Pressure Switch Jumpered Out for Calibr Check.Caused by Personnel Oversight.Shift Supervision Counseled on Occurrence |
- on 840525,reactor Water Cleanup Differential Pressure Switch Jumpered Out for Calibr Check.Caused by Personnel Oversight.Shift Supervision Counseled on Occurrence
| 10 CFR 50.73(a)(2)(1) |
| 05000387/LER-1984-007, :on 840202,shear Valve Explosive Cartridge Unexpectedly Fired During Surveillance Testing,Shearing Transversing in-core Probe Detector Cable.Cause Unknown.New Detector & Cable Installed.Procedure Changed |
- on 840202,shear Valve Explosive Cartridge Unexpectedly Fired During Surveillance Testing,Shearing Transversing in-core Probe Detector Cable.Cause Unknown.New Detector & Cable Installed.Procedure Changed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1984-008, :on 840209,during Outage RHR Seal Water Coolers Discovered Improperly Designed.Coolers Replaced.Teledyne Engineering Svc Conducting Independent Review |
- on 840209,during Outage RHR Seal Water Coolers Discovered Improperly Designed.Coolers Replaced.Teledyne Engineering Svc Conducting Independent Review
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000388/LER-1984-008-01, :on 840527,turbine Bypass Valve 1 Failed to Close Below Open Position,Resulting in Reactor Protection Sys Manual Scram.Caused by Chipping Hammer Wedged Between Bypass Valve Seat & Valve Disc.Disc Replaced |
- on 840527,turbine Bypass Valve 1 Failed to Close Below Open Position,Resulting in Reactor Protection Sys Manual Scram.Caused by Chipping Hammer Wedged Between Bypass Valve Seat & Valve Disc.Disc Replaced
| 10 CFR 50.73(a)(2) |
| 05000387/LER-1984-009, :on 840221,during Restart,Hpci Steam Supply Line Pressure Indicator Did Not Respond to Warm Up & Reactor Pressure Exceeded 150 Psig.Checkoff List & Operating Procedure Revised |
- on 840221,during Restart,Hpci Steam Supply Line Pressure Indicator Did Not Respond to Warm Up & Reactor Pressure Exceeded 150 Psig.Checkoff List & Operating Procedure Revised
| |
| 05000388/LER-1984-009-01, :on 840611,dual Position Indication Received for One Suppression Chamber Drywell Vacuum Breaker & Containment Vacuum Breaker Div 1 Open Alarm Received.Caused by Loose Locking Nut.Actuating Bolts Adjusted |
- on 840611,dual Position Indication Received for One Suppression Chamber Drywell Vacuum Breaker & Containment Vacuum Breaker Div 1 Open Alarm Received.Caused by Loose Locking Nut.Actuating Bolts Adjusted
| |
| 05000387/LER-1984-010, :on 840225,reactor Manually Scrammed When One of Six Automatic Depressurization Sys Safety Relief Valves Stuck Open & Would Not Close in 2 Minutes.Caused by Faulty Valve Solenoid.Solenoid Replaced |
- on 840225,reactor Manually Scrammed When One of Six Automatic Depressurization Sys Safety Relief Valves Stuck Open & Would Not Close in 2 Minutes.Caused by Faulty Valve Solenoid.Solenoid Replaced
| 10 CFR 50.73(a)(2)(1) |
| 05000388/LER-1984-010, :on 840627,pressure Drop Occurred on HPCI Pump Suction Piping During Heatup Plateau Review.Caused by Blockage in Startup Strainer.Strainers Removed |
- on 840627,pressure Drop Occurred on HPCI Pump Suction Piping During Heatup Plateau Review.Caused by Blockage in Startup Strainer.Strainers Removed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000388/LER-1984-010-01, :on 840627,HPCI Sys Declared Inoperable for 22 H to Facilitate Removal of Startup Strainer.Caused by Blockage in Startup During Heatup Plateau Review.Startup Strainer Removed & Ring Spacer Installed |
- on 840627,HPCI Sys Declared Inoperable for 22 H to Facilitate Removal of Startup Strainer.Caused by Blockage in Startup During Heatup Plateau Review.Startup Strainer Removed & Ring Spacer Installed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000388/LER-1984-011-01, :on 840705 & 06,four Spurious Actuations of Standby Gas Treatment Sys & Control Room Emergency Outside Air Supply Sys Experienced.Caused by Malfunctioning Output Breaker.Breaker Replaced |
- on 840705 & 06,four Spurious Actuations of Standby Gas Treatment Sys & Control Room Emergency Outside Air Supply Sys Experienced.Caused by Malfunctioning Output Breaker.Breaker Replaced
| 10 CFR 50.73(a)(2) |
| 05000387/LER-1984-011, :on 840301,two Initiations of Control Room Emergency Outside Air Supply Sys & Standby Gas Treatment Sys Occurred.Caused by Voltage Drop & Incorrect Removal of Test Jumper Cables |
- on 840301,two Initiations of Control Room Emergency Outside Air Supply Sys & Standby Gas Treatment Sys Occurred.Caused by Voltage Drop & Incorrect Removal of Test Jumper Cables
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1984-012, :on 840229,discovered Functional Testing of Common Offgas Sys Hydrogen Analyzer Channel B Not Performed on 840225 as Required.Caused by Due Date Omitted from Surveillance Authorization |
- on 840229,discovered Functional Testing of Common Offgas Sys Hydrogen Analyzer Channel B Not Performed on 840225 as Required.Caused by Due Date Omitted from Surveillance Authorization
| 10 CFR 50.73(a)(2)(i) |
| 05000388/LER-1984-012-01, :840709,core Spray Logic Control Power Fuses Removed Since Fuses Thought to Be Possible Blocking Point for Personnel Protection.Removal Affected Listed Equipment. Fuses Reinstalled |
- 840709,core Spray Logic Control Power Fuses Removed Since Fuses Thought to Be Possible Blocking Point for Personnel Protection.Removal Affected Listed Equipment. Fuses Reinstalled
| 10 CFR 50.73(a)(2)(1) |
| 05000387/LER-1984-012-01, Revised LER 84-012-01:on 840225,due Date & Violation Date Inadvertently Omitted from Cover Sheet of Quarterly Surveillance Procedure SI-072-301.Administrative Procedures Revised | Revised LER 84-012-01:on 840225,due Date & Violation Date Inadvertently Omitted from Cover Sheet of Quarterly Surveillance Procedure SI-072-301.Administrative Procedures Revised | 10 CFR 50.73(a)(2)(i) |
| 05000388/LER-1984-013, Attachments to LER 84-013-00 | Attachments to LER 84-013-00 | |
| 05000388/LER-1984-013-01, :on 840726,during Scram Due to Turbine Control Valve Fast Closure & Deenergization of 13.8 Kv & 14.16 Kv Buses,Control Rods Did Not Fully Insert.Caused by Failure of Diesel Generators to Start Automatically |
- on 840726,during Scram Due to Turbine Control Valve Fast Closure & Deenergization of 13.8 Kv & 14.16 Kv Buses,Control Rods Did Not Fully Insert.Caused by Failure of Diesel Generators to Start Automatically
| |
| 05000387/LER-1984-013, :on 840303,main Turbine Tripped on Spurious Trip of Turbine Thrust Bearing Wear Detector (TBWD) Pressure Switches.Caused by Spurious Malfunction of Blocking Relay in TBWD Circuitry.Relay Replaced |
- on 840303,main Turbine Tripped on Spurious Trip of Turbine Thrust Bearing Wear Detector (TBWD) Pressure Switches.Caused by Spurious Malfunction of Blocking Relay in TBWD Circuitry.Relay Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1984-014-01, :on 840723,reactor Water Cleanup Inlet Outboard Board Isolation Valve (2F004) Closed Due to High Temp in Filter Demineralizer Room.Caused by Problems W/Reactor Bldg Chilled Water Sys |
- on 840723,reactor Water Cleanup Inlet Outboard Board Isolation Valve (2F004) Closed Due to High Temp in Filter Demineralizer Room.Caused by Problems W/Reactor Bldg Chilled Water Sys
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1984-014, :on 840305,transformer T20 Tripped,Resulting in Isolation of Reactor Bldg Ventilation Zones II & Iii. Caused by Momentary Closure of Contact in High Speed Ground Switch |
- on 840305,transformer T20 Tripped,Resulting in Isolation of Reactor Bldg Ventilation Zones II & Iii. Caused by Momentary Closure of Contact in High Speed Ground Switch
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1984-015-01, :on 840802,reactor Water Cleanup Sys Isolated on High Flow.No Pipe Break Identified.Caused by PDIS-G33-2N044A Out of Calibr Due to Instrument Drift. Instrument Recalibr & Returned to Svc |
- on 840802,reactor Water Cleanup Sys Isolated on High Flow.No Pipe Break Identified.Caused by PDIS-G33-2N044A Out of Calibr Due to Instrument Drift. Instrument Recalibr & Returned to Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1984-015, :on 840802,reactor Water Cleanup Sys Isolated on High Flow.Caused by Instrument Drift.Switch PDIS-G33-2NO44A Recalibr |
- on 840802,reactor Water Cleanup Sys Isolated on High Flow.Caused by Instrument Drift.Switch PDIS-G33-2NO44A Recalibr
| 10 CFR 50.73(a)(2) |
| 05000387/LER-1984-015, :on 840121,background Radiation Surrounding Svc Water Radiation Monitor Reached Levels That Exceeded Tech Spec Limits.Cause Not Stated.Calibr Procedure Revised |
- on 840121,background Radiation Surrounding Svc Water Radiation Monitor Reached Levels That Exceeded Tech Spec Limits.Cause Not Stated.Calibr Procedure Revised
| 10 CFR 50.73(a)(2)(i) |
| 05000388/LER-1984-016-01, :on 840809,31-day Surveillance Test Completed Late.Caused by Verbal Miscommunication Between Instrumentation & Controls (I&C) Assistant Foreman & Scheduler.I&C Shop Instruction Implemented |
- on 840809,31-day Surveillance Test Completed Late.Caused by Verbal Miscommunication Between Instrumentation & Controls (I&C) Assistant Foreman & Scheduler.I&C Shop Instruction Implemented
| 10 CFR 50.73(a)(2)(1) |
| 05000387/LER-1984-016, :on 840308,shiftly Channel Check of New Fuel Criticality Monitors Not Completed During Scheduled Time Period.Caused by Personnel Error.Personnel Counseled |
- on 840308,shiftly Channel Check of New Fuel Criticality Monitors Not Completed During Scheduled Time Period.Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(1) |
| 05000387/LER-1984-017, :on 840310,spray Pond Riser Networks A-1 & B-2 Found Frozen.Cause Not Stated.Networks Thawed by Ambient Temp & Guidelines Developed for Spray Pond Operation to Avoid Riser Freezing |
- on 840310,spray Pond Riser Networks A-1 & B-2 Found Frozen.Cause Not Stated.Networks Thawed by Ambient Temp & Guidelines Developed for Spray Pond Operation to Avoid Riser Freezing
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000387/LER-1984-017-01, Updated LER 84-017-01:on 840310,during Performance of Weekly Preventive Maint Activity,Spray Pond Riser Networks A-1 & B-2 Found Frozen.W/Advent of Mild Weather,Networks Thawed & Pumped down.Long-term Fixes Investigated | Updated LER 84-017-01:on 840310,during Performance of Weekly Preventive Maint Activity,Spray Pond Riser Networks A-1 & B-2 Found Frozen.W/Advent of Mild Weather,Networks Thawed & Pumped down.Long-term Fixes Investigated | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000388/LER-1984-018-01, :on 840908,turbine Control Valve Fast Closure Signal Generated from False Power Load Unbalance Signal. Caused by Zero Shift Pressure Transmitter PT-20107. Transmitter Recalibr |
- on 840908,turbine Control Valve Fast Closure Signal Generated from False Power Load Unbalance Signal. Caused by Zero Shift Pressure Transmitter PT-20107. Transmitter Recalibr
| 10 CFR 50.73(a)(2) |
| 05000387/LER-1984-018, :on 840303,during Recirculation Pump Discharge Valve & Bypass Operability Test,Recirculation Discharge Valve 1F031B Failed to Operate.Caused by Valve Stem Binding W/Packing Glands |
- on 840303,during Recirculation Pump Discharge Valve & Bypass Operability Test,Recirculation Discharge Valve 1F031B Failed to Operate.Caused by Valve Stem Binding W/Packing Glands
| |
| 05000387/LER-1984-019, :on 840415,false High Drywell Pressure Signal Resulted from Removal of Two Primary Containment Isolation Logic Fuses.Caused by Incorrectly Installed Bypass Jumper. Fuses Reinstalled |
- on 840415,false High Drywell Pressure Signal Resulted from Removal of Two Primary Containment Isolation Logic Fuses.Caused by Incorrectly Installed Bypass Jumper. Fuses Reinstalled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1984-019-01, :on 840919,RHR Pump D Declared Inoperable Due to Failure to Start on Manual Initiation Signal on 840918. HPCI Sys Inoperable Due to Lube Oil Changeout.Rhr Problem Due to Misoperation of Relay Contacts |
- on 840919,RHR Pump D Declared Inoperable Due to Failure to Start on Manual Initiation Signal on 840918. HPCI Sys Inoperable Due to Lube Oil Changeout.Rhr Problem Due to Misoperation of Relay Contacts
| 10 CFR 50.73(a)(2)(1) |
| 05000388/LER-1984-020-01, :on 840929,unplanned ESF Actuation Occurred During Calibr of Differential Pressure Instrument Resulting in Isolation of Reactor Water Cleanup Sys.Caused by Closure of Containment Isolation Valve |
- on 840929,unplanned ESF Actuation Occurred During Calibr of Differential Pressure Instrument Resulting in Isolation of Reactor Water Cleanup Sys.Caused by Closure of Containment Isolation Valve
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) |
| 05000387/LER-1984-020, :on 840321,shutdown Cooling Suction Inboard & Outboard Isolation Valves Closed Due to Spurious Actuation of RHR Sys Differential Pressure Switches.Cause Not Stated. Shutdown Cooling Operation Will Be Observed |
- on 840321,shutdown Cooling Suction Inboard & Outboard Isolation Valves Closed Due to Spurious Actuation of RHR Sys Differential Pressure Switches.Cause Not Stated. Shutdown Cooling Operation Will Be Observed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1984-021-01, :on 840930,reactor Scrammed Due to Turbine Trip on Moisture Separator B Drain Tank High Level.Task Team Established to Evaluate Drain Tank Level Control Sys |
- on 840930,reactor Scrammed Due to Turbine Trip on Moisture Separator B Drain Tank High Level.Task Team Established to Evaluate Drain Tank Level Control Sys
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-1984-021, :on 840930,reactor Scrammed Due to Turbine Trip on Moisture Separator B Drain Tank High Level During Performance of Startup Test to Determine Max Feedwater Pump Runout Capabilities.Check Valve Installed |
- on 840930,reactor Scrammed Due to Turbine Trip on Moisture Separator B Drain Tank High Level During Performance of Startup Test to Determine Max Feedwater Pump Runout Capabilities.Check Valve Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000387/LER-1984-021, :on 840323,during Installation of Mod to Emergency Svc Water Sys,Fire Barrier Wrapping of Several Cable Raceways Overlooked.Fire Watch Established & Will Remain Until Fire Barrier Wrapping Complete |
- on 840323,during Installation of Mod to Emergency Svc Water Sys,Fire Barrier Wrapping of Several Cable Raceways Overlooked.Fire Watch Established & Will Remain Until Fire Barrier Wrapping Complete
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000387/LER-1984-022, :on 840331,purge Flow,Indicating Purge Mode of Operation Alarms Occurred at Same Time in Printout of Control Terminal.Caused by Sping Purge Command Not Being Entered at Local or Remote Control Consoles |
- on 840331,purge Flow,Indicating Purge Mode of Operation Alarms Occurred at Same Time in Printout of Control Terminal.Caused by Sping Purge Command Not Being Entered at Local or Remote Control Consoles
| 10 CFR 50.73(a)(2)(i) |
| 05000388/LER-1984-022, :on 841010,HPCI Sys Declared Inoperable Due to High Vibration Identified During Maint Check.Hpci Booster & Main Pumps & Turbine Realigned & Rerun.Eccs & RCIC Sys Declared Inoperable on 841013 for Routine Test |
- on 841010,HPCI Sys Declared Inoperable Due to High Vibration Identified During Maint Check.Hpci Booster & Main Pumps & Turbine Realigned & Rerun.Eccs & RCIC Sys Declared Inoperable on 841013 for Routine Test
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) |
| 05000388/LER-1984-022-01, :on 841010,HPCI Sys Declared Inoperable Due to High Vibration Detected During Maint Check of HPCI Bearings. Caused by Misalignment Between Booster Pump Reduction Gear Unit & Main Pump & Turbine.Pumps Realigned |
- on 841010,HPCI Sys Declared Inoperable Due to High Vibration Detected During Maint Check of HPCI Bearings. Caused by Misalignment Between Booster Pump Reduction Gear Unit & Main Pump & Turbine.Pumps Realigned
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) |
| 05000388/LER-1984-023-01, :on 841206,fire Watch Discontinued Following Completion of One of Two Independent Work Activities.Caused by Failure to Ref Two Work Activities in Fire Watch Log. Evaluation Being Conducted |
- on 841206,fire Watch Discontinued Following Completion of One of Two Independent Work Activities.Caused by Failure to Ref Two Work Activities in Fire Watch Log. Evaluation Being Conducted
| 10 CFR 50.73(a)(2) |
| 05000388/LER-1984-023, :on 841206,fire Watch Required for Two Independent Work Activities.Caused by Fire Watch Log Not Referencing Activities.Addl Guidelines for Tracking Fire Protection Activities & Separate Log Developed |
- on 841206,fire Watch Required for Two Independent Work Activities.Caused by Fire Watch Log Not Referencing Activities.Addl Guidelines for Tracking Fire Protection Activities & Separate Log Developed
| 10 CFR 50.73(a)(2)(1) |