PNO-IV-88-035, on 880503,control Element Assembly Exceeded Tech Spec Limit of 3 During Rod Drop Test.Plant Startup on Hold Pending Resolution of Issue.Licensee Reviewing Safety Analysis Assumptions & Anticipate Tech Spec Amend
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| ML20154A046 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/04/1988 |
| From: | Chamberlain D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| References | |
| PNO-IV-88-035, PNO-IV-88-35, NUDOCS 8805130123 | |
| Download: ML20154A046 (1) | |
Similar Documents at Arkansas Nuclear | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-IV-98-066, on 981225,large Influx of Fish (Shad) Affected Unit 1 Intake Structure,Resulting in Degraded Available Circulating Water Pump Suction Pressure.Shade Runs Have Historically Occurred as Result of Cyclic Changes1998-12-29029 December 1998
[Table view]PNO-IV-98-066:on 981225,large Influx of Fish (Shad) Affected Unit 1 Intake Structure,Resulting in Degraded Available Circulating Water Pump Suction Pressure.Shade Runs Have Historically Occurred as Result of Cyclic Changes PNO-IV-98-001A, on 980105,plant Shutdown When Heavy Rains Caused Accumulation of Debris at Circulating & Svc Water Intake Structure.Debris Damaged Some Intake Structure Components.Repairs to Intake Components Completed on 9801091998-01-13013 January 1998 PNO-IV-98-001A:on 980105,plant Shutdown When Heavy Rains Caused Accumulation of Debris at Circulating & Svc Water Intake Structure.Debris Damaged Some Intake Structure Components.Repairs to Intake Components Completed on 980109 PNO-IV-98-001, on 980105,unit 1 Shutdown Due to Accumulation of Debris at Circulating Water & Svc Water Intake Structure Which Damaged non-safety Intake Structure Components.Nrc Resident Inspectors Closely Monitoring Activities1998-01-0909 January 1998 PNO-IV-98-001:on 980105,unit 1 Shutdown Due to Accumulation of Debris at Circulating Water & Svc Water Intake Structure Which Damaged non-safety Intake Structure Components.Nrc Resident Inspectors Closely Monitoring Activities PNO-IV-97-017, on 970324,Arkansas Nuclear One Initiated Loading of Third VSC-24 Canister for Storage of Spent Fuel at Plant Isfsi.Licensee Initiated Repair of Crack by Grinding Out Defective Area1997-03-31031 March 1997 PNO-IV-97-017:on 970324,Arkansas Nuclear One Initiated Loading of Third VSC-24 Canister for Storage of Spent Fuel at Plant Isfsi.Licensee Initiated Repair of Crack by Grinding Out Defective Area PNO-IV-96-063, on 960603,licensee Restricted from Loading Spent Fuel Into Sierra Nuclear VSC-24 Casks Per Terms of Confirmatory Action Ltr (Cal).Licensee Responded to Both CAL & Bulletin & NRC Completed Review of Responses1996-12-0404 December 1996 PNO-IV-96-063:on 960603,licensee Restricted from Loading Spent Fuel Into Sierra Nuclear VSC-24 Casks Per Terms of Confirmatory Action Ltr (Cal).Licensee Responded to Both CAL & Bulletin & NRC Completed Review of Responses PNO-IV-96-061, on 961116,ANO Unit 2 Shutdown for Small SG Tube Leak.Licensee Plans to Conduct Insps to Locate, Characterize & Repair Leaking Tube.State of AR Informed & Plans to Issue Press Release1996-11-18018 November 1996 PNO-IV-96-061:on 961116,ANO Unit 2 Shutdown for Small SG Tube Leak.Licensee Plans to Conduct Insps to Locate, Characterize & Repair Leaking Tube.State of AR Informed & Plans to Issue Press Release PNO-IV-96-058A, on 961017,fire Occurred in ANO Unit 1 Containment During Plant Heatup After Completion of Refueling Outage.Nrc Met W/Licensees Re Configuration of Lube Oil Sys & Required Lube Oil Collection Sys on 9610181996-10-22022 October 1996 PNO-IV-96-058A:on 961017,fire Occurred in ANO Unit 1 Containment During Plant Heatup After Completion of Refueling Outage.Nrc Met W/Licensees Re Configuration of Lube Oil Sys & Required Lube Oil Collection Sys on 961018 PNO-IV-96-058, on 961017,licensee Declared Notification of Unusual Event Due to Fire in Containment.Operators Pressurized Firewater Hose & Used Light Fog Pattern to Spray Insulation Panels1996-10-18018 October 1996 PNO-IV-96-058:on 961017,licensee Declared Notification of Unusual Event Due to Fire in Containment.Operators Pressurized Firewater Hose & Used Light Fog Pattern to Spray Insulation Panels PNO-IV-93-032, on 931021,licensee Informed Region IV That Plant Would Commence Shutdown on 931021 for Period of 5 Days.Purpose of Shutdown Was to Replace Pump Seal Cartridge on Rc Pump1993-10-28028 October 1993 PNO-IV-93-032:on 931021,licensee Informed Region IV That Plant Would Commence Shutdown on 931021 for Period of 5 Days.Purpose of Shutdown Was to Replace Pump Seal Cartridge on Rc Pump PNO-IV-89-042, on 890623,plant Shutdown Commenced Due to Increased RCS Leakage.Caused by Fatigue in Vent Line on Reactor Coolant Pump C Seal Pressure Sensing Line.Plant Heatup Expected to Begin on 8906261989-06-26026 June 1989 PNO-IV-89-042:on 890623,plant Shutdown Commenced Due to Increased RCS Leakage.Caused by Fatigue in Vent Line on Reactor Coolant Pump C Seal Pressure Sensing Line.Plant Heatup Expected to Begin on 890626 PNO-IV-89-034, on 890517,unisolable RCS Pressure Boundary Leak Identified on Socket Weld on Cold Leg Drain Line. Possible Control Rod Drive Flange Leak Being Investigated & Insp of Reactor Bldg Continuing1989-05-17017 May 1989 PNO-IV-89-034:on 890517,unisolable RCS Pressure Boundary Leak Identified on Socket Weld on Cold Leg Drain Line. Possible Control Rod Drive Flange Leak Being Investigated & Insp of Reactor Bldg Continuing PNO-IV-89-028, on 890418,reactor Trip Due to Main Turbine Trip Occurred.Cause Unknown.Pump Reset & Restarted & Both Turbine Driven & Motor Driven Emergency Feedwater Pumps Operated to Maintain Steam Generator Water Level1989-04-18018 April 1989 PNO-IV-89-028:on 890418,reactor Trip Due to Main Turbine Trip Occurred.Cause Unknown.Pump Reset & Restarted & Both Turbine Driven & Motor Driven Emergency Feedwater Pumps Operated to Maintain Steam Generator Water Level PNO-IV-89-012, on 890204,licensee Issued Condition Rept Re DHR Suction Line Pipe Support Damage.Damage Involves Obvious Unexpected Movement at Pipe Support Which Caused Damage to Lugs.Conference Call to Review Scheduled for 8903011989-03-0101 March 1989 PNO-IV-89-012:on 890204,licensee Issued Condition Rept Re DHR Suction Line Pipe Support Damage.Damage Involves Obvious Unexpected Movement at Pipe Support Which Caused Damage to Lugs.Conference Call to Review Scheduled for 890301 PNO-IV-88-091, on 881123,hot Particle Was Identified by Portal Monitor as Worker Was Exiting non-radiological Work Area Located on Turbine Bldg Roof.Licensee Conducting Investigation to Determine Origin1988-11-25025 November 1988 PNO-IV-88-091:on 881123,hot Particle Was Identified by Portal Monitor as Worker Was Exiting non-radiological Work Area Located on Turbine Bldg Roof.Licensee Conducting Investigation to Determine Origin PNO-IV-88-086, on 881102,individual Performing Maint Activities on Steam Generator B Insp Cover Received Radiological Exposure of 3.216 Rem to Right Thigh.Nrc Dispatched to Site on 881103.Region IV Informed1988-11-0303 November 1988 PNO-IV-88-086:on 881102,individual Performing Maint Activities on Steam Generator B Insp Cover Received Radiological Exposure of 3.216 Rem to Right Thigh.Nrc Dispatched to Site on 881103.Region IV Informed PNO-IV-88-062A, on 880922,0.1 Gpm Reactor Coolant Pump a Seal Sensing Line Leak Identified.Caused by Tubing Rubbing Against Upstream Isolation Valve.Licensee Continuing Assessment of Problem1988-09-23023 September 1988 PNO-IV-88-062A:on 880922,0.1 Gpm Reactor Coolant Pump a Seal Sensing Line Leak Identified.Caused by Tubing Rubbing Against Upstream Isolation Valve.Licensee Continuing Assessment of Problem PNO-IV-88-074, on 880901,addl Case of Personnel Heat Exhaustion & Transport of Contaminated Individual Occurred. Individual Became Ill After 25 Minutes in Area W/Wbgt of 86.6 F.Program to Reduce Risk of Exhaustion Instituted1988-09-0101 September 1988 PNO-IV-88-074:on 880901,addl Case of Personnel Heat Exhaustion & Transport of Contaminated Individual Occurred. Individual Became Ill After 25 Minutes in Area W/Wbgt of 86.6 F.Program to Reduce Risk of Exhaustion Instituted PNO-IV-88-073, on 880830,personnel Heat Exhaustion Occurred Due to Physical Exertion While Wearing Anticontamination Clothing in High Temp Environ.Personnel Treated in Hosp. Restrictions Placed on Future Work Activities1988-08-30030 August 1988 PNO-IV-88-073:on 880830,personnel Heat Exhaustion Occurred Due to Physical Exertion While Wearing Anticontamination Clothing in High Temp Environ.Personnel Treated in Hosp. Restrictions Placed on Future Work Activities PNO-IV-88-059, on 880724,unit Shut Down & Cooldown Commenced to Replace Leaking Gaskets for Two Flanges on Pressurizer. Plant Restart Expected to Begin by 8807271988-07-25025 July 1988 PNO-IV-88-059:on 880724,unit Shut Down & Cooldown Commenced to Replace Leaking Gaskets for Two Flanges on Pressurizer. Plant Restart Expected to Begin by 880727 PNO-IV-88-038, on 880507,outage Extension Occurred Due to Uncoupled Control Element Assembly.Cause Under Investigation.Initial Investigation Indicates Vessel Assembly Weight Coupling Checks Performed1988-05-0909 May 1988 PNO-IV-88-038:on 880507,outage Extension Occurred Due to Uncoupled Control Element Assembly.Cause Under Investigation.Initial Investigation Indicates Vessel Assembly Weight Coupling Checks Performed PNO-IV-88-040, on 880509,System Energy Resources,Inc to Manage & Operate All Middle South Nuclear Plants.Arkansas Power & Light & Louisiana Power & Light Will Apply for Appropriate License Amends1988-05-0909 May 1988 PNO-IV-88-040:on 880509,System Energy Resources,Inc to Manage & Operate All Middle South Nuclear Plants.Arkansas Power & Light & Louisiana Power & Light Will Apply for Appropriate License Amends PNO-IV-88-035, on 880503,control Element Assembly Exceeded Tech Spec Limit of 3 During Rod Drop Test.Plant Startup on Hold Pending Resolution of Issue.Licensee Reviewing Safety Analysis Assumptions & Anticipate Tech Spec Amend1988-05-0404 May 1988 PNO-IV-88-035:on 880503,control Element Assembly Exceeded Tech Spec Limit of 3 During Rod Drop Test.Plant Startup on Hold Pending Resolution of Issue.Licensee Reviewing Safety Analysis Assumptions & Anticipate Tech Spec Amend PNO-IV-88-014, on 880224,contractor Employee Fell & Received Gash on Forehead After Hitting Head on Overhead Duck.Individual Surveyed But No Contamination Found.Employee Transported to Local Hosp.State of AR Not Informed1988-02-26026 February 1988 PNO-IV-88-014:on 880224,contractor Employee Fell & Received Gash on Forehead After Hitting Head on Overhead Duck.Individual Surveyed But No Contamination Found.Employee Transported to Local Hosp.State of AR Not Informed PNO-IV-87-038A, preliminary Results of Investigations of Reported High Containment Temps at Facility Substantiated Basis for Justifications for Continued Operations Submitted by Licensee on 870814 & 181987-08-20020 August 1987 PNO-IV-87-038A:preliminary Results of Investigations of Reported High Containment Temps at Facility Substantiated Basis for Justifications for Continued Operations Submitted by Licensee on 870814 & 18 PNO-IV-87-038, region Initiated Augmented Insp Team (AIT) to Review Circumstances Associated W/Elevated Reactor Bldg Temps & Assess Impact on Equipment Operability & USAR Accident Analysis.Ait Scheduled to Begin Work on 8708181987-08-17017 August 1987 PNO-IV-87-038:region Initiated Augmented Insp Team (AIT) to Review Circumstances Associated W/Elevated Reactor Bldg Temps & Assess Impact on Equipment Operability & USAR Accident Analysis.Ait Scheduled to Begin Work on 870818 PNO-IV-87-032, on 870706,leakage Found in RCS Pressure Boundary.Caused by Leaking Seal Weld on Dummy Heater Plug on Bottom of Pressurizer.Rcs Drained & Seal Weld Repaired. Outage Duration About 1 Wk.State of AR Informed1987-07-0707 July 1987 PNO-IV-87-032:on 870706,leakage Found in RCS Pressure Boundary.Caused by Leaking Seal Weld on Dummy Heater Plug on Bottom of Pressurizer.Rcs Drained & Seal Weld Repaired. Outage Duration About 1 Wk.State of AR Informed PNO-IV-87-022, on 870424,nonisolable Leak on RCS Pressurizer Vessel Lower Head Discovered & Plant Shut & Cooled Down. Cause Under investigation.C-E Sending Personnel to Assist in Investigation1987-04-27027 April 1987 PNO-IV-87-022:on 870424,nonisolable Leak on RCS Pressurizer Vessel Lower Head Discovered & Plant Shut & Cooled Down. Cause Under investigation.C-E Sending Personnel to Assist in Investigation PNO-IV-87-003, on 870109,commenced Unit Shutdown & Cooldown to Repair Small Tube Leak in Steam Generator A.On 870110, Plant in Cold Shutdown.Licensee Plans to Place Unit Back on Line on 8701181987-01-12012 January 1987 PNO-IV-87-003:on 870109,commenced Unit Shutdown & Cooldown to Repair Small Tube Leak in Steam Generator A.On 870110, Plant in Cold Shutdown.Licensee Plans to Place Unit Back on Line on 870118 PNO-IV-86-033, on 861104,power Reduced from 100% to Go to Cold Shutdown to Repair body-to-bonnet Seal Ring Leak on Check Valve a in Main Feed Header to Steam Generator B.Leak Rate Estimated to Be Approx 2 to 3 Gpm1986-11-0404 November 1986 PNO-IV-86-033:on 861104,power Reduced from 100% to Go to Cold Shutdown to Repair body-to-bonnet Seal Ring Leak on Check Valve a in Main Feed Header to Steam Generator B.Leak Rate Estimated to Be Approx 2 to 3 Gpm PNO-IV-86-032, on 861023,boric Acid Corrosion on HPI Nozzle for Penetration Into Reactor Coolant Pump a Discharge Pipe discovered.Body-to-bonnet Leak on Manual Isolation Valve in HPI Apparent Source.B&W to Assist in Evaluation of Problem1986-10-23023 October 1986 PNO-IV-86-032:on 861023,boric Acid Corrosion on HPI Nozzle for Penetration Into Reactor Coolant Pump a Discharge Pipe discovered.Body-to-bonnet Leak on Manual Isolation Valve in HPI Apparent Source.B&W to Assist in Evaluation of Problem PNO-IV-86-030, on 860924,following Reactor Trip on High RCS Pressure,Quench Tank Parameters & Tail Pipe Temp Indicated That One or Both Pressurizer Safety Valves Lifted.Caused by Improper Setup During Lift Test.Retest in Progress1986-09-25025 September 1986 PNO-IV-86-030:on 860924,following Reactor Trip on High RCS Pressure,Quench Tank Parameters & Tail Pipe Temp Indicated That One or Both Pressurizer Safety Valves Lifted.Caused by Improper Setup During Lift Test.Retest in Progress PNO-IV-86-025, during Refueling Outage & Valve Insp of Unit 2,valve Operator Environ Qualification Deficiencies Identified in Limitorque motor-operated Valves.Cause Unknown.Insp & Rework of Valves Continuing1986-07-17017 July 1986 PNO-IV-86-025:during Refueling Outage & Valve Insp of Unit 2,valve Operator Environ Qualification Deficiencies Identified in Limitorque motor-operated Valves.Cause Unknown.Insp & Rework of Valves Continuing PNO-IV-86-005, on 860113,emergency Diesel Generator Declared Inoperable Due to Failing Monthly Surveillance Test.On 860116,reactor Shut Down for Outage to Repair Generator. Several Damaged Piston Wrist Pin Bearings Found1986-01-16016 January 1986 PNO-IV-86-005:on 860113,emergency Diesel Generator Declared Inoperable Due to Failing Monthly Surveillance Test.On 860116,reactor Shut Down for Outage to Repair Generator. Several Damaged Piston Wrist Pin Bearings Found PNO-IV-85-061, on 851206,scheduled Maint Outage Will Begin. Replacement of Expansion Joint in Feedwater Heater & Repair of Main Generator Cooling Sys Hydrogen Leak Will Be Completed.Restart Scheduled for 8512111985-12-0606 December 1985 PNO-IV-85-061:on 851206,scheduled Maint Outage Will Begin. Replacement of Expansion Joint in Feedwater Heater & Repair of Main Generator Cooling Sys Hydrogen Leak Will Be Completed.Restart Scheduled for 851211 PNO-IV-85-056, on 851108,info Pickets Established at Const Contractor Entrance Following 851107 Press Release by State of AR.AFL-CIO Protesting Replacement of Bechtel W/Daniel Const.Security Will Be Increased for 851123 Protest1985-11-0808 November 1985 PNO-IV-85-056:on 851108,info Pickets Established at Const Contractor Entrance Following 851107 Press Release by State of AR.AFL-CIO Protesting Replacement of Bechtel W/Daniel Const.Security Will Be Increased for 851123 Protest PNO-IV-85-049, on 850928,cooldown Commenced to Replace Seal on Reactor Coolant Pump C.Seal Cartridge Developed Crack Where Middle Cavity Seal Pressure Sensing Line Joins Cartridge.Startup Scheduled for 8510031985-09-30030 September 1985 PNO-IV-85-049:on 850928,cooldown Commenced to Replace Seal on Reactor Coolant Pump C.Seal Cartridge Developed Crack Where Middle Cavity Seal Pressure Sensing Line Joins Cartridge.Startup Scheduled for 851003 PNO-IV-85-048, on 850917,control Rod Dropped,Causing Plant Runback to Approx 38% Power.Caused by Repair to CRD Stator. Cooldown Commenced to Repair Stator1985-09-18018 September 1985 PNO-IV-85-048:on 850917,control Rod Dropped,Causing Plant Runback to Approx 38% Power.Caused by Repair to CRD Stator. Cooldown Commenced to Repair Stator PNO-IV-85-047, on 850913,during Shutdown for Replacement of Seals on Two Reactor Contact Pumps,Main Steam Isolation Actuated.Caused by Personnel Error.Unit Will Be Shut Down for Approx 1 Wk.Press Release Will Be Issued by Licensee1985-09-13013 September 1985 PNO-IV-85-047:on 850913,during Shutdown for Replacement of Seals on Two Reactor Contact Pumps,Main Steam Isolation Actuated.Caused by Personnel Error.Unit Will Be Shut Down for Approx 1 Wk.Press Release Will Be Issued by Licensee PNO-IV-85-042, on 850819,manual Reactor Trip Occurred When Main Feedwater Pump B Turbine Speed Governor Failed, Causing Transient.Repairs Underway on Leaking Secondary Handhole of Steam generator.One-wk Outage to End 8507261985-08-20020 August 1985 PNO-IV-85-042:on 850819,manual Reactor Trip Occurred When Main Feedwater Pump B Turbine Speed Governor Failed, Causing Transient.Repairs Underway on Leaking Secondary Handhole of Steam generator.One-wk Outage to End 850726 PNO-IV-85-033, on 850715,licensee Announced Significant Cost Curtailment Program Due to State of AR PSC Rejection of Licensee Settlement Proposal for Sharing Const Cost of Grand Gulf1985-07-17017 July 1985 PNO-IV-85-033:on 850715,licensee Announced Significant Cost Curtailment Program Due to State of AR PSC Rejection of Licensee Settlement Proposal for Sharing Const Cost of Grand Gulf PNO-IV-85-026, on 850607,unit Placed in Mode 2 for More than 2 Days.Caused by Listed Maint Needed After Operation at 95% Full Power.Unit Scheduled to Return to Power on 8506121985-06-10010 June 1985 PNO-IV-85-026:on 850607,unit Placed in Mode 2 for More than 2 Days.Caused by Listed Maint Needed After Operation at 95% Full Power.Unit Scheduled to Return to Power on 850612 PNO-IV-85-025, on 850531,unit Tripped from 100% Power Due to Unexplained Closure of Main Turbine Intercept Valves.Steam Pressure from Valves Caused Long,Narrow Crack in Expansion Joint.Steam Leak Isolated When Turbine Tripped1985-05-31031 May 1985 PNO-IV-85-025:on 850531,unit Tripped from 100% Power Due to Unexplained Closure of Main Turbine Intercept Valves.Steam Pressure from Valves Caused Long,Narrow Crack in Expansion Joint.Steam Leak Isolated When Turbine Tripped PNO-IV-82-029A, on 820808,seal on Reactor Coolant Pump C Failed During Heatup Following Weld Repair on Valve MU-45B. Leakage Rate on Pump Reached Max of 51 Gpm.State of AR Notified1982-08-0909 August 1982 PNO-IV-82-029A:on 820808,seal on Reactor Coolant Pump C Failed During Heatup Following Weld Repair on Valve MU-45B. Leakage Rate on Pump Reached Max of 51 Gpm.State of AR Notified PNO-IV-82-029, on 820804,control Rod 11,group 7,dropped. During Subsequent Runback,Reactor Tripped.Reactor Protection Sys Indicated Loss of Both Main Feedwater Pumps When Pump B Tripped.Low Resistance Readings Found on Rod Drive Stator1982-08-0606 August 1982 PNO-IV-82-029:on 820804,control Rod 11,group 7,dropped. During Subsequent Runback,Reactor Tripped.Reactor Protection Sys Indicated Loss of Both Main Feedwater Pumps When Pump B Tripped.Low Resistance Readings Found on Rod Drive Stator PNO-IV-82-028A, on 820730,licensee Field Teams Visited Residences,Businesses & Organizations Located within 10-mile Emergency Planning Zone Outside Area of Siren Coverage Delivering Ebs Tone Alert Receivers1982-08-0303 August 1982 PNO-IV-82-028A:on 820730,licensee Field Teams Visited Residences,Businesses & Organizations Located within 10-mile Emergency Planning Zone Outside Area of Siren Coverage Delivering Ebs Tone Alert Receivers PNO-IV-82-028, on 820731,licensee Will Implement Procedures to Assure Adequate Public Notification of Warning Sys Operability.Rural Areas Will Be Provided W/Tone Receivers. Actions Will Be Completed by 8208021982-07-30030 July 1982 PNO-IV-82-028:on 820731,licensee Will Implement Procedures to Assure Adequate Public Notification of Warning Sys Operability.Rural Areas Will Be Provided W/Tone Receivers. Actions Will Be Completed by 820802 PNO-IV-82-027, on 820727,control Rod Drop Occurred.Caused by Upper Gripper Coil on Control Element Drive Motor Faulting. Interferences Will Be Removed & Control Element Drive Motor 28 Will Be Replaced1982-07-29029 July 1982 PNO-IV-82-027:on 820727,control Rod Drop Occurred.Caused by Upper Gripper Coil on Control Element Drive Motor Faulting. Interferences Will Be Removed & Control Element Drive Motor 28 Will Be Replaced PNO-IV-80-032, on 800905,uncontrolled Release of Radioactive Gases Through Plant Stack Occurred When During Cooldown Letdown,Sys Relief Valve Lifted & Remained Open About 5 Minutes.Estimated Release Less than Tech Spec Limit1980-09-0808 September 1980 PNO-IV-80-032:on 800905,uncontrolled Release of Radioactive Gases Through Plant Stack Occurred When During Cooldown Letdown,Sys Relief Valve Lifted & Remained Open About 5 Minutes.Estimated Release Less than Tech Spec Limit PNO-IV-80-004, licensee Discovered Cracks in One of Two Containment Spray Sys in Reactor Bldg.Licensee Will Inspect. Plant Presently in Cold Shutdown While Performing Mods Required by NUREG-05781980-01-21021 January 1980 PNO-IV-80-004:licensee Discovered Cracks in One of Two Containment Spray Sys in Reactor Bldg.Licensee Will Inspect. Plant Presently in Cold Shutdown While Performing Mods Required by NUREG-0578 PNO-IV-79-010, on 791017,inadvertent Release of Radioactive Gas.Air Sample in Makeup Tank Initiated,Stack Monitor Alarmed & Sampling Terminated.Rate of Radioactive Release Exceeded Tech Spec Limit by 2.361979-10-18018 October 1979 PNO-IV-79-010:on 791017,inadvertent Release of Radioactive Gas.Air Sample in Makeup Tank Initiated,Stack Monitor Alarmed & Sampling Terminated.Rate of Radioactive Release Exceeded Tech Spec Limit by 2.36 1998-12-29 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000313/19990121999-09-0101 September 1999
[Table view]Insp Repts 50-313/99-12 & 50-368/99-12 on 990711-0821.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000313/19990111999-08-12012 August 1999 Insp Repts 50-313/99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Major Areas Inspected:Licensee Requalification Program IR 05000313/19990081999-07-21021 July 1999 Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support ML20196D4851999-06-21021 June 1999 Partially Deleted Notice of Violation from Insp on 990204. Violation Noted.Ed Mccormic,Individual Licensed Operator, Violated 10CFR50.53(j) by Use of Illegal Drug (Marijuana) as Evidence by Confirmed Positive Test for Urine on 981222 IR 05000313/19990051999-06-10010 June 1999 Insp Repts 50-313/99-05 & 50-368/99-05 on 990411-0529.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support IR 05000313/19990061999-06-0808 June 1999 Insp Repts 50-313/99-06 & 50-368/99-06 on 990524-28. Violations Identified & Being Treated as Noncited Violation. Major Areas Inspected:Radiological Environ Monitoring Program ML20207G8511999-06-0707 June 1999 Notice of Violation from Investigation Rept A4-1998-042 on 990127.Violation Noted:After 980528,ES Feemster,Initiated Reactor Simulator Training Attendance Record Indicating Attendance at 980528 Training Session Not Attended IR 05000313/19980211999-05-24024 May 1999 Insp Repts 50-313/98-21 & 50-368/98-01 on 981116-990406.One Violation Occurred & Being Treated as non-cited Violation. Major Areas Inspected:Review of Licensee Implementation of post-fire Alternative Shutdown Requirements ML20206S4881999-05-14014 May 1999 Insp Repts 50-313/99-07 & 50-368/99-07 on 990426-30.No Violations Noted.Major Areas Inspected:Access Authorization, Alarm Stations,Communications,Protected Area Access Control of Personnel,Packages & Vehicles & Assessment Aids IR 05000313/19990041999-05-10010 May 1999 Insp Repts 50-313/99-04 & 50-368/99-04 on 990228-0410. Non-cited Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000313/19990031999-04-0909 April 1999 Insp Repts 50-313/99-03 & 50-368/99-03 on 990202-17.No Violations Noted.Major Areas Inspected:Operations IR 05000313/19990011999-04-0202 April 1999 Insp Repts 50-313/99-01 & 50-368/99-01 on 990117-0227.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000313/19980101999-02-0909 February 1999 Insp Repts 50-313/98-10 & 50-368/98-10 on 981206-990116.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support IR 05000313/19990021999-01-25025 January 1999 Insp Repts 50-313/99-02 & 50-368/99-02 on 990111-15.No Violations Noted.Major Areas Inspected:Exposure Controls, Controls of Radioactive Matl & Contamination,Surveying & Monitoring & Program to Maintain Occupational Exposure IR 05000313/19983031999-01-0707 January 1999 NRC Operator Licensing Exam Rept 50-313/98-303 & 50-368/98-303 on 981218.Exam Results:On Reactor Operator License Applicant Passed Written Exam PNO-IV-98-066, on 981225,large Influx of Fish (Shad) Affected Unit 1 Intake Structure,Resulting in Degraded Available Circulating Water Pump Suction Pressure.Shade Runs Have Historically Occurred as Result of Cyclic Changes1998-12-29029 December 1998 PNO-IV-98-066:on 981225,large Influx of Fish (Shad) Affected Unit 1 Intake Structure,Resulting in Degraded Available Circulating Water Pump Suction Pressure.Shade Runs Have Historically Occurred as Result of Cyclic Changes IR 05000313/19980091998-12-21021 December 1998 Insp Repts 50-313/98-09 & 50-368/98-09 on 981025-1205.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support ML20196G4001998-11-19019 November 1998 Notice of Violation from Insp on 980913-1024.Violation Noted:Procedure 1104.032,Rev 51, FP Sys, Supplement 2, Surveillance Test of Diesel Fire Pump, Specified Limit on Max Coolant Temp Which Was Inconsistent Temp Set in Manual IR 05000313/19980081998-11-19019 November 1998 Insp Repts 50-313/98-08 & 50-368/98-08 on 980913-1024. Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000313/19980191998-11-11011 November 1998 Insp Repts 50-313/98-19 & 50-368/98-19 on 981019-22.No Violations Noted.Major Areas Inspected:Exposure Controls, Control of Radioactive Matls & Contamination,Surveying & Monitoring & QA Oversight of Radiation Protection Program IR 05000313/19980201998-10-27027 October 1998 Insp Repts 50-313/98-20 & 50-368/98-20 on 981019-22.No Violations Noted.Major Areas Inspected:Operational Status of Licensee Emergency Preparedness Program IR 05000313/19980071998-10-15015 October 1998 Corrected Pages to Insp Repts 50-313/98-07 & 50-368/98-07 on 980925.Typo Was Identified in Numbering of Insp Followup Sys Closed Items IR 05000368/19983011998-10-14014 October 1998 NRC Operator Licensing Exam Rept 50-368/98-301 for Test Administered on 980831-0904 ML20154H0581998-10-0808 October 1998 NRC Operator Licensing Exam Repts 50-313/98-302 & 50-368/98-302 for Tests Administered on 980914-18.Overall, Operator License Applicants Demonstrated Good Performance & Use of Good Communication Practices,As Well as Peer Checks ML20153H2461998-09-25025 September 1998 Insp Repts 50-313/98-07 & 50-368/98-07 on 980802-0912.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support IR 05000313/19980161998-09-15015 September 1998 Insp Repts 50-313/98-16 & 50-368/98-16 on 980831-0904.No Violations Noted.Major Areas Inspected:Testing & Maintenance,Protected Area Barrier & Detection Aids, Compensatory Measures & Security Sys Power Supply IR 05000313/19980111998-09-0303 September 1998 Insp Repts 50-313/98-11 & 50-368/98-11 Has Been Canceled.No Other Rept Will Be Issued IR 05000313/19980151998-09-0202 September 1998 Insp Repts 50-313/98-15 & 50-368/98-15 on 980818-21.No Violations Noted.Major Areas Inspected:Licensee Performance & Capabilities During full-scale,biennial Exercise of Emergency Plan & Implementing Procedures IR 05000313/19980061998-08-18018 August 1998 Insp Repts 50-313/98-06 & 50-368/98-06 on 980621-0801. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20237C9271998-08-18018 August 1998 Notice of Violation from Insp on 980621-0801.Violation Noted:Between 970601 & 980709,four Unit 1 Sros,Five Unit 2 Sros,One Unit 1 RO & Five Unit 2 ROs Resumed Activities Authorized by License W/O Performing RO or SRO Functions IR 05000313/19980051998-07-16016 July 1998 Insp Repts 50-313/98-05 & 50-368/98-05 on 980510-0620.No Violations Noted.Major Areas Inspected:Operations, Engineering,Maintenance & Plant Support ML20248J5751998-06-0404 June 1998 Notice of Violation from Insp on 980329-0509.Violation Noted:Licensed Senior Reactor Operators Completing Listed Form Did Not Identify That Two Craftsmen Were Signed in on Hold Card 98-1-0364 IR 05000313/19980041998-06-0404 June 1998 Insp Repts 50-313/98-04 & 50-368/98-04 on 980329-0509. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20216D2521998-05-11011 May 1998 Errata to Insp Repts 50-313/98-12 & 50-368/98-12 ML20247K0301998-05-0808 May 1998 Insp Repts 50-313/98-14 & 50-368/98-14 on 980427-0501. Violations Noted.Major Areas Inspected:Access Authorization, Alarm Stations,Communications,Access Control of Personnel & Packages & Vehicles ML20247K0261998-05-0808 May 1998 Notice of Violation from Insp on 980427-0501.Violation Noted:On 980430,inspector Determined That Computer Controlled Intrusion Detection Sys Failed to Provide Audible Alarm Signal Upon Recognizing Unauthorized Access Attempt ML20217A9231998-04-17017 April 1998 Notice of Violation from Insp on 980215-0328.Violation Noted:Licensee Failed to Update Radiological Info Posting at Entrance of HPSI Pump Room a to Reflect Results of Radiological Surveys Performed Between 980221 & 0302 ML20217A9351998-04-17017 April 1998 Insp Repts 50-313/98-03 & 50-368/98-03 on 980215-0328. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000313/19980131998-04-14014 April 1998 Insp Repts 50-313/98-13 & 50-368/98-13 on 980330-0403. Violations Noted.Major Areas Inspected:Review of Radiation Protection Program Focussing on Unit 1 Refueling Outage Activities ML20236L5221998-04-13013 April 1998 Notice of Violation from Investigation on 970916-980210. Violation Noted:Mj Talley Deliberately Documented Radiation & Contamination Survey Results for Areas Which Were Not Surveyed ML20217N2711998-04-0202 April 1998 Notice of Violation from Insp on 980302-11.Violation Noted: Engineering Technique Specification Sheet Etss 4 Instructed Outage 2P98 Eddy Current Analysts to Use Phase Rotation Setting Inappropriate for Plus Point Probe ML20217N3021998-04-0202 April 1998 Insp Repts 50-313/98-12 & 50-368/98-12 on 980302-11. Violations Noted.Major Areas Inspected:Maint & Engineering ML20248L6321998-03-18018 March 1998 Notice of Violations from Insp on 971027-31 & 1110-14. Violations Noted:Activities Affecting Quality Were Not Accomplished IAW Procedure 1000.028 ML20216B8621998-03-10010 March 1998 Notice of Violation from Insp on 980104-0214.Violation Noted:Instrumentation & Control Technicians Failed to Remove Three Jumpers Before Restoring Reactor Protection Sys Channel C to Svc ML20216B8751998-03-10010 March 1998 Insp Repts 50-313/98-02 & 50-368/98-02 on 980104-0214. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20202E3401998-02-0606 February 1998 Insp Repts 50-313/97-21 & 50-368/97-21 on 971027-31 & 1110- 14.Violations Noted.Major Areas Inspected:Engineering & Plant Support.Nrc Identified Fire Barrier Deficiency & Licensee Took Promp Compensatory Actions as Required ML20202E3201998-02-0606 February 1998 Notice of Violation from Insp on 971027-31 & 1110-14. Violation Noted:As of 911123,procedure 1010.002, Transient History/Transient Cycle Logging, Was Inappropriate to Circumstances IR 05000313/19980991998-02-0404 February 1998 SALP Repts 50-313/98-99 & 50-368/98-99 for Period of 970707-980103 IR 05000313/19970081998-01-23023 January 1998 Insp Repts 50-313/97-08 & 50-368/97-08 on 971123-980103.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support PNO-IV-98-001A, on 980105,plant Shutdown When Heavy Rains Caused Accumulation of Debris at Circulating & Svc Water Intake Structure.Debris Damaged Some Intake Structure Components.Repairs to Intake Components Completed on 9801091998-01-13013 January 1998 PNO-IV-98-001A:on 980105,plant Shutdown When Heavy Rains Caused Accumulation of Debris at Circulating & Svc Water Intake Structure.Debris Damaged Some Intake Structure Components.Repairs to Intake Components Completed on 980109 1999-09-01 |
T .
- May 4, 1988 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE -- PNO-IV-88-35 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by the Region IV staff on this date.
FACILITY: ANO - Unit #2 Licensee Emergency Classification:
Arkansas Power & Light Co. Notification of Unusual Event Russellville, AR Alert DN: 50-368 Site Area Emergency General Emergency
_X_ Not Applicable
SUBJECT:
CONTROL ELEMENT ASSEMBLY (CEA) DROP TIME TESTING On May 3, 1988, at 5:00 p.m., CDT, the licensee informed N Region IV and the senior resident inspector that certain CEAs had exceeded the 'echnical Specification (TS) limit of three seconds during pre-critical rod drop test 1ng. Four have been confirmed and eight potentially exceed the TS limit. The licensee was using a new method of rod drop testing than has been used during prev'ous refueling outages. The old method involved testing individual CEAs by opening individual CEA breakers and using a visicorder to record the time from breaker opening to CEA 90% inserted. The CEA drop times with this old method typically ranged from 2.65 to 2.85 seconds. The new testing method developed by Combustion Engineering involves testing several CEAs at one time by opening the reactor trip breaker.
The control element assembly calculator and core protection computer were used to record the time from reactor trip breaker opening to CEAs 90% inserted. With this new method the highest drop time recorded was 3.2 seconds. Plant startup is on hold pending resolution of this issue. The licensee is reviewing safety analysis assumptions and basis and they anticipate requesting an emergency TS amendment.
The Office of Nuclear Reactor Regulation has been informed.
Two specialist inspectors from NRC Region IV Division of Reactor Safety are on site along with the resident inspectors to monitor licensee actions.
The licensee has not informed the news media.
Neither the licensee nor the NRC plans to issue a press release.
This information has been confirned with a licensee representative.
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