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	Issue date	Title	Topic
PNO-III-80-032, on 800219,correspondents from ABC 20/20 Program Will Interview Regional Director & Other Members Re NRC Investigation Into Allegations of Falsification of Qualification Records of Personnel Doing Design Work	19 February 1980	PNO-III-80-032:on 800219,correspondents from ABC 20/20 Program Will Interview Regional Director & Other Members Re NRC Investigation Into Allegations of Falsification of Qualification Records of Personnel Doing Design Work
PNO-III-80-054, on 800318,licensee Informed Region 3 That Channel 7 News in Detroit,Mi Plans to Televise 800321 Interview W/Site Contractor Employees Re Allegations of Improper Receipt Insp of Small Bore Pipe	19 March 1980	PNO-III-80-054 :on 800318,licensee Informed Region 3 That Channel 7 News in Detroit,Mi Plans to Televise 800321 Interview W/Site Contractor Employees Re Allegations of Improper Receipt Insp of Small Bore Pipe
PNO-III-85-050, on 850621,initial Criticality Achieved within Two Steps of Estimated Critical Position.Control Rods Withdrawn to Criticality	21 June 1985	PNO-III-85-050:on 850621,initial Criticality Achieved within Two Steps of Estimated Critical Position.Control Rods Withdrawn to Criticality
PNO-III-85-055, on 850709,reactor Tripped on Low Water Level. Caused by Operator Inattentiveness to Level Indicator.No ECCS Injection Occurred	10 July 1985	PNO-III-85-055:on 850709,reactor Tripped on Low Water Level. Caused by Operator Inattentiveness to Level Indicator.No ECCS Injection Occurred	Reactor Vessel Water Level
PNO-III-85-058, on 850702,reactor Brought to Criticality W/O Shift Supervisor Realizing Incident.Caused by Reactor Operator Failing to Follow Proper Procedures for Moving Control Rods in Full Out Position.Incident Being Reviewed	15 July 1985	PNO-III-85-058:on 850702,reactor Brought to Criticality W/O Shift Supervisor Realizing Incident.Caused by Reactor Operator Failing to Follow Proper Procedures for Moving Control Rods in Full Out Position.Incident Being Reviewed
PNO-III-85-058A, on 850716,confirmatory Action Ltr Issued Documenting Util Commitment to Restrict Power Level to 5%, Pending Completion of Evaluation of 850702 Inadvertent Criticality Incident.Investigation Continuing	17 July 1985	PNO-III-85-058A:on 850716,confirmatory Action Ltr Issued Documenting Util Commitment to Restrict Power Level to 5%, Pending Completion of Evaluation of 850702 Inadvertent Criticality Incident.Investigation Continuing
PNO-III-85-063, on 850723,reactor Shut Down to Repair Thrust Bearing Housing on Feedwater Pump,Damaged During 850722 Demonstration Testing.Further Exam Underway	24 July 1985	PNO-III-85-063:on 850723,reactor Shut Down to Repair Thrust Bearing Housing on Feedwater Pump,Damaged During 850722 Demonstration Testing.Further Exam Underway
PNO-III-85-063A, investigation Concluded That Vibration in South Reactor Feeder Pump Turbine,Plus Inadequate Securing of Outboard Bearing Cap Caused Turbine Failure.Study of Problem Continuing	5 August 1985	PNO-III-85-063A:investigation Concluded That Vibration in South Reactor Feeder Pump Turbine,Plus Inadequate Securing of Outboard Bearing Cap Caused Turbine Failure.Study of Problem Continuing
PNO-III-85-066, on 850729,low Svc Water Flow Alarm Received During Surveillance Testing of Div I Diesel Generator. Generator Manually Tripped.Caused by Closed Bypass Valve in Line Returning Water to Reservoir.Investigation Underway	30 July 1985	PNO-III-85-066:on 850729,low Svc Water Flow Alarm Received During Surveillance Testing of Div I Diesel Generator. Generator Manually Tripped.Caused by Closed Bypass Valve in Line Returning Water to Reservoir.Investigation Underway
PNO-III-85-067, on 850730,licensee Announced That Low Power Testing Would Not Resume Until Various Equipment & Procedural Difficulties Resolved.Shutdown Caused by Premature Criticality on 850702	31 July 1985	PNO-III-85-067:on 850730,licensee Announced That Low Power Testing Would Not Resume Until Various Equipment & Procedural Difficulties Resolved.Shutdown Caused by Premature Criticality on 850702
PNO-III-85-067A, on 850809,licensee Will Resume Low Power Testing.Region III Approved Util Corrective Action Program Submitted on 850807,in Response to 850702 Premature Criticality.Plant Still Restricted to 5% Power	9 August 1985	PNO-III-85-067A:on 850809,licensee Will Resume Low Power Testing.Region III Approved Util Corrective Action Program Submitted on 850807,in Response to 850702 Premature Criticality.Plant Still Restricted to 5% Power
PNO-III-85-070, on 850806,Monroe County Board of Commissioners Requested Full Investigation of Operational Procedures & Employee Credentials Due to 850702 Unplanned Criticality Not Reported to NRC Until 850715	8 August 1985	PNO-III-85-070:on 850806,Monroe County Board of Commissioners Requested Full Investigation of Operational Procedures & Employee Credentials Due to 850702 Unplanned Criticality Not Reported to NRC Until 850715
PNO-III-85-076, on 850825,recirculation Pump B Problem Resulted in Brief Power Increase from 2.9 to 8.8%.Reactor Operators Tripped Pump After Failing to Reduce Pump Speed. Testing Disclosed No Problems W/Speed Control Circuitry	26 August 1985	PNO-III-85-076:on 850825,recirculation Pump B Problem Resulted in Brief Power Increase from 2.9 to 8.8%.Reactor Operators Tripped Pump After Failing to Reduce Pump Speed. Testing Disclosed No Problems W/Speed Control Circuitry
PNO-III-85-077, on 850904,leak Rate Test Connection Valve Installed on 850620 in Containment Sampling Sys Found Open & Attached Line Uncapped,Due to Unrevised Containment Valve Lineup Procedure.Valve Closed	5 September 1985	PNO-III-85-077:on 850904,leak Rate Test Connection Valve Installed on 850620 in Containment Sampling Sys Found Open & Attached Line Uncapped,Due to Unrevised Containment Valve Lineup Procedure.Valve Closed
PNO-III-85-083, on 850917,leak Observed in East Steam Bypass Line.Transient Power Spike Observed While Attempting to Isolate Line & Open Valve.Cause of Transient Not Determined. Cracked Piping Around Valve Under Investigation	19 September 1985	PNO-III-85-083:on 850917,leak Observed in East Steam Bypass Line.Transient Power Spike Observed While Attempting to Isolate Line & Open Valve.Cause of Transient Not Determined. Cracked Piping Around Valve Under Investigation
PNO-III-85-095, on 851113,unusual Noise & Vibration Observed in Emergency Diesel Generator.Operator Manually Tripped Diesel.Preliminary Evaluation Indicates Damage to Connecting Rod Bearing for Upper Crankshaft & Upper Piston Skirt	14 November 1985	PNO-III-85-095:on 851113,unusual Noise & Vibration Observed in Emergency Diesel Generator.Operator Manually Tripped Diesel.Preliminary Evaluation Indicates Damage to Connecting Rod Bearing for Upper Crankshaft & Upper Piston Skirt
PNO-III-85-095A, on 851201,during Reassembly of Steam Generator 13,discontinuities Observed on Three Connecting Rod Journals.Vendor Will Supply Documentation.Investigation Continuing.Startup Projected for 851211	3 December 1985	PNO-III-85-095A:on 851201,during Reassembly of Steam Generator 13,discontinuities Observed on Three Connecting Rod Journals.Vendor Will Supply Documentation.Investigation Continuing.Startup Projected for 851211
PNO-III-85-095B, during Insp of Emergency Diesel Generator 11,degradation of Six Upper Crankshaft Bearings Noted.Cause Undetermined.Findings & Relation of Findings to Other Diesel Generators Being Evaluated	4 December 1985	PNO-III-85-095B:during Insp of Emergency Diesel Generator 11,degradation of Six Upper Crankshaft Bearings Noted.Cause Undetermined.Findings & Relation of Findings to Other Diesel Generators Being Evaluated
PNO-III-85-095C, on 851212,diesel Generator 14 Tripped on Low Lube Oil Pressure During Test Run.Bearing Failure & Erratic Behavior of Svc Water Pump Under Investigation as Possible Causes.Generator Will Be Monitored	12 December 1985	PNO-III-85-095C:on 851212,diesel Generator 14 Tripped on Low Lube Oil Pressure During Test Run.Bearing Failure & Erratic Behavior of Svc Water Pump Under Investigation as Possible Causes.Generator Will Be Monitored
PNO-III-85-095D, on 851113,bearing Damage Occurred to Diesel Generators 13,11 & 14.Caused by Insufficient break-in Period.Bearing Replacement Required for Diesel Generator 11. Decrease in Lubricating Oil Viscosity Noted for 12 & 14	24 December 1985	PNO-III-85-095D:on 851113,bearing Damage Occurred to Diesel Generators 13,11 & 14.Caused by Insufficient break-in Period.Bearing Replacement Required for Diesel Generator 11. Decrease in Lubricating Oil Viscosity Noted for 12 & 14
PNO-III-85-098, on 851117,between 17,000 & 35,000 Gallons of Radioactive Water Released from Ruptured Seam in Condensate Storage Tank.Water Radioactivity Less than 0.4% of Regulatory Limit for Offsite Release	18 November 1985	PNO-III-85-098:on 851117,between 17,000 & 35,000 Gallons of Radioactive Water Released from Ruptured Seam in Condensate Storage Tank.Water Radioactivity Less than 0.4% of Regulatory Limit for Offsite Release
PNO-III-86-004, RHR Pump Motor Removed Offsite for Testing & Insp Following 851125 Failure Due to Mfg Defect.Pump Replaced.Generic Implications Under Investigation	23 January 1986	PNO-III-86-004:RHR Pump Motor Removed Offsite for Testing & Insp Following 851125 Failure Due to Mfg Defect.Pump Replaced.Generic Implications Under Investigation
PNO-III-86-008, on 860125,roving Fire Watch Discovered Burning Insulation on Exhaust Line of Emergency Diesel Generator 13.Caused by Oil Soaking Insulation During Prior Disassembly & Oil Flushing.Fire Extinguished.Leak Repaired	27 January 1986	PNO-III-86-008:on 860125,roving Fire Watch Discovered Burning Insulation on Exhaust Line of Emergency Diesel Generator 13.Caused by Oil Soaking Insulation During Prior Disassembly & Oil Flushing.Fire Extinguished.Leak Repaired	Fire Watch
PNO-III-86-024, on 860317,backup Reactor Protection Sys Trip Breaker Failed to Trip During Bus a Transfer from Primary Electrical Supply.Caused by Repeated Testing.Manual Scram Inserted.Investigation Underway	17 March 1986	PNO-III-86-024:on 860317,backup Reactor Protection Sys Trip Breaker Failed to Trip During Bus a Transfer from Primary Electrical Supply.Caused by Repeated Testing.Manual Scram Inserted.Investigation Underway
PNO-III-86-037, on 860418,util Announced Extension of Outage to mid-Jul 1986.Licensee Review of Reevaluation of Design Work Performed on Concrete Embedments & Pipe Supports Will Be Completed by 860501	18 April 1986	PNO-III-86-037:on 860418,util Announced Extension of Outage to mid-Jul 1986.Licensee Review of Reevaluation of Design Work Performed on Concrete Embedments & Pipe Supports Will Be Completed by 860501
PNO-III-86-067, on 860708,Monroe County Board of Commissioners Adopted Resolution,By 5 to 3 Vote,Requesting Congressman Dingell to Hold Hearings on Adequacy of GE Mark 1 Containment	9 July 1986	PNO-III-86-067:on 860708,Monroe County Board of Commissioners Adopted Resolution,By 5 to 3 Vote,Requesting Congressman Dingell to Hold Hearings on Adequacy of GE Mark 1 Containment
PNO-III-86-069, on 860715,full Scram & ECCS Actuation Occurred During Heatup of Reactor Pressure Vessel.Approx 10 Gallons of Water Injected Into Vessel.Caused by Pressure Spike from Flow Perturbation.State of Mi Informed	16 July 1986	PNO-III-86-069:on 860715,full Scram & ECCS Actuation Occurred During Heatup of Reactor Pressure Vessel.Approx 10 Gallons of Water Injected Into Vessel.Caused by Pressure Spike from Flow Perturbation.State of Mi Informed	Hydrostatic
PNO-III-86-074, on 860731,licensee Authorized to Resume Operation Up to 5% Power.Further NRC Authorization Required for Higher Power Levels.Startup Will Begin on 860801	1 August 1986	PNO-III-86-074:on 860731,licensee Authorized to Resume Operation Up to 5% Power.Further NRC Authorization Required for Higher Power Levels.Startup Will Begin on 860801
PNO-III-86-074A, on 860804,start Up Initiated W/Removal of Control Rods.Activities Postponed from 860801 for Repair of Bypass Valve.Problem W/Position Indicators for MSIVs Also Corrected	4 August 1986	PNO-III-86-074A:on 860804,start Up Initiated W/Removal of Control Rods.Activities Postponed from 860801 for Repair of Bypass Valve.Problem W/Position Indicators for MSIVs Also Corrected
PNO-III-86-077, on 860806,fire & Electric Overload Alarm Received.Fire Located in Cubicle Containing Power Supply Breaker.Cause Unknown.Fire Extinguished.Power Supply Breaker & Affected Motor Control Ctr Inspected	7 August 1986	PNO-III-86-077:on 860806,fire & Electric Overload Alarm Received.Fire Located in Cubicle Containing Power Supply Breaker.Cause Unknown.Fire Extinguished.Power Supply Breaker & Affected Motor Control Ctr Inspected
PNO-III-86-083A, on 860828,nine NRC Licensing Examiners Completed Simulator Portion of Requalification Exams.All Nine Passed Exams.Licensee Requalification Program for Licensed Operators Acceptable	29 August 1986	PNO-III-86-083A:on 860828,nine NRC Licensing Examiners Completed Simulator Portion of Requalification Exams.All Nine Passed Exams.Licensee Requalification Program for Licensed Operators Acceptable
PNO-III-86-088, on 860902,normal Plant Shutdown Began for Repair of Malfunctioning torus-to-reactor Bldg Vacuum Breaker Isolation Valve.Repair Effort Expected to Take More than 48 H.Addl Maint Will Be Conducted During Shutdown	3 September 1986	PNO-III-86-088:on 860902,normal Plant Shutdown Began for Repair of Malfunctioning torus-to-reactor Bldg Vacuum Breaker Isolation Valve.Repair Effort Expected to Take More than 48 H.Addl Maint Will Be Conducted During Shutdown
PNO-III-86-097, on 860912,authorization Granted to Increase Power Level to 20%.Power Escalation Expected This Wk.Power Increase Previously Recommended for 860910	15 September 1986	PNO-III-86-097:on 860912,authorization Granted to Increase Power Level to 20%.Power Escalation Expected This Wk.Power Increase Previously Recommended for 860910
PNO-III-86-106, on 860926,suspicious Device Found on Hatch Cover on Fourth Floor of Auxiliary Bldg.Bomb Disposal Specialists Investigated Device & Found Device Empty.Device Was Piece of Pipe Placed on Hatch by Maint Personnel	26 September 1986	PNO-III-86-106:on 860926,suspicious Device Found on Hatch Cover on Fourth Floor of Auxiliary Bldg.Bomb Disposal Specialists Investigated Device & Found Device Empty.Device Was Piece of Pipe Placed on Hatch by Maint Personnel
PNO-III-86-111, on 861005,reactor Manually Scrammed from 15% Power Due to Partial Loss of Vacuum in Condenser Causing Temp Increase.Also,On 861005,during Test of Water Level Transmitters,Pressure Spike Inadvertently Introduced	8 October 1986	PNO-III-86-111:on 861005,reactor Manually Scrammed from 15% Power Due to Partial Loss of Vacuum in Condenser Causing Temp Increase.Also,On 861005,during Test of Water Level Transmitters,Pressure Spike Inadvertently Introduced
PNO-III-86-112, on 861009,problem Occurred W/Rod Sequence Control Sys,Hindering Normal Manual Insertion of Control Rods.Caused by Low Voltage in Normal Power Supply.Evaluation of Problem Underway	10 October 1986	PNO-III-86-112:on 861009,problem Occurred W/Rod Sequence Control Sys,Hindering Normal Manual Insertion of Control Rods.Caused by Low Voltage in Normal Power Supply.Evaluation of Problem Underway
PNO-III-86-118, on 861023,licensee Demonstrated Remote Shutdown Capability.Demonstration Successful W/All Equipment Operating as Designed.Plant Control Returned to Control Room After 45 Minutes.Plant in Cold Shutdown for Scheduled Maint	24 October 1986	PNO-III-86-118:on 861023,licensee Demonstrated Remote Shutdown Capability.Demonstration Successful W/All Equipment Operating as Designed.Plant Control Returned to Control Room After 45 Minutes.Plant in Cold Shutdown for Scheduled Maint
PNO-III-86-125, on 861031,operator Inadvertently Skipped Step in Rod Withdrawal Procedure & Pulled Next Rod in Sequence Out One Notch (6 Inches).Rod Reinserted to Proper Position & Correct Rod Sequence Restored	31 October 1986	PNO-III-86-125:on 861031,operator Inadvertently Skipped Step in Rod Withdrawal Procedure & Pulled Next Rod in Sequence Out One Notch (6 Inches).Rod Reinserted to Proper Position & Correct Rod Sequence Restored
PNO-III-86-131, on 861107,unit Shut Down Due to Air Leakage Into Main Condenser.Caused by Leakage in Thermal Expansion Joint Between One Low Pressure Turbine & Main Condenser. Licensee Plans to Inspect Remaining Joints	10 November 1986	PNO-III-86-131:on 861107,unit Shut Down Due to Air Leakage Into Main Condenser.Caused by Leakage in Thermal Expansion Joint Between One Low Pressure Turbine & Main Condenser. Licensee Plans to Inspect Remaining Joints
PNO-III-86-131A, 4-ft Tear Identified in North Condenser Boot During Repairs to Condenser Thermal Expansion Boots.Caused by Structural Damage to Condenser Supports.North & Ctr Condenser Thermal Expansion Boots Replaced	14 November 1986	PNO-III-86-131A:4-ft Tear Identified in North Condenser Boot During Repairs to Condenser Thermal Expansion Boots.Caused by Structural Damage to Condenser Supports.North & Ctr Condenser Thermal Expansion Boots Replaced

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