Pages that link to "PNO-III-88-001, on 871231,reactor Scrammed from 75% Power as Result of High Water Level in Reactor,Caused by Personnel Error During Installation of Auxiliary Computer Intended to Monitor Feedwater Heater Temp"
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The following pages link to PNO-III-88-001, on 871231,reactor Scrammed from 75% Power as Result of High Water Level in Reactor,Caused by Personnel Error During Installation of Auxiliary Computer Intended to Monitor Feedwater Heater Temp:
Displayed 30 items.
- PNO-III-87-116A, updates Discovery of Turbine Bldg Pipe Support Damage.Addl Damage to Feedwater Heater Emergency Drain Lines Identified.Cause Undetermined.Damage Under Evaluation & Repair Plans Developed (← links)
- PNO-III-87-116, on 870831,maint Personnel Discovered Evidence of Pipe Movement & Damage to Pipe Hangers & Supports on Emergency Drain Lines.Cause Undetermined. Investigation Continuing.Unit in Maint Since 870731 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- PNO-III-87-022A, on 870308,plant Reached NRC Imposed Limit of 50% Power.Licensee Will Operate Plant at Approx 50% While Conducting Test on HPCI Sys,Rwcu Sys & Safety Relief Valves. Util Also Plans to Conduct Loss of Offsite Power Test (← links)
- PNO-III-87-001A, on 870102,licensee Discovered Three Small Steam Leaks on Two of Four Main Steam Lines & on 870105, Following Repairs & Return of Steam Lines to Svc,Cracked Weld on Instrument Line/Valve Connection Found (← links)
- 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 (← links)
- 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 (← links)
- PNO-III-87-022, on 870216,Region III Authorized Facility to Exceed Previous 20% Power Limitation & Continue Testing Activities Up to 50% Power.Power Escalation Expected Pending Restoration of HPCI to Operable Status (← links)
- 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 (← links)
- PNO-III-87-012, on 870123,licensee Informed Region That NRC- Licensed Nuclear Supervising Operator Suspended on 870122 Due to Positive Testing in Random Drug Screening on 870115. No Evidence of Error Found in Performance (← links)
- PNO-III-87-016, on 870129,small Steam Leak Discovered in Spare Instrument Line Attached to Body of West Main Steam Bypass Valve.Caused by Crack in Weld Attaching Valve to Instrument Line.Valves Cut Off & Instrument Lines Plugged (← links)
- PNO-III-85-050, on 850621,initial Criticality Achieved within Two Steps of Estimated Critical Position.Control Rods Withdrawn to Criticality (← links)
- PNO-III-87-001B, on 870108,normal Plant Shutdown Commenced to Repair Series of Small Steam Leaks on Main Steam Piping Attachments.Leak Located on Main Turbine Stop Valve 3 & Can Only Be Isolated by Closing MSIVs (← links)
- PNO-III-87-048A, on 870406-10,NRC Special Insp Concluded That All Licensed Reactor Operators,Currently on Shift,Duty Up to Date W/Util Operator Requalification Program.Addl Review of Past Requalification Program Will Be Conducted (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- PNO-III-98-048, on 981008,Detroit Edison Declared Alert Based on Operator Rept of Smoke & Fire Alarm Coming from EDG 12 Control Panel in Switchgear Room.Operator Tripped EDG 12, Opened Output Breaker & Left Switchgear Room (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)