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PNO-I-99-048, on 991022,operators Initiated Plant Shutdown from 100% Reactor Power,Due to Continued RCS Leakage Through B Pressurizer Code Safety Valve to Primary Relief Tank. Operators Are Reducing Reactor Power at 12% Per H22 October 1999PNO-I-99-048:on 991022,operators Initiated Plant Shutdown from 100% Reactor Power,Due to Continued RCS Leakage Through B Pressurizer Code Safety Valve to Primary Relief Tank. Operators Are Reducing Reactor Power at 12% Per H
PNO-I-99-036, on 990718,update to Beaver Valley,Unit 2 Forced Outage Made.Licensee Replaced Suspected Voltage Regulator Control Relays & Satisfactorily Retested EDG 2-2.Resident Inspectors Continue to Monitor Licensee Corrective Action26 July 1999PNO-I-99-036:on 990718,update to Beaver Valley,Unit 2 Forced Outage Made.Licensee Replaced Suspected Voltage Regulator Control Relays & Satisfactorily Retested EDG 2-2.Resident Inspectors Continue to Monitor Licensee Corrective ActionZebra Mussel
PNO-I-99-033, on 990716,apparent Electrical Fault Occurred During EDG Full Load Test,Which Opened Supply Breaker Between Emergency & Normal 4 Kilovolt Busses.Station Personnel Intend to Resolve & Correct Electrical Fault19 July 1999PNO-I-99-033:on 990716,apparent Electrical Fault Occurred During EDG Full Load Test,Which Opened Supply Breaker Between Emergency & Normal 4 Kilovolt Busses.Station Personnel Intend to Resolve & Correct Electrical FaultZebra Mussel
PNO-I-98-002, on 980130,operators Declared Both Trains of Component Cooling Reactor & Reactor Plant River Water Sys Inoperable Due to Failure to Meet TS Surveillance Testing Requirements.Entered TS 3.0.3 & 4.0.32 February 1998PNO-I-98-002:on 980130,operators Declared Both Trains of Component Cooling Reactor & Reactor Plant River Water Sys Inoperable Due to Failure to Meet TS Surveillance Testing Requirements.Entered TS 3.0.3 & 4.0.3Enforcement Discretion
PNO-I-97-077, on 971216,Duquesne Light Co Initiated Unit 2 Reactor Shutdown in Accordance W/Ts 3.0.3.Licensee Plans to Address Unit 2 Design Deficiency for CR Emergency Air Cleanup & Pressurization,During Shutdown17 December 1997PNO-I-97-077:on 971216,Duquesne Light Co Initiated Unit 2 Reactor Shutdown in Accordance W/Ts 3.0.3.Licensee Plans to Address Unit 2 Design Deficiency for CR Emergency Air Cleanup & Pressurization,During Shutdown
PNO-I-97-040, on 970627,Unit 1 RPS Trip Functions Did Not Meet Design Requirements & Were Inoperable.Licensee Intends to Install Design Change to Resolve IEEE-279 Postulated Failure Concerns.Operators Began TS Required Shutdown30 June 1997PNO-I-97-040:on 970627,Unit 1 RPS Trip Functions Did Not Meet Design Requirements & Were Inoperable.Licensee Intends to Install Design Change to Resolve IEEE-279 Postulated Failure Concerns.Operators Began TS Required Shutdown
PNO-I-97-020, on 970407,Allegheny Power Sys Inc & Dqe Inc, Parent Co of Duquesne Light Co,Announced Billion Dollar Agreement to Merge Companies.Merger Unanimously Approved by Both Companies Boards of Directors7 April 1997PNO-I-97-020:on 970407,Allegheny Power Sys Inc & Dqe Inc, Parent Co of Duquesne Light Co,Announced Billion Dollar Agreement to Merge Companies.Merger Unanimously Approved by Both Companies Boards of Directors
PNO-I-97-017, on 970319,Units 1 & 2 Experienced Dual Unit Reactor Trip from Full Power Due to Electrical Fault Protection Signal from 345 Kv Bus in Onsite Switchyard. Signal Tripped Both Main Generators20 March 1997PNO-I-97-017:on 970319,Units 1 & 2 Experienced Dual Unit Reactor Trip from Full Power Due to Electrical Fault Protection Signal from 345 Kv Bus in Onsite Switchyard. Signal Tripped Both Main Generators
PNO-I-97-001, on 970106,unit 2 Experienced Reactor Trip from 98% Power Due to Turbine Trip.All Control Rods Inserted Completely.Auxiliary Feedwater Sys Started on Low SG Water Level Signal as Expected.Plant Remains Stable in Mode 38 January 1997PNO-I-97-001:on 970106,unit 2 Experienced Reactor Trip from 98% Power Due to Turbine Trip.All Control Rods Inserted Completely.Auxiliary Feedwater Sys Started on Low SG Water Level Signal as Expected.Plant Remains Stable in Mode 3
PNO-I-93-061A, on 931119,determined That Util Adequately Met Commitments in CAL 1-93-20,dtd 931109.Determination Based on Completed Actions & Tests Which Demonstrated Reasonable Assurance That Both EDG Sequencers Operable & Reliable22 November 1993PNO-I-93-061A:on 931119,determined That Util Adequately Met Commitments in CAL 1-93-20,dtd 931109.Determination Based on Completed Actions & Tests Which Demonstrated Reasonable Assurance That Both EDG Sequencers Operable & Reliable
PNO-I-93-061, on 931104 & 1106,EDG Number 1 & 2,failed auto-load Test When Loads Did Not Sequence on Emergency Bus During Simulated Loss of Offsite Power W/Safety Injection Signal.Ait Sent to Review Circumstances9 November 1993PNO-I-93-061:on 931104 & 1106,EDG Number 1 & 2,failed auto-load Test When Loads Did Not Sequence on Emergency Bus During Simulated Loss of Offsite Power W/Safety Injection Signal.Ait Sent to Review Circumstances
PNO-V-90-038, A:on 900927,main Generator Trip Resulted in Unplanned Plant Shutdown.Transient Caused 140 MW Excursion on Grid,Tripped Off Nearby Substation & Shook Turbine Bldg Deck.Ge Contacted for Recommendations27 September 1990PNO-V-90-038-A:on 900927,main Generator Trip Resulted in Unplanned Plant Shutdown.Transient Caused 140 MW Excursion on Grid,Tripped Off Nearby Substation & Shook Turbine Bldg Deck.Ge Contacted for Recommendations
PNO-I-90-070, on 900830,licensee Declared Alert Following Apparent Release of CO2 Gas Into Several Spaces.Isolation Valve Apparently Leaked.Licensee Immediately Dispatched Onsite Fire Brigade in self-contained Breathing Apparatus30 August 1990PNO-I-90-070:on 900830,licensee Declared Alert Following Apparent Release of CO2 Gas Into Several Spaces.Isolation Valve Apparently Leaked.Licensee Immediately Dispatched Onsite Fire Brigade in self-contained Breathing Apparatus
PNO-I-89-046, on 890621,unusual Event Declared Due to Plant Shutdown,Necessitated by Excessive RCS Leakage Into C Steam Generator,During Which Auxiliary Feedwater Auto Start & Auto Isolation Experienced.Generator Levels Reestablished22 June 1989PNO-I-89-046:on 890621,unusual Event Declared Due to Plant Shutdown,Necessitated by Excessive RCS Leakage Into C Steam Generator,During Which Auxiliary Feedwater Auto Start & Auto Isolation Experienced.Generator Levels Reestablished
PNO-I-89-043, on 890607,unit Declared Unusual Event Due to Excessive RCS Leakage & Initiated Tech Spec Required Shutdown.Leak Stopped.Facility Stabilized at About 20% Power & Monitoring Plant Parameters to Confirm That Leak Stopped7 June 1989PNO-I-89-043:on 890607,unit Declared Unusual Event Due to Excessive RCS Leakage & Initiated Tech Spec Required Shutdown.Leak Stopped.Facility Stabilized at About 20% Power & Monitoring Plant Parameters to Confirm That Leak Stopped
PNO-I-88-086, on 880822,Unit 2 Experienced one-out-of-three Actuation of Chlorine Detection Sys.Unit 1 Actuated on two-out-of-three Coincidence.Bottled Air Pressurization Sys Began to Discharge Into Control Room.Addl Tests Performed23 August 1988PNO-I-88-086:on 880822,Unit 2 Experienced one-out-of-three Actuation of Chlorine Detection Sys.Unit 1 Actuated on two-out-of-three Coincidence.Bottled Air Pressurization Sys Began to Discharge Into Control Room.Addl Tests Performed
PNO-I-87-107, on 871117,turbine Reactor Tripped Due to Spuriously Generated Turbine Thrust Bearing Trip.Caused by Technician Inadvertently Tripping Power Switch on Turbine Rotor Position Drawer.Offsite Transformer Inspected18 November 1987PNO-I-87-107:on 871117,turbine Reactor Tripped Due to Spuriously Generated Turbine Thrust Bearing Trip.Caused by Technician Inadvertently Tripping Power Switch on Turbine Rotor Position Drawer.Offsite Transformer Inspected
PNO-I-87-073, on 870803,reactor Trip Breakers Shut to Commence Approach to Initial Criticality.Criticality Achieved on 870804.Insp Team on Site Providing Continuous Coverage Throughout Low Power Physics Testing4 August 1987PNO-I-87-073:on 870803,reactor Trip Breakers Shut to Commence Approach to Initial Criticality.Criticality Achieved on 870804.Insp Team on Site Providing Continuous Coverage Throughout Low Power Physics Testing
PNO-I-87-016, on 870310-11 Commissioner KM Carr Will Visit Plant.Agenda Consists of Briefing & Tour9 March 1987PNO-I-87-016:on 870310-11 Commissioner KM Carr Will Visit Plant.Agenda Consists of Briefing & Tour
ML20210E9646 February 1987PNS-I-87-001:on 870206,site Telephone Operator Received Anonymous Call Stating That Three Bombs Placed in Facility. Bomb Threat Procedure & Security Survey Initiated
ML20212B18122 December 1986PNS-I-86-024:on 861218,discovered Power Available Indicator for One of Six safety-related Auxiliary Feedwater Valves Dark.Caused by Security Guard Tampering W/Breaker Device.Guard Suspended Pending Completion of Investigation
ML20211E29517 October 1986PNS-I-86-019:on 861016,contractor Providing Security Svcs for Plant Changed from Burns Intl Security Svcs to Security Bureau,Inc.Licensee Advised NRC of Proposed Change During 861014 Meeting
PNO-I-86-079, on 860926,facility Switchboard Operator Received Bomb Threat by Telephone.Reactor Bldg Evacuated. Licensee Will Resume Work in Reactor Bldg,If No Bomb Found26 September 1986PNO-I-86-079:on 860926,facility Switchboard Operator Received Bomb Threat by Telephone.Reactor Bldg Evacuated. Licensee Will Resume Work in Reactor Bldg,If No Bomb Found
PNO-I-86-071, on 860911,bomb Threats Received by Telephone. Nonessential Personnel Released & Bldg Searched11 September 1986PNO-I-86-071:on 860911,bomb Threats Received by Telephone. Nonessential Personnel Released & Bldg Searched
PNO-I-86-070, on 860905,telephone Bomb Threat Received for Unit 2.Fuel Bldgs of Both Units Evacuated & Searched.No Bomb Found.Info Assessment Team & Commonwealth of PA Notified5 September 1986PNO-I-86-070:on 860905,telephone Bomb Threat Received for Unit 2.Fuel Bldgs of Both Units Evacuated & Searched.No Bomb Found.Info Assessment Team & Commonwealth of PA Notified
PNO-I-85-083, on 851031,unmonitored Release of 1,600 Gallons Radioactive Water from Unit 1 Boric Acid Holding Tank Occurred.Caused by Personnel Error.Leak Isolated & Sewers Monitored.Unit 2 Worker Contaminated on Shoe31 October 1985PNO-I-85-083:on 851031,unmonitored Release of 1,600 Gallons Radioactive Water from Unit 1 Boric Acid Holding Tank Occurred.Caused by Personnel Error.Leak Isolated & Sewers Monitored.Unit 2 Worker Contaminated on ShoeBoric Acid
PNO-I-85-062, on 850829,at 100% Power,Reactor Tripped & Safety Injection Occurred.Caused by Broken Pipe Fitting on Instrument Air Compressor Tank in Turbine Bldg.Pressurizer Pressure Restored to Normal29 August 1985PNO-I-85-062:on 850829,at 100% Power,Reactor Tripped & Safety Injection Occurred.Caused by Broken Pipe Fitting on Instrument Air Compressor Tank in Turbine Bldg.Pressurizer Pressure Restored to Normal
PNO-I-85-051A, on 850717,diesel Generator 1 Failed Monthly Surveillance Test.Initially Attributed to Possible Tampering W/Load Limit Setting Knob.Investigation Concluded That Knob May Have Been Inadvertently Moved During Cleaning25 July 1985PNO-I-85-051A:on 850717,diesel Generator 1 Failed Monthly Surveillance Test.Initially Attributed to Possible Tampering W/Load Limit Setting Knob.Investigation Concluded That Knob May Have Been Inadvertently Moved During Cleaning
PNO-I-85-051, on 850717,diesel Generator 1 Failed Monthly Surveillance Test Due to Woodward Governor Load Limit Setting Being Set at 3,instead of Normal Setting of 10. Caused by Possible Tampering W/Generator Setting18 July 1985PNO-I-85-051:on 850717,diesel Generator 1 Failed Monthly Surveillance Test Due to Woodward Governor Load Limit Setting Being Set at 3,instead of Normal Setting of 10. Caused by Possible Tampering W/Generator Setting
ML20148D7619 October 1979PNS-I-79-001A:on 791008,licensee & Ibew Union Committee Reached Tentative Agreement on New Contract.Licensee Believes New Contract Will Be Ratified Thereby Avoiding Strike
ML20249A6317 August 1978PNS-78-038:on 780804,phone Call Was Received at Plant Welding Shop.Unidentified Person Stated That Bomb Was in Power House & Hung Up.Site Was Not Evacuated.Cursory Search Was Conducted
ML20207G63917 November 1977PNO-77-202:on 771116,facilty Shutdown from 100 Percent Power to Investigate Noises Which Developed in Main Generator. Exams Performed on 771116 Revealed That Hot Hydrogen Gas Return Duct Inside Generator Had Loosened
ML20151X49024 August 1977PNO-77-148:on 770823,licensee Discovered That Small Amounts of Radioactive,Borated Water Had Been Leaking from Unit 1 Auxiliary Bldg Via Concrete Trench to Unit 2 Construction Area for Undetermined TimeBoric Acid
ML20126D19012 August 1977PNO-77-143:Pacific Pump Co Supplied Facilities W/Production Lot of 40 Pumps Mfg Using Shafts Made of Inferior Matl. Cause Unstated.All Utils W/Pumps Were Notified.Nrc Headquarters Notified on 770812
ML20151X75726 July 1977PNO-77-134:on 770725,primary Water Storage Tank Overflowed During Filling Operation & Dumped 9000 Gallons of Slightly Radioactive Water Onto Ground.Unplanned Release Caused by Valving Error During Tank Filling Operation
ML20151U9249 June 1977PNO-77-100:on 770608,makeup Water from Primary Water Storage Tank Contaminated Plant Water Treatment Sys Which Provides Inplant Domestic Water.Licensee Posted All Domestic Water Outlets (Drinking Fountains & Lavoratories)
ML20151U64221 April 1977PNO-77-064:on 770420,plant Shutdown Due to Inadvertent MSIV Closure,Caused Safety Injection Signal & Plant Trip.Nrc Inspector or Site Reviewing Licensee Findings.Press Release Not Planned
ML20236L0356 January 1977PNO-77-004:on 770105,plant Automatically Scrammed,Steam Flow Feed Flow Mismatch,From 54 Percent Power When Feedwater Line Vibration Experienced.Licensee Determining Extent of Damage Which Occurred
ML20236F32227 December 1976PNO-76-225:on 761227,plant Was Shutdown When Feedline Vibration Was Experienced.Power Level at Time of Disturbance Was Approx 75%.Licensee Determining Extent of Damage as Result of Event.Commonwealth of Pennsylvania Informed
ML20236F2658 November 1976PNO-76-186:on 761105,rumbling Was Heard in Operating Areas & Guard House.Drain Line 3/4 Inch on AFW Line to B SG Had Failed.Licensee Plans to Have Westinghouse & Stone & Webster Analyze Event to Determine CauseNondestructive Examination
ML20236F51216 July 1976PNS-76-032:on 760716,Shippingport Police Received Phone Call Advising That Two Bombs Were in Conventional Power Plant; One Bomb in Stack & One in Power House.Midland Police Dept Advised of Call & in Turn Advised Licensee
ML20249B51018 June 1976PNO-76-105:on 760617,7,000 Gallons of Water Leaked to Containment from 3/8 Inch Flexible Pressure Hose in RCS Pressure Transmitter Line.Appears That Operators Failed to Respond to Sump Pump Alarms & Addl Pump Operation
ML20249B32611 May 1976PNO-76-084:on 760510,initial Criticality Achieved.Region 1 Inspector Witnessed Evolution & Repts That Actual Boron Concentration in Close Agreement W/Predicted Values.Media Interest Expected Because of Close Attention to Plant