PNO-V-87-035, on 870507,individual W/Contamination Level of 160,000 Dpm/Square Centimeters on Knees Became Ill While Removing Protective Clothing Worn for Decontaminating Equipment.Individual Transported to Hosp & Decontaminated
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| ML20215L594 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/08/1987 |
| From: | Hooker C, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| References | |
| PNO-V-87-035, PNO-V-87-35, NUDOCS 8705120298 | |
| Download: ML20215L594 (1) | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-V-93-002, on 930113,L Marbet Held Press Conference W/ Portland,Or Media & Alleged That NRC Had Inappropriately Authorized Feb 1992 Restart of Plant.Util Announced on 930104 That Operation of Plant Would Be Permanently Ceased1993-01-13013 January 1993
[Table view]PNO-V-93-002:on 930113,L Marbet Held Press Conference W/ Portland,Or Media & Alleged That NRC Had Inappropriately Authorized Feb 1992 Restart of Plant.Util Announced on 930104 That Operation of Plant Would Be Permanently Ceased PNO-V-93-001, on 930104,Licensee Notified Region V That Util Board Decided That Plant Will Not Be Restarted & Currently Shutdown for Insp & Repair of SG Tubes.Licensee Notified Media1993-01-0404 January 1993 PNO-V-93-001:on 930104,Licensee Notified Region V That Util Board Decided That Plant Will Not Be Restarted & Currently Shutdown for Insp & Repair of SG Tubes.Licensee Notified Media PNO-V-92-038, on 921209,B Roberts Plans to Notify News Media of Request of or Energy Facility Siting Council to Hold Hearing on Utility Steam Generator Safety1992-12-0808 December 1992 PNO-V-92-038:on 921209,B Roberts Plans to Notify News Media of Request of or Energy Facility Siting Council to Hold Hearing on Utility Steam Generator Safety PNO-V-92-037, on 921201,meeting Conducted at Plant to Address 921109 Steam Generator Tube Leak & Licensee Request for Emergency TS Change to Permit Restart1992-12-0101 December 1992 PNO-V-92-037:on 921201,meeting Conducted at Plant to Address 921109 Steam Generator Tube Leak & Licensee Request for Emergency TS Change to Permit Restart PNO-V-92-004, on 920225,Trojan Power Plant Entered Mode 2 After Extended Outage.Plant Currently Critical at Less than 1 Percent Power & Licensee Conducting Low Power Physics Testing.Tests Expected to Be Completed by 9202271992-02-25025 February 1992 PNO-V-92-004:on 920225,Trojan Power Plant Entered Mode 2 After Extended Outage.Plant Currently Critical at Less than 1 Percent Power & Licensee Conducting Low Power Physics Testing.Tests Expected to Be Completed by 920227 PNO-V-91-002, on 910303,Trojan Declared an Unsual Event & Initiated Plant Shutdown Due to Inability to Meet Requirements of TS 3.8.2.1,which Requires That Four 120 Volts AC Preferred Instrument Busses Be Operable1991-03-0505 March 1991 PNO-V-91-002:on 910303,Trojan Declared an Unsual Event & Initiated Plant Shutdown Due to Inability to Meet Requirements of TS 3.8.2.1,which Requires That Four 120 Volts AC Preferred Instrument Busses Be Operable PNO-V-90-045, State of or Measure 4 Re Closure of Facility Defeated in 901106 Vote.Util Will Hold News Conference1990-11-0707 November 1990 PNO-V-90-045:State of or Measure 4 Re Closure of Facility Defeated in 901106 Vote.Util Will Hold News Conference 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 Recommendations1990-09-27027 September 1990 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 Recommendations PNO-V-90-032, on 900711,steam Dumps Did Not Automatically Open to Pick Up Load Lost from Turbine During Performance of Turbine Test.Operators Took Manual Control & Stabilized Plant.Plant Shutdown to Investigate Event1990-07-11011 July 1990 PNO-V-90-032:on 900711,steam Dumps Did Not Automatically Open to Pick Up Load Lost from Turbine During Performance of Turbine Test.Operators Took Manual Control & Stabilized Plant.Plant Shutdown to Investigate Event PNO-V-90-010, on 900320,facility Entered TS 3.0.3 After Engineering Organization Determined Main Steam Flow Trip Setpoints Were Incorrect & Nonconservative.Plant Shutdown Began IAW TSs1990-03-20020 March 1990 PNO-V-90-010:on 900320,facility Entered TS 3.0.3 After Engineering Organization Determined Main Steam Flow Trip Setpoints Were Incorrect & Nonconservative.Plant Shutdown Began IAW TSs PNO-V-90-011, on 900919,Vice President Nuclear DW Cockfield Announced Resignation After Being in Position Since March 1987.TD Walt Will Serve as Vice President-Nuclear Until Licensee Identify Replacement1990-03-20020 March 1990 PNO-V-90-011:on 900919,Vice President Nuclear DW Cockfield Announced Resignation After Being in Position Since March 1987.TD Walt Will Serve as Vice President-Nuclear Until Licensee Identify Replacement PNO-V-89-048, on 890809,plant Tripped on Overtemp Differential Temp.Caused by Spurious Trip Signal Received from Other Channel.Reactor Shutdown in Mode 3 in Order for Licensee to Attempt to Identify Source & Cause of Signal1989-08-10010 August 1989 PNO-V-89-048:on 890809,plant Tripped on Overtemp Differential Temp.Caused by Spurious Trip Signal Received from Other Channel.Reactor Shutdown in Mode 3 in Order for Licensee to Attempt to Identify Source & Cause of Signal ML20245G6101989-06-16016 June 1989 PNS-V-89-005:on 890615,licensee Informed NRC of Possible Onsite Use & Sale of Marijuana & Cocaine by Five Contract Employees,Employed by Northwest Energy Svcs Co.Employees Interviewed,Searched & Given Urinanalyses on 890616 PNO-V-88-060, on 881113,turbine Trip/Reactor Trip on hi-hi Steam Generator Level Occurred.Caused by Faulty Controller for Feedwater Regulation Valve on Steam Generator B.Licensee Developing Actions to Address Problems1988-11-15015 November 1988 PNO-V-88-060:on 881113,turbine Trip/Reactor Trip on hi-hi Steam Generator Level Occurred.Caused by Faulty Controller for Feedwater Regulation Valve on Steam Generator B.Licensee Developing Actions to Address Problems PNO-V-88-057, on 880916,while Verifying Pressure Transmitter PT-458,bistables Tripped.Caused by Technician Error & Exceeding Shutdown by More than 48 H.Problems Encountered During Reactor Startup Listed1988-09-19019 September 1988 PNO-V-88-057:on 880916,while Verifying Pressure Transmitter PT-458,bistables Tripped.Caused by Technician Error & Exceeding Shutdown by More than 48 H.Problems Encountered During Reactor Startup Listed PNO-V-88-031, on 880512,engineering Walkdowns of Pipe Whip Restraints Identified That Pressurizer Surge Line in Contact W/Upper Shim Pack of Pipe Whip Restraint 1.2.Possibly Caused by Difference Between Pressurizer & Hot Leg1988-05-12012 May 1988 PNO-V-88-031:on 880512,engineering Walkdowns of Pipe Whip Restraints Identified That Pressurizer Surge Line in Contact W/Upper Shim Pack of Pipe Whip Restraint 1.2.Possibly Caused by Difference Between Pressurizer & Hot Leg PNO-V-88-026, on 880418,workers Removed Flange from Pressurizer Relief Tank,Releasing Radioactive Noble Gas. Level of Activity Resulted in Containment Purge Isolation Signal.Release Caused by Inadequate Procedural Control1988-04-19019 April 1988 PNO-V-88-026:on 880418,workers Removed Flange from Pressurizer Relief Tank,Releasing Radioactive Noble Gas. Level of Activity Resulted in Containment Purge Isolation Signal.Release Caused by Inadequate Procedural Control PNO-V-88-001, on 880108,reactor Trip/Turbine Trip Occurred & Plant Shutdown for Greater than 48 H.Caused by Dirty Contact in Cable Connection to pre-amplifier.Containment Leakage Also Discovered.Manway Cover Bolts Torqued1988-01-12012 January 1988 PNO-V-88-001:on 880108,reactor Trip/Turbine Trip Occurred & Plant Shutdown for Greater than 48 H.Caused by Dirty Contact in Cable Connection to pre-amplifier.Containment Leakage Also Discovered.Manway Cover Bolts Torqued PNO-V-87-081, on 871209,indication of Increased Leakage in Containment Identified.Caused by Leakage from Charging Sys Valve & Steam Generator Tubesheet Drain Valve Due to Abnormal Seal Performance.Seals Examined & Valves Repaired1987-12-10010 December 1987 PNO-V-87-081:on 871209,indication of Increased Leakage in Containment Identified.Caused by Leakage from Charging Sys Valve & Steam Generator Tubesheet Drain Valve Due to Abnormal Seal Performance.Seals Examined & Valves Repaired PNO-V-87-062, on 870928,unit Shut Down to Repair Boron Injection Tank Leaking Pressure Relief Valve Psv 8852. Leaking Relief Valve Removed & Blank Flange Put Over Line. Plant Remains in Shutdown Status1987-09-29029 September 1987 PNO-V-87-062:on 870928,unit Shut Down to Repair Boron Injection Tank Leaking Pressure Relief Valve Psv 8852. Leaking Relief Valve Removed & Blank Flange Put Over Line. Plant Remains in Shutdown Status PNO-V-87-057, on 870824,Oregon State Agreement Program Director,R Paris,Informed NRC That State Employee Union Voted to Strike on 870913.If Settlement Not Reached Prior to Walk Out,Managers Will Handle Radioactive Matls Program1987-08-24024 August 1987 PNO-V-87-057:on 870824,Oregon State Agreement Program Director,R Paris,Informed NRC That State Employee Union Voted to Strike on 870913.If Settlement Not Reached Prior to Walk Out,Managers Will Handle Radioactive Matls Program PNO-V-87-048A, on 870702,significant Unexpected Erosion on Straight Sections of safety-related Feed Sys Piping Identified.Licensee Plans to Replace Piping Prior to Restart.Inpo Requested to Distribute Findings Via Network1987-07-0707 July 1987 PNO-V-87-048A:on 870702,significant Unexpected Erosion on Straight Sections of safety-related Feed Sys Piping Identified.Licensee Plans to Replace Piping Prior to Restart.Inpo Requested to Distribute Findings Via Network PNO-V-87-048, during Insp of Main Feedwater Sys in June 1987, Licensee Found Some Indications of Pipe Wall Thinning.Caused by Flow Transition & Turbulence.Licensee Replacing All Piping W/Below Min Wall Thickness Indications1987-06-30030 June 1987 PNO-V-87-048:during Insp of Main Feedwater Sys in June 1987, Licensee Found Some Indications of Pipe Wall Thinning.Caused by Flow Transition & Turbulence.Licensee Replacing All Piping W/Below Min Wall Thickness Indications PNO-V-87-045, licensee Discovered Seperation Between Base Plate Grout & Concrete on Support SS-81 on Main Steam Line B.On 870616,dynamic Analysis Reperformed for Main Steam Supports.Supports Reinstalled W/Proper Design Loads1987-06-16016 June 1987 PNO-V-87-045:licensee Discovered Seperation Between Base Plate Grout & Concrete on Support SS-81 on Main Steam Line B.On 870616,dynamic Analysis Reperformed for Main Steam Supports.Supports Reinstalled W/Proper Design Loads PNO-V-87-040, on 870523,360 Degrees Circumferential Break of SI Accumulator a Fill Line Occurred While Transferring Water from SI Accumulator a to D.Caused by Low Cycle,High Fatigue. Util Conducting Analyses to Determine Force & Fatigue Cycl1987-05-26026 May 1987 PNO-V-87-040:on 870523,360 Degrees Circumferential Break of SI Accumulator a Fill Line Occurred While Transferring Water from SI Accumulator a to D.Caused by Low Cycle,High Fatigue. Util Conducting Analyses to Determine Force & Fatigue Cycl PNO-V-87-037, on 870512,fatigue Fracture Occurred on 1-inch Safety Injection Fill Line on Accumulator Tank a & 2,000 Gallons of 2,000 Ppm Borated Water Drained Onto Containment Floor.By 870514,two Addl Accumulator Tanks Found W/Cracks1987-05-14014 May 1987 PNO-V-87-037:on 870512,fatigue Fracture Occurred on 1-inch Safety Injection Fill Line on Accumulator Tank a & 2,000 Gallons of 2,000 Ppm Borated Water Drained Onto Containment Floor.By 870514,two Addl Accumulator Tanks Found W/Cracks PNO-V-87-038, on 870513,female Air Lock Operator Received Injury to Neck While Opening Air Lock Door to Transfer Matl from Containment.Operator Transported Offsite for Medical Attention.No Serious Injuries or Contamination Found1987-05-14014 May 1987 PNO-V-87-038:on 870513,female Air Lock Operator Received Injury to Neck While Opening Air Lock Door to Transfer Matl from Containment.Operator Transported Offsite for Medical Attention.No Serious Injuries or Contamination Found PNO-V-87-035, on 870507,individual W/Contamination Level of 160,000 Dpm/Square Centimeters on Knees Became Ill While Removing Protective Clothing Worn for Decontaminating Equipment.Individual Transported to Hosp & Decontaminated1987-05-0808 May 1987 PNO-V-87-035:on 870507,individual W/Contamination Level of 160,000 Dpm/Square Centimeters on Knees Became Ill While Removing Protective Clothing Worn for Decontaminating Equipment.Individual Transported to Hosp & Decontaminated PNO-V-87-031A, on 870417,licensee Reported Potential Foot Exposure of Plant Worker Exceeding 18.75 Rem Limit.Staff Retrained in Precautions to Minimize Exposure from Radioactive Matl & Appropriate Radiological Control Started1987-04-29029 April 1987 PNO-V-87-031A:on 870417,licensee Reported Potential Foot Exposure of Plant Worker Exceeding 18.75 Rem Limit.Staff Retrained in Precautions to Minimize Exposure from Radioactive Matl & Appropriate Radiological Control Started PNO-V-87-031, on 870417,licensee Reported Potential Foot Exposure of Plant Worker Exceeding 18.75 Rem Limit.Caused by Dispersal of Irradiated Fuel Fragments.Work Stopped in Containment Bldg.Investigation Initiated1987-04-17017 April 1987 PNO-V-87-031:on 870417,licensee Reported Potential Foot Exposure of Plant Worker Exceeding 18.75 Rem Limit.Caused by Dispersal of Irradiated Fuel Fragments.Work Stopped in Containment Bldg.Investigation Initiated PNO-V-87-029A, on 870414,licensee Reported That Degraded Pellet Between Reactor Vessel & Head Flange Source of Radioactive Contamination of Area & Personnel Inside Containment Bldg on 870409.Decontamination Efforts Ongoing1987-04-14014 April 1987 PNO-V-87-029A:on 870414,licensee Reported That Degraded Pellet Between Reactor Vessel & Head Flange Source of Radioactive Contamination of Area & Personnel Inside Containment Bldg on 870409.Decontamination Efforts Ongoing PNO-V-87-029, on 870409,while Installing Reactor Stud Plugs, Release of Radioactivity Occurred Resulting in 21 Workers Experiencing Personal Contamination.Work in Reactor Cavity Stopped Until Source of Problem Identified1987-04-10010 April 1987 PNO-V-87-029:on 870409,while Installing Reactor Stud Plugs, Release of Radioactivity Occurred Resulting in 21 Workers Experiencing Personal Contamination.Work in Reactor Cavity Stopped Until Source of Problem Identified PNO-V-86-077, on 861107 & 10,green & Yellow Wires Attached to Primer Cord Discovered at Excavation Site.Army Explosive Ordnance Detachment Removed Wire & Primer Cord.Util Studying Effects If Charge Detonated1986-11-10010 November 1986 PNO-V-86-077:on 861107 & 10,green & Yellow Wires Attached to Primer Cord Discovered at Excavation Site.Army Explosive Ordnance Detachment Removed Wire & Primer Cord.Util Studying Effects If Charge Detonated PNO-V-86-058A, on 860901,reactor Shut Down Due to Condenser Tube Leak.High Temp Alarms on Reactor Coolant Pump Motor Lower Radial Bearing B Received While in Mode 3.Caused by Bearing Damage.Bearing Being Replaced.Restart Due on 8609071986-09-0404 September 1986 PNO-V-86-058A:on 860901,reactor Shut Down Due to Condenser Tube Leak.High Temp Alarms on Reactor Coolant Pump Motor Lower Radial Bearing B Received While in Mode 3.Caused by Bearing Damage.Bearing Being Replaced.Restart Due on 860907 PNO-V-86-058, on 860901,controlled Shutdown Conducted Due to Condenser Tube Leakage.Blown Out Plugged Condenser Tube Found.Startup on Hold Due to Cleaning of Steam Generators W/ Chemical Impurities1986-09-0202 September 1986 PNO-V-86-058:on 860901,controlled Shutdown Conducted Due to Condenser Tube Leakage.Blown Out Plugged Condenser Tube Found.Startup on Hold Due to Cleaning of Steam Generators W/ Chemical Impurities PNO-V-86-054, on 860821,State of Wa Informed NRC of 860813 Suspension of Util Permit,Based on 860806 Shipment to Us Ecology.Shipment Contained 30 Gallons of Untreated Liquid in Shipping Cask1986-08-22022 August 1986 PNO-V-86-054:on 860821,State of Wa Informed NRC of 860813 Suspension of Util Permit,Based on 860806 Shipment to Us Ecology.Shipment Contained 30 Gallons of Untreated Liquid in Shipping Cask PNO-V-86-051, on 860805,safety Injection Occurred When Steam Line Pressure Transmitter Failed While Surveillance Being Performed on Second Steam Line Pressure Transmitter.All Sys Responded as Designed.Plant in Mode 3 Condition1986-08-0505 August 1986 PNO-V-86-051:on 860805,safety Injection Occurred When Steam Line Pressure Transmitter Failed While Surveillance Being Performed on Second Steam Line Pressure Transmitter.All Sys Responded as Designed.Plant in Mode 3 Condition PNO-V-86-033, on 860616,reactor Taken Critical.Caused by Physics Testing.Reactor Will Be Returned to Power on 860618. Problems W/Reactor Control Sys Thermal Expansion & Control Room Ventilation Sys Resolved1986-06-17017 June 1986 PNO-V-86-033:on 860616,reactor Taken Critical.Caused by Physics Testing.Reactor Will Be Returned to Power on 860618. Problems W/Reactor Control Sys Thermal Expansion & Control Room Ventilation Sys Resolved PNO-V-86-026, during 1985 Refueling Outage,Determined Hydraulic Snubbers Could Have Failed During Seismic Event & Unusual Movement of Pressurizer Surge Line Observed.Caused by Lockup of Snubbers.Snubbers Rebuilt1986-05-0202 May 1986 PNO-V-86-026:during 1985 Refueling Outage,Determined Hydraulic Snubbers Could Have Failed During Seismic Event & Unusual Movement of Pressurizer Surge Line Observed.Caused by Lockup of Snubbers.Snubbers Rebuilt PNO-V-86-017, on 860411,merchant Ship in Columbia River Veered Into Shore Near Plant,Damaging 30 Ft of Outfall Pipe. Svc Water Flow Uninterrupted.Plant Operating at 73% Power. Repairs Considered for Apr 1986 Refueling Outage1986-04-14014 April 1986 PNO-V-86-017:on 860411,merchant Ship in Columbia River Veered Into Shore Near Plant,Damaging 30 Ft of Outfall Pipe. Svc Water Flow Uninterrupted.Plant Operating at 73% Power. Repairs Considered for Apr 1986 Refueling Outage ML20138H1731985-12-10010 December 1985 PNS-V-85-007:on 851209,discovered 16 Oz ball-peen Hammer Inside Valve Cover of East Diesel Generator in Position Where Hammer Could Vibrate Into Moving Machinery.Tool Checkout Records Did Not Reflect Hammer Being Checked Out PNO-V-85-070, on 851008,two Plant Mod Personnel Received First & Second Degree Burns on Hands & Arms Due to Fire in Motor Control Ctr.Caused by Short Circuiting of Bus Bar by hand-held Cordless Drill1985-10-0808 October 1985 PNO-V-85-070:on 851008,two Plant Mod Personnel Received First & Second Degree Burns on Hands & Arms Due to Fire in Motor Control Ctr.Caused by Short Circuiting of Bus Bar by hand-held Cordless Drill PNO-V-85-063, on 850924,reactor Tripped Due to Loss of Main Feedwater Pump.Caused by Work on Condensate Demineralizer Sys Resulting in Flow Oscillations.Reactor Will Be Taken to Mode 5 to Repair Pressurizer Safety Valves1985-09-24024 September 1985 PNO-V-85-063:on 850924,reactor Tripped Due to Loss of Main Feedwater Pump.Caused by Work on Condensate Demineralizer Sys Resulting in Flow Oscillations.Reactor Will Be Taken to Mode 5 to Repair Pressurizer Safety Valves PNO-V-85-046, on 850720,reactor Tripped from 100% Power Due to Turbine Trip on Loss of Unit Auxiliary Transformer.Caused by High Temp When Failure of Control Relay Caused Loss of Cooling Fans1985-07-22022 July 1985 PNO-V-85-046:on 850720,reactor Tripped from 100% Power Due to Turbine Trip on Loss of Unit Auxiliary Transformer.Caused by High Temp When Failure of Control Relay Caused Loss of Cooling Fans PNO-V-85-039, on 850704,17 Gpm Leak Occurred Through RCS Drain Valves.Cause Not Reported.Leak Reduced by Increasing Torque on Valves.Torque within Manufacturer Requirements. Restart Activities Recommended After Valve Correction1985-07-0505 July 1985 PNO-V-85-039:on 850704,17 Gpm Leak Occurred Through RCS Drain Valves.Cause Not Reported.Leak Reduced by Increasing Torque on Valves.Torque within Manufacturer Requirements. Restart Activities Recommended After Valve Correction PNO-V-84-061A, on 840913,licensee Declared Unusual Event When Primary Coolant Began Leaking from High Pressure Tubing Fitting at Seal Table from Movable Incore Nuetron Detection Sys Tube E-5.Licensee Issued Press Release1984-09-14014 September 1984 PNO-V-84-061A:on 840913,licensee Declared Unusual Event When Primary Coolant Began Leaking from High Pressure Tubing Fitting at Seal Table from Movable Incore Nuetron Detection Sys Tube E-5.Licensee Issued Press Release PNO-V-84-010, on 840218,reactor Trip Safety Injection Occurred,When Replacement of Fuse During Isolation Valve Surveillance Test Caused Voltage Drop on Preferred Instrument Bus.State of or Notified1984-02-21021 February 1984 PNO-V-84-010:on 840218,reactor Trip Safety Injection Occurred,When Replacement of Fuse During Isolation Valve Surveillance Test Caused Voltage Drop on Preferred Instrument Bus.State of or Notified PNO-V-82-028A, on 820621,pieces of Metal Dislodged from Bottom of Core Barrel Assembly During Reinstallation.Plans for Recovery of Metal & for Exam of Bottom of Assembly Being Developed1982-06-21021 June 1982 PNO-V-82-028A:on 820621,pieces of Metal Dislodged from Bottom of Core Barrel Assembly During Reinstallation.Plans for Recovery of Metal & for Exam of Bottom of Assembly Being Developed PNO-V-82-028, on 820617,remote Video Exam of Metal Pieces Found in Bottom of Reactor Vessel Indicated That Pieces Are Probably from Thermal Sleeves.Thermal Sleeves Not Required Per Discussions W/Westinghouse1982-06-17017 June 1982 PNO-V-82-028:on 820617,remote Video Exam of Metal Pieces Found in Bottom of Reactor Vessel Indicated That Pieces Are Probably from Thermal Sleeves.Thermal Sleeves Not Required Per Discussions W/Westinghouse ML20216K0871978-09-15015 September 1978 PNO-78-165:on 780914 Licensee Notified Region V Resident Inspector or Crash of Light twin-engine Aircraft Adjacent to Trojan Site 1993-01-04 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000344/19990061999-09-0909 September 1999
[Table view]Insp Rept 50-344/99-06 on 990630-0701,21 & 0404-08.No Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls & Decommissioning Performance & Status Review, Insp of Transportation Activities & Maint & Surveillance IR 05000344/19990051999-05-0707 May 1999 Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Major Areas Inspected:Decommissioning Performance & Status Review IR 05000344/19990041999-05-0707 May 1999 Insp Repts 50-344/99-04 & 72-0017/99-02 on 0322-25 & 29- 0408.Non-cited Violations Noted.Major Areas Inspected: Licensee Readiness to Load Sf Into Independent ISFSI IR 05000344/19990031999-04-20020 April 1999 Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted.Major Areas Inspected:Site Tours & Review of Licensee Preparedness for ISFSI Operations IR 05000344/19990021999-04-13013 April 1999 Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Access Authorization,Alarm Station & Communications & Access Control of Personnel & Packages IR 05000344/19980041999-01-21021 January 1999 Insp Repts 50-344/98-04 & 72-0017/98-01 on 981106-07 & 1202-10.Violations Noted.Major Areas Inspected: Decommissioning & Dismantlement Activities at Plant Site ML20202C2111999-01-21021 January 1999 Notice of Violation from Insp on 971207-10.Violation Noted: Licensee Did Not Perform Survey to Assure Compliance with 10CFR20.1902(d) IR 05000344/19982021998-10-30030 October 1998 Insp Rept 50-344/98-202 on 980831-0903.No Violations Noted. Major Areas Inspected:Safety Review Program Re Modular Sf Cooling Sys & Maint Program IR 05000344/19980031998-08-25025 August 1998 Insp Rept 50-344/98-03 on 980727-30.No Violations Noted. Major Areas Inspected:Sfp Safety,Ore,Decommissioning Performance & Status Review,Organization Mgt & Cost Controls & Solid Radioactive Waste & Transport IR 05000344/19980021998-07-0101 July 1998 Insp Rept 50-344/98-02 on 980601-04.No Violations Noted. Major Areas Inspected:Activities Including Spent Fuel Pool Safety,Occupational Radiation Exposure & Decommissioning Performance & Status Review IR 05000344/19980011998-05-22022 May 1998 Insp Rept 50-344/98-01 on 980504-07.No Violations Noted. Major Areas Inspected:Specific Areas of Licensee Physical Security Program IR 05000344/19982011998-04-29029 April 1998 Insp Rept 50-344/98-201 on 980223-26.No Violations Noted. Major Areas Inspected:Safety Review Program & Insp follow- Up ML20199D7511998-01-23023 January 1998 Cover Page for Insp Rept 50-344/97-05 on 971201-03, Inadvertently Omitted in Original Submittal ML20199F0361998-01-23023 January 1998 Insp Rept 50-344/97-05 on 971201-03.Violations Noted.Major Areas Inspected:Status of Dismantlement Activities,Changes to Util Emergency Exercise Plan Implementing Procedures & Decommissioning ML20199F0291998-01-15015 January 1998 Notice of Violation from Insp on 971201-03.Violation Noted: Licensee Failed to Ensure Adequate Survey of Certain Contaminated Tools IR 05000344/19970041997-11-21021 November 1997 Insp Repts 50-344/97-04 & 72-0017/97-04 on 970929-1002.No Violations Noted.Major Areas Inspected:Fuel Debris Processing,Dry Cask Storage & Control of Radioactive Matl. Insp Repts Reissued Due to Omission of Pages 4 & 5 ML20198N3461997-10-31031 October 1997 Insp Repts 50-344/97-04 & 72-0017/97-04 on 970929-1010.No Violations Noted.Major Areas Inspected:Fuel Debris Processing Preparation for Pouring Concrete for Portion of ISFSI Pad & Control & Release of Contaminated Matl ML20210S7131997-09-0909 September 1997 Notice of Violation from Insp on 970721-24.Violation Noted: from 960923-970515,licensee Failed to Conduct Surveys Adequate to Evaluate Quantity of Radioactive Matl Released from Radiological Controlled Area IR 05000344/19970031997-09-0909 September 1997 Insp Repts 50-344/97-03 & 72-0017/97-03 on 970721-24. Violations Noted.Major Areas Inspected:Control of Radioactive Material,Spent Fuel Pool Debris Project,Dry Cask Storage,Spent Fuel Pool & Health Physics Activities IR 05000344/19970021997-05-0606 May 1997 Insp Repts 50-344/97-02 & 72-0017/97-02 on 970414-17.No Violations Noted.Major Areas Inspected:Health Physics, Training Program,Spent Fuel Pool,Independent Spent Fuel Storage Installation & Fuel Building Crane Tests IR 05000344/19970011997-02-25025 February 1997 Insp Repts 50-344/97-01 & 72-0017/97-01 on 970204-06. Violations Noted.Major Areas Inspected:Review of Radiation Protection Program,Compliance W/Ts,Operations Involving Licensee Insp of Spent Fuel & Quality Assurance Program ML20135B7491997-02-25025 February 1997 Notice of Violation from Insp on 970204-06.Violation Noted: Licensee Had Not Audited Annual Radiological Environmental Report TS 6.9.1.5.1 Since 890519 IR 05000344/19960081997-02-13013 February 1997 Insp Repts 50-344/96-08 & 72-0017/96-02 on 961104-07.No Violations Noted.Major Areas Inspected:Decommissioning Activities Related to Ongoing Efforts to Decontaminate Facility & Place Spent Fuel in Storage at ISFSI IR 05000344/19960051997-02-13013 February 1997 Correction to Insp Repts 50-344/96-05 & 72-0017/96-02. Requests That Encl Pages Be Added as Last Two Pages of Listed Insp Rept ML20059A1421993-12-15015 December 1993 Notice of Violation from Insp on 930930-1112.Violation Noted:Detailed Construction Package 1 Associated W/Request for Design Change 78-103,installed in May 1980,did Not Correctly Translate Design Basis Into Applicable Procedures IR 05000344/19930151993-12-14014 December 1993 Insp Rept 50-344/93-15 on 931115-18.No Violations Noted. Major Areas Inspected:Operational Status of EP Program & of Annual EP Exercise IR 05000344/19930141993-12-0606 December 1993 Insp Rept 50-344/93-14 on 930930-1112.Violations Noted.Major Areas Inspected:Resident Insp of Operational Safety Verification,Maintenance,Surveillance & follow-up of Previously Identified Items IR 05000344/19930121993-10-22022 October 1993 Insp Rept 50-344/93-12 on 930817-0929.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19930131993-09-24024 September 1993 Insp Rept 50-344/93-13 on 930913-17.No Violations Noted. Major Areas Inspected:Listed Portions of Licensee Physical Security Program IR 05000344/19930111993-09-0303 September 1993 Insp Rept 50-344/93-11 on 930706-0816.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup of Previously Identified Items IR 05000344/19930101993-08-12012 August 1993 Insp Rept 50-344/93-10 on 930706-08.No Violations Noted. Major Areas Inspected:Chemistry & Radiation Protection Program Organization & Staffing & Solid Radwaste Storage IR 05000344/19930081993-06-25025 June 1993 Insp Rept 50-344/93-08 on 930422-0531.No Violations Noted. Major Areas Inspected:Operational Safety Verification,Maint, Emergency Preparedness & Followup of Previously Identified Items PNO-V-93-002, on 930113,L Marbet Held Press Conference W/ Portland,Or Media & Alleged That NRC Had Inappropriately Authorized Feb 1992 Restart of Plant.Util Announced on 930104 That Operation of Plant Would Be Permanently Ceased1993-01-13013 January 1993 PNO-V-93-002:on 930113,L Marbet Held Press Conference W/ Portland,Or Media & Alleged That NRC Had Inappropriately Authorized Feb 1992 Restart of Plant.Util Announced on 930104 That Operation of Plant Would Be Permanently Ceased IR 05000344/19920321993-01-0808 January 1993 Insp Rept 50-344/92-32 on 921027-1207.Violations Noted.Major Areas Inspected:Maintenance,Surveillance,Event Followup & Followup of Previously Identified Items ML20127E9461993-01-0808 January 1993 Notice of Violation from Insp on 921027-1207.Violation Noted:Licensees Corrective Actions Not Effective in That,On 921112 & 15,access Doors to Plant Issue Warehouse Not Controlled by Authorized Personnel PNO-V-93-001, on 930104,Licensee Notified Region V That Util Board Decided That Plant Will Not Be Restarted & Currently Shutdown for Insp & Repair of SG Tubes.Licensee Notified Media1993-01-0404 January 1993 PNO-V-93-001:on 930104,Licensee Notified Region V That Util Board Decided That Plant Will Not Be Restarted & Currently Shutdown for Insp & Repair of SG Tubes.Licensee Notified Media IR 05000344/19920341992-12-31031 December 1992 Meeting Rept 50-344/92-34 on 921201.Areas Discussed:Sg Tube Leak & Licensees Subsequent Insp of SGs IR 05000344/19920331992-12-29029 December 1992 Insp Rept 50-344/92-33 on 921207-11.No Violations or Deviations Noted.Major Areas Inspected:Licensee Erosion/ Corrosion Program Activities,Including Followup of Previously Identified Items IR 05000344/19920281992-12-21021 December 1992 Insp Rept 50-344/92-28 on 921109-1215.No Violations or Deviations Noted.Major Areas Inspected:Rev 7 to Emergency Plan Implementing Procedure EP-001, Emergency Classification PNO-V-92-038, on 921209,B Roberts Plans to Notify News Media of Request of or Energy Facility Siting Council to Hold Hearing on Utility Steam Generator Safety1992-12-0808 December 1992 PNO-V-92-038:on 921209,B Roberts Plans to Notify News Media of Request of or Energy Facility Siting Council to Hold Hearing on Utility Steam Generator Safety PNO-V-92-037, on 921201,meeting Conducted at Plant to Address 921109 Steam Generator Tube Leak & Licensee Request for Emergency TS Change to Permit Restart1992-12-0101 December 1992 PNO-V-92-037:on 921201,meeting Conducted at Plant to Address 921109 Steam Generator Tube Leak & Licensee Request for Emergency TS Change to Permit Restart ML20126E9101992-11-25025 November 1992 Notice of Violation from Insp on 920915-1026.Violation Noted:Supervisor Informed of Receipt of a Nonconforming Component,Chlorine Detector & Did Not Initiate an Ncr ML20126E9131992-11-25025 November 1992 Notice of Deviation from Insp on 920915-1026.Deviation Noted:Containment Air Locks Not Tested Using Pressure Decay Method IR 05000344/19920301992-11-25025 November 1992 Insp Rept 50-344/92-30 on 920915-1026.Violations Noted. Major Areas Inspected:Operational Safety Verification, Maintenance,Surveillance & Followup of Previously Identified IR 05000344/19920311992-11-10010 November 1992 Insp Rept 50-344/92-31 on 920928-1002.No Violations Noted. Major Areas Inspected:Environ Monitoring,Cr Ventilation & Control of Radwaste Activities PNO-V-92-004, on 920225,Trojan Power Plant Entered Mode 2 After Extended Outage.Plant Currently Critical at Less than 1 Percent Power & Licensee Conducting Low Power Physics Testing.Tests Expected to Be Completed by 9202271992-02-25025 February 1992 PNO-V-92-004:on 920225,Trojan Power Plant Entered Mode 2 After Extended Outage.Plant Currently Critical at Less than 1 Percent Power & Licensee Conducting Low Power Physics Testing.Tests Expected to Be Completed by 920227 IR 05000344/19910161991-06-0404 June 1991 Insp Rept 50-344/91-16 on 910506-16.No Violations or Deviations Noted.Major Areas Inspected:Proposed Rev 6 to Emergency Procedure (EP)-001, Emergency Classification PNO-V-91-002, on 910303,Trojan Declared an Unsual Event & Initiated Plant Shutdown Due to Inability to Meet Requirements of TS 3.8.2.1,which Requires That Four 120 Volts AC Preferred Instrument Busses Be Operable1991-03-0505 March 1991 PNO-V-91-002:on 910303,Trojan Declared an Unsual Event & Initiated Plant Shutdown Due to Inability to Meet Requirements of TS 3.8.2.1,which Requires That Four 120 Volts AC Preferred Instrument Busses Be Operable ML20062F9301990-11-0808 November 1990 Notice of Violation from Insp on 900902-1006.Violation Noted:Temp of Train B Component Cooling Water Pump (ASME Code Class 3 Pump) Taken W/Instrument W/Scale More than Three Times Ref Value of Bearing Temp PNO-V-90-045, State of or Measure 4 Re Closure of Facility Defeated in 901106 Vote.Util Will Hold News Conference1990-11-0707 November 1990 PNO-V-90-045:State of or Measure 4 Re Closure of Facility Defeated in 901106 Vote.Util Will Hold News Conference 1999-09-09 |
PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-V-87-35 Date: May'8, 1987 This preliminary notification constitutes EARLY notice of events of POSSIBLE. safety or ,
public interest significance. The infonnation presented is as initially received '
without verification or evaluation and is basically-all that is known by Region V staff en this date.
FACILITY: Portland General Electric Company Emergency Classification l Trojan Nuclear Power Plant X Notification of Unusual Event Docket No.: 50-344 Alert Rainier, Oregon Site Area Emergency General Emergency Not Applicable
SUBJECT:
TRANSPORT OF A CONTAMINATED, INJURED INDIVIDUAL OFFSITE (H00 REPORTABLE EVENT NO. 8600)
On May 7, 1987, at 6:45 PM, (EDT), the licensee reported an Unusual Event, to the H:adquarters Operations Officer by telephone, in regard to a contaminated individual who had to be transported off-site for medical attention due to heat exhaustion. On May 8, 1987, at 7:30 AM, (PDT), the licensee infonned the Region V office by telephone, that this individual had been decontaminating equipment in a tented area in the spent fuel building. The individual was. wearing protective clothing and ice vest. The individual b came ill, left the tent, and fell'to his knees in a contaminated area while removing-his protective clothing. General contamination levels on his knees indicated 160,000 dps/
100. square centimeters. After initial decontamination the individual was transported by ambulance with 4,000 dpm/100 square centimeters on his right knee. Two Radiation Protection Tcchnicians and a Certified Health-Physicist accompanied the individual to St. John's Hospital in Longview, Washington, pursuant to their Emergency Plan Procedures. Follow-up surveys revealed that no contamination was spread to the ambulance or hospital and the w:rksr was effectively decontaminated. The individual returned to work on May 8, 1987.
=Th2 licensee has issued a press release.
Thisinformationiscurrentasof10:30AM,(PDT),May8,1987.
CONTACT: C. Hooker, FTS 463-3784 - G. Yuhas, FTS 463-3748 DISTRIBUTION
'H St. MNBB Phillips E/W Willste Air Rights Mail:
Chairman Zech EDO NRR NRR7PU5 NMSS SP ADM:DMB Cons. Carr PA OIA RES DOT:Trans Only Comm. Bernthal MPA NRR/DREP Applicable State Conn. Roberts OGC Conn. Asselstine Regions: X SECY INP0 X NSAC ACRS Licensee: Trojan CA. (ReactorLicensees)
PDR Resident Inspector,_X_ j 8705120298 870508 n f PDR 18 E PNO-V-87-035 PDR
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