ML20207G426
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| ML20207G426 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/07/1977 |
| From: | Bidinger G, Liza Cunningham NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| PNO-77-218, NUDOCS 9903120072 | |
| Download: ML20207G426 (1) | |
Similar Documents at Dresden | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-III-97-014, on 970227,employee Exiting Plant Had Set Off Radiation Detector.Employee Hands Found to Have Low Levels of Contamination.Staff from Dresden Plant Interviewed Employee Re Work Activities to Determine Contamination1997-02-28028 February 1997
[Table view]PNO-III-97-014:on 970227,employee Exiting Plant Had Set Off Radiation Detector.Employee Hands Found to Have Low Levels of Contamination.Staff from Dresden Plant Interviewed Employee Re Work Activities to Determine Contamination PNO-III-96-066, on 961026,3B Reactor Recirculation Pump motor-generator Tripped.Licensee Determined Recovery of Idle Loop Impossible W/O Plant Shutdown & Began Controlled Shutdown.Independent Insp Safety Team Onsite for Review1996-10-28028 October 1996 PNO-III-96-066:on 961026,3B Reactor Recirculation Pump motor-generator Tripped.Licensee Determined Recovery of Idle Loop Impossible W/O Plant Shutdown & Began Controlled Shutdown.Independent Insp Safety Team Onsite for Review PNO-III-92-062A, provides Update on 920918 Incident in Which Rod Movement Error Occurred But Not Documented or Reported to Util Mgt.Util Terminated Employment of Four of Five Individuals Involved in Incident1992-12-0303 December 1992 PNO-III-92-062A:provides Update on 920918 Incident in Which Rod Movement Error Occurred But Not Documented or Reported to Util Mgt.Util Terminated Employment of Four of Five Individuals Involved in Incident PNO-III-92-039A, on 920701,annunciators on Four CR Panels Were Lost About Three Times in Five Seconds.Later During Troubleshooting Efforts,Annunciators Were Again Lost.Cause Was Loose Connection in Copper Link within Fuse Holder1992-07-0202 July 1992 PNO-III-92-039A:on 920701,annunciators on Four CR Panels Were Lost About Three Times in Five Seconds.Later During Troubleshooting Efforts,Annunciators Were Again Lost.Cause Was Loose Connection in Copper Link within Fuse Holder PNO-III-91-038, w/Dresden Unit 3 in Cold Shutdown & Reactor Defueled,Licensee Experienced Loss of All Unit 3 Annunciators in Control Room.Loss Caused by Blown 3 Amp Fuse.Fuse Replaced & Control Room Annunciators Restored1991-09-23023 September 1991 PNO-III-91-038:w/Dresden Unit 3 in Cold Shutdown & Reactor Defueled,Licensee Experienced Loss of All Unit 3 Annunciators in Control Room.Loss Caused by Blown 3 Amp Fuse.Fuse Replaced & Control Room Annunciators Restored PNO-III-90-054, on 900802,safety Relief Valve Opened Unexpectedly & Remained Open.Licensee Evaluating Event,Which Exceeded Tech Spec Limit for Reactor Cooldown Rate.Valve Will Be Replaced & Failed Valve Will Be Inspected1990-08-0202 August 1990 PNO-III-90-054:on 900802,safety Relief Valve Opened Unexpectedly & Remained Open.Licensee Evaluating Event,Which Exceeded Tech Spec Limit for Reactor Cooldown Rate.Valve Will Be Replaced & Failed Valve Will Be Inspected PNO-III-89-042, on 890629,unit 1 Turbine Tripped,Causing Reactor Scam.Licensee in Process of Placing Reactor in Cold Shutdown to Repair Degraded Inner Seal on 1B Reactor Circulation Pump Prior to Startup.State of Il Notified1989-06-30030 June 1989 PNO-III-89-042:on 890629,unit 1 Turbine Tripped,Causing Reactor Scam.Licensee in Process of Placing Reactor in Cold Shutdown to Repair Degraded Inner Seal on 1B Reactor Circulation Pump Prior to Startup.State of Il Notified PNO-III-88-053, on 880604,while Unit 3 Was Shutdown for Refueling Outage,Contractor Fire Watch Noticed Smoke Coming from Beneath Welder Working on Struts Being Installed on RWCU Sys Piping Penetration Inside RWCU Pipe Way Pit1988-06-0707 June 1988 PNO-III-88-053:on 880604,while Unit 3 Was Shutdown for Refueling Outage,Contractor Fire Watch Noticed Smoke Coming from Beneath Welder Working on Struts Being Installed on RWCU Sys Piping Penetration Inside RWCU Pipe Way Pit PNO-III-88-046, on 880517,test Performed as Part of Investigation of Dec 1987 Incident in Which Air Line Became Disconnected on One MSIV & Did Not Fully Close.Ait Will Maintain Insp Coverage of Activities Associated W/Msiv1988-05-20020 May 1988 PNO-III-88-046:on 880517,test Performed as Part of Investigation of Dec 1987 Incident in Which Air Line Became Disconnected on One MSIV & Did Not Fully Close.Ait Will Maintain Insp Coverage of Activities Associated W/Msiv PNO-III-87-127, on 870904,manipulation of Controls by non- Licensed Engineer Occurred.Caused by Personnel Error. Licensee Met W/Licensed Operators & Nuclear Engineers to Review Requirement Policy1987-10-0101 October 1987 PNO-III-87-127:on 870904,manipulation of Controls by non- Licensed Engineer Occurred.Caused by Personnel Error. Licensee Met W/Licensed Operators & Nuclear Engineers to Review Requirement Policy PNO-III-87-125, on 870918,both Units Shutdown Due Inability to Maintain Required Pressure Differential Between Secondary Containment & Atmosphere.Licensee Investigating Source of Leakage.State of Il Notified1987-09-21021 September 1987 PNO-III-87-125:on 870918,both Units Shutdown Due Inability to Maintain Required Pressure Differential Between Secondary Containment & Atmosphere.Licensee Investigating Source of Leakage.State of Il Notified PNO-III-87-105, on 870807,reactor Manually Scrammed.Caused by Variations in Feedwater Flow to Reactor & Leakage from Feedwater Sys.Ndt Performed Small Diameter Feedwater Piping & Other High Stress Areas1987-09-0404 September 1987 PNO-III-87-105:on 870807,reactor Manually Scrammed.Caused by Variations in Feedwater Flow to Reactor & Leakage from Feedwater Sys.Ndt Performed Small Diameter Feedwater Piping & Other High Stress Areas PNO-III-87-096, on 870711,reactor Trip Occurred.Caused by Increased Feedwater Flow from 2.2 to 5.6 Million Gallons/H & Closure of All Msivs.Licensee Has No Plans to Operate in Element Control 3 on Feed Sys in the Near Future1987-07-13013 July 1987 PNO-III-87-096:on 870711,reactor Trip Occurred.Caused by Increased Feedwater Flow from 2.2 to 5.6 Million Gallons/H & Closure of All Msivs.Licensee Has No Plans to Operate in Element Control 3 on Feed Sys in the Near Future PNO-III-87-081, on 870610,earthquake Measuring 5.0 on Richter Scale Occurred Near Lawrenceville,Il.Unusual Events Declared by Six Power Stations But No Damage Observed.Ground Motion Felt at Five Other Plants1987-06-11011 June 1987 PNO-III-87-081:on 870610,earthquake Measuring 5.0 on Richter Scale Occurred Near Lawrenceville,Il.Unusual Events Declared by Six Power Stations But No Damage Observed.Ground Motion Felt at Five Other Plants PNO-III-87-054, on 870409,unit Manually Shut Down & Scrammed Following Vacuum Problem in Main Condenser & Increasing Temp in Hotwell.Caused by Partially Dislodged Ceiling Embedment Plate Supporting Portion of Lpci.Plate Repaired1987-04-13013 April 1987 PNO-III-87-054:on 870409,unit Manually Shut Down & Scrammed Following Vacuum Problem in Main Condenser & Increasing Temp in Hotwell.Caused by Partially Dislodged Ceiling Embedment Plate Supporting Portion of Lpci.Plate Repaired PNO-III-87-031A, updates Four Possible Equipment Tampering Incidents at Plant.No Final Conclusions Reached Following Interviews W/About 140 Plant Workers.On 870306,mgt Reacted to Rept of Hoax Explosive Device at Plant.Workers Suspended1987-03-27027 March 1987 PNO-III-87-031A:updates Four Possible Equipment Tampering Incidents at Plant.No Final Conclusions Reached Following Interviews W/About 140 Plant Workers.On 870306,mgt Reacted to Rept of Hoax Explosive Device at Plant.Workers Suspended PNO-III-87-029, on 870126,six of Twelve ROs & SROs Failed Requalification Exam.Operators Who Failed Exam Removed from Licensed Operating Activities1987-03-0606 March 1987 PNO-III-87-029:on 870126,six of Twelve ROs & SROs Failed Requalification Exam.Operators Who Failed Exam Removed from Licensed Operating Activities PNO-III-87-033, on 870303,shutdown Cooling Sys Pump 3A Declared Inoperable Following Insp Which Showed Degradation of Oil Quality from Upper Bearing Housing.Util Does Not Plan to Resume Reactor Operation Prior to 8703041987-03-0303 March 1987 PNO-III-87-033:on 870303,shutdown Cooling Sys Pump 3A Declared Inoperable Following Insp Which Showed Degradation of Oil Quality from Upper Bearing Housing.Util Does Not Plan to Resume Reactor Operation Prior to 870304 PNO-III-87-031, on 870217,loosened Bolt Discovered on Diesel Generator Cooling Pump Flange.Caused by Deliberate Loosening of Bolts.Licensee Increased Security Coverage Pending Completion of Investigation1987-02-27027 February 1987 PNO-III-87-031:on 870217,loosened Bolt Discovered on Diesel Generator Cooling Pump Flange.Caused by Deliberate Loosening of Bolts.Licensee Increased Security Coverage Pending Completion of Investigation PNO-III-86-142, on 861205,licensees Notified NRC That Electrical Splices Did Not Meet Environ Qualification Requirements & Plants Shut Down.Each Unit Has 150 Splices Which Must Be Repaired.Repairs Expected to Take 5 Days1986-12-0505 December 1986 PNO-III-86-142:on 861205,licensees Notified NRC That Electrical Splices Did Not Meet Environ Qualification Requirements & Plants Shut Down.Each Unit Has 150 Splices Which Must Be Repaired.Repairs Expected to Take 5 Days PNO-III-86-099, on 860917,licensee Shut Reactor Down to Permit Cleaning of Main Condenser.Condenser Tubes Became Partially Blocked by Clams/Clam Shells.Other Maint Work Also Planned.Restart Expected No Earlier than 8609191986-09-17017 September 1986 PNO-III-86-099:on 860917,licensee Shut Reactor Down to Permit Cleaning of Main Condenser.Condenser Tubes Became Partially Blocked by Clams/Clam Shells.Other Maint Work Also Planned.Restart Expected No Earlier than 860919 PNO-III-86-087, on 860827,plant Shut Down Due to Equipment Problems Resulting in Inoperable HPCI Sys & Train B of Core Spray Sys.Addl Problems Identified During Shutdown.Repairs Underway1986-08-29029 August 1986 PNO-III-86-087:on 860827,plant Shut Down Due to Equipment Problems Resulting in Inoperable HPCI Sys & Train B of Core Spray Sys.Addl Problems Identified During Shutdown.Repairs Underway PNO-III-86-078, on 860806,leakage of Approx 144,000 Gallons of Primary Sys Coolant Water from RWCU Sys Into Torus Bldg Sumps Reported.Cause Undetermined.Rwcu Sys Isolated & Leakage Terminated.Investigation Continuing1986-08-0707 August 1986 PNO-III-86-078:on 860806,leakage of Approx 144,000 Gallons of Primary Sys Coolant Water from RWCU Sys Into Torus Bldg Sumps Reported.Cause Undetermined.Rwcu Sys Isolated & Leakage Terminated.Investigation Continuing PNO-III-86-076, on 860804,isolation Valves in Nitrogen Lines to CRD Accumulators Found Closed.Caused by Mispositioning of Valve.Licensee Investigating Mispositioning to Determine Cause1986-08-0606 August 1986 PNO-III-86-076:on 860804,isolation Valves in Nitrogen Lines to CRD Accumulators Found Closed.Caused by Mispositioning of Valve.Licensee Investigating Mispositioning to Determine Cause PNO-V-86-016, on 860407,State of Wa Informed Region That One Drum in 860403 Radwaste Shipment from Facility Had Hole in Side.Util Barred from Use of Burial Site.Burial Permit 2280 Suspended Effective on 8604041986-04-11011 April 1986 PNO-V-86-016:on 860407,State of Wa Informed Region That One Drum in 860403 Radwaste Shipment from Facility Had Hole in Side.Util Barred from Use of Burial Site.Burial Permit 2280 Suspended Effective on 860404 PNO-III-86-032, on 860401,main Control Room Panels for Both Units Found Unbolted.Caused by Improper Installation Per Design Drawings.Panels Being Bolted to Support Beams.Cause of Discrepancy Under Investigation1986-04-0202 April 1986 PNO-III-86-032:on 860401,main Control Room Panels for Both Units Found Unbolted.Caused by Improper Installation Per Design Drawings.Panels Being Bolted to Support Beams.Cause of Discrepancy Under Investigation PNO-III-86-003A, on 860120,inspectors Discovered That Temps Created by Polyurethane Insulation Fire on 860120 May Have Been High Enough to Cause Physical Changes to Portions of Drywell Vessel Metal1986-01-30030 January 1986 PNO-III-86-003A:on 860120,inspectors Discovered That Temps Created by Polyurethane Insulation Fire on 860120 May Have Been High Enough to Cause Physical Changes to Portions of Drywell Vessel Metal PNO-III-86-003, on 860120,insulating Matl Between Outer Drywell Surface & Concrete Shielding Wall Began to Smolder During Welding.Personnel Evacuated.Area Hosed Down.Licensee Evaluating Consequences of Fire1986-01-21021 January 1986 PNO-III-86-003:on 860120,insulating Matl Between Outer Drywell Surface & Concrete Shielding Wall Began to Smolder During Welding.Personnel Evacuated.Area Hosed Down.Licensee Evaluating Consequences of Fire PNO-III-85-101, on 851214,contractor Employee Found Dead in Reactor Bldg Basement.Caused by Fall of Approx 40 Ft from Exterior of Torus & Striking of Valve During Fall.Grundy County Sheriff Dept & Coroner Notified1985-12-16016 December 1985 PNO-III-85-101:on 851214,contractor Employee Found Dead in Reactor Bldg Basement.Caused by Fall of Approx 40 Ft from Exterior of Torus & Striking of Valve During Fall.Grundy County Sheriff Dept & Coroner Notified PNO-III-85-084, on 850919,reactor Scrammed Due to Mechanic Bumping Circuit Board.Reactor Bldg Evacuated Due to Steam Leak & High Radiation Alarms.Four People Slightly Contaminated1985-09-20020 September 1985 PNO-III-85-084:on 850919,reactor Scrammed Due to Mechanic Bumping Circuit Board.Reactor Bldg Evacuated Due to Steam Leak & High Radiation Alarms.Four People Slightly Contaminated PNO-III-85-071A, circuitry Mods to Plant Transformers Completed & Successfully Tested on 850819.Mods Instituted Due to Failure in Switching Mechanism in Auxiliary Main Station Transformer1985-08-20020 August 1985 PNO-III-85-071A:circuitry Mods to Plant Transformers Completed & Successfully Tested on 850819.Mods Instituted Due to Failure in Switching Mechanism in Auxiliary Main Station Transformer PNO-III-80-176, potentially High Press Interest Exists in Results of Institute of Nuclear Power Operations Insp of Station.Summary of Insp Rept Encl1980-09-15015 September 1980 PNO-III-80-176:potentially High Press Interest Exists in Results of Institute of Nuclear Power Operations Insp of Station.Summary of Insp Rept Encl PNO-III-80-169A, since 800905,extensive Investigations by Region 3 & Util Personnel Into Allegations of Radioactive Release Has Not Determined Whether Actual Release of Low Level Radioactive Water Occurred1980-09-10010 September 1980 PNO-III-80-169A:since 800905,extensive Investigations by Region 3 & Util Personnel Into Allegations of Radioactive Release Has Not Determined Whether Actual Release of Low Level Radioactive Water Occurred PNO-III-80-169, on 800904,reporter from Chicago Sun Times Contacted NRC Resident Inspectors Re Allegations That 400,000 Gallons of Radioactive Water Leaked from Station Since Jul 19801980-09-0505 September 1980 PNO-III-80-169:on 800904,reporter from Chicago Sun Times Contacted NRC Resident Inspectors Re Allegations That 400,000 Gallons of Radioactive Water Leaked from Station Since Jul 1980 ML20217A5851979-12-12012 December 1979 PNO-78-208:on 791212,fire Occurred in Main Transformer ML20217B2071978-08-30030 August 1978 PNO-78-156:on 780829,shipment of Solidified (Cement) Radwaste Enroute from Dresden Site to Chem Nuclear Burial Ground Near Barnwell,South Carolina Overturned.Survey Teams from Oakridge,State of Georgia & Sequoyah Responded ML20248L0741978-02-10010 February 1978 PNO-78-027:on 780209,semitrailer Truck Carrying Loaded Sf Shipping Cask Buckled While Vehicle Traveling on Illinois Highway 54 Near Gibson City,Il.Cask Contained Six Spent mixed-oxide Fuel Rods from Dresden Nuclear Power Station ML20207G4261977-12-0707 December 1977 PNO-77-218:on 771206,util Reported That Stack Release Rate for Gross beta-gamma Activity 1.9 Curies/Second for Period of 3 to 4 Minutes.Licensee Immediately Commenced Power Reduction to Reduce Release Rate to Less than Requirements ML20207G3971977-11-0808 November 1977 PNO-77-196:on 771102,during Testing of Facility Crds,Seal Purge Flow from CRD Hydraulic Sys Pressurized 1-A Recirculation Pump Number One Seal Cavity to 1450 Psig, Potential Violation of Safety Limit,In Technical Sense ML20151X5661977-09-16016 September 1977 PNO-77-160:on 770916,910 Gallons of Contaminated Laundry Water Released from Dresden Unit 1 Nuclear Station to Discharge Canal at Concentration Greater than That Allowed by Tss.Error Made in Calculation of Dilution Needed ML20151X5931977-08-0505 August 1977 PNO-77-140:on 770805,while Unit 2 & 3 Were Operating & Unit 1 Was Shutdown,Chemical Spill Occurred in Area Below Control Room.Control Room Ventilation Sys Was Switched to Alternate Mode Which Cleared Control Room of Fumes ML20236F2791976-10-0707 October 1976 PNO-76-189:on 761110,driver Slowed Down to Exit for Routine Load Check,Load Apparently Shifted Causing Side of Septic Tank to Give Way.Incident Caused Seam of Steel Outer Container to Split,Resulting in Liquid Spilling Onto Ground ML20249B8931976-09-17017 September 1976 PNO-76-157:on 760916,util Notified Region III That Leak Had Been Discovered in HPCI Test Return Line to Condensate Storage Tank ML20249B5591976-09-15015 September 1976 PNO-76-096A:on 760913,Region III Ofc Testified Before State of Il Commerce Commission Hearing in Chicago Re Handling of Radioactive Effluents at Commonwealth Plants.Attorneys for Licensee Objected to NRC Testimony on Listed Grounds ML20236F3621976-08-0303 August 1976 PNS-76-038:on 760803,bomb Threat Phoned in by Anonymous Caller.Nonessential Persons Were Cleared from Control Room Through Search of Control Room & Adjacent Areas Disclosed No Unidentified Matls.Fbi,Police & Civil Defense Notified ML20249B3401976-04-0707 April 1976 PNO-76-067:on 760406,Region III Notified That Ultrasonic Reading of 100% of DAC Observed in Isolation Condenser Steam Line.Evaluation Indicates Measurement to Represent Circumferential Crack Originating at Inner Surface of Pipe ML20236U8801975-10-0808 October 1975 PN-75-103:on 751007,crack Discovered in 18 Inch Containment Purge Line Where 8 Inch Nitrogen Supply Line Joins.Unit Was at 85% Power at Time Crack Found.State of Illinois Notified ML20236V3061975-09-0202 September 1975 PN-75-084:on 750901,licensee Reported That Circumferential Crack Was Found on an Unisolatable Section of 6-inch Primary Coolant Cleanup Sys Line Return from Primary Side to B SG ML20236T9631975-07-0202 July 1975 PN-75-044:during Extended Refueling Outage,Licensee Discovered Circumferential Cracks in Thin Section of CRD Collet Housing.Cracks Have Been Found on 12 of 21 Drives Checked & Stated to Result from Thermal Stress ML20236U5281975-05-16016 May 1975 PN-75-025:licensee Informed Oie Inspector at Site That Scheduled Visual Insp of Dresden 3 Reactor Vessel Internals Had Disclosed Cracks Near Welds in Feedwater Spargers 1997-02-28 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000010/19990131999-08-0202 August 1999
[Table view]Insp Rept 50-010/99-13 on 990702-27.No Violations Noted. Major Areas Inspected:Aspects of Facility Management & Control & Radiological Safety IR 05000237/19990081999-06-18018 June 1999 Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000010/19990091999-05-13013 May 1999 Insp Rept 50-010/99-09 on 990325-0506.Non-cited Violations Noted.Major Areas Inspected:Licensee Mgt & Control, Decommissioning Support Activities & Radiological Safety IR 05000010/19990071999-04-0202 April 1999 Partially Withheld Security Insp Repts 50-010/99-07, 50-237/99-07 & 50-249/99-07 on 990308-12.Portions Withheld (Ref 10CFR2.790) IR 05000010/19990021999-02-10010 February 1999 Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted. Major Areas Inspected:Licensee Mgt & Control IR 05000010/19980181998-11-13013 November 1998 Partially Withheld Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 (Ref 10CFR73.21).Violations Noted. Major Areas Inspected:Physical Protection of Plant Facility IR 05000010/19980161998-10-0606 October 1998 Insp Rept 50-010/98-16 on 980723-0918.No Violations Noted. Major Areas Inspected:Aspects of Licensee Mgt & Control, Sf Safety & Radiological Safety.Followup Insp Performed on Previously Identified Issue IR 05000010/19980131998-07-0606 July 1998 Insp Rept 50-010/98-13 on 980319-0630.No Violations Noted. Major Areas Inspected:Mgt & Control,Sf Safety & Radiological Safety ML20236F1591998-06-29029 June 1998 Partially Withheld Insp Repts 50-010/98-15,50-237/98-18 & 50-249/98-18 on 980601-04 (Ref 10CFR73.71).No Violations Noted.Major Areas Inspected:Plant Support Activities Re Physical Protection of Plant Facility ML20237B1511998-06-29029 June 1998 Errata to NOV from Insp on 980601-04.Violations Noted:On 980527,licensee Identified That Both Supervisor & Clerk Failed to Document Personnel Contacts on Required call-out Work Record Form.Nov Does Not Contain Safeguards Info IR 05000237/19980141998-06-26026 June 1998 Insp Repts 50-237/98-14 & 50-249/98-14 on 980403-0527.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20217D6151998-03-25025 March 1998 Partially Withheld Insp Repts 50-010/98-08,50-237/98-08 & 50-249/98-08 (Ref 10CFR73.71) on 980302-11.Violations Noted. Major Areas Inspected:Elements of Security Program ML20248L8031998-03-18018 March 1998 Notice of Violation from Insp on 971215-980226.Violation Noted:Between 970101-1121,air Samples Not Always Immediately Counted Using HP Germanium Detector When Inital Beta/Gamma Activity Determined Greater Than/Equal to 30% DAC Limit IR 05000010/19980021998-03-18018 March 1998 Insp Rept 50-010/98-02 on 971215-980226.Violations Noted. Major Areas Inspected:Licensee Mgt & Control,Decommissioning Support Activities & Radiological Safety IR 05000010/19970261997-12-23023 December 1997 Insp Repts 50-010/97-26,50-237/97-26 & 50-249/97-26 on 971029 & 1106.No Violations Noted.Major Areas Inspected: Selective Review of Plant Support Activities Re FFD Program, Licensee Procedures & Implementation Requirements IR 07100016/20110221997-12-19019 December 1997 Notice of Violation from Insp on 971016-1122.Violation Noted:Between 971027 & 971028,both Standby Liquid Control Subsystems Were Inoperable & Plant Was Not Brought to at Least Hot Shutdown Condition ML20197F0541997-12-19019 December 1997 Insp Repts 50-010/97-24,50-237/97-24 & 50-249/97-24 on 971016-1122.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support ML20203C9381997-12-0404 December 1997 Notice of Violation from Insp on 970828-1016.Violations Noted:As of 970828,licensee Failed to Maintain Operating Surveillance Procedure DOS 6600-01 Sufficiently to Operate EDG by Not Providing Adequate Procedural Guidance IR 05000010/19970191997-12-0404 December 1997 Insp Repts 50-010/97-19,50-237/97-19 & 50-249/97-19 on 970828-1016.Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support IR 05000010/19970251997-11-26026 November 1997 Insp Repts 50-010/97-25,50-237/97-25 & 50-249/97-25 on 971031.No Violations Noted.Major Areas Inspected:Procedures, Policies for Maintaining Exam Security During Development & Administration of Annual Licensed Operator Requalification IR 05000010/19970221997-11-0404 November 1997 Insp Repts 50-010/97-22,50-237/97-22 & 50-249/97-22 Between 971014 & 17.No Violations Noted.Major Areas Inspected: Plant Support,Which Reviewed & Evaluated Quality of Security Related Audits ML20212F7491997-10-30030 October 1997 NOV from Insp on 970915-1002.Violation Noted:Reactor Bldg Sample Panel Drain Valve Was Not Closed After Sample Was Collected IR 05000010/19970201997-10-30030 October 1997 Insp Repts 50-010/97-20,50-237/97-20 & 50-249/97-20 on 970915-1002.Violations Noted.Major Areas Inspected: Radiological Protection & Chemistry (Rp&C) Controls,Status of Pr&C Facilities & Equipment IR 05000010/19970111997-10-30030 October 1997 Errata to Insp Repts 50-010/97-11,50-237/97-11 & 50-249/97-11,correcting Unit 1 Spent Fuel Pool Monitoring Which Was Characterized as by Unit 2/3 Control Room Level Indicator to Unit 2/3 Operators ML20198N2981997-10-24024 October 1997 Notice of Violation from Insp on 970715-0827.Violation Noted:Corrective Actions Taken by Licensee Were Not Adequate to Preclude Repetition of Event Involving Inadequate Staffing of Control Room ML20198N3031997-10-24024 October 1997 Insp Repts 50-010/97-13,50-237/97-13 & 50-249/97-13 on 970715-0827.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000237/19970141997-10-0606 October 1997 Insp Repts 50-237/97-14 & 50-249/97-14 on 970819-22.No Violations Noted.Major Areas Inspected:Evaluation of Performance During Plant Biennial Exercise of Emergency Plan & Review of Previous Emergency Preparedness Open Items IR 05000237/19970161997-10-0202 October 1997 Insp Rept 50-237/97-16 on 970728-0801.No Violations Noted. Major Areas Inspected:Licensee Operations,Maint & Engineering IR 05000010/19970171997-10-0101 October 1997 Partially Withheld Insp Repts 50-010/97-17,50-237/97-17, & 50-249/97-17 on 970804-20 (Ref 10CFR73.71).Violations Noted.Major Areas Inspected:Review of Plant Support Activities Re Physical Security Protection of Facility IR 05000010/19970151997-09-15015 September 1997 Insp Repts 50-010/97-15,50-237/97-15 & 50-249/97-15 on 970722-0828.No Violations Noted.Major Areas Inspected: Solid Radioactive Waste Processing,Transportation & Portable & Area Radiation Monitor Test IR 05000010/19970121997-08-0808 August 1997 Insp Repts 50-010/97-12,50-237/97-12 & 50-249/97-12 on 970531-0714.No Violations Noted.Major Areas Inspected: Licensee Operations,Maintenance,Engineering & Plant Support ML20149K1811997-07-0101 July 1997 Notice of Violation from Insp on 970419-0530.Violation Noted:From 970108 Until 0527,conditions Adverse to Quality Were Not Promptly Corrected in That Licensee Did Not Correct Improper Storage of Boric Acid & Borax Staged ML20149K1851997-07-0101 July 1997 Insp Repts 50-010/97-09,50-237/97-09 & 50-249/97-09 on 970419-0530.Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support ML20148H8501997-06-0101 June 1997 Insp Repts 50-010/97-06,50-237/97-06 & 50-249/97-06 on 970308-0418.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support ML20148H8391997-06-0101 June 1997 Notice of Violation from Insp on 970308-0418.Violation Noted:On 970316,DVM Installed on safety-related Component (3A 24/48 Vdc Battery) W/O Approved Procedure or Engineering Approved Work Request IR 05000010/19970041997-05-0101 May 1997 Insp Repts 50-010/97-04,50-237/97-04 & 50-249/97-04 on 970125-0307.No Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support IR 05000010/19960161997-03-0303 March 1997 Insp Repts 50-010/96-16,50-237/96-16 & 50-249/96-16 on 961208-970124.No Violations Noted.Major Areas Inspected: Licensee Operation,Maint,Engineering & Plant Support PNO-III-97-014, on 970227,employee Exiting Plant Had Set Off Radiation Detector.Employee Hands Found to Have Low Levels of Contamination.Staff from Dresden Plant Interviewed Employee Re Work Activities to Determine Contamination1997-02-28028 February 1997 PNO-III-97-014:on 970227,employee Exiting Plant Had Set Off Radiation Detector.Employee Hands Found to Have Low Levels of Contamination.Staff from Dresden Plant Interviewed Employee Re Work Activities to Determine Contamination IR 05000237/19960011997-02-10010 February 1997 SALP 14 Repts 50-237/96-01 & 50-249/96-01 for Period 950319-961228 ML20134G1041997-02-0404 February 1997 Insp Repts 50-010/96-14,50-237/96-14 & 50-249/96-14 on 961021-1206.Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support ML20134G1021997-02-0404 February 1997 Notice of Violation from Insp on 961021-1206.Violation Noted:On 960529,new Emergency Diesel Generator Test Valve Technical Info Not Forwarded to VETIP Coordinator Nor Incorporated Into Controlled Manual IR 05000010/19960131996-12-31031 December 1996 Insp Repts 50-010/96-13,50-237/96-13 & 50-249/96-13 on 960901-1018.Violations Noted.Major Areas Inspected:Licensee Operational,Maint,Engineering & Plant Support Activities ML20129K3831996-11-14014 November 1996 Notice of Violation from Insp on 960708-1017.Violation Noted:Maint Procedure Des 6700-03,rev 7,dtd 960418, Insp & Maint of GE 4KV Magne-Blast Circuit Breakers Types AM4.76-250-OD, Activity Was Not Appropriate PNO-III-96-066, on 961026,3B Reactor Recirculation Pump motor-generator Tripped.Licensee Determined Recovery of Idle Loop Impossible W/O Plant Shutdown & Began Controlled Shutdown.Independent Insp Safety Team Onsite for Review1996-10-28028 October 1996 PNO-III-96-066:on 961026,3B Reactor Recirculation Pump motor-generator Tripped.Licensee Determined Recovery of Idle Loop Impossible W/O Plant Shutdown & Began Controlled Shutdown.Independent Insp Safety Team Onsite for Review IR 05000010/19960091996-10-16016 October 1996 Insp Repts 50-010/96-09,50-237/96-09 & 50-249/96-09 on 960713-0830.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support ML20129A2381996-10-13013 October 1996 Notice of Violation from Insp on 960713-0830.Violation Noted:Sro Whose License Had Been Amended to Prohibit Licensed Activities,Assigned to Regular Shift Duty in Control Room Prior to License Reactivation IR 05000010/19960111996-09-19019 September 1996 Partially Withheld Insp Repts 50-010/96-11,50-237/96-11 & 50-249/96-11 on 960731-0830 Ref 10CFR73.21.Violations Noted. Major Areas Inspected:Aspects of Plant Support Activities in Area of Physical Security IR 05000425/20060121995-07-12012 July 1995 Notice of Violation from Insp on 950425-0612.Violation Noted:Licensee Failed to Submit to Written Rept Describing Local Leak Rate Test Failures Which Exceeded TS Type B & C Leakage Limits During 1994 Unit 3 Refueling Outage IR 05000010/19950081995-07-12012 July 1995 Insp Repts 50-010/95-08,50-237/95-08 & 50-249/95-08 on 950425-0612.Violations Noted.Major Areas Inspected:Maint & Surveillance,Engineering & Technical Support,Plant Support, Plant Matl Condition & Quality Verification ML20062K2051993-12-0909 December 1993 Notice of Violation from Insp on 931020-1103.Violation Noted:As of 931103,measures Were Not Established to Assure That Deficiencies & Deviations Identified by Flour Quality Control Inspectors Were Corrected 1999-08-02 |
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y educ( Cu y f :.: &uj PRELIMINARY NOTIFICATION December 7, 1977 PRELIMINARY NOTIFICATION OF EVENT OR UNUS
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gQi POSSI3LE safety or public interest significance.This The information presented is as initially received without verification or evaluation and is basically all tha", is known by IE staff on this date. - _
Facility:
Commonwealth Edison Company,,Dresden Unit No. 3 (DN 50-249) Morris, Illinois
Subject:
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OFFGAS RELEASE DRESDEN UNIT NO. 3 E -
This report is being issued because of potential public interest .
Commonwealth Edison Company reported to RIII on ,December that 6, 1 the stack second for a releast pedod of rate 3 to 4for gross beta-gamma activity minutes. .
was 19 curi limi; is 1.0 curie /second. The Technical Specification l
the licensee Thetherelease occurred at 10:05 a.m. when rates. The high bypassed flow rates resulte augmented offgas system because of prevent a loss of condenser vacuum.d from the licensee's attempt to Specification requirements.a power reduction to reduce the r
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ma w The release is not considered an immed'iate health and. safety pr e i .. .
the.Dresden Station at 3:19 p.mRIII (Chicago) received noti i is considering issuing a press r. on December 6, 1977. RIII (Chicago) be notified. elease. The State of Illinois will
Contact:
GHBidinger IE x28188 LJCunningham, IE x28188 e.
' Distribution:- 9 ,
Chairman Hendrie Transmitted'H St // L5~
Comissioner Kennedy Commissione~r Bradford -
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Commissioner Gilinsky S. J. Chilk, SECY C. C. Kammerer, CA ,
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Transmitted: MNBBJ/'k7' L. V. Gossick EDO '
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E. G. Ca'se, NRR S. H. Hanauer., EDO. Region g ,l(',) V [
J. J. Fouchard, PA .
R. Hartfield, MIPC SSBldgdjj/ (MAIL)
I R. G. Ryan, OSP C. V. ' Snfi ;h, NMSS R. J. McTiernan, OIA l
H. K. Shapar, ELD R. Minogue SD PRELIMINARY NOTIFICATION
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