ML20248K009
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| ML20248K009 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/13/1978 |
| From: | Blackwood E, Klingler G, Whitt K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| References | |
| PNO-78-079, PNO-78-79, NUDOCS 9806090392 | |
| Download: ML20248K009 (1) | |
Similar Documents at Oconee | |
|---|---|
Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-II-97-065, on 971228,initiated Controlled Shutdown of Unit Due to Exceeding TS Leakage Limit of 150 Gpd.Licensee Continuing W/Plant Depressurization & Cooldown & Outage Planned of Several Days to Investigate & Repair SG1997-12-29029 December 1997
[Table view]PNO-II-97-065:on 971228,initiated Controlled Shutdown of Unit Due to Exceeding TS Leakage Limit of 150 Gpd.Licensee Continuing W/Plant Depressurization & Cooldown & Outage Planned of Several Days to Investigate & Repair SG PNO-II-97-034, on 970613,extended Shutdown to Meet CAL 2-97-03 Commitments to Shutdown Unit 1 No Later than 970614 & to Implement Actions Re HPI Sys.Nrc Resident Inspector Will Followup on Unit 1 Shutdown & Recovery Activities1997-06-13013 June 1997 PNO-II-97-034:on 970613,extended Shutdown to Meet CAL 2-97-03 Commitments to Shutdown Unit 1 No Later than 970614 & to Implement Actions Re HPI Sys.Nrc Resident Inspector Will Followup on Unit 1 Shutdown & Recovery Activities PNO-II-93-039, on 930823,reactor Trip Occurred Due to Loss of Power to Vital Panelboard.Investigation Team Dispatched to Site to Review Root Cause & Plant Response.State & Local Authorities Notified1993-08-24024 August 1993 PNO-II-93-039:on 930823,reactor Trip Occurred Due to Loss of Power to Vital Panelboard.Investigation Team Dispatched to Site to Review Root Cause & Plant Response.State & Local Authorities Notified PNO-II-92-070, on 921019,several Circuit Breakers Failed in 230KV Switchyard to Open Position for Unknown Reasons. Licensee Has Inititated Investigation to Review Event to Determine Cause & Determine Why Certain Equipment Failed1992-10-20020 October 1992 PNO-II-92-070:on 921019,several Circuit Breakers Failed in 230KV Switchyard to Open Position for Unknown Reasons. Licensee Has Inititated Investigation to Review Event to Determine Cause & Determine Why Certain Equipment Failed PNO-II-91-074B, on 911123,unit Remained in Cold Shutdown,Per Declaration of Alert at 0214 Due to Leak in Rcs.As of 911126,total of 7,800 Gallons of Treated Water Released from Plant to Lake Hartwell1991-11-26026 November 1991 PNO-II-91-074B:on 911123,unit Remained in Cold Shutdown,Per Declaration of Alert at 0214 Due to Leak in Rcs.As of 911126,total of 7,800 Gallons of Treated Water Released from Plant to Lake Hartwell PNO-II-90-070, on 901108,unit Commenced Controlled Shutdown from 60% Power Due to Tube Leak in Steam Generator a1990-11-0808 November 1990 PNO-II-90-070:on 901108,unit Commenced Controlled Shutdown from 60% Power Due to Tube Leak in Steam Generator a PNO-II-88-013, on 880211,two Workers Slightly Contaminated W/ Radioactive Water.Caused by Approx 1,000 Gallon Leak of Radioactive Water Occurring During Maint on Valve.Workers Showered to Remove Contamination1988-02-12012 February 1988 PNO-II-88-013:on 880211,two Workers Slightly Contaminated W/ Radioactive Water.Caused by Approx 1,000 Gallon Leak of Radioactive Water Occurring During Maint on Valve.Workers Showered to Remove Contamination PNO-II-86-092, on 861218,licensee Shut Down Unit to Begin Scheduled Refueling Outage 6 Wks Early.Caused by Excessive Vibrations in Reactor Coolant Pump 3B2.During Outage,Reactor Coolant Pumps 3B1,3B2 & 3A1 Will Be Modified1986-12-18018 December 1986 PNO-II-86-092:on 861218,licensee Shut Down Unit to Begin Scheduled Refueling Outage 6 Wks Early.Caused by Excessive Vibrations in Reactor Coolant Pump 3B2.During Outage,Reactor Coolant Pumps 3B1,3B2 & 3A1 Will Be Modified PNO-II-86-078, on 861021,2 Gallons of Hydrazine Spilled in Turbine Bldg.Caused by Leak in Deionized Water Mixing Valve Overflowing Mix Tank.Spill Cleaned Up1986-10-22022 October 1986 PNO-II-86-078:on 861021,2 Gallons of Hydrazine Spilled in Turbine Bldg.Caused by Leak in Deionized Water Mixing Valve Overflowing Mix Tank.Spill Cleaned Up PNO-II-86-069, on 861002,Units 1 & 2 Shut Down Due to Loss of Low Pressure Svc Water Pump Suction After Surveillance Test. Caused by Air Leakage in Pump Flange Seals.Leakage Areas Wrapped.All Units Shutdown Until Exact Cause Determined1986-10-0303 October 1986 PNO-II-86-069:on 861002,Units 1 & 2 Shut Down Due to Loss of Low Pressure Svc Water Pump Suction After Surveillance Test. Caused by Air Leakage in Pump Flange Seals.Leakage Areas Wrapped.All Units Shutdown Until Exact Cause Determined PNO-II-86-055, on 860806,plant Began Shutdown Due to Leak in Steam Generator a Tube Calculated at 0.26 Gallons Per Minute.Shutdown Expected to Last 10 Days1986-08-0707 August 1986 PNO-II-86-055:on 860806,plant Began Shutdown Due to Leak in Steam Generator a Tube Calculated at 0.26 Gallons Per Minute.Shutdown Expected to Last 10 Days PNO-II-86-036, on 860515,during Power Escalation Tests at 100% Power,Steam Generator Tube Leak Detected.Unit Out of Svc for 10 Days to Repair Leak1986-05-19019 May 1986 PNO-II-86-036:on 860515,during Power Escalation Tests at 100% Power,Steam Generator Tube Leak Detected.Unit Out of Svc for 10 Days to Repair Leak PNO-II-86-014, on 860213,mild Earthquake Felt at Site.Plant Turbine & Auxiliary Bldgs Surveyed & No Damage Found. Preliminary Review of Detection Equipment at Site Indicated No Evidence of Ground Movement or Tremor1986-02-13013 February 1986 PNO-II-86-014:on 860213,mild Earthquake Felt at Site.Plant Turbine & Auxiliary Bldgs Surveyed & No Damage Found. Preliminary Review of Detection Equipment at Site Indicated No Evidence of Ground Movement or Tremor PNO-II-85-111, on 851124,unscheduled Shutdown Greater than 48 H Anticipated.Caused by Failure of High Pressure Turbine Bearing.Outage of at Least 8 Days Expected for Evaluation & Repairs1985-11-25025 November 1985 PNO-II-85-111:on 851124,unscheduled Shutdown Greater than 48 H Anticipated.Caused by Failure of High Pressure Turbine Bearing.Outage of at Least 8 Days Expected for Evaluation & Repairs PNO-II-85-107, on 851107,plant Taken out-of-svc After Verification of Turbine High Bearing Temp.Caused by Main Turbine Bearing Failure.Plant Expected to Be Shut Down for 5 to 14 Days for Repairs1985-11-0707 November 1985 PNO-II-85-107:on 851107,plant Taken out-of-svc After Verification of Turbine High Bearing Temp.Caused by Main Turbine Bearing Failure.Plant Expected to Be Shut Down for 5 to 14 Days for Repairs PNO-II-85-094, on 851007,unit Shut Down Due to Steam Generator Tube Leak.Leakage Amounted to 0.15 Gallon Per Minute & Increasing.Generator Isolated.Shutdown Expected for 10-12 Days1985-10-0808 October 1985 PNO-II-85-094:on 851007,unit Shut Down Due to Steam Generator Tube Leak.Leakage Amounted to 0.15 Gallon Per Minute & Increasing.Generator Isolated.Shutdown Expected for 10-12 Days PNO-II-85-068, on 850721,two Threatening Telecons Received by Switchboard & Another Call Received on Telephone Answering Machine in Ofc of NRC Resident Inspector.Security Contingency Plan Implemented & Agencies Informed1985-07-22022 July 1985 PNO-II-85-068:on 850721,two Threatening Telecons Received by Switchboard & Another Call Received on Telephone Answering Machine in Ofc of NRC Resident Inspector.Security Contingency Plan Implemented & Agencies Informed PNO-II-85-065, on 850708,routine Receipt Survey Identified Four Smears on Exterior of Empty NAC-1 Fuel Shipping Cask from Nuclear Assurance Corp in Excess of Max Permissible Limits.Measured Levels Posed No Threat to Public Safety1985-07-0909 July 1985 PNO-II-85-065:on 850708,routine Receipt Survey Identified Four Smears on Exterior of Empty NAC-1 Fuel Shipping Cask from Nuclear Assurance Corp in Excess of Max Permissible Limits.Measured Levels Posed No Threat to Public Safety PNO-II-85-058, on 850607,licensee Reported That Individual Received Radiation Overdose to Small Area of Skin on Underarm.Caused by Particle Transfer from Protective Clothing.Person Decontaminated1985-06-0707 June 1985 PNO-II-85-058:on 850607,licensee Reported That Individual Received Radiation Overdose to Small Area of Skin on Underarm.Caused by Particle Transfer from Protective Clothing.Person Decontaminated PNO-II-85-043, on 850425,most Control Room Annunciators Lost Due to Failure of Inverter Power Supply.Possibly Caused by Blown Fuse.One Feedwater Pump Restored to Operation1985-04-25025 April 1985 PNO-II-85-043:on 850425,most Control Room Annunciators Lost Due to Failure of Inverter Power Supply.Possibly Caused by Blown Fuse.One Feedwater Pump Restored to Operation ML20054L5211982-06-29029 June 1982 Updated PNO-II-82-072A:on 820628,break Occurred in Outside Radius of Elbow 24-inch Line Which Branches Off 42-inch High Pressure Turbine Exhaust.Apparently Caused by Thinning from Steam Erosion PNO-II-82-072, on 820628,at 95% Power,High Pressure Turbine Extraction Steam Line Break Resulted in Release of Steam to Turbine Bldg Basement.Three Workers Reported Injured by Steam.Reactor Manually Shut Down & Placed in Hot Standby1982-06-28028 June 1982 PNO-II-82-072:on 820628,at 95% Power,High Pressure Turbine Extraction Steam Line Break Resulted in Release of Steam to Turbine Bldg Basement.Three Workers Reported Injured by Steam.Reactor Manually Shut Down & Placed in Hot Standby PNO-II-82-065, visual & Ultrasonic Exams Revealed Cracks in 51 of 96 Thermal Shield Bolts.Removal of Bolts & Associated Locking Clips Revealed 19 of 27 Bolt Heads Broken.Bolts Will Be Replaced W/Stud & Nut Assemblies1982-06-11011 June 1982 PNO-II-82-065:visual & Ultrasonic Exams Revealed Cracks in 51 of 96 Thermal Shield Bolts.Removal of Bolts & Associated Locking Clips Revealed 19 of 27 Bolt Heads Broken.Bolts Will Be Replaced W/Stud & Nut Assemblies PNO-II-81-002, on 810107,two of Three Individuals Found to Have Nasal Contamination (3200 Dpm Max) Following Maint on Control Rod Drive Mechanisms in Reactor Bldg.Workers Nostrils Decontaminated.Whole Body Counts Performed1981-01-0707 January 1981 PNO-II-81-002:on 810107,two of Three Individuals Found to Have Nasal Contamination (3200 Dpm Max) Following Maint on Control Rod Drive Mechanisms in Reactor Bldg.Workers Nostrils Decontaminated.Whole Body Counts Performed PNO-II-80-150, on 801013,during Routine Check of Unit 2 Containment Purge Valve 5,purge Path Opened to Environ for 46 S.Caused by Failure to Follow Procedures in Proper Sequence.No Tech Spec Limits Exceeded.State of Sc Informed1980-10-14014 October 1980 PNO-II-80-150:on 801013,during Routine Check of Unit 2 Containment Purge Valve 5,purge Path Opened to Environ for 46 S.Caused by Failure to Follow Procedures in Proper Sequence.No Tech Spec Limits Exceeded.State of Sc Informed ML20249A2051978-11-0808 November 1978 PNS-78-054:on 781106,NRC Region II Received Telephone Call from Security Guard Re Security Guard Training at Oconee.On 781107,NRC Investigators Met W/Group of Former & Present Guards Who Alleged Inadequate Training.Media Informed ML20216J5881978-08-0404 August 1978 PNO-78-141:on 780804,licensee Reported That Chemical Anaylsis of Reactor Vessel Weld Matl Performed by B&W Revealed That Silicon & Nickel Content Differed from That Specified ML20216J6071978-08-0404 August 1978 PNO-78-140:on 780803,employee at Plant Passed Out from Heat Exhaustion After Exiting Unit 1 Containment.Worker Was Treated,Released & Returned to Work Later That Day.No Injury Due to Radiation or Radioactive Contamination Occurred ML20248H8611978-05-0505 May 1978 PNO-78-102:on 780504,while RCS Was Open to Atmosphere, 50,000 Gallons of Reactor Coolant Overflowed Onto Containment Building Floor.Licensee Reported No Release of Radioactivity.State of South Carolina Notified ML20248H6111978-04-24024 April 1978 PN0-78-090:on 980421,Unit 1 Shutdown Commenced Due to SG Tube Leak.Unit 1 Will Be Placed in Cold Shutdown Condition, Portion of RCS Drained & SG Leak Tested to Identify Leaking Tubes for Repair.Estimated Duration of 2 Weeks for Shutdown ML20248L0291978-04-20020 April 1978 PNO-78-079B:supplements PNO 78-79A Dtd 780414.Informs That Addl Analyses Being Conducted by B&W.Licensee Reported That Operators Have Been Stationed at HPI Crossover Piping to Promptly Realign Sys for 2 Flow Paths Upon Break Detection ML20248K9841978-04-14014 April 1978 PNO-78-079A:supplements & Corrects Preliminary Info Provided in PNO-78-79 .Reanalysis Assumed Pipe Break of .04 Square Feet in RCP Discharge Piping.Region II Received Updated Info on 980413 & State of South Carolina Notified ML20248K0091978-04-13013 April 1978 PNO-78-079:licensee Reported That B&W Identified Error in Safety Analysis for Small Break in Rcs.Original Safety Analysis Was Done W/Small Break Occurring on Pump Discharge Line.State of Sc Notified ML20207G4181977-12-0505 December 1977 PNO-77-217:on 771205,following Refueling of Unit 3 & During Startup Physics Testing of Reloaded Core on 771204,core Power Distribution Measurements Revealed Seven Percent Flux Tilt at twenty-five Percent Power ML20207G8131977-11-0404 November 1977 PNO-77-193:on 771103,due to an Apparent SG Tube Leak of Approx 1.0 Gallon Per Minute (Gpm) Unit Was Shutdown ML20207G6351977-10-25025 October 1977 PNO-77-189:on 771016,following Refueling of Unit 1 & During Startup Physics Testing of Reloaded Core,Measured Values for Ejected Rod Worth Showed an Unexpected Reduction from Predicted Values ML20151X7081977-10-11011 October 1977 PNO-77-178:on 771007,unit Shutdown Commenced Due to SG Tube Leak of Approx 0.2 Gpm.Unit to Be Placed in Cold Shutdown for Approx 2 Wks While Repairs Conducted.Press & State of Sc Notified ML20151X4151977-09-0101 September 1977 PNO-77-152:film Badge Dosimeters Provided & Used by Five Contract Workers from Todd Shipyards,Galveston,Tx at Oconee Nuclear Station Indicated High Exposures Ranging from 1.3 Rems to 55 Rems ML20151Y1631977-07-15015 July 1977 PNO-77-129:on 770714,Unit Shutdown Was Commenced Due to Apparent SG Tube Leak.Unit Will Be Placed in Cold Shutdown Condition,Portion of RCS Will Be Drained & SG Will Be Leak Tested to Identify Leaking Tubes for Repair ML20151V2051977-05-12012 May 1977 PNO-77-083:on 770511,unplanned Release of Radioactivity in Liquid Occurred.Plant Personnel Investigating to Determine Cause.Monitoring of Turbine Bldg Sump & Yard Drainage Sys Continuing ML20236K9341977-02-0202 February 1977 PNO-77-019:on 770117,during SG Repair Activities,About 8,000 Gallons of Secondary Sys Water Was Inadvertently Released to Turbine Building Sumps ML20236X0371975-12-23023 December 1975 PN-75-155:on 751223,licensee Called Region II to Rept That Telephone Call Received from Man in Spartanburg,Sc Re Bomb Placed in Plant ML20236U2251975-06-13013 June 1975 PN-75-036:on 750613,DPC Notified Region II That Following Turbine Trip,Primary Sys Pressure Increased Where Primary Sys Electromatic Rv Opened to Reduce Pressure.Rv Stuck in Open Position & Pressure Reduced in 30 Minutes 1997-06-13 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARPNO-II-97-065, on 971228,initiated Controlled Shutdown of Unit Due to Exceeding TS Leakage Limit of 150 Gpd.Licensee Continuing W/Plant Depressurization & Cooldown & Outage Planned of Several Days to Investigate & Repair SG1997-12-29029 December 1997
[Table view]PNO-II-97-065:on 971228,initiated Controlled Shutdown of Unit Due to Exceeding TS Leakage Limit of 150 Gpd.Licensee Continuing W/Plant Depressurization & Cooldown & Outage Planned of Several Days to Investigate & Repair SG ML20211K9431997-09-26026 September 1997 Notice of Violation from Insp on 970721-26.Violation Noted: Licensee Failed to Follow Procedures for Security Badges & Access Control of Facility ML20210S0391997-08-27027 August 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000.Violation Noted:Between 970501-02,w/ Fuel in Oconee Unit 3 Core & RCS Temp Greater than 350 F, Licensee Failed to Maintain HPI Sys Operable as Required PNO-II-97-034, on 970613,extended Shutdown to Meet CAL 2-97-03 Commitments to Shutdown Unit 1 No Later than 970614 & to Implement Actions Re HPI Sys.Nrc Resident Inspector Will Followup on Unit 1 Shutdown & Recovery Activities1997-06-13013 June 1997 PNO-II-97-034:on 970613,extended Shutdown to Meet CAL 2-97-03 Commitments to Shutdown Unit 1 No Later than 970614 & to Implement Actions Re HPI Sys.Nrc Resident Inspector Will Followup on Unit 1 Shutdown & Recovery Activities IR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts PNO-II-93-039, on 930823,reactor Trip Occurred Due to Loss of Power to Vital Panelboard.Investigation Team Dispatched to Site to Review Root Cause & Plant Response.State & Local Authorities Notified1993-08-24024 August 1993 PNO-II-93-039:on 930823,reactor Trip Occurred Due to Loss of Power to Vital Panelboard.Investigation Team Dispatched to Site to Review Root Cause & Plant Response.State & Local Authorities Notified IR 05000269/19930061993-03-22022 March 1993 Partially Withheld Insp Repts 50-269/93-06,50-270/93-06 & 50-287/93-06 on 930222-25 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Licensee Physical Security Program for Power Reactors IR 05000269/19930011993-02-0101 February 1993 Safeguards Insp Repts 50-269/93-01,50-270/93-01 & 50-287/93-01 on 930104-07.No Violations Noted.Major Areas Inspected:Physical Security Program.Details Withheld (Ref 10CFR73.21) IR 05000269/19920251992-12-0303 December 1992 Insp Repts 50-269/92-25,50-270/92-25 & 50-287/92-25 on 921102-06.No Violations or Deviations Noted.Major Areas Inspected:Physical Security Program for Power Reactors, Audits,Protected & Vital Area Barriers.Details Withheld PNO-II-92-070, on 921019,several Circuit Breakers Failed in 230KV Switchyard to Open Position for Unknown Reasons. Licensee Has Inititated Investigation to Review Event to Determine Cause & Determine Why Certain Equipment Failed1992-10-20020 October 1992 PNO-II-92-070:on 921019,several Circuit Breakers Failed in 230KV Switchyard to Open Position for Unknown Reasons. Licensee Has Inititated Investigation to Review Event to Determine Cause & Determine Why Certain Equipment Failed PNO-II-91-074B, on 911123,unit Remained in Cold Shutdown,Per Declaration of Alert at 0214 Due to Leak in Rcs.As of 911126,total of 7,800 Gallons of Treated Water Released from Plant to Lake Hartwell1991-11-26026 November 1991 PNO-II-91-074B:on 911123,unit Remained in Cold Shutdown,Per Declaration of Alert at 0214 Due to Leak in Rcs.As of 911126,total of 7,800 Gallons of Treated Water Released from Plant to Lake Hartwell ML20134D2581991-06-0404 June 1991 Notice of Violation from Insp on 910312-15.Violations Noted:Station Was Not Maintained According to Main Procedure MP/0/A/1800/105,Section 6.5,which Clearly Identified That Flange Was to Be Installed on Valve 3LP19 IR 05000269/19910081991-04-10010 April 1991 Insp Repts 50-269/91-08,50-270/91-08 & 50-287/91-08 on 910312-15.violations Noted.Major Areas Inspected:Maint, Control Room Operation,Planning & Scheduling Activities, Training & Procedures,Plant Physical Condition & Mgmt PNO-II-90-070, on 901108,unit Commenced Controlled Shutdown from 60% Power Due to Tube Leak in Steam Generator a1990-11-0808 November 1990 PNO-II-90-070:on 901108,unit Commenced Controlled Shutdown from 60% Power Due to Tube Leak in Steam Generator a IR 05000269/19900321990-11-0505 November 1990 Partially Withheld Insp Repts 50-269/90-32,50-270/90-32 & 50-287/90-32 on 901015-19.No Violations Noted.Major Areas Inspected:Physical Security Program Plans,Mgt Support, Security Program Plans & Protected & Vital Area Barriers IR 05000269/19900241990-10-0202 October 1990 SALP Repts 50-269/90-24,50-270/90-24,50-287/90-24 & 72-0004/90-24 for Feb 1989 - Jul 1990 IR 05000269/19900221990-07-24024 July 1990 Partially Withheld Safeguard Insp Repts 50-269/90-22, 5-270/90-22 & 50-287/90-22 on 900625-29.No Violations or Deviation Noted.Major Areas Inspected:Core Insp Program for Power Reactors & Safeguards Contingency Plan Implementation IR 05000269/19900181990-06-21021 June 1990 Partially Withheld Insp Repts 50-269/90-18,50-270/90-18 & 50-287/90-18 on 900604-08 (Ref 10CFR2.790 & 73.21).No Violations Noted.Major Areas Inspected:Security Program Audit,Detection & Assessment Aids & Key Control IR 05000269/19890201989-07-25025 July 1989 Partially Withheld Insp Repts 50-269/89-20,50-270/89-20 & 50-287/89-20 on 890626-30 (Ref 10CFR2.790.(d) & 73.21). Violations Noted.Major Areas Inspected:Physical Security Program for Power Reactors & Security Audit IR 05000269/19890101989-05-19019 May 1989 Partially Withheld Insp Repts 50-269/89-10,50-270/89-10 & 50-287/89-10 on 890410-14 (Ref 10CFR2.790 & 73.21). Violations Noted.Major Areas Inspected:Mgt Support,Security Program Plans & Audits & Protected & Vital Area Barriers IR 05000269/19890091989-04-10010 April 1989 Insp Repts 50-269/89-09,50-270/89-09 & 50-287/89-09 on 890306-10.No Violations Noted.Weaknesses Noted Re Data Base Used to Prepare computer-generated Work Requests.Major Areas Inspected:Design Control,Mods & Open Items IR 05000269/19890071989-03-10010 March 1989 Insp Repts 50-269/89-07,50-270/89-07 & 50-287/89-07 on 890213-17.Deviation Noted.Major Areas Inspected:Conformance to Reg Guide 1.97 Re Instrumentation for light-water-cooled Plants to Assess Conditions During & Following Accident IR 05000269/19880051988-03-21021 March 1988 Insp Repts 50-269/88-05,50-270/88-05 & 50-287/88-05 on 880217-0316.No Violations Noted.Major Areas Inspected:Maint, Operations,Surveillance,Physical Security & Design Changes PNO-II-88-013, on 880211,two Workers Slightly Contaminated W/ Radioactive Water.Caused by Approx 1,000 Gallon Leak of Radioactive Water Occurring During Maint on Valve.Workers Showered to Remove Contamination1988-02-12012 February 1988 PNO-II-88-013:on 880211,two Workers Slightly Contaminated W/ Radioactive Water.Caused by Approx 1,000 Gallon Leak of Radioactive Water Occurring During Maint on Valve.Workers Showered to Remove Contamination ML20237B2261987-12-15015 December 1987 EN-87-017A:informs That 870309 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Withdrawn Due to Determination That Violation Did Not Occur. Violation Based on Failure of Emergency Feedwater Pumps ML20235T5821987-09-18018 September 1987 Exam Rept 50-269/OL-87-02 on 870713-23.Exam Results:Seven of Ten Reactor Operator (RO) & Eight of Nine Senior Reactor Operator (SRO) Candidates Passed Written Exam.All RO & SRO Candidates Passed Operating Exam ML20238F7081987-09-0909 September 1987 Exam Rept 50-269/OL-87-01 for Units 1,2 & 3 on 870713-17. Exam results:7 of 10 Reactor Operators & 3 of 6 Senior Reactor Operators Passed ML20236E5111987-07-14014 July 1987 EN-86-056:on 870717,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Will Be Issued to Licensee.Action Based on Failure to Properly Implement Startup Procedure Causing Trains to Fail IR 05000269/19870091987-03-17017 March 1987 Insp Repts 50-269/87-09,50-270/87-09 & 50-287/87-09 on 870209-13.No Violations Noted.Major Areas Inspected:Onsite Review of Liquid & Gaseous Radwaste Programs & Review of TMI Action Items II.B.3 & II.F.1.2 IR 05000269/19870101987-03-17017 March 1987 Insp Repts 50-269/87-10,50-270/87-10 & 50-287/87-10 on 870210-0309.No Violations or Deviations Noted.Major Areas Inspected:Areas of Operations,Surveillance,Maint,Followup of Events & Verification of ESF Lineups ML20207T5431987-03-12012 March 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Noncompliance Noted:Measures Not Established to Assure That Regulatory Requirements & Design Bases Correctly Translated Into Specs,Drawings & Procedures IR 05000269/19870061987-03-0909 March 1987 Insp Repts 50-269/87-06,50-270/87-06 & 50-287/87-06 on 870126-30.No Violations or Deviations Noted.Major Areas Inspected:Inservice Insp,Ongoing Repairs in Reactor Coolant Pumps & Maint & Welding Activities ML20207R4851987-03-0909 March 1987 EN-87-017:on 870312,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Will Be Issued to Util Based on Failure to Provide Adequate Design Control to Ensure Emergency Feedwater Pump Operability IR 05000269/19870041987-02-17017 February 1987 Insp Repts 50-269/87-04,50-270/87-04 & 50-287/87-04 on 870113-0209.No Violation or Deviation Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Linups,Followup of Events & Shutdown Work in Progress IR 05000269/19870021987-02-11011 February 1987 Partially Withheld Insp Repts 50-269/87-02,50-270/87-02 & 50-287/87-02 on 870126-30 (Ref 10CFR2.790).Violation Noted Re Inadequate App R Circuit Analysis ML20211A4991987-02-11011 February 1987 Notice of Violation from Insps on 870112-16 IR 05000269/19870031987-02-10010 February 1987 Insp Repts 50-269/87-03,50-270/87-03 & 50-287/87-03 on 870112-16.Violation Noted:Failure to Adequately Evaluate Radiological Hazards ML20210U3211987-02-0505 February 1987 Notice of Violation from Insp on 861015-1110.Violation Noted:For Periods in 1978,1981 & 1986 When Lake Keowee Elevation Less than 792 Ft,Emergency Condenser Cooling Water Sys Inoperable & Unable to Provide Sustained Siphon Flow IR 05000269/19870071987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-07,50-270/87-07 & 50-287/87-07 on 861222.Major Areas Discussed:Sequence of Events & Corrective Actions Re Emergency Condenser Circulating Water Sys Degradation IR 05000269/19870081987-02-0505 February 1987 Enforcement Conference Repts 50-269/87-08,50-270/87-08 & 50-287/87-08 on 861222.Major Areas Discussed:Safety Sys Functional Insp & Associated Safety Implications IR 05000269/19860341987-02-0505 February 1987 Corrected Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.Insp Erroneously Reported as Having Been Conducted on 861111-0112 ML20211A0871987-02-0303 February 1987 Notice of Violation from Insp on 870105-08 IR 05000269/19870011987-01-30030 January 1987 Insp Repts 50-269/87-01,50-270/87-01 & 50-287/87-01 on 870105-08.Violation Noted:Failure to Provide Procedures W/Appropriate Qualitative or Quantitative Acceptance Criteria for Activities Important to Safety ML20211A0061987-01-23023 January 1987 Insp Repts 50-269/86-34,50-270/86-34 & 50-287/86-34 on 861111-870112.No Violations or Deviations Noted.Major Areas Inspected:Operations,Surveillance,Maint,Verification of ESF Lineups & Emergency Drills ML20210U9961987-01-22022 January 1987 Exam Rept 50-269/OL-86-03 on 861215.Exam Results:Two Reactor Operator Candidates Passed Written Reexam.Written Exam Questions & Answer Key Encl IR 05000269/19860351987-01-0707 January 1987 Insp Repts 50-269/86-35,50-270/86-35 & 50-287/86-35 on 861208-12.No Violations or Deviations Noted.Major Areas Inspected:Radiation Protection Program,Including Review of Organization & Mgt of Health Physics Staff ML20212F5511986-12-24024 December 1986 Notice of Violation from Insp on 861103-12 PNO-II-86-092, on 861218,licensee Shut Down Unit to Begin Scheduled Refueling Outage 6 Wks Early.Caused by Excessive Vibrations in Reactor Coolant Pump 3B2.During Outage,Reactor Coolant Pumps 3B1,3B2 & 3A1 Will Be Modified1986-12-18018 December 1986 PNO-II-86-092:on 861218,licensee Shut Down Unit to Begin Scheduled Refueling Outage 6 Wks Early.Caused by Excessive Vibrations in Reactor Coolant Pump 3B2.During Outage,Reactor Coolant Pumps 3B1,3B2 & 3A1 Will Be Modified IR 05000269/19860321986-12-10010 December 1986 Insp Repts 50-413/86-44,50-414/86-47,50-369/86-32, 50-370/86-32,50-269/86-32,50-270/86-32 & 50-287/86-32 on 861103-12.Violations Noted:Failure to Follow Procedures for Radiological Sample Analyses & Inadequate Surveys IR 05000269/19860281986-11-0303 November 1986 Partially Withheld Physical Security Insp Repts 50-269/86-28,50-270/86-28 & 50-287/86-28 on 861014-17 (Ref 10CFR2.790 & 73.21).Violation Noted:Inadequate Protected Area Barrier 1997-09-26 |
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_(wyl PRELIMINARY NOTIFICATION [ ,
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April 13, 1978 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE -- PNO-78-79 This preliminary notification constitutes EARLY notice of an event of POSSIBLE safety or Dublic interest significance. The information '
presented is as initially received without verification or evaluation and is basically all that is known by IE staff as of this date.
FACILITY: Duke Power Company Oconee, Unit Nos. 1, 2 and 3 DNS 50-269, 50-270 and 50-287 Oconee County, South Carolina p.
SUBJECT:
ERROR IN SMALL BREAK ANALYSIS OF REACTOR COOLANT SYSTEM The licensee reported that B&W identified an error in the safety analysis for a small break (up to 0.04 square feet) in the Reactor Coolant system !
(RCS). The reanalysis reveals that one train of the High Pressure Injection system is incapable of supplying sufficient flow tq maintain the water level in the reactor vessel above the core, if the small break , ;,gg
~,- occurs on the reactor coolant pump suction line. The original safety i ~~
analysis was done with the small break occurring on the pump discharge
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line. In the identified break, the P.CS pressure could remain above the #
Low Pressure Injection and core flood actuation pressures. The problem, /
which is being evaluated by NRR, is reported to be generic to all B&W facilities. [3 There has been no media interest to date. A news release is not planned by the licensee or NRC. The State of South Carolina has been notified.
Region II (Atlanta) received notification of this occurrence by telephone from station management at 10:00 p.m. on April 12. This information is current as of 10:00 a.m. on April 13.
Contact:
GRKlingler, IE x28019 EBBlackwood, IE x28019 KWhitt, X28019 Distribution: Transmitted H St/** N Chairman Hendrie Commissioner Bradford Commissioner Kennedy S. J. Chilk, SECY C. C. Kammerer, CA ,
(for Distribution) l Transmitted: Commissioner MNBB Gilinsky/.*bj P Bldg /.' E. Volgenau / l L. V. Gossick, EDO E. G. Case, NRR Region.~2T IE>M\ "
l S. H. Hanauer, EDO J. J. Fouchard, PA SS Bldg g.id D/' (MAIL 1 R. Hartfield, MIPC C. V. Smith, NMSS T. J. McTiernan, DIA R. G. Ryan, OSP R. Minogue, SD H. K. Shapar, ELD
- i t !
PRELIMINARY NOTIFICATION
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