Ro:On 730423,water Spill from Refueling Water Storage Tank to Storm Drainage Sys.Caused by Inadequate Procedures & Personnel Error.Plant Mgt Will Review Methods & Have Cautioned Operators to Exercise Extreme CautionML19317D468 |
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Oconee, Robinson ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
05/01/1973 |
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From: |
Utley E CAROLINA POWER & LIGHT CO. |
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Shared Package |
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ML19317D464 |
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References |
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NUDOCS 7912030369 |
Download: ML19317D468 (4) |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20042F3541990-04-30030 April 1990 Special Rept Re Failure to Prevent Performance Degradation of Reactor Bldg Cooling Units.Caused by Mgt Deficiency & Inadequate Program.Cooling Unit Declared Inoperable & Removed from Svc for Cleaning & Placed Back in Operation ML20024C1271983-07-0101 July 1983 Ro:On 830623,visual Insp Revealed Three Broken Holddown Springs.Investigation Incomplete.Ro 269/83-13 Will Be Submitted by 830721 ML20024C4181983-07-0101 July 1983 Ro:On 830525,fire Barrier Penetrations Found Nonfunctional. Caused by Design Deficiency.Fire Watch Posted,Penetrations Repaired & Procedures Revised ML20024C4141983-06-29029 June 1983 Ro:On 830509 & 12,fire Barrier Smoke Exhaust Penetrations 3-K-5-2,3-C-5-3 & 4 Found W/O Seal & 3-C-5-3 Did Not Have Fusible Damper,Respectively.Caused by Inadequate Info & Insufficient Guidance Provided by Design Engineering ML20023B6511983-04-29029 April 1983 ROs 269/83-10 & 287/83-04 Re 821212 & 830303 Loss of Containment Integrity.Mgt Audit in Progress.Summary List of Completed & Remaining Activities,W/Projected Completion Dates,Encl ML20028F3931983-01-19019 January 1983 Ro:On 821220,reactor Trip Circuit Breaker a Failed to Trip When Trip Signal Initiated.Caused by Sticking Undervoltage Relay.Relay Replaced.Contacts Cleaned ML20027B8581982-09-21021 September 1982 Ro:Advising That 820820 Occurrence Involving Loss of Electric Power to Valve CCW-8 Determined Not Reportable. Operability of Valve Demonstrated.No Further Action Required ML20027B7691982-09-16016 September 1982 RO 269/82-14:investigation Re Reactor Bldg Penetrations That May Not Have Been Leak Rate Tested Incomplete.Rept to Be Submitted by 820930 ML20052A3291982-04-0909 April 1982 Informs That Review Per RO-269/82-07 Has Determined That Plant Design & Const Predate Std Re Westinghouse SAI-1 Type Relays Not Meeting Full Surge Requirements ML20052A4261982-04-0202 April 1982 RO 269/82-06:on 820306,steam Generator 1B Indicated Tube Leak of 0.08 Gpm.Incident Under Investigation.Next Rept Expected by 820416 ML20050A9751982-03-12012 March 1982 RO 287/82-04:on 820226,3A2 HPI Normal Makeup Nozzle Found to Have Broken Thermal Sleeve Tack Welds.Investigation Revealed Cracks in Safe End & Upstream Piping.Next Rept Expected by 820409 ML20049J5541982-02-25025 February 1982 Ro:Advising of Delay Until 820311 to Provide Complete Rept of RO-281/82-03 Re Steam Generator Tube Leak ML20040F7611982-02-0505 February 1982 Ro:On 820122,during Visual Insp of Core Barrel Assembly, Thermal Shield & Shock Pad Bolts Found Broken & Shock Pad Was Skewed.Thermal Shock Bolts to Be Replaced.Loosened Shock Pad Evaluation Underway ML20040E6871982-01-28028 January 1982 RO 269/81-50:on 811229,reactor Bldg Cooling Unit C Declared Inoperable Due to Inability to Open Discharge Valve 1LPSW-24.Investigation & Rept Expected to Be Completed by 820211 ML20040C8421982-01-0808 January 1982 Suppl 3 to RO 269/81-11:re Broken Lower Thermal Shield Bolts.Caused by Intergranular Stress Corrosion Cracking in Region of Pronounced Microstructure Transition at head-to-shank Fillet.Bolts Replaced.Drawings Encl ML20039F6081981-12-28028 December 1981 Ro:On 811228,review of Info Re Reactor Vessel Matl Surveillance Program Revealed Calculational Error in Analyses Used to Update Heatup & Cooldown Curves.Unrevised Tech Spec Figures 3.1-1 & 3.1-2 Remain Conservative ML20038B5001981-12-0303 December 1981 Ro:On 811201,pressurizer Block Valves Found to Not Meet Design Specs of Closing Against Design Pressure.Caused by Undersized Motor Operator Which Will Not Develop Sufficient Torque to Shut Block Valve ML20038C7961981-12-0202 December 1981 Ro:On 811201,discovered Pressurizer Block Valves Did Not Meet Design Spec in That They May Not Close Against Design Pressure.Caused by Undersized Limitorque Operator Model SMB-000-5 ML20011A7231981-10-21021 October 1981 Ro:On 811019,four Liquid Waste Releases Were Made W/O Adequate Sampling.Caused by Failure to Make Change to Sample Point.Procedure Revised to Specify Correct Sampling Point for Sys Configuration ML20010F6791981-09-0404 September 1981 RO 270/81-14:on 810821,2A1 Reactor Coolant Pump Electrical Penetration Was Discovered Depressurized & Could Not Be Repressurized w/SF6 Gas.Cause Not Stated.Investigation & Complete Rept Will Be Sent by 810918 ML20038C8171981-08-25025 August 1981 Ro:On 810814,tritium Concentrations in Downstream Water Samples Exceeded Tech Spec Control Level for Second Quarter of 1981.Analysis of Max Dose Estimates Concluded That Concentrations Will Not Adversely Affect Public Health ML20010A8721981-08-0505 August 1981 RO 269/81-11,Suppl 1:on 810715,core Barrel Assembly Thermal Shield Bolts Found Broken.Cause Not Stated.Search for Loose Parts Turned Up All Missing Thermal Shield Parts Except for One Thermal Shield Bolt Head.Investigation Continuing ML20009H6891981-07-30030 July 1981 Nonroutine 30-day Rept:On 810623,fire Door 5 Opened to Relieve Excessive Heat from Auxiliary Feedwater Pump Room. Heat Caused by Backleakage Combined W/Hot Temp & Lack of Ventilation.Repairs Scheduled for Fall Refueling Outage ML20009E7351981-07-28028 July 1981 Ro:On 810717,fire Suppression Water Sys Found Inoperable. Caused by Open Main Control Source Breakers.Breakers Closed & Sys Successfully Tested ML20009H5771981-07-22022 July 1981 Ro:On 810608,fire Barrier Penetration Fire Seals Found in Nonconformance W/Approved Configuration Requirements. Deficiencies Occurred During Mod 445-N Implementation.Seals Will Be Repaired During Refueling Outage ML20038C8031981-07-0606 July 1981 Ro:On 810210,radioactivity Levels of Aquatic Vegetation Samples Exceeded Control Level by Greater than 50 Times.Info Supersedes 810225 Submittal ML20009F4311981-07-0101 July 1981 Ro:On 810630,during Performance of Normal Power Procedure, Backup Function of Units Isolating & Transfer Diodes on 125 Volt Dc Instrumentation & Control Sys Was Observed. Proposed Tech Spec Change Will Be Submitted ML20009H2701981-04-0101 April 1981 RO:810319 Determination Declaring Portions of Low Power Injection Sys Seismically Inoperable Was Premature.Hanger Noncomformance Repaired within 48-h Per IE Bulletin 79-14. Item Not Reportable Per Tech Spec 6.6.2.1a(9) ML20005A8771981-02-25025 February 1981 Ro:On 810219 Analytical Results of Aquatic Vegetation Samples Collected on 810210 Indicated That Radioactivity Levels Exceeded Tech Specs.Cause Not Stated ML19341B2741981-01-15015 January 1981 Ro:On 810114,both Channels of Heat Trace for Both Boric Acid Transfer Pumps Determined Inoperable in Violation of Tech Spec 3.2.3.C.Caused by Misleading Step in Procedure for Taking Pump Out of Svc ML18004B9871979-08-30030 August 1979 Ro:On 790829,svc Water Booster Pump a Tripped When Svc Water Booster Pump B Was Stopped,In Violation of Tech Specs 3.3.4.1.a.Power Reduction Initiated & Svc Water Booster Pumps Returned to Svc ML19282D0291979-01-15015 January 1979 RO 269/7827 on 781214:on 781213,reactor Coolant Temp Became Erratic.Feedwater Problem Resulted from Operation of One or More Feedwater Valves.Power Cords Have Been Fitted ML19263C9841978-11-30030 November 1978 RO 270/78-12 on 781105:stop Check Valve from 2AHPI Pump to 2A12C Pump Closed During Flow Test.Valve Was Opened & Check Valve Functional Test Completed ML19316A3701978-06-0505 June 1978 RO 269/78-13:on 780427,primary-to-secondary Leak in 1B Steam Generator Occurred.Caused by Tube Leaks.Tube 69-1 Had Weld Crack.Tube 74-2 Had Circumferential Crack.Cracked & Suspect Tubes explosive-plugged.Investigation Continuing ML19312C2361978-04-21021 April 1978 RO-269/78-07 & 09:on 780314 & 22,field Flashing Breaker Found Inoperable.Cause for Repeated Inoperability Has Not Been Determined.Faulty Relays Replaced Before 780322 Failure.Recorder Will Be Installed to Monitor Trip Circuits ML19316A3811978-04-11011 April 1978 RO 269/78-08:on 780315,valve FDW-108 Failed to Close.Failure Has Occurred Previously.Caused by Apparent Unsuitability of Valves for long-term Operation in Sys Environ.Valve Stem Lubricated.Valves Will Be Replaced ML19316A3891978-04-0707 April 1978 RO 269/78-10:on 780323,Unit 2 Not Verified Operable within Time Limit.Caused by Personnel Error.Station Procedure, Removal & Restoration of Equipment, Not Properly Used. Personnel Instructed by Operating Engineer ML19316A4041978-04-0707 April 1978 RO 269/78-06:on 780310,field Flashing Breaker Failed to Close During Startup of Keowee Hydro Unit 2.Breakers & Associated Relays Checked.Circuits Checked.Cause of Breaker Malfunction Unknown.Search for Possible Causes Continues ML19308A7531978-03-23023 March 1978 RO 269/78-03:on 780222,Unit 2 Field Flashing Breaker Failed to Close.Cause of Breaker Malfunction Not Determined.Relays in Breaker Control Circuit Were Replaced.Investigation to Control Breaker Sys Faults Continues ML19316A4641978-03-15015 March 1978 RO 269/78-04:on 780301,two Reactor Bldg Cooling Units Found Inoperable Simultaneously.Caused by Insufficient Installation Procedures Allowing Trip Point to Be Set Too Low.Breaker Reset & Trip Setpoint Increased ML19316A4171978-02-0303 February 1978 RO 269/78-01:on 780203,field Flashing Breaker Failed to Close.Controls Checked & Found in Proper Condition.Breaker Checked & Cleaned.Cause of Failure Not Determined ML19317F3461978-02-0202 February 1978 RO 270/78-04:on 780202,nuclear Instruments Found Out of Calibr in Less Conservative Direction & Could Have Prevented Fulfillment of Functional Requirements of Reactor Protective Sys.Cause Not Stated.Administrative Measures Taken ML19308A7971978-01-31031 January 1978 RO 269/78-02:on 780105,Keowee Hydro Unit 1 Not Verified Operable within 1-h of Taking Keowee Unit 2 Out of Svc. Caused by Failure to Follow Established Procedures by Personnel.Operators Instructed in Tech Specs ML19317E0451978-01-26026 January 1978 RO 269/77-31:on 771229,leakage of Less than 1 Gallon Per Minute Noted.Caused by Failure of Switch 1PS-364 Diaphragm. Switch 1PS-364 to Be Replaced During Future outage.1PT-21P Switch Recalibr & Returned to Svc ML19316A4841978-01-19019 January 1978 RO 269/77-30:on 771220,primary Leak Through Pressurizer Spray Bypass Valve RC-2 Indicated.Caused by Packing Leak on Pressurizer Spray Bypass Valve.Valve RC-2 Repacked & Tested for Leaks ML19317D9631978-01-18018 January 1978 Incident Investigation Rept RO-B-692:on 780117,Keowee Unit 2 Removed from Svc for Maint & Keowee Unit 1 Not Verified Operable within 1-h Per Tech Specs.Keowee Unit 1 Verified Operable Upon Discovery ML19308A7841978-01-18018 January 1978 RO 269/77-29:on 771219,Keowee Hydro Unit 2 Failed to Start on Initiation from Oconee Control Room.Field Flashing Breaker Failed to Close.Cause Not Determined.Breaker Inspected & Serviced & Found Operable ML19317D9591978-01-13013 January 1978 Incident Investigation Rept RO-B-690:on 780113,indications Reading High During Calibr on a Core Flood Tank (IP/0/A/020/01A).Error May Have Allowed Unit Operation in Violation of Tech Specs 3.3.3 ML19317D8781977-12-19019 December 1977 RO 269/77-28:on 771216,B&W Discovered Min Vol & Concentration Requirements Were Insufficient for Reactor Shutdown.Cause Not Given.Boron Solution Vol Increased to Provide Adequate Margin for Shutdown ML19308B1701977-12-15015 December 1977 RO 269/77-27:on 771215,B&W Discovered Error in Computer Used for Incore Detector Signal Processing.Initial Action to Reduce Positive Imbalance Trip Setpoints by 2.5% 1990-04-30
[Table view] Category:LER)
MONTHYEARML20042F3541990-04-30030 April 1990 Special Rept Re Failure to Prevent Performance Degradation of Reactor Bldg Cooling Units.Caused by Mgt Deficiency & Inadequate Program.Cooling Unit Declared Inoperable & Removed from Svc for Cleaning & Placed Back in Operation ML20024C1271983-07-0101 July 1983 Ro:On 830623,visual Insp Revealed Three Broken Holddown Springs.Investigation Incomplete.Ro 269/83-13 Will Be Submitted by 830721 ML20024C4181983-07-0101 July 1983 Ro:On 830525,fire Barrier Penetrations Found Nonfunctional. Caused by Design Deficiency.Fire Watch Posted,Penetrations Repaired & Procedures Revised ML20024C4141983-06-29029 June 1983 Ro:On 830509 & 12,fire Barrier Smoke Exhaust Penetrations 3-K-5-2,3-C-5-3 & 4 Found W/O Seal & 3-C-5-3 Did Not Have Fusible Damper,Respectively.Caused by Inadequate Info & Insufficient Guidance Provided by Design Engineering ML20023B6511983-04-29029 April 1983 ROs 269/83-10 & 287/83-04 Re 821212 & 830303 Loss of Containment Integrity.Mgt Audit in Progress.Summary List of Completed & Remaining Activities,W/Projected Completion Dates,Encl ML20028F3931983-01-19019 January 1983 Ro:On 821220,reactor Trip Circuit Breaker a Failed to Trip When Trip Signal Initiated.Caused by Sticking Undervoltage Relay.Relay Replaced.Contacts Cleaned ML20027B8581982-09-21021 September 1982 Ro:Advising That 820820 Occurrence Involving Loss of Electric Power to Valve CCW-8 Determined Not Reportable. Operability of Valve Demonstrated.No Further Action Required ML20027B7691982-09-16016 September 1982 RO 269/82-14:investigation Re Reactor Bldg Penetrations That May Not Have Been Leak Rate Tested Incomplete.Rept to Be Submitted by 820930 ML20052A3291982-04-0909 April 1982 Informs That Review Per RO-269/82-07 Has Determined That Plant Design & Const Predate Std Re Westinghouse SAI-1 Type Relays Not Meeting Full Surge Requirements ML20052A4261982-04-0202 April 1982 RO 269/82-06:on 820306,steam Generator 1B Indicated Tube Leak of 0.08 Gpm.Incident Under Investigation.Next Rept Expected by 820416 ML20050A9751982-03-12012 March 1982 RO 287/82-04:on 820226,3A2 HPI Normal Makeup Nozzle Found to Have Broken Thermal Sleeve Tack Welds.Investigation Revealed Cracks in Safe End & Upstream Piping.Next Rept Expected by 820409 ML20049J5541982-02-25025 February 1982 Ro:Advising of Delay Until 820311 to Provide Complete Rept of RO-281/82-03 Re Steam Generator Tube Leak ML20040F7611982-02-0505 February 1982 Ro:On 820122,during Visual Insp of Core Barrel Assembly, Thermal Shield & Shock Pad Bolts Found Broken & Shock Pad Was Skewed.Thermal Shock Bolts to Be Replaced.Loosened Shock Pad Evaluation Underway ML20040E6871982-01-28028 January 1982 RO 269/81-50:on 811229,reactor Bldg Cooling Unit C Declared Inoperable Due to Inability to Open Discharge Valve 1LPSW-24.Investigation & Rept Expected to Be Completed by 820211 ML20040C8421982-01-0808 January 1982 Suppl 3 to RO 269/81-11:re Broken Lower Thermal Shield Bolts.Caused by Intergranular Stress Corrosion Cracking in Region of Pronounced Microstructure Transition at head-to-shank Fillet.Bolts Replaced.Drawings Encl ML20039F6081981-12-28028 December 1981 Ro:On 811228,review of Info Re Reactor Vessel Matl Surveillance Program Revealed Calculational Error in Analyses Used to Update Heatup & Cooldown Curves.Unrevised Tech Spec Figures 3.1-1 & 3.1-2 Remain Conservative ML20038B5001981-12-0303 December 1981 Ro:On 811201,pressurizer Block Valves Found to Not Meet Design Specs of Closing Against Design Pressure.Caused by Undersized Motor Operator Which Will Not Develop Sufficient Torque to Shut Block Valve ML20038C7961981-12-0202 December 1981 Ro:On 811201,discovered Pressurizer Block Valves Did Not Meet Design Spec in That They May Not Close Against Design Pressure.Caused by Undersized Limitorque Operator Model SMB-000-5 ML20011A7231981-10-21021 October 1981 Ro:On 811019,four Liquid Waste Releases Were Made W/O Adequate Sampling.Caused by Failure to Make Change to Sample Point.Procedure Revised to Specify Correct Sampling Point for Sys Configuration ML20010F6791981-09-0404 September 1981 RO 270/81-14:on 810821,2A1 Reactor Coolant Pump Electrical Penetration Was Discovered Depressurized & Could Not Be Repressurized w/SF6 Gas.Cause Not Stated.Investigation & Complete Rept Will Be Sent by 810918 ML20038C8171981-08-25025 August 1981 Ro:On 810814,tritium Concentrations in Downstream Water Samples Exceeded Tech Spec Control Level for Second Quarter of 1981.Analysis of Max Dose Estimates Concluded That Concentrations Will Not Adversely Affect Public Health ML20010A8721981-08-0505 August 1981 RO 269/81-11,Suppl 1:on 810715,core Barrel Assembly Thermal Shield Bolts Found Broken.Cause Not Stated.Search for Loose Parts Turned Up All Missing Thermal Shield Parts Except for One Thermal Shield Bolt Head.Investigation Continuing ML20009H6891981-07-30030 July 1981 Nonroutine 30-day Rept:On 810623,fire Door 5 Opened to Relieve Excessive Heat from Auxiliary Feedwater Pump Room. Heat Caused by Backleakage Combined W/Hot Temp & Lack of Ventilation.Repairs Scheduled for Fall Refueling Outage ML20009E7351981-07-28028 July 1981 Ro:On 810717,fire Suppression Water Sys Found Inoperable. Caused by Open Main Control Source Breakers.Breakers Closed & Sys Successfully Tested ML20009H5771981-07-22022 July 1981 Ro:On 810608,fire Barrier Penetration Fire Seals Found in Nonconformance W/Approved Configuration Requirements. Deficiencies Occurred During Mod 445-N Implementation.Seals Will Be Repaired During Refueling Outage ML20038C8031981-07-0606 July 1981 Ro:On 810210,radioactivity Levels of Aquatic Vegetation Samples Exceeded Control Level by Greater than 50 Times.Info Supersedes 810225 Submittal ML20009F4311981-07-0101 July 1981 Ro:On 810630,during Performance of Normal Power Procedure, Backup Function of Units Isolating & Transfer Diodes on 125 Volt Dc Instrumentation & Control Sys Was Observed. Proposed Tech Spec Change Will Be Submitted ML20009H2701981-04-0101 April 1981 RO:810319 Determination Declaring Portions of Low Power Injection Sys Seismically Inoperable Was Premature.Hanger Noncomformance Repaired within 48-h Per IE Bulletin 79-14. Item Not Reportable Per Tech Spec 6.6.2.1a(9) ML20005A8771981-02-25025 February 1981 Ro:On 810219 Analytical Results of Aquatic Vegetation Samples Collected on 810210 Indicated That Radioactivity Levels Exceeded Tech Specs.Cause Not Stated ML19341B2741981-01-15015 January 1981 Ro:On 810114,both Channels of Heat Trace for Both Boric Acid Transfer Pumps Determined Inoperable in Violation of Tech Spec 3.2.3.C.Caused by Misleading Step in Procedure for Taking Pump Out of Svc ML18004B9871979-08-30030 August 1979 Ro:On 790829,svc Water Booster Pump a Tripped When Svc Water Booster Pump B Was Stopped,In Violation of Tech Specs 3.3.4.1.a.Power Reduction Initiated & Svc Water Booster Pumps Returned to Svc ML19282D0291979-01-15015 January 1979 RO 269/7827 on 781214:on 781213,reactor Coolant Temp Became Erratic.Feedwater Problem Resulted from Operation of One or More Feedwater Valves.Power Cords Have Been Fitted ML19263C9841978-11-30030 November 1978 RO 270/78-12 on 781105:stop Check Valve from 2AHPI Pump to 2A12C Pump Closed During Flow Test.Valve Was Opened & Check Valve Functional Test Completed ML19316A3701978-06-0505 June 1978 RO 269/78-13:on 780427,primary-to-secondary Leak in 1B Steam Generator Occurred.Caused by Tube Leaks.Tube 69-1 Had Weld Crack.Tube 74-2 Had Circumferential Crack.Cracked & Suspect Tubes explosive-plugged.Investigation Continuing ML19312C2361978-04-21021 April 1978 RO-269/78-07 & 09:on 780314 & 22,field Flashing Breaker Found Inoperable.Cause for Repeated Inoperability Has Not Been Determined.Faulty Relays Replaced Before 780322 Failure.Recorder Will Be Installed to Monitor Trip Circuits ML19316A3811978-04-11011 April 1978 RO 269/78-08:on 780315,valve FDW-108 Failed to Close.Failure Has Occurred Previously.Caused by Apparent Unsuitability of Valves for long-term Operation in Sys Environ.Valve Stem Lubricated.Valves Will Be Replaced ML19316A3891978-04-0707 April 1978 RO 269/78-10:on 780323,Unit 2 Not Verified Operable within Time Limit.Caused by Personnel Error.Station Procedure, Removal & Restoration of Equipment, Not Properly Used. Personnel Instructed by Operating Engineer ML19316A4041978-04-0707 April 1978 RO 269/78-06:on 780310,field Flashing Breaker Failed to Close During Startup of Keowee Hydro Unit 2.Breakers & Associated Relays Checked.Circuits Checked.Cause of Breaker Malfunction Unknown.Search for Possible Causes Continues ML19308A7531978-03-23023 March 1978 RO 269/78-03:on 780222,Unit 2 Field Flashing Breaker Failed to Close.Cause of Breaker Malfunction Not Determined.Relays in Breaker Control Circuit Were Replaced.Investigation to Control Breaker Sys Faults Continues ML19316A4641978-03-15015 March 1978 RO 269/78-04:on 780301,two Reactor Bldg Cooling Units Found Inoperable Simultaneously.Caused by Insufficient Installation Procedures Allowing Trip Point to Be Set Too Low.Breaker Reset & Trip Setpoint Increased ML19316A4171978-02-0303 February 1978 RO 269/78-01:on 780203,field Flashing Breaker Failed to Close.Controls Checked & Found in Proper Condition.Breaker Checked & Cleaned.Cause of Failure Not Determined ML19317F3461978-02-0202 February 1978 RO 270/78-04:on 780202,nuclear Instruments Found Out of Calibr in Less Conservative Direction & Could Have Prevented Fulfillment of Functional Requirements of Reactor Protective Sys.Cause Not Stated.Administrative Measures Taken ML19308A7971978-01-31031 January 1978 RO 269/78-02:on 780105,Keowee Hydro Unit 1 Not Verified Operable within 1-h of Taking Keowee Unit 2 Out of Svc. Caused by Failure to Follow Established Procedures by Personnel.Operators Instructed in Tech Specs ML19317E0451978-01-26026 January 1978 RO 269/77-31:on 771229,leakage of Less than 1 Gallon Per Minute Noted.Caused by Failure of Switch 1PS-364 Diaphragm. Switch 1PS-364 to Be Replaced During Future outage.1PT-21P Switch Recalibr & Returned to Svc ML19316A4841978-01-19019 January 1978 RO 269/77-30:on 771220,primary Leak Through Pressurizer Spray Bypass Valve RC-2 Indicated.Caused by Packing Leak on Pressurizer Spray Bypass Valve.Valve RC-2 Repacked & Tested for Leaks ML19317D9631978-01-18018 January 1978 Incident Investigation Rept RO-B-692:on 780117,Keowee Unit 2 Removed from Svc for Maint & Keowee Unit 1 Not Verified Operable within 1-h Per Tech Specs.Keowee Unit 1 Verified Operable Upon Discovery ML19308A7841978-01-18018 January 1978 RO 269/77-29:on 771219,Keowee Hydro Unit 2 Failed to Start on Initiation from Oconee Control Room.Field Flashing Breaker Failed to Close.Cause Not Determined.Breaker Inspected & Serviced & Found Operable ML19317D9591978-01-13013 January 1978 Incident Investigation Rept RO-B-690:on 780113,indications Reading High During Calibr on a Core Flood Tank (IP/0/A/020/01A).Error May Have Allowed Unit Operation in Violation of Tech Specs 3.3.3 ML19317D8781977-12-19019 December 1977 RO 269/77-28:on 771216,B&W Discovered Min Vol & Concentration Requirements Were Insufficient for Reactor Shutdown.Cause Not Given.Boron Solution Vol Increased to Provide Adequate Margin for Shutdown ML19308B1701977-12-15015 December 1977 RO 269/77-27:on 771215,B&W Discovered Error in Computer Used for Incore Detector Signal Processing.Initial Action to Reduce Positive Imbalance Trip Setpoints by 2.5% 1990-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20206P1501999-01-0505 January 1999 LER 98-S03-00:on 981207,security Officer Discovered Uncontrolled Safeguards Info Drawing.Caused by Failure to Follow Established Procedures & Policies.Drawing Was Controlled by Site Security.With ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198E6381998-12-17017 December 1998 LER 98-S02-00:on 981130,security Access Was Revoked Due to Falsification of Criminal Record.Individual Was Escorted from Protected Area & Unescorted Access Was Restricted. with ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20247L9041997-12-31031 December 1997 1997 Annual Rept for Duke Energy Corporation & Saluda River Electric Cooperative,Inc,Financial Statements as of Dec 1997 & 1996 Together W/Auditors Rept RA-97-0258, LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review1997-12-19019 December 1997 LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20217Q2751997-06-30030 June 1997 CP&L Fitness for Duty Program Performance Data for Period 970101-0630 ML20148S3141997-06-30030 June 1997 Ro:On 970422,Oconee Unit 2 Was Shut Down Due to Leak in Rcs. Leak Was Caused by Crack in Pipe to safe-end Weld Connection at RCS Nozzle for HPI Sys A1 Injection Line.Unit 1 Was Shut Down to Inspect Hpis Injection Lines & Implement Ldst Mods ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20134N7121997-02-20020 February 1997 Safety Evaluation Accepting Relief Request 96-04 for Plant ML20138L2151997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Oconee Nuclear Station,Units 1,2 & 3 ML20138L2281996-12-31031 December 1996 Revised Monthly Operating Repts for Dec 1996 for Oconee Nuclear Station,Units 1,2 & 3 ML20133C1231996-12-23023 December 1996 Informs Commission of Staff Review of Request for License Amends from DPC to Perform Emergency Power Engineered Safeguards Functional Test on Three Oconee Nuclear Units ML20115F2471996-07-0303 July 1996 Part 21 Rept Re Piping (Small Portion of Unmelted Matl Drawn Lengthwise Into Bar During Drawing Process) Defect That Existed in Bar as Received from Mill.Addl Insp Procedure for Raw Matl Instituted ML17353A4341995-10-31031 October 1995 Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. ML20107M8931995-10-31031 October 1995 Nonproprietary DPC Fuel Reconstitution Analysis Methodology ML14183A6951995-09-18018 September 1995 Safety Evaluation Approving Relocation of Technical Support Ctr ML17264A1181995-07-31031 July 1995 Response to Part (1) of GL 92-01,Rev 1,Suppl 1. ML20086M0851995-06-29029 June 1995 DPC TR QA Program ML20077R3631994-12-31031 December 1994 Monthly Operating Repts for Dec 1994 for Bfnpp ML20236L5971994-12-29029 December 1994 SER in Response to 940314 TIA 94-012 Requesting NRR Staff to Determine Specific Mod to Keowee Emergency Power Supply Logic Must Be Reviewed by Staff Prior to Implementation of Mod ML20064L2001994-01-31031 January 1994 Final Rept EPRI TR-103591, Burnup Verification Measurements on Spent-Fuel Assemblies at Oconee Nuclear Station ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20062K7481993-12-0101 December 1993 ISI Rept for Unit 2 McGuire 1993 Refueling Outage 8 ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20046C1291993-08-0202 August 1993 LER 93-007-00:on 930701,determined That Unit 1 Ssf Rc Makeup Sys Inoperable in Past Due to Design Deficiency.Operations Procedures Revised to Reflect Newly Calculated Operating Limits for Rc Makeup Pump,Rcps & RCS.W/930802 Ltr ML20056G0131993-07-27027 July 1993 Rev 0 to ISI Rept Unit 2 Oconee 1993 Refueling Outage 13 ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20117A5981992-11-23023 November 1992 Special Rept:On 921119,ability of Control Battery Racks to Withstand Seismic Event Could Not Be Confirmed & Batteries Declared Inoperable.Batteries Expected to Be Restored in TS Required Time ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20097G0421992-05-31031 May 1992 Analysis of Capsule OCIII-D Duke Power Company Oconee Nuclear Station Unit-3 ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20079H1571991-09-30030 September 1991 Nonproprietary Evaluation of Revised Transfer to Cold Leg Recirculation Procedure,Hb Robinson Unit 2 ML20086T2951991-06-14014 June 1991 Rev 1 to EQ Documentation Package Eqdp 36.0, Boston Insulated Wire Cable ML20086T2861991-03-0808 March 1991 Rev 1 to EQ Documentation Package Eqdp 11.1, Dekoron Instrumentation Cables ML20086T2561991-03-0808 March 1991 Rev 1 to EQ Documentation Package 10.0, Continental Shielded Instrument Cable ML20067A5241990-12-31031 December 1990 Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.' ML20065K6971990-10-31031 October 1990 Thermal Hydraulic Compatibility Analysis of Anf High Thermal Performance Fuel for Hb Robinson,Unit 2 ML20065K6961990-10-31031 October 1990 Mechanical Licensing Rept for Hb Robinson High Thermal Performance Fuel Assemblies 1999-09-22
[Table view] |
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Mr. John F. O' Leary - '
Directorate of Reactor Licensins MAY 7 1973 s-U. S. At6mic Energy Con:nission E g gi. mg .,
Washington, D. C. 20545 cwa:s wxsur 50-261 g rui:ca
Dear Mr. O' Leary:
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H. B. ROBINSON UNIT NO. 2 LICENSE DPR-23 REFUELING WATER STORAGE TANK SPILL TO THE PLLNT DRAINAGE SYSTEM In accordance uith paragraph 6.6.2.D, Technical Specifications, it is reported that on April 23, 1973, with the reactor in a refueling shutdoms condition, a spill of water from the Refueling Water Storage Tank (RUST) to the plant storm drainage system occurred.
Following core reload, the louer icvcis of the containment refueling cavity were being drained to the Reactor Coolant Drain Tank and then pumped to the RWST. At approximately 1530, the icvel in the RWST as indicated on the RTCB vas 987.. The cavity was being drained at approximat:cly 35 gpm. Draining cnntinued until, at 2300, it was dis-covered that the RWST uas overflowing to the plant drainage system. The cavity draining was immediately stopped, and transfer of the water from the RWST to the Spent Fuci Pit was begun. Overflow of the RNST imrediately diminit:hed, and by 0013, April 24, all flow to the storm drainage system ,
had ceased.
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It is estimated that the RNST filled to overflow 1cvel at 1845.
Assuming' that all water pumped irem this time until the pump was stopped !
floucd to the drain, this would amount to approximately 8,925 gallons. l The water uhich was released flowed to the storm drain and subsequently into Black Crcck belou the Robinson impoundment dam.
A sampic was collected from the PNST and analyzed by gamma spectrometry for total activity and isotopic identification. Since the water was released from the 3NST overflou line, the activity in this sample is idcutical to that uhich was relcased. Concentrations of specific radionuclides from this sampic are shcun in the attached table. Based on the total release of 8,925 gallons of water, 379.29 millicuries of radio-activity, excluding tritium, were relcased to the drainage ditch and subsequently to Black Crcck. At the time of the release there was a flow
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Mr. O', Leary May 1, 1973 of 680 gpm in the drainage ditch and a flow of 260 CFS in Black Creek resulting in coi.centrations in these streams averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as shown in the cabic.
This release resulted in a concentration, averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, of 1807. of MPC values shown in 10CFR20 in the drainage ditch and 17. of these values in Black Creek. Due to the dilution flow in Black Creek at the time of the release no adverse environmental effects vould result. An automatic water sampler was in operation on Black Creek downstream of where the drainage ditch enters during the entire period of the release.
Gross beta and gamma spectrum analyses of this sampic showed no detectable radioactivity which verifics that no adverse environmental effects would result from the release.
Since Technical Specification limits for liquid discharge are based on equilibrium values of radionuclides which are released to the lake, a comparison of this release (to the stream belou the impoundment) to those limits han no meaning. This release does represent, houcver, 77.5% of the total liquid activity released to the environment during 1973. j This incident is not reportabic under 10CFR20 because the 24-hour average concentration in the drainage ditch did not eneced 10 tir.cs the MPC values and because the 8-hour average (reference Tech. Spec. Section 3.9.1.2) did not execed 10 times the permitted values of Technical l Specifications and Basos. I To prevent recurrence of this incident, the following corrective measures have been or will be initiated:
I
- 1. Plant management will revicu methods to prevent recurrence - j of these type incidents.
I
- 2. All operators have been cautioned to exercise extreme I caution when transferring radioactive liquids.
- 3. Normal water level in the Refueling Water Storage Tank will be maintained at 927. instead of the previous level of 987..
- 4. A high 1cyc1 nlarm will be installed to annunciate on the RTGB should the refueling water storage tank icyc1 reach 957..
- 5. A modification to route the overflou from the RNST to the plant liquid waste system has been under investigation and will be pursued further.
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i Mr,, O'Ictry r May 1, 1973 The Plant Nucicar Safety Comittee reviewed this incident on .
April 24, 1973, and it was reported to Mr. !!crb Whitener of DRO by telephone and to Mr. Norman C. Mosely of the same office by telegraph on the same date. The South Caroline State Board of Health has also been informed of the incident.
Very truly yours, E. E. Uticy (. 6 Vice-President Bulk Power Supply DBW/za Attachment cc: Mr. C. D. Barham
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CONCENTRATION .
/ SAMPLE S(PC IN IN MILLICURIES .
ISOTOPE ANAI.YSIS 10 CFR 20 DRAINAGE DITCH MPCF BLACK CREEK ( } MPCF RELEASED ( }
2.02 x 10 ~7 ~9
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l Co-57 2.23 x 10 4 x 10 0.0005 0.75 1.18 x 10 . 000003 1.25 x 10 -5
~3 Cr-51 1.37 x 10~ 2 x 10 0.00625 7.28 x 10 -8 .000036 46.28 .g Co-58 6.09 x 10~ 9 x 10~ 6.09 x 10~ 0.677 3.55 x 10~ .003944 255.99 I Cs-134 2.96 x 10~ -6 ~0 ~0 9 x 10 2.71 x 10 0.301 1.58 x 10 .001756 10.07
~0 C3-137 3.53 x 10~ 2 x 10~ 3.21 x 10 0.1605 1.87 x 10~ .000935 11.92 Mb-95 1.03 x 10 1 x 10 9.38 x 10~ 0.0094 5.47 x 10 ~9 .000055 3.48 "a-54 ~0 3.82 x 10~ 1 x 10 3.48 x 10 0.0348 2.03 x 10~ .000203 12.90 Co-60 2.01 x 10~ 3 x 10~ 1.83 x 10~ 0.610 1.07 x 10~ .00356 67.90 TOTALS 1.804 .0105 379.29
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(1) Based on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average.and a flow in the ditch of 680 gpa $, g if Yki
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! (2) Based on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average and a flow in Black Creek of 260 ft 3/sec
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(3) Based on a release of 8925 gallons. g j
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