ML19308B007
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| ML19308B007 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/07/1973 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19308B002 | List: |
| References | |
| RO-269-73-12, NUDOCS 7912120765 | |
| Download: ML19308B007 (1) | |
Similar Documents at Oconee | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20042F3541990-04-30030 April 1990
[Table view]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 ML20024C4181983-07-0101 July 1983 Ro:On 830525,fire Barrier Penetrations Found Nonfunctional. Caused by Design Deficiency.Fire Watch Posted,Penetrations Repaired & Procedures Revised 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 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 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 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 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 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 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 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 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 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% ML19317F2651977-12-0606 December 1977 Ro:On 771206,valve 3LP-28 Not Locked Open as Required by Tech Specs.Valve Locked Open Upon Discovery.Forwards Util Incident Investigation Rept B-674 ML19308A8451977-11-10010 November 1977 Ro:On 771107,analysis of Raw Water Supply Samples Collected in July,Aug & Sept 1977 Showed Tritium Concentration Exceeding Control Level by Greater than Ten Times ML19312C6131977-10-31031 October 1977 Ro:On 771026,milk Samples Collected 771005 Showed I-131 Concentrations Exceeded Control Levels Per Tech Specs Section 6.6.2.2.a.Higher Levels Attributed to 770917 Chinese Nuclear Test ML19312C7141977-09-26026 September 1977 Ro:On 770920,radionuclide (Cs-134 & Cs-137) Levels of Keowee River Sediment Samples Collected in Aug 1977 Registered 10 Times Control Level.Based on Diluted Tailrace Concentrations,Levels Lie within Expected Values ML19312C6251977-08-25025 August 1977 Ro:On 770819,fish Samples Collected During July 1977 Showed Cs-137 Levels Exceeding Control Limits by Over Ten Times. Concentrations within Health & Safety Limits & No Corrective Actions Planned ML19312C6181977-08-18018 August 1977 Ro:On 770812,composite Surface Water Samples Collected from Apr-June 1977 Showed Tritium Concentration Exceeding Control Level by 50 Times.No Threat to Public Safety & No Corrective Action Planned ML19317F3221977-08-16016 August 1977 RO 270/77-10:on 770803,reactor Bldg Purge & Penetration Room Ventilation Sys Running Time Check Revealed That Required Surveillance of Filter Sys Was Not Performed.Caused by Failure to Implement Adequate Administrative Procedures ML19317D9971977-08-16016 August 1977 RO 269/77-17A:on 770517,emergency Power Source Inadvertently Isolated.Caused by Procedural Inadequacy of Some Tests. Periodic Test Procedure Revised for Restoring Emergency Power Sys to Proper Lineup 1990-04-30 Category:LER) MONTHYEARML20042F3541990-04-30030 April 1990
[Table view]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 ML20024C4181983-07-0101 July 1983 Ro:On 830525,fire Barrier Penetrations Found Nonfunctional. Caused by Design Deficiency.Fire Watch Posted,Penetrations Repaired & Procedures Revised 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 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 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 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 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 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 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 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 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 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% ML19317F2651977-12-0606 December 1977 Ro:On 771206,valve 3LP-28 Not Locked Open as Required by Tech Specs.Valve Locked Open Upon Discovery.Forwards Util Incident Investigation Rept B-674 ML19308A8451977-11-10010 November 1977 Ro:On 771107,analysis of Raw Water Supply Samples Collected in July,Aug & Sept 1977 Showed Tritium Concentration Exceeding Control Level by Greater than Ten Times ML19312C6131977-10-31031 October 1977 Ro:On 771026,milk Samples Collected 771005 Showed I-131 Concentrations Exceeded Control Levels Per Tech Specs Section 6.6.2.2.a.Higher Levels Attributed to 770917 Chinese Nuclear Test ML19312C7141977-09-26026 September 1977 Ro:On 770920,radionuclide (Cs-134 & Cs-137) Levels of Keowee River Sediment Samples Collected in Aug 1977 Registered 10 Times Control Level.Based on Diluted Tailrace Concentrations,Levels Lie within Expected Values ML19312C6251977-08-25025 August 1977 Ro:On 770819,fish Samples Collected During July 1977 Showed Cs-137 Levels Exceeding Control Limits by Over Ten Times. Concentrations within Health & Safety Limits & No Corrective Actions Planned ML19312C6181977-08-18018 August 1977 Ro:On 770812,composite Surface Water Samples Collected from Apr-June 1977 Showed Tritium Concentration Exceeding Control Level by 50 Times.No Threat to Public Safety & No Corrective Action Planned ML19317F3221977-08-16016 August 1977 RO 270/77-10:on 770803,reactor Bldg Purge & Penetration Room Ventilation Sys Running Time Check Revealed That Required Surveillance of Filter Sys Was Not Performed.Caused by Failure to Implement Adequate Administrative Procedures ML19317D9971977-08-16016 August 1977 RO 269/77-17A:on 770517,emergency Power Source Inadvertently Isolated.Caused by Procedural Inadequacy of Some Tests. Periodic Test Procedure Revised for Restoring Emergency Power Sys to Proper Lineup 1990-04-30 Category:TEXT-SAFETY REPORT MONTHYEARML20206P1501999-01-0505 January 1999
[Table view]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 ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units 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 ML20107M8931995-10-31031 October 1995 Nonproprietary DPC Fuel Reconstitution Analysis Methodology ML17353A4341995-10-31031 October 1995 Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. 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 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 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 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 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 ML20067A5241990-12-31031 December 1990 Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.' ML20042F3541990-04-30030 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 ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML19332D5391989-10-31031 October 1989 Core Thermal-Hydraulic Methodology Using VIPRE-01. ML20042F2321989-08-31031 August 1989 Nonproprietary DCHF-1 Correlation for Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies. ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20245B6061988-08-31031 August 1988 Inadequate NPSH in HPSI Sys in Pwrs, Engineering Evaluation Rept ML20239A6991987-11-30030 November 1987 Addendum 1 to Rev 2 to Integrated Reactor Vessel Matl Surveillance Program (Addendum) ML20236T0791987-11-25025 November 1987 Advises LER 269/87-09,re Degradation of More than One Functional Unit of Emergency Power Switching Logic for Units 2 & 3,in Preparation & Will Be Submitted by 871215. Incident Originally Discussed in Special Rept ML20236Q9491987-10-31031 October 1987 Monthly Operating Repts for Oct 1987 ML20235W9611987-09-30030 September 1987 Monthly Operating Repts for Sept 1987 ML20234B1861987-08-31031 August 1987 Monthly Operating Repts for Aug 1987 ML20237K4761987-07-31031 July 1987 Monthly Operating Repts for Jul 1987 ML20236Y0221987-07-0808 July 1987 Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at Plant ML20235S6311987-06-30030 June 1987 Monthly Operating Repts for June 1987 1999-01-05 |
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DUKE POWER COMPANY OCONEE NUCLEAR STATION - UNIT 1 UNUSUAL EVENT REPORT UE-269/73-12 ENGINEERED SAFEGUARDS VALVE VDW-108 Description of the Incident On November 8, 1973. Engineered Safeguards Valve FDW-108 failed to close during a monthly test of Engineered Safeguards System Channel 6. This valve serves to isolate the sample line from No. 1B steam generator in the event of Engineered Safeguard System actuation. Regulatory Operations, Region II, was verbally notified of the incident on November 8, 1973.
Corrective Action Instrument technicians checked out the system immediately, but no problem was found. The valve operated properly on six successive trials. The valve was checked once a day for proper operation during November 9-11, 1973 and functioned properly each time. On November 12, 1973, local observation revealed some hesitation in valve operation. During successive operation, it was noted that the hesitation seemed to be the result of the slow operation of a solenoid which functions to admit opening air to the pneumatic operator of a valve. This solenoid was replaced and the valve FDW-108 was successfully tested for proper operation.
Safety Analysis FDW-108 is a pneumatic isolation valve on the sample line from steam generator 1B and closes on signal from Channel 6 of the Engineered Safeguards System.
Engineered Safeguards System Channel 6 is actuated from high reactor building pressure. On the same sample line, there is an electric motor-operated isolation valve, FDW-107, which is actuated by redundant Engineered Safe-guards System Channel 5. In the event that FDW-108 had failed to close during Engineered Safeguards System actuation, reactor building isolation would have been provided by the redundant valve FDW-107 actuated by Engineered Safeguards Channel 5. This incident did not affect the safe operation of the plant or the health and safety of the public.
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