ML19317F068
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| ML19317F068 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/07/1974 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19317F057 | List: |
| References | |
| NUDOCS 8001080760 | |
| Download: ML19317F068 (1) | |
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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19312C2161976-01-0707 January 1976
[Table view]Abnormal Occurrence AO-269/75-15:on 751219,borated Water Storage Tank Level Indication Failed.Caused by Failure of Trace Heating to Level Instrumentation Air Lines.Station Mod Initiated to Provide Power for Heat Tracing ML19312C2011975-12-11011 December 1975 Abnormal Occurrence AO-269/75-14:on 751127,tritium Released in Excess of Allowable Limits.Caused by Personnel Misreading Max Release Rate Recommendations.Personnel Advised of Extreme Care Necessary When Interpreting Operations Info ML19312C1971975-11-21021 November 1975 Abnormal Occurrence Rept AO-269/75-13:on 751108,Keowee Hydro Unit 1 Failed to Autostart.Caused by Electrical Malfunction of Breaker.Malfunctioning Generator Supply Breaker Removed, Cleaned & Repaired.Keowee Unit 2 Tested & Returned to Svc ML19317F0601975-11-10010 November 1975 AO-287/75-12:on 751028,reactor Bldg Air Sampling Line Inlet Valve 3PR-7 Failed to Close During Engineered Safeguards Actuation Testing.Caused by Personnel Error.Breaker Closed & Valve Tested for Operability ML19317D9851975-10-21021 October 1975 Abnormal Occurrence Rept AO-269/75-12:on 751007,borated Water Storage Tank Drained to Spent Fuel Pool.Caused by Operator Error.Operator Counseled Re Proper Procedure ML19312C8641975-10-20020 October 1975 AO-270/75-20:on 751006,temp Detector in Reactor Protective Sys Channel a Failed.Caused by Faulty Resistance Temp Detector.Resistance Temp Detector to Be Replaced Next Shutdown.Channel a Returned to Svc 751201 ML19312C9391975-10-17017 October 1975 AO-270/75-19:on 751017,pipe Connecting Unit 2 Component Drain Pump Discharge Header to Turbine Bldg Trench Leading to Units 1 & 2 Turbine Bldg Sump Found Leaking.Caused by Incorrect Installation of Line Discharging to Sump ML19316A6171975-09-0808 September 1975 AO-270/75-17:on 750824,component Cooling Sys Activity Increased.Caused by Letdown Cooler a Leak.Letdown Cooler a Removed from Svc & Repairs in Progress.Redundant Cooler Placed in Svc ML19312C8511975-09-0808 September 1975 AO-270/75-18:on 750825,loss of Required Overlap Between Operating Control Rod Groups.Caused by Dropping Group 7 Rods & Withdrawing Group 6.Power Supplies Examined & No Problems Identified.Required Overlap Immediately re-established ML19316A4111975-08-25025 August 1975 Abnormal Occurrence Rept AO-269/75-11:on 750811,backup Emergency Power Source Improperly Removed from Svc for Charge.Caused by Personnel Error.Situation Discussed W/Superintendent Re Need for Shift Supervisor Approval ML19316A5931975-08-22022 August 1975 AO-270/75-16:on 750808,operable Bldg Spray Train Not Provided During Startup.Caused by Personnel Error.Control Operator Relied on Out of Normal Checklist.Deficiencies in Personnel Performance Pointed Out.Startup Procedure Changed ML19317F1711975-08-21021 August 1975 Abnormal Occurrence Rept AO-287/75-11:on 750807,Control Rod Drive Breaker 10 Failed to Trip.Caused by Breaker Maladjustment.Break Cleaned,Lubricated & Adjusted ML19316A5881975-08-19019 August 1975 AO-270/75-15:on 750805,trip Point Decrease Noted.Caused by Faulty Amplifier in Channel D Power Imbalance Circuit. Channel D Remains in Manual Bypass Until Amplifier Replaced. Surveillance Program Adequate ML19316A5821975-08-11011 August 1975 AO-270/75-13:on 750728,string of Keowee & Switching Station Batteries Simultaneously Removed from Svc.Caused by Operator Error.Charging Procedure for Battery Sys Revised to Require Control Operation Confirmation Prior to Charging ML19317F0541975-07-25025 July 1975 AO-287/75-10:on 750714,during Instrument Surveillance Test Both Level Tramsmitters for Borated Water Storage Tank Discovered Out of Calibr by Greater than Calibr Tolerance. Caused by Incorrect Initial Calibr ML19317F2351975-07-25025 July 1975 AO-287/75-09 on 750713,power Level Cutoff Exceeded During Transient Xenon Condition.Caused by Failed Module within Turbine Bypass Valve Controls.Turbine Bypass Valve Control Section Replaced & Functional Check Performed ML19312C1881975-07-18018 July 1975 Abnormal Occurrence Rept AO-269/75-08:on 750704,while Keowee Hydro Unit 1 Inoperable,Emergency Power Sources Not Provided.Caused by Dispatcher Error.Keowee Unit 2 Returned to Svc & Tested.Lee Combustion Turbine Utilized ML19312C2091975-07-18018 July 1975 Abnormal Occurrence Rept AO-269/75-09:on 750708,effluent Discharge Isolation Valve LWD-132 Failed to Close During Source Check.Caused by Differential Pressure Created by Condensate Monitor Pump Lifting Valve Off Seat ML19312C1911975-07-0909 July 1975 AO-269/75-07:on 750624,leak Detected in Reactor Coolant Letdown Line Relief Valve HP-43.Caused by Lifting of Line Relief Valve.Limit Switch on Valve 2HP-12 Replaced & Limit Switch Location Being Changed to Prevent Recurrence ML19317F0831975-07-0303 July 1975 AO-287/75-08:on 750619,reactor Bldg Engineered Safeguards Pressure Transmitter Was Discovered Out of Calibr.Caused by Drift of Pressure Transmitter.Channel C of Pressure Transmitter Recalibr.Surveillance Will Continue ML19317F0421975-06-27027 June 1975 AO-287/75-07:on 750613,excessive RCS Cooldown Rate Occurred During Maint Shutdown.Caused by Operator Error.Evaluation Performed to Determine Max Allowable Cooldown Rate.Valve 3RC-66 Removed,Repaired & Replaced ML19312C1791975-06-12012 June 1975 Abnormal Occurrence Rept AO-269/75-06:on 750528,reactor Bldg High Pressure Trip Switch Setpoints Found Set Improperly. Caused by Omission from Sys Recalibr.Switches Reset & Instrument Procedures Revised ML19317D8721975-05-20020 May 1975 Abnormal Occurrence Rept AO-269/75-05:on 750506,during Liquid Waste Release,Process Radiation monitor,RIA-33, Failed.Caused by Water Leaking from Gasket Into Detector Junction Box.Box Repaired & Gasket Replaced ML19317D8651975-05-14014 May 1975 Abnormal Occurrence Rept AO-269/75-04:on 750430,during Emergency Start Test,Keowee Unit 1 Tripped Due to Low Thrust Bearing Oil Level Signal.Caused by Instability in Control Sys for Keowee Unit 2 While Operating in Unloaded Condition ML19317F2251975-04-11011 April 1975 AO-287/75-06:on 750327,inadvertent Isolation of Keowee Underground Feeder Occurred During Emergency Start Test. Caused by Deficiency in Test Procedure.Test Procedure Modified to Assure Breaker Is Closed at All Times ML19317D8481975-04-10010 April 1975 Abnormal Occurrence Rept 269/75-03:on 750326,B&W Informed Util of Defects in Fuel Rod of Spent Fuel Assembly 1A10.No Safety Hazard.Diagram of Defects Encl ML19317F4181975-03-12012 March 1975 AO-287/75-04:on 750226,engineered Safeguards Logic Buffer Failed.Caused by Intermittent Failure of Mercury Whetted Relay Contacts on Logic Buffer Analog Channel 1 Output. Buffer Replaced.Surveillance Program Adequate ML19317F3641975-02-24024 February 1975 AO-287/75-03:on 750209 Proper Overlap Between Control Rod Groups 6 & 7 Not Provided.Caused by Failure to Monitor Individual Rod Positions Necessitated by Faulty Indication Switch.Potential Sequence Problems Reviewed W/Personnel ML19317F1271975-02-18018 February 1975 AO-287/75-01 on 750203,reaction Protective Sys Channel C Indicated Low Reactor Coolant Temp.Caused by Steam Leaking from Feedwater Valve in Penetration Room & Condensing on Resistance Temp Detector.Penetration Room Purged ML19317F2431975-02-0909 February 1975 AO-287/75-02:on 750205,during Maint Shutdown,Unsuccessful Attempts to Open Valve 3LP-18 Revealed Fuse Failure in Control Power Transformer.Caused by Either Voltage Surge or Defective Fuse.Blown Fuse Replaced ML19317D9321975-01-21021 January 1975 Abnormal Occurrence Rept 269/75-01:on 750107,Channel a Reactor Coolant Pressure Buffer Amplifier Did Not Respond to Input.Caused by Faulty Operational Amplifier.Component Replaced ML19317F0931974-12-26026 December 1974 AO-287/74-11:on 741210,failure to Monitor Reactor Quadrant Power Tilt Occurred During 40% Power Physics Testing.Caused by Operator Error.Operations Supervisors Instructed in Measurement of Quadrant Power Tilt ML19317F0891974-12-0404 December 1974 AO-287/74-10:on 741119,ac Vital Instrumentation Bus Energized from Improper Source.Caused by Personnel Error. Inverter Replaced by Use of Regulated Ac Source. Interpretation of Tech Spec Reviewed W/Operating Personnel ML19317F0281974-11-29029 November 1974 AO-287/74-09:on 741114,personnel Hatch Gasket Failed During Hatch Leak Rate Test.Caused by Knife Edge of Door Off Center of Gasket.Hatch Inner Door Repaired & Hatch Successfully Completed Requirements for Leak Test ML19317F0191974-11-29029 November 1974 AO-287/74-08:on 741114,reactor Protective Sys Bistable Failed Following Flux Trip Setpoint Change.Cause Not Stated.High Flux Bistable Replaced & Proper Operation Verified ML19317F1031974-11-14014 November 1974 AO-287/74-07:on 741102,Channel a Pressure Transmitter, RC3A-PT1,found Out of Calibr.Caused by Drift in High Pressure Trip Setpoint.Pressure Transmitter Recalibr to Require Specs:Will Be Checked on Monthly Basis ML19317F1631974-11-12012 November 1974 AO-287/74-06:on 741029,leak in LPIS Piping in Decay Heat Removal Room Discovered.Caused by Failure of Piping Due to Low Pressure Injection Discharge Header Vibration.Sample Line Repaired & Vibration Coil Added ML19317F0681974-11-0707 November 1974 AO-287/74-05:on 741024,core Flood Discharge valve,3CF-1, Electrical Breaker Discovered Open & Tagged W/Padlock in Place But Not Locked.Caused by Personnel Error.Padlocks Now Rechecked After Locking ML19317D8831974-10-25025 October 1974 Abnormal Occurrence AO-269/74-17:on 741012,room Containing Low Pressure Injection Pumps 1B & 2B Flooded.Caused by Open Drain Valves.Evaluation of Sump Pump Reliability to Be Performed.Sump Pump Monitoring Alarm to Be Installed ML19317D9351974-10-23023 October 1974 AO-269/74-16:on 741008,contents of a Gaseous Waste Decay Tank Released to Auxiliary Bldg During Increased Vent Header Pressure.Caused by Operation of a Gaseous Waste Compressor & B Gaseous Waste Decay Tank During Release ML19308B0591974-10-23023 October 1974 Abnormal Occurrence AO-269/74-05:on 741008,RCS Letdown Flow to a Bleed Holdup Tank Caused Increased Vent Header Pressure.Caused by Operation of Gas Compressors During Performance of Mod Work.Control Operator Stopped RCS Flow ML19317D8281974-10-22022 October 1974 Abnormal Occurrence Rept AO-269/74-15:on 741007,core Flood Tank Pressure Not Increased Prior to Increasing RCS Pressure.Caused by Omission of Procedural Step.Checkoff for Procedure OP/1/A/1102/01 Revised ML19317F0801974-10-22022 October 1974 AO-287/74-04:on 741007,flow Instrumentation Indicated RCS Flow Imbalance.Cause Unknown.Reactor Operations at Full Flow Limited to Sys Flows Not Exceeding Core Life Valve & Restricted to Power Levels Less than 80% of Full Power ML19308A7301974-10-18018 October 1974 Supplemental Abnormal Occurrence Rept AO-269/74-12A Re Event on 740806.Describes Further Tests Performed 740819-0901 to Determine Cause of Low Boron Concentration.No Mechanism Identified for Cause of Dilution in Incore Flood Tank ML19317D9201974-10-18018 October 1974 Revised Abnormal Occurrence Rept AO-269/74-14:on 741005,4 Gallon Per Minute Reactor Coolant Leak Found.Caused by Leaking Diaphragm in Pressure Switch 1PS-364.Switch Isolated & Removed,Piping Capped ML19317D8401974-10-18018 October 1974 Abnormal Occurrence Rept AO-269/74-14:on 741005,pressure Switch 1PS-364 Found Leaking.Caused by Defective Diaphragm. Switch Removed & Piping Capped.No Adverse Effects on Health & Safety ML19317F1231974-09-27027 September 1974 AO-287/74-03:on 740915,Failure to Maintian Containment Integrity Occurred During Repairs to Engineered Safeguards Valve 3CS-5.Caused by Incorrect Evaluation Re Intermittent Operability of Valve ML19317F1761974-09-27027 September 1974 AO-287/74-02:on 740909,analysis Sample from Pressurizer Indicated Excess Oxygen Concentration.Caused by Personnel Misunderstanding & Continuous Venting Not in Effect from 740909-11.Oxygen Concentration in Pressurizer Restored ML19317F1871974-09-17017 September 1974 AO-287/74-01:on 740903,weld Failure Dectected on Reactor Coolant Pump Seal Injection Piping During Leak Test.Caused by Lack of Fusion Between Weld Fill Matl & Elbow Fitting. Defective Weld Repaired ML19312C4711974-08-30030 August 1974 AO-269/74-13:on 740816,inadvertent Radwaste Gas Release Occurred During Routine Drainage of Waste Gas Decay Tank B.Caused by Operator Error.Operating Procedure Being Revised 1976-01-07 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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