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| Issue date | Title | Topic | |
|---|---|---|---|
| ML18039A666 | 31 December 1998 | Ro:On 981215,HRPCRM 2-RM-90-273C Was Declared Inoperable. Caused by Downscale Indication.Containment RM Will Be Utilized as Planned Alternate Method of Monitoring Until Hrpcrm 2-RM-90-273C Can Be Returned to Operable Status | Post Accident Monitoring |
| ML18032A418 | 2 July 1987 | Ro:On 870227 & 0505 Oil Spills Occurred Resulting in Oil Sheens.Spilled Matl Did Not Involve PCB-contaminated Oil. Feb Spill Went to Plant Intake Forebay & May Spill Went Directly Into Tennessee River | |
| ML18031B285 | 31 March 1987 | Special Rept:On 870321,loss of Seismic Monitoring Instrumentation Discovered.Caused by Inadequacy in Instructions & Training.All Instruments Removed from Site Will Be Repaired & Restored to Operation | |
| ML20024C061 | 29 June 1983 | Telecopy Ro:On 830613 & 14,train B Discovered Inoperable & Operability of Standby Gas Treatment Sys Trains Exceeded Tech Specs for Approx 6 H.Caused by Malfunctioning Square Root Converter.Plant Instruction Rev in Progress | |
| ML18025B724 | 9 February 1982 | Ro:On 820104,suspended Solids Samples Exceeded Daily Max Limit of 100 Mg/L.Caused by High Increase in Turbidity & Suspended Solids Due to 3.4 Inches of Rainfall.No Corrective Action Taken Because Occurrences Not Typical | |
| ML20009F669 | 30 June 1981 | Ro:On 810629,during Refueling Outage,Ultrasonic Test Insp Revealed Reactor Water Cleanup Sys Inboard Primary Containment Isolation Valve Indication.Cause Unknown. Indication Will Be Removed & Weld Repaired | |
| ML20010B863 | 5 March 1981 | RO 50-259/81-09:on 810304,during Evaluation of IE Info Notice 80-45,mode Selector Switch Had Same Deficiency Identified in Notice.Apparently Caused by Circuitry Design Deficiency.Procedure Revisions Will Be Made | |
| ML19343C114 | 10 February 1981 | Environ RO BFRO-50-259/8105:on 810131,combined Discharge of Spent Demineralizer Regenerants from Makeup Water Treatment Plant & Biothermal Research Facility Had Ph Value of 9.2, Exceeding Tech Spec Limits.Caused by Natural Phenomena | |
| ML20049A464 | 2 February 1981 | RO 50-259/8105:on 810131,during Normal Operation,Ph of Reservoir Was in Excess of Discharge Limit.Cause Unknown. Discharge of Demineralizer Regenerants Was Stopped.Raw Water Samples Were Taken & Analyzed for Ph | |
| ML20049A463 | 27 January 1981 | RO 50-259/8103:on 810124,during Normal Operation, Notification Was Received That 1-inch Vent Line on Scram Discharge Vol Was Not Seismically Qualified.Caused by Nonconformance to Design Requirements.Restraints Installed | |
| ML18025B363 | 5 December 1980 | Ro:On 801205,w/unit in Operation,Rhr Heat Exchanger 2C Was Removed from Svc Due to Leakage.Cause Is Undetermined. Surveillance Testing Was Performed Per Tech Specs | |
| ML19345B974 | 26 November 1980 | RO 50-260/80-47:on 801107,chlorine Residual Reached 0.49 mg/1 Exceeding Max Allowable of 0.05 mg/1.Caused by Failure of Main Condenser Cooling Water Pumps to Provide Adequate Dilution.Chlorination Stopped.Procedures Revised | |
| ML19347B595 | 8 October 1980 | Limiting Conditions of Operations Violation Rept:On 800928 & 29,Wheeler Reservoir Water Temp Exceeded Tech Spec Limit. Caused by Thermal Monitoring Sys Error.Unit 3 Sys Placed on Cooling Tower.Design Change Requests Being Prepared | |
| ML19347B629 | 8 October 1980 | Environ RO 50-259/8073:on 800928 & 29,temp Rise of Wheeler Reservoir Between Upstream & Downstream Thermal Monitors Exceeded Tech Specs.Caused by Extensive Rainfall & Lower than Normal Ambient Temp,Adding to Errors in Prediction | |
| ML20049A329 | 6 October 1980 | Ro:On 801004,w/unit Operating at 749 Mw,Load Limited,Hpci Declared Inoperable Due to High Level Indication in Exhaust Drain Pot Indicating Blockage of Drain Line.Caused by Faulty O-ring in Level Sensing Line | |
| ML20049A331 | 6 October 1980 | Ro:On 801006,faulty Indication on Outboard Isolation Valve of Reactor Coolant Isolation Sys Would Not Allow Operator to Be Aware of Actual Valve Position.Caused by Open Circuit in Valve Position Indication.Surveillance Testing Performed | |
| ML19326D856 | 15 July 1980 | RO 50-259/8054:on 800706,river Temp Exceeded Max Limitation for Over 1-h at Downstream Monitor.Caused by Computer Error. Predictive Computer Program Underestimated Max Downstream Temp by 2 F.Cooling Towers Used,Station Load Reduced | |
| ML19330A975 | 8 July 1980 | Ro:On 800708,during Routine Surveillance Instruction,Pcv 73-43,which Controls Cooling Water to Gland Seal Condensor & Lube Oil Cooler,Was Found Stuck in Closed Position.Cause Unknown.Equipment Expected to Be Returned to Svc by 800708 | |
| IR 05000296/1980024 | 30 June 1980 | RO-BFRO-50-296/8024:on 800628,during Routine Maint Shutdown, Approx 68 of 185 Control Rods Failed to Fully Insert When Reactor Was Manually Tripped.Unit Is Shut Down Until Cause Determined & Corrective Action Taken | |
| ML18025A959 | 30 June 1980 | RO-BFRO-50-296/8024:on 800628,during Routine Maint Shutdown, Approx 68 of 185 Control Rods Failed to Fully Insert When Reactor Was Manually Tripped.Unit Is Shut Down Until Cause Determined & Corrective Action Taken | |
| IR 05000260/1980025 | 17 June 1980 | RO-BFRO-50-260/8025:on 800617,Dresser Industries Safety Valves Identified as Possibly Having Guides W/Cracks. Condition Identified in Similar Valves Loaned to Another Util from Browns Ferry.Cause Unknown | |
| ML18025A951 | 17 June 1980 | RO-BFRO-50-260/8025:on 800617,Dresser Industries Safety Valves Identified as Possibly Having Guides W/Cracks. Condition Identified in Similar Valves Loaned to Another Util from Browns Ferry.Cause Unknown | |
| ML18024B349 | 1 February 1980 | RO 50-259/511:on 800201,w/Unit 1 in Cold Shutdown & Units 2 & 3 Operating Normally,Discovered Potential Loss of Secondary Containment If Primary Containment Purging Is Conducted During Hot Standby.Caused by Pressure Surge | |
| ML19290C681 | 18 January 1980 | RO 50-259/804:on 800118,w/Unit 1 in Refueling Outage,Water Cleanup Sys Inboard Primary Containment Isolation Valve 69-1 Had Indication Requiring Repair.Cause Unknown.Indication Removed | |
| ML19290C682 | 18 January 1980 | RO 50-259/805:on 800118,during Insp,Determined That Seismic Restraints Not Installed on Reactor Bldg closed-cooling Water Lines Inside Drywell.Restraints Will Be Installed | |
| IR 05000296/1979021 | 11 December 1979 | RO 50-296/79-21:on 791208,w/load Approx 200 Mwe Following Return to Svc After Fuel Outage,Difficulty Occurred in Maintaining drywell-to-torus Pressure Differential.Caused by Leak Around Equipment Hatch Seal.Fasteners Retightened | Backfit |
| ML18024B229 | 11 December 1979 | RO 50-296/79-21:on 791208,w/load Approx 200 Mwe Following Return to Svc After Fuel Outage,Difficulty Occurred in Maintaining drywell-to-torus Pressure Differential.Caused by Leak Around Equipment Hatch Seal.Fasteners Retightened | Backfit |
| ML18024B179 | 5 December 1979 | RO 50-296/79-19:on 791204,during Augmented Ultrasonic Insp of Core Spray Piping,Indication Located Adjacent to safe-end to Core Spray Pipe Weld.Caused by Stress Corrosion Cracking.Piping Replaced W/Carbon Steel | |
| ML18024B173 | 29 November 1979 | RO-50-259/79-32:on 791128,during Insp of Restraints,Typical Hanger Identified as Possibly Unacceptable.Caused by Possible Misapplication of Hanger.Insp & Analyses Will Be Conducted to Determine Effect on Sys | |
| IR 05000259/1979032 | 29 November 1979 | RO-50-259/79-32:on 791128,during Insp of Restraints,Typical Hanger Identified as Possibly Unacceptable.Caused by Possible Misapplication of Hanger.Insp & Analyses Will Be Conducted to Determine Effect on Sys | |
| IR 05000296/1979018 | 2 November 1979 | RO-50-296/79-18:on 791030,during Logic Testing Per LPCI Mods,Simultaneous Starting of Two RHR Pumps Occurred.Caused by Mismatch Between Current Transformer Ratios on Normal Supply to Shutdown Boards.Transformers Will Be Changed | |
| ML18024B197 | 2 November 1979 | RO-50-296/79-18:on 791030,during Logic Testing Per LPCI Mods,Simultaneous Starting of Two RHR Pumps Occurred.Caused by Mismatch Between Current Transformer Ratios on Normal Supply to Shutdown Boards.Transformers Will Be Changed | |
| ML18024A847 | 30 May 1979 | RO 50-260/79-011 on 790526:rod Inadvertently Pulled Three Notches During Attempt to Reach Criticality.Cause Not Established.Operator Interviewed | |
| IR 05000260/1979011 | 30 May 1979 | RO 50-260/79-011 on 790526:rod Inadvertently Pulled Three Notches During Attempt to Reach Criticality.Cause Not Established.Operator Interviewed | |
| ML18024A575 | 6 December 1978 | RO-50-296/782:Bendix Connectors Used Inside Primary Containment Which Failed post-aging Environ Test Were Modified by Potting Plug & Receptacle Portion of Connectors & Passed 10 Year Qualifying Tests | |
| ML18024A521 | 8 November 1978 | Supplementary Reportable Occurence Rept BFRO-50-296/7822: on 780822,during Startup at 3 Percent Thermal Pwr,Msrv 1-4 Opened & Did Not Completely Close Resulting in Excessive Cooldown Rate.Caused by Excessive Pilot Leakage | |
| ML18024A523 | 8 November 1978 | Supplementary Reportable Occurrence Rept#BFRO-50-296/7821 on 780817.Following Reactor Scram,Cooldown Rate Was Exceeded Due to Safety Valves Actuating & Not Completely Closing. Caused by Excessive Pilot Leakage | |
| IR 05000296/1978021 | 8 November 1978 | Supplementary Reportable Occurrence Rept#BFRO-50-296/7821 on 780817.Following Reactor Scram,Cooldown Rate Was Exceeded Due to Safety Valves Actuating & Not Completely Closing. Caused by Excessive Pilot Leakage | |
| ML18024A538 | 8 November 1978 | RO#50-296/7822 on 780822:during Startup at 3% Thermal Pwr, MSRV 1-4 Opened & Did Not Reclose Completely,Resulting in Excessive Vessel Cooldown Rate,Due Apparently to Excessive Pilot & second-stage Leakage in the Valves | |
| IR 05000296/1978022 | 8 November 1978 | RO#50-296/7822 on 780822:during Startup at 3% Thermal Pwr, MSRV 1-4 Opened & Did Not Reclose Completely,Resulting in Excessive Vessel Cooldown Rate,Due Apparently to Excessive Pilot & second-stage Leakage in the Valves |