IR 05000296/1979021
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| ML18024B229 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/11/1979 |
| From: | Abercrombie H TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 8001140293 | |
| Download: ML18024B229 (4) | |
Similar Documents at Browns Ferry | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML18039A6661998-12-31031 December 1998
[Table view]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 ML18032A4181987-07-0202 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 ML18031B2851987-03-31031 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 ML20024C0611983-06-29029 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 ML18025B7241982-02-0909 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 ML20009F6691981-06-30030 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 ML20010B8631981-03-0505 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 ML19343C1141981-02-10010 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 ML20049A4641981-02-0202 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 ML20049A4631981-01-27027 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 ML18025B3631980-12-0505 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 ML19345B9741980-11-26026 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 ML19347B5951980-10-0808 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 ML19347B6291980-10-0808 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 ML20049A3291980-10-0606 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 ML20049A3311980-10-0606 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 ML19326D8561980-07-15015 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 ML19330A9751980-07-0808 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 05000296/19800241980-06-30030 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 ML18025A9591980-06-30030 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 05000260/19800251980-06-17017 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 ML18025A9511980-06-17017 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 ML18024B3491980-02-0101 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 ML19290C6811980-01-18018 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 ML19290C6821980-01-18018 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 05000296/19790211979-12-11011 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 ML18024B2291979-12-11011 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 ML18024B1791979-12-0505 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 ML18024B1731979-11-29029 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 05000259/19790321979-11-29029 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 05000296/19790181979-11-0202 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 ML18024B1971979-11-0202 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 ML18024A8471979-05-30030 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 05000260/19790111979-05-30030 May 1979 RO 50-260/79-011 on 790526:rod Inadvertently Pulled Three Notches During Attempt to Reach Criticality.Cause Not Established.Operator Interviewed ML18024A5751978-12-0606 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 ML18024A5211978-11-0808 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 ML18024A5231978-11-0808 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 05000296/19780211978-11-0808 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 ML18024A5381978-11-0808 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 05000296/19780221978-11-0808 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 1998-12-31 Category:LER) MONTHYEARML18039A6661998-12-31031 December 1998
[Table view]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 ML18032A4181987-07-0202 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 ML18031B2851987-03-31031 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 ML20024C0611983-06-29029 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 ML18025B7241982-02-0909 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 ML20009F6691981-06-30030 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 ML20010B8631981-03-0505 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 ML19343C1141981-02-10010 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 ML20049A4641981-02-0202 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 ML20049A4631981-01-27027 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 ML18025B3631980-12-0505 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 ML19345B9741980-11-26026 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 ML19347B5951980-10-0808 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 ML19347B6291980-10-0808 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 ML20049A3291980-10-0606 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 ML20049A3311980-10-0606 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 ML19326D8561980-07-15015 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 ML19330A9751980-07-0808 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 05000296/19800241980-06-30030 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 ML18025A9591980-06-30030 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 05000260/19800251980-06-17017 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 ML18025A9511980-06-17017 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 ML18024B3491980-02-0101 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 ML19290C6811980-01-18018 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 ML19290C6821980-01-18018 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 05000296/19790211979-12-11011 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 ML18024B2291979-12-11011 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 ML18024B1791979-12-0505 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 ML18024B1731979-11-29029 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 05000259/19790321979-11-29029 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 05000296/19790181979-11-0202 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 ML18024B1971979-11-0202 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 ML18024A8471979-05-30030 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 05000260/19790111979-05-30030 May 1979 RO 50-260/79-011 on 790526:rod Inadvertently Pulled Three Notches During Attempt to Reach Criticality.Cause Not Established.Operator Interviewed ML18024A5751978-12-0606 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 ML18024A5211978-11-0808 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 ML18024A5231978-11-0808 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 05000296/19780211978-11-0808 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 ML18024A5381978-11-0808 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 05000296/19780221978-11-0808 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 1998-12-31 Category:TEXT-SAFETY REPORT MONTHYEARML18039A9041999-10-15015 October 1999
[Table view]LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML20210N1221999-08-0202 August 1999 Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML20209J0771999-07-16016 July 1999 Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML20196F8811999-06-23023 June 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr. ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205F9341999-04-0101 April 1999 Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr. ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6661998-12-31031 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 ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML20199F2791998-12-0303 December 1998 Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept ML20198D9621998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr 1999-09-30 |
Inspection Report - Browns Ferry - 1979021 | |
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REGULATORY ORMATION Ol'STRISUTION SYSl (RODS)ACCESSION NBR:80011r10293 DOC~DATE: 79/12/11 NOTARIZED'O PACiL:50 296 Browns Perry Nuclear Power Stat>onr Onlt 3i Tennessee AOTH~NAME AUTHOR AFFILIATION ASPACROMBIEiH
~L Tennessee Val 1 ey Author f ty ABC lP~NAME'ECIPIEblT'FFILIATION DOCKET 05000296 SUBJECT: RO 50 296 retur n to ma i nta i ni by leak a DISTRIBUTION CODE: TifLEe NOTES:/7921:on 791208rw/load approx 200 MNe following svc after fuel outageidifficulty occurred in ng drywell to.-torus pressure differential, Caused round equipment hatch seal,F'asteners ret19Rteneds M007S COPIES RECEIVED;L'TR g ENCL+SIZE: L LEA (Backfit)REC IP I EN 1'D CODE/NAME INTE~01 REG ILE NSIC S HANAUER EXTERNAL: 03 LPDR COPIES L'fiR ENCL 1 2 i 1 RECIPIENT ID CODE/NAME 02 NRC PDR MPA R IRELAND COPIES LlTA"ENCL 1 1 i 1 ggQ~gpss X 0 TOTAL NUMBER OF COPIES REQUIRED;LTTR 9 ENCL 0 R I s Ni, kR l'RN I, R'l if,l h rS, N II N II I]l R y sR NII R,'l S>~I CN IN'li f I'C lt,)R N I"I I N l'IN l Rn I.f-R 4 p s RRSR R
'I CGA TA NiC vesiber XX%979'SNRO'REoi~g'j.P.OREH.LV,",:
.t TL',PgTg, Region.XX,.;',;:-', w~eseSR Mf~z'f~tte Street,'g'.',-'.'.,'.g.g.UPRiGHT','.'uite ZlDQ,'.':.-'-',.j.D.GHEHDEN." Atkaajta,~rgb 393g9,',;';,-.~"': W-8.KEHN, 9 Off I p p 8 q f."..j f J, LOHG';.-*";"}p,',.)MURPHY g, T, SUTHERLAND gs EFR9 58-296/792>.
'~Reports aa8er Technics Spec~gcaaf g 7 2.<3.XCma ae accorxence-Technical ByeciHcatiaa.
hxvaiva8: 4 7 4,,2.g Candicions Pfior ca Occurrence I Unit f.ac 970 Kfe, end-of-core eoastcbwn ,Unit 2 st S39 NMe, Hmitd bF 2'eactor feed pump maintenance.
Uakt 3 ibad at zpproxhuateiy 260 HWe foilevJng return ter service af the unit-fracn re&xeHng, cmtage st 163.5, k2/S/79 MC ia eeet p~reai I Identifkaation and Descry tiom ef Qccnmence be%.ag eaKLskderod.
w 8 i, Abercrombie
>'-':-.',"';";;"'.','".";"~'g":,~,".Passer Flaa,e, Superintendent
..-',';...*-".."'..8m~F~~NucIeax plume/'*~\C I ooo>>4o 2'fg~~-" a.u t~~l f~4*4 DHHmBy in maintaining de'yeeXX&Axus pxessuxe cKHerenchQ
~~catect problems*with dryva21 leakage.Farther invastigatfma.
reveals&mt.exceask~e d~kX Leakage,existed Leak psch.%8eatiHed cu4 repaired ae 0839>>XZ(9t79>within 45 bc'ment par Yaebnicaf Speciff.cation 4 2 4 2 h(2)>C.~et Cause of Occurrence I I XeA am&southeast equipaumt hatch esaX due tc heaenad fsscenees.
Retaught'en%us of faateaers fmmeNeceXy texmfaated
%esker.other Rebated Events-: '..,',-',-, None I Corrective Act$.on Takeo, or Pkannnk'Retightening cf fasteners corrected Xaahage ocher.corrective sctien is O.I/l I