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| Issue date | Title | Topic | |
|---|---|---|---|
| 05000259/LER-1980-031, Updated LER 80-031/03X-1:on 820415,during 4 Kv Shutdown Bus 2 Transfer,Fault on Normal Feeder Bus from TS1B to 480-volt SD Bd 1B Caused Loss of Power to Board.Caused by Fault Condition at Busway Joint Above Board | 1 June 1982 | Updated LER 80-031/03X-1:on 820415,during 4 Kv Shutdown Bus 2 Transfer,Fault on Normal Feeder Bus from TS1B to 480-volt SD Bd 1B Caused Loss of Power to Board.Caused by Fault Condition at Busway Joint Above Board | |
| 05000259/LER-1982-018, Updated LER 82-018/03X-1:on 820317,inspector Observed Bolts Missing from Reactor Core Isolation Cooling Turbine Exhuast Rupture Diaphragm Assembly.Outer Rupture Diaphragm Missing. Caused by Failure to Install Outer Rupture Disc | 1 June 1982 | Updated LER 82-018/03X-1:on 820317,inspector Observed Bolts Missing from Reactor Core Isolation Cooling Turbine Exhuast Rupture Diaphragm Assembly.Outer Rupture Diaphragm Missing. Caused by Failure to Install Outer Rupture Disc | |
| 05000259/LER-1982-023, Followup LER 82-023/03X-2:on 820327,recirculation Pump 1A Tripped Due to Spurious Generator Starter Relay Operation. Caused by Hi-temp Relay Trip.Relay Reset in 20 Minutes & Pump Returned to Svc.No Recurrence Control Planned | 13 October 1982 | Followup LER 82-023/03X-2:on 820327,recirculation Pump 1A Tripped Due to Spurious Generator Starter Relay Operation. Caused by Hi-temp Relay Trip.Relay Reset in 20 Minutes & Pump Returned to Svc.No Recurrence Control Planned | |
| 05000259/LER-1982-039, Reissued LER 82-039/03L-0:on 820609,fuse Blew Resulting in Inboard Primary Containment Isolation.Caused by Shorted Coil for Relay 16A-K66B,GE Type CR120A.Fuse & Relay Coil Replaced & Hydrogen Analyzers Returned to Normal | 6 July 1982 | Reissued LER 82-039/03L-0:on 820609,fuse Blew Resulting in Inboard Primary Containment Isolation.Caused by Shorted Coil for Relay 16A-K66B,GE Type CR120A.Fuse & Relay Coil Replaced & Hydrogen Analyzers Returned to Normal | |
| 05000259/LER-1982-064, Updated LER 82-064/03X-1:on 820823 & Jan 1984,Station II Cable Tray Fixed Spray Sys Did Not Meet Tech Spec Requirements.Caused by Restriction in Supply Line Strainer Due to Buildup of Silt & Clam Shells | 20 April 1984 | Updated LER 82-064/03X-1:on 820823 & Jan 1984,Station II Cable Tray Fixed Spray Sys Did Not Meet Tech Spec Requirements.Caused by Restriction in Supply Line Strainer Due to Buildup of Silt & Clam Shells | Fire Watch |
| 05000259/LER-1982-089, Updated LER 82-089/03T-1:on 821103,primary Containment Purge Sys Failed to Achieve Required Flow Rate.Caused by Sand Dust Clogging HEPA Filters.New Filters Installed | 8 April 1983 | Updated LER 82-089/03T-1:on 821103,primary Containment Purge Sys Failed to Achieve Required Flow Rate.Caused by Sand Dust Clogging HEPA Filters.New Filters Installed | |
| 05000259/LER-1983-018, Updated LER 83-018/031-2:on 830325,while Performing SI 4.2.A-13,standby Gas Train B Found Inoperable.Caused by Erratic Mcdonnel & Miller Flow Switch.Switch Replaced & SI 4.7.B-1 & SI 4.7.A-13 Completed | 27 July 1984 | Updated LER 83-018/031-2:on 830325,while Performing SI 4.2.A-13,standby Gas Train B Found Inoperable.Caused by Erratic Mcdonnel & Miller Flow Switch.Switch Replaced & SI 4.7.B-1 & SI 4.7.A-13 Completed | |
| 05000259/LER-1983-029, Updated LER 83-029/03L-1:on 830604,during Standby Gas Treatment Sys Operability Test,Train B Discovered Inoperable.Caused by Erratic Mcdonnel & Miller Model AF-1 Flow Switches.Damper Adjusted.W/Undated Ltr | 27 February 1984 | Updated LER 83-029/03L-1:on 830604,during Standby Gas Treatment Sys Operability Test,Train B Discovered Inoperable.Caused by Erratic Mcdonnel & Miller Model AF-1 Flow Switches.Damper Adjusted.W/Undated Ltr | |
| 05000259/LER-1983-066, Updated LER 83-066/03X-1:on 831112,interlock That Prevents Bridge Travel Over Core W/One Rod Withdrawn & Fuel Grapple Extended Failed to Operate,Resulting in Loss of Rod Block Function.Caused by Improper adjustment.W/840309 Ltr | 9 March 1984 | Updated LER 83-066/03X-1:on 831112,interlock That Prevents Bridge Travel Over Core W/One Rod Withdrawn & Fuel Grapple Extended Failed to Operate,Resulting in Loss of Rod Block Function.Caused by Improper adjustment.W/840309 Ltr | |
| 05000259/LER-1984-004, Updated LER 84-004-01:on 840106,reactor Mode Switch Moved from Run to Startup,Causing Half Scram.Caused by Personnel Error.Unit Manually Scrammed.Operator & Nuclear Engineer Counseled Re Use of Rod Notch Override | 11 April 1984 | Updated LER 84-004-01:on 840106,reactor Mode Switch Moved from Run to Startup,Causing Half Scram.Caused by Personnel Error.Unit Manually Scrammed.Operator & Nuclear Engineer Counseled Re Use of Rod Notch Override | Half scram |
| 05000259/LER-1984-007, Followup LER 84-007-01:on 840127,operator Observed Decreasing Pressure on Control Atmospheric Dilution Tanks. Caused by Two Isolation Valves Being in Closed Position. Operating Instructions Revised | 2 March 1984 | Followup LER 84-007-01:on 840127,operator Observed Decreasing Pressure on Control Atmospheric Dilution Tanks. Caused by Two Isolation Valves Being in Closed Position. Operating Instructions Revised | |
| 05000259/LER-1984-014, Updated LER 84-014-01:on 840222,reactor Scrammed When Turbine High Pressure First Stage Pressure Exceeded 142 Psig W/Turbine Stop Valves Closed.Caused by Procedural Error. Operating Instruction Revised | 13 March 1984 | Updated LER 84-014-01:on 840222,reactor Scrammed When Turbine High Pressure First Stage Pressure Exceeded 142 Psig W/Turbine Stop Valves Closed.Caused by Procedural Error. Operating Instruction Revised | |
| 05000259/LER-1984-022, Updated LER 84-022-01:on 840212,investigation Determined That Single Failure or LOCA & Loss of Offsite Power Could Cause Equipment Necessary for Electrical Board Room Cooling to Be Lost.Caused by Design Oversight | 20 July 1984 | Updated LER 84-022-01:on 840212,investigation Determined That Single Failure or LOCA & Loss of Offsite Power Could Cause Equipment Necessary for Electrical Board Room Cooling to Be Lost.Caused by Design Oversight | |
| 05000259/LER-1985-049, Corrected Page 1 to LER 85-049-00:on 850623,during Performance of Work on Diesel Generator Battery Racks, Several Rack Support Studs Found Broken.Caused by Use of Stud Matl Not Suitable for Welding | 25 October 1985 | Corrected Page 1 to LER 85-049-00:on 850623,during Performance of Work on Diesel Generator Battery Racks, Several Rack Support Studs Found Broken.Caused by Use of Stud Matl Not Suitable for Welding | |
| 05000259/LER-1985-054, Advises That LER 85-054-00 Cancelled | 10 February 1986 | Advises That LER 85-054-00 Cancelled | |
| 05000260/LER-1981-052, Updated LER 81-052/03X-1:on 811007,containment Atmosphere Hydrogen Analyzer B Sample Return Pump Discovered Cycling. Probably Caused by Randon Failure.Gas Calibr Performed & Analyzer Returned to Svc | 12 April 1982 | Updated LER 81-052/03X-1:on 811007,containment Atmosphere Hydrogen Analyzer B Sample Return Pump Discovered Cycling. Probably Caused by Randon Failure.Gas Calibr Performed & Analyzer Returned to Svc | |
| 05000260/LER-1982-010, Corrected LER 82-010/03L-0 on 811021,during Full Power,Avg Power Range Monitor Output Signal Calibr Was Not Performed within Required Frequency During 811014-28.Caused by Personnel Error.Personnel Instructed to Be More Careful | 4 March 1982 | Corrected LER 82-010/03L-0 on 811021,during Full Power,Avg Power Range Monitor Output Signal Calibr Was Not Performed within Required Frequency During 811014-28.Caused by Personnel Error.Personnel Instructed to Be More Careful | |
| 05000260/LER-1982-013, Updated LER 82-013/03X-1:on 820412,pressure Switch 2-PS-68-96 Found to Operate Above Tech Spec Limits.Caused by Drifted Calibr.Barton Model 288 Pressure Switch Recalibr, Functionally Tested & Returned to Svc | 1 June 1982 | Updated LER 82-013/03X-1:on 820412,pressure Switch 2-PS-68-96 Found to Operate Above Tech Spec Limits.Caused by Drifted Calibr.Barton Model 288 Pressure Switch Recalibr, Functionally Tested & Returned to Svc | |
| 05000260/LER-1982-028, Followup LER 82-028/03X-3:on 810921,turbine Reactor Bldg Doors 237 & 238 Opened Simultaneously,Breaching Secondary Containment.Caused by Failed Folger Adams Interlock Sys Due to Loose Door Latch Screws.Procedures Revised | 9 March 1984 | Followup LER 82-028/03X-3:on 810921,turbine Reactor Bldg Doors 237 & 238 Opened Simultaneously,Breaching Secondary Containment.Caused by Failed Folger Adams Interlock Sys Due to Loose Door Latch Screws.Procedures Revised | |
| 05000260/LER-1983-074, Updated LER 83-074/03X-1:on 831105 & 10,turbine Exhaust Inner Rupture Diaphragms Failed During HPCI Initiation. Investigation Underway to Determine Cause of Failures. Diaphragms Replaced & HPCI Returned to Svc | 5 December 1983 | Updated LER 83-074/03X-1:on 831105 & 10,turbine Exhaust Inner Rupture Diaphragms Failed During HPCI Initiation. Investigation Underway to Determine Cause of Failures. Diaphragms Replaced & HPCI Returned to Svc | |
| 05000260/LER-1986-003, Corrected Page 2 to LER 86-003-00:on 860226,energized Isolation Logic Tripped.Caused by Personnel Error.Temporary Cover for Protection Against Accidental Bumping of Bus Transfer Switch Provided | 10 April 1986 | Corrected Page 2 to LER 86-003-00:on 860226,energized Isolation Logic Tripped.Caused by Personnel Error.Temporary Cover for Protection Against Accidental Bumping of Bus Transfer Switch Provided | |
| 05000296/LER-1979-005, Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved | 27 April 1984 | Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved | |
| 05000296/LER-1983-026, Supplemental LER 83-026/03X-4:on 830411,while Attempting to Establish EECW Flow Rate to Emergency Diesel Generator 3 Coolers,Head on HX Found Cracked.Caused by Mfg Defect.Cast Iron Head Replaced | 25 November 1983 | Supplemental LER 83-026/03X-4:on 830411,while Attempting to Establish EECW Flow Rate to Emergency Diesel Generator 3 Coolers,Head on HX Found Cracked.Caused by Mfg Defect.Cast Iron Head Replaced | Hydrostatic |
| 05000296/LER-1984-004, Followup LER 84-004-01:on 840228,RHR Outboard Loop II Isolation Valve CFV-74-67 Stem Found Broken Upon Disassembly.Caused by Overloading.Valve Stem Replaced W/Stronger & More Durable Matl | 15 June 1984 | Followup LER 84-004-01:on 840228,RHR Outboard Loop II Isolation Valve CFV-74-67 Stem Found Broken Upon Disassembly.Caused by Overloading.Valve Stem Replaced W/Stronger & More Durable Matl | |
| 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 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 | |
| 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 | |
| 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 | |
| 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 | |
| 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 | |
| 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 |
| 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 | |
| ML16148A396 | 3 December 1980 | LER 80-009 Has Been Cancelled | Backfit |
| ML17276B802 | 31 December 1981 | BWR Transient Analysis Model Utilizing Retran Program. | |
| ML18024A449 | 29 September 1978 | LER#78-024/03L-0 on 780911:during Refueling While Performing Surveillance Instru SI-42B-31 2 Broken Wire Was Found on Signal Lead for RCIC Turbine High Steam Flow Switch PDIS-71- 1B Which Provides RCIC Isolation.Loose Connection Repaired | |
| ML18024A457 | 29 September 1978 | LER#78-025/01T-0 on 780917:during refueling,4 Mstv'S Exceeded Leakage Limits.Defective Valves Will Be Repaired & Retested | |
| ML18024A490 | 13 October 1978 | LER 78-016/01T-0:on 780930,cracking Discovered in 1-inch Instrument Line & 3/4-inch Bonnet Vent Line on FCV-68-1. Cause Undetermined | |
| ML18024A494 | 17 October 1978 | LER 78-026/03L-0:on 780924,during Refueling Outage,Smoke Detector XS-39-93KB Alarmed W/O Cause & Could Not Be Cleared.Caused by Normal Aging | |
| ML18024A498 | 25 October 1978 | LER 78-017/03L-0:on 781004,drywell Oxygen Concentration Was Not Reduced to 4% within 24 H Period After Placing Reactor in Run Mode.Caused by Personnel Safety Considerations During Repair of Inner Drywell Air Lock Repairs | |
| ML18024A518 | 2 November 1978 | Monthly Oper Rept for Oct 1978 | Packing leak Scram Discharge Volume |
| 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 | |
| ML18024A527 | 8 November 1978 | LER#78-027/03L-0 on 781012:during Refueling Outage,Panel 3-25-327 Was Inoperable,Placing 2 Smoke Detector Zones Out of Svc.Caused by a Contact on Power Transfer Relay Which Failed to Close After Short Power Interruption | |
| ML18024A534 | 6 November 1978 | LER#78-028/03L-0 on 781014:during Refuel outage,1 Smoke Detector XS-39-108ZE in Mech Equip Room on Elevation 617 Caused False Alarm That Would Not Clear.Caused by Normal Natural Aging of Detector | |
| 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 | |
| ML18024A561 | 27 November 1978 | LER#78-030/03L-0 on 781031:evidence of Grease in 6 Snubbers Located in Core Spray,Main Steam & Residual Heat Removal Sys.Snubbers Replaced.Recurrence Control Action Incl Replacement of Grease Fittings W/Those Incompatible W/Guns | |
| ML18024A574 | 4 December 1978 | LER#78-018/03L-0 on 781103:reactor Pressure Switch PS-6B-96, Switch 1 Failed to Operate During Surveillance Testing. Switch Exercised & Adjusted | |
| 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 | |
| ML18024A579 | 7 December 1978 | LER#78-020/03L-0 on 781110:during Normal Pwr Oper,Reactor & Turbine Bldg & Refueling Zone Ventilation Exhaust Monitor, RM-90-250 Became Inoperable.Instr & Its Sensing Line Dried Out & Returned to Svc | |
| ML18024A588 | 11 December 1978 | LER#78-031/01T-0 on 781128:during CRD Scram Timing & Associated LPRM Connect on Verification Noted That All LPRMs Had Been Connected in Reverse Order.Caused by Lack of Explanation in Documents Describing Connection Procedure |