Pages that link to "NRC Form 306A"
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The following pages link to NRC Form 306A:
Displayed 50 items.
- 05000341/LER-1987-018, :on 870520,during Troubleshooting of Leakage Discovered in Drywell,Rwcu Inboard Isolation Valve Isolated Twice & Outboard Isolation Valve Once.Caused by Latent Heat Migration in Sys Piping.Valve Repacked (← links)
- 05000414/LER-1986-016, :on 860521,main Feedwater Isolation Occurred. Caused by Insufficient Info Provided by Mfg to Allow Adequate Initial Calibr of Feedwater Control Sys.Sys Tuned & Startup & Shutdown Procedures Revised (← links)
- 05000400/LER-1986-004-03, :on 861107,safety Injection Signal Occurred During Mod Work to safety-related Inverters.Caused by Operator Failure to Recognize That de-energizing Process Cabinets Would Set Off Signal.Safety Injection Reset (← links)
- 05000364/LER-1986-010-01, :on 860804,reactor Tripped During Testing of Solid State Protection Sys.Caused by Faulty Secondary Disconnecting Contacts on Train B Reactor Trip Bypass Breakers.Contacts Replaced as Needed (← links)
- 05000409/LER-1986-024, :on 860719,water Splashed Off Pipe Onto Solenoid Causing Ventilation Header Solenoids to Deenergize. Caused by Blown Fuse 30-2.Fuse Replaced (← links)
- 05000338/LER-1987-005-01, :on 870419,primary Coolant I-131 Dose Equivalent Specific Activity Exceeded 1.0 Mci/G Limit Set by Tech Spec 3.4.8.a Following Reactor Trip.Caused by Minor Fuel Cladding Defects in Reactor Core (← links)
- 05000382/LER-1986-025, :on 861022,reactor Trip Occurred.Caused by Trying to Maintain Steam Generator Levels at Low Reactor Power for Prolonged Period,Following Reactor Trip on 861021. Valve Positioner Replaced (← links)
- 05000382/LER-1986-022, :on 861020,control Room Isolation Occurred. Caused by Degraded Electrical Connection in Barton Model 765 Flow Transmitter.Transmitter Replaced (← links)
- 05000413/LER-1987-011-01, Forwards LER 87-011-01 Re Shutdown Due to Diesel Generator Inoperability Because of Mfg Deficiency.Part 21 Related (← links)
- 05000327/LER-1986-059, :on 861231,eight Fire Dampers in Diesel Generator Bldg Identified as Not Being Verified Functional by Visual Insp Every 18 Months.Caused by Personnel Error. Surveillance Instruction SI-233.3 Changed (← links)
- 05000336/LER-1999-011, :on 990823,thermal Reactor Power Limit Was Exceeded.Caused by Lack of Conservatism in Procedures & Alarm Setpoints Used to Limit Reactor Power.Revised Operating Procedures (← links)
- 05000317/LER-1998-011, :on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With (← links)
- 05000370/LER-1999-003-01, :on 990616,inadvertent Actuation of Turbine Driven Auxiliary Feedwater Pump Occurred.Caused by Inadequate Policy or Directive.Station Directives Will Be Reviewed & Appropriately Revised (← links)
- 05000293/LER-1999-008-02, :on 990805,automatic Scram Occurred While at 100% Power Due to Automatic Turbine Trip.Caused by Malfunction of Moisture Separator Drain Tank a Drain Valve Controller.Level Controllers Replaced.With (← links)
- 05000409/LER-1986-034, :on 861112,containment Ventilation Valves Closed Automatically When Indication on Containment Bldg Immediate Particulate Monitor Spiked High.Caused by Manipulation of Range Switch.Contacts Cleaned (← links)
- 05000413/LER-1999-014, :on 990816,missed Surveillances & Operation Prohibited by TS Was Noted.Caused by Defective Procedures or Programs Inappropriate TS Requirements.Affected Procedures/ Programs Were Revised & Testing Was Performed (← links)
- 05000302/LER-1997-028, :on 970902,flow Element Accuracy Uncertainty That May Be Greater than Assumed Identified.Caused by Design Error.No Immediate Corrective Actions Necessary.Testing of Existing Flow Elements to Be Completed by 971031 (← links)
- 05000413/LER-1987-002, :on 870111,unit Shutdown Commenced When Unidentified Reactor Coolant Leakage Greater than 1 Gpm Determined.Caused by Leak in Loop C RTD Manifold Tubing. Leak Repaired & Unit Returned to Power (← links)
- 05000423/LER-1987-003, :on 870114 & 0205,Train B Emergency Diesel Generator Did Not Start within Required 10 During Surveillance Testing.Caused by Inadequate Purge of Air from Fuel Injectors & Low Oil Temp.Maint Performed (← links)
- 05000338/LER-1997-007, :on 970818,NIS High Flux Trip Setpoint Errors Occurred.Caused by Inherent Inaccuracies Associated with Calorimetric Heat Balance at Low Power Levels.High Power Trip Setpoints Were Reduced (← links)
- 05000293/LER-1999-006-02, :on 990705,both EDGs Were Inoperable.Caused by Ambient Air Temp Exceeding 88 Degrees Fahrenheit.Temporary Mods Tm 99-41 & Tm 99-42,implemented for EDG a Were Completed on 990706.With (← links)
- 05000302/LER-1997-020, :on 970718,identified Failure of CREVS in-place Testing of HEPA Filters to Meet Improved TS Surveillance Requirement.Caused by Cognitive Personnel Error.Will Revise Ventilation Filter Test Program (← links)
- 05000382/LER-1997-024, :on 970528,emergency Diesel Generator Autostart Occurred Due to start-up Transformer Failure.Implemented Procedures OP-901-311,OP-901-511 & OP-901-513 (← links)
- 05000335/LER-1986-008-03, :on 860827,Train B Exhaust Ventilation Fan HVE-9B Became Inoperable When Thermal Overload Relay Spuriously Actuated & Redundant Train a Fan HVE-9A Found Inoperable Due to Oil Tank Level.Causes Not Identified (← links)
- 05000461/LER-1997-020, :on 970715,discovered Failure to Document Effect of Degraded Coatings in Containment on Eccs.Caused by Failure of Personnel to Perform Evaluation on Degraded Coatings.Performed Evaluation & Removed Degraded Coatings (← links)
- 05000424/LER-1999-002-03, :on 990630,high-energy Line Break Instrument Channels Were Inadequately Calibrated.Caused by Inadequate Surveillance Testing Procedures.Procedure Revs to Add Relay Testing in Progress.With (← links)
- 05000327/LER-1987-001, :on 870106,trip Setpoint for Acbs on Shutdown Boards That Feed Control & Auxiliary Bldg Vent Boards Discovered Incorrect.Caused by Design Error.Breaker Trip Settings Will Be Corrected (← links)
- 05000338/LER-1985-029, :on 851228,during Performance of RCS Leak Rate Test,Leak of 1.28 Gpm Noted.Caused by Reactor Vessel Seal Ring Leaks Chemical & Vol Control Sys Pipe Crack.Seal Rings & Pipe Replaced (← links)
- 05000382/LER-1987-001-01, :on 870330,gaseous Waste Mgt Effluent Radiation Monitor Alarm/Trip Setpoint Set Factor of 10 Too High Since Plant Startup.Caused by Personnel Error.Rms,Its Database & Data Base Change Methodology Under Review (← links)
- 05000414/LER-1999-001, :on 990115,relay Failure Occurred Which Resulted in Degradation of Auxiliary Feedwater Sys.Caused by Inadequate Single Failure Analysis.Maint Repaired Relay (← links)
- 05000289/LER-1999-008, :on 990604,discovered That Air Flow Through Each of RB Fan Cooler Units Was Below Design Basis Requirement.Caused by Accumulation of Boric Acid from Rc Leakage.Normal Cooling Coils Have Been Cleaned (← links)
- 05000409/LER-1987-001, :on 870107,reactor Scrammed When Turbine Stop Valve Partially Closed.Possibly Caused When Turbine Reset During Simulated Overspeed Test or Oil Pressure at Stop Valve Temporarily Decreasing.Valve Closed (← links)
- 05000220/LER-1987-004, :on 870210,discovered That Instrument Control Surveillance Test Not Performed on 870116,per Tech Specs. Caused by Failure to Complete Rev to Test Procedure Prior to Scheduled Test.Procedures Revised (← links)
- 05000483/LER-1999-001, :on 990119,failure to Implement Operating License Amend 106 Requirements within 30 Day Implementation Period Was Discovered.Caused by Programmatic Deficiency. Corrective Actions Implemented in Dec 1998.With (← links)
- 05000414/LER-1986-026-01, :on 860621,feedwater Isolation Occurred Due to Spurious hi-hi Steam Generator Level Signal.Caused by Design Problem Re Transfer from Main Steam Bypass Isolation Valve to Msiv.Procedures Will Be Revised (← links)
- 05000328/LER-1986-010-04, :on 861203,containment Phase B Isolation Occurred During Performance of Surveillance Procedure.Caused by Deficient Procedure.Procedures Re ESF Actuations During Testing Will Be Revised (← links)
- 05000334/LER-1999-002, :on 990121,4 Input Parameters Were Identified Which Underestimated DBA Dose.Caused by non-conservative Concurrent Iodine Spike Radiological Dose Calculation Methodology.Acs Have Been Implemented.With (← links)
- 05000461/LER-1999-001, :on 990129,determined Degradation of Bearings in Two Divisions of Shutdown Sws.Caused by Improper Assembly of Motor.Revised Vendor Manuals & Procedures to Address Shaft Current Concerns for Susceptible Motors (← links)
- 05000440/LER-1986-026, :on 860618,containment Isolation Valves Closed. Caused by Technician Inadvertently Grounding Power Lead During pre-operational Test.Technician Counseled.Testing Instructions to Include Caution Note (← links)
- 05000413/LER-1999-007, :on 990426,operation Prohibited by TS 3.4.7 Was Noted Due to Inoperable Train of Rhr.Caused by Inadequate Work Sequencing.Returned B Train RHR to Operable Status by Restoring Power to Valve 1NI136B (← links)
- 05000281/LER-1986-007-02, :on 860617,reactor Trip Occurred Due to High Level in Steam Generator A.Caused by Failure of Valve FCV-2478 to Close Due to Metal Debris Between Plug & Valve Seat.Metal Debris Removed & Valve Reassembled (← links)
- 05000461/LER-1999-004, :on 990126,plant Was Operating Outside Design Basis.Caused Because Design for CR Operator Dose Calculation Did Not Consider Single Failure of CR Ventilation Sys. Revised CR Operator Dose Calculation.With (← links)
- 05000414/LER-1998-007-03, :on 981211,mispositioned Thumbwheel on Process CS Circuit Card Caused Inoperability of Overtemperature & Overpower Delta Temp Functions.Caused by Inadequate Program Design.Revised Procedures (← links)
- 05000461/LER-1999-006, :on 990419,values Used for Containment & Drywell Free Vols Found to Be Smaller than Originally Analyzed Due to Inadequate Calculation Control During Initial Plant Const.With 9905517 Ltr (← links)
- 05000263/LER-1999-002-01, :on 990329,event Sequence That Results in Available ECCS Being Reduced to Less than That Assumed in Current Safety Analysis.Caused by Failure of Edg.Plant Operating Procedures Revised.With (← links)
- 05000316/LER-1986-023, :on 860715 & 18,erroneous Accumulator Level Indication Resulted in Low Accumulator Vol.Caused by Instrumentation Failure.Diagnostic Testing of Instrumentation Planned for Mar 1987 Outage (← links)
- 05000328/LER-1985-002-01, :on 850112,while Operating at 100% Power,Unit Experienced Automatic Reactor Trip from lo-lo Steam Generator Level on Loop.Caused by Failure of Discharge Valve LCV-6-106A on Heater Drain Tank Pump 3 (← links)
- 05000324/LER-1999-002-02, :on 990329,reactor Tripped.Caused by Failed Electrical Connections on Vibration Detector for Number 9 Main Turbine Bearing.Vibration Detectors for Main Turbine Number 9 Bearing Replaced.With (← links)
- 05000301/LER-1999-002-01, :on 990323,discovered That Red Channel of SG Pressure Indication Passes Through Fire Zone.Caused by 1983 Modification Oversight.Twice Per Shift Fire Round Has Been Established for Fire Zone Pending Cable Routing Correction (← links)
- 05000245/LER-1986-017-01, :on 860521,during Downpowering of Planned Shutdown,Reactor Pressure Dropped Briefly Then Increased Rapidly to 1,047 Psig,Causing Manual Reactor Scram.Rate Stop Adjustment Screws Replaced (← links)