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 Issue dateTitleTopic
05000244/LER-1976-007, Revised LER 76-07/30:on 760207,relays for Train a Containment Isolation & Ventilation Isolation Failed to Latch.Caused by MG-6 Relays Having Improper Latch Screw Factory Adjustment25 May 1977Revised LER 76-07/30:on 760207,relays for Train a Containment Isolation & Ventilation Isolation Failed to Latch.Caused by MG-6 Relays Having Improper Latch Screw Factory Adjustment
05000244/LER-1976-014, Updated LER 76-014/03O-1:on 760412,N44 Power Range Detector High Voltage Power Supply Failed.Caused by Defective Modular Block Part IV-101.Power Supply Recalibr20 October 1976Updated LER 76-014/03O-1:on 760412,N44 Power Range Detector High Voltage Power Supply Failed.Caused by Defective Modular Block Part IV-101.Power Supply Recalibr
05000244/LER-1976-024, Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking8 June 1977Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion CrackingBoric Acid
05000244/LER-1976-027, Updated LER 76-027/03O-1:on 761216,liquid Noticed Coming Through Insulation on 2-inch Letdown Diversion Line.Caused by Pinhole Leak in Socket Weld Between Pipe & Elbow.Section Line Replaced27 May 1977Updated LER 76-027/03O-1:on 761216,liquid Noticed Coming Through Insulation on 2-inch Letdown Diversion Line.Caused by Pinhole Leak in Socket Weld Between Pipe & Elbow.Section Line Replaced
05000244/LER-1982-003, RO 82-007/01T:on 820125,unit Experienced Event Described in LER 82-003 Leading to RCS Cooldown Rate Greater than 100 F/H.Further Info Will Be Submitted w/14-day Written Rept24 February 1982RO 82-007/01T:on 820125,unit Experienced Event Described in LER 82-003 Leading to RCS Cooldown Rate Greater than 100 F/H.Further Info Will Be Submitted w/14-day Written Rept
ML17059A3616 July 1994Emergency Action Level Verification & Validation Rept.Earthquake
ML17244A34324 January 1979LER 79-001/03L-0 on 790103:during Test C,Safety Injection Pump Failed to Start from Bus 14 Breaker on First Attempt. Caused by Loose Wire Connection to Alarm Switch in Circuit Breaker.Switch Replaced
ML17244A48515 March 1979Annual Financial Rept 1978.Temporary Modification
ML17244A5218 May 1979Monthly Operating Rept for Apr 1979Boric Acid
ML17244A54129 May 1979Offsite Dose Calculating Manual
ML17244A5872 July 1979Inservice Insp Program for 1980-89 (App B of QA Manual)Hydrostatic
Nondestructive Examination
Liquid penetrant
ML17244A7659 August 1979Monthly Operating Rept for Jul 1979
ML17244A79731 December 1978Annual Operating Rept 1978Boric Acid
Shutdown Margin
Fire Barrier
Hydrostatic
Backfit
ML17244A81712 September 1979Monthly Operating Rept for Aug 1979Boric Acid
ML17244A82031 August 1979Discusses RO 79-17 Re Boric Acid Storage Tanks Out of Spec for Vol & % Weight of Boric Acid.Tanks Restored to within SpecsBoric Acid
Backfit
ML17244A86731 August 1979Sixty-Day Response to IE Bulletin 79-14, 'Seismic Analysis for As-Built Safety-Related Piping Sys.'Boric Acid
ML17244A86831 August 1979Piping & Piping Analysis Drawing List. Attachment 1 to 60-day Response to IE Bulletin 79-14Boric Acid
ML17249A19410 October 1979Monthly Operating Rept for Sept 1979
ML17249A20010 October 1979LER 79-018/03L-0:on 790913,output Breaker to Bus 16 Did Not Close.Caused by Overcurrent Relay Contact Lacking Continuity.Relay Inspected & Actuated
ML17249A29015 November 1979App C to QA Manual Re Revised Inservice Pump & Valve Testing Program for May 1979-Dec 1980Safe Shutdown
Boric Acid
ML17249A29619 November 1979Discussion of TMI Lessons Learned Short-Term Requirements.Anticipated operational occurrence
ML17249A3296 December 1979Design Analysis Adequacy of Station Electric Distribution Sys Voltages.
ML17249A3313 December 1979Ro:On 791201,air Ejector Radiation Monitor Was Detected Trending Upwards on Radiation Monitoring Recorder.Leak Test Measured Approx 0.007 Gallons/Minute.Facility Shut Down on 791203
ML17249A34531 October 1979Steam Generator Water Hammer Technical Evaluation.
ML17249A36211 December 1979RO 79-023:on 791207,liquid Penetrant Examination of safe- End of 4-inch Relief Nozzle Adjacent to Nozzle to safe-end Weld Revealed 6-inch Long Indication.Further Analysis Required to Determine CauseLiquid penetrant
Backfit
ML17249A37031 December 1979Fuel & LOCA Evaluation of Mixed Oxide Fuel Assemblies.
ML17249A3723 July 1979Plant Transient Analysis, Revision 1Boric Acid
Shutdown Margin
ML17249A37328 November 1979Addendum to Criticality Analysis for Fuel Storage Racks to Address Storage of Mixed Oxide Fuel Assemblies.
ML17249A37414 December 1979Cycle 10 SAR W/Mixed Oxide Assemblies.Boric Acid
Shutdown Margin
ML17249A38031 December 1979Safe Shutdown - Fire Study.Safe Shutdown
Boric Acid
Fire Barrier
Fire Watch
ML17249A45128 December 1979Discussion of TMI Lessons Learned Short-Term Requirements.Boric Acid
Reactor Vessel Water Level
Anticipated operational occurrence
Emergency Lighting
Earthquake
ML17249A4839 January 1980Monthly Operating Rept for Dec 1979Boric Acid
ML17249A51023 January 1980Design Analysis,Rcs Subcooling Margin Monitoring Sys Error Analysis.
ML17249A5738 February 1980Monthly Operating Rept for Jan 1980
ML17249A60310 October 1979Design Criteria,Spent Fuel Cooling Sys, Revision 1Safe Shutdown Earthquake
Operating Basis Earthquake
Spent Fuel Pool Instrumentation
Earthquake
ML17249A7687 March 1980Monthly Operating Rept for Feb 1980
ML17249A82910 April 1980Monthly Operating Rept for Mar 1980
ML17249A84714 April 1980RO 80-003:eddy Current Exams Conducted to Detect Potential Tube Defects.Based on Results,Pulling Initiated to Remove Tube W/Abnormal Absolute SignalBackfit
ML17249A8988 May 1980Monthly Operating Rept for Apr 1980
ML17249A97331 December 1979Design Review of Plant Shielding & Environ Qualification of Equipment for Spaces/Sys Which May Be Used in Post-Accident Operations Outside Containment.Safe Shutdown
Boric Acid
ML17250A3047 May 1980RO 80-04:during Performance of post-mod Installation Testing Both Power Operated Relief Valves Determined Inoperable & RCS Vent Established.Caused by Two Switches Which Supply Dc Power in Off Position
ML17250A30929 February 1980Metallurgical Investigation of Cracks in Pressurizer Nozzle-to-Safe-End Weld of Robert Emmett Ginna Nuclear Power Generating Station.Liquid penetrant
ML17250A3183 June 1980RO 80-05:on 800603,during Performance of Procedure S-30.1, Breaker for A-loop Accumulator Discharge valve,MDV-865 Discovered in Closed Position.Cause Not Stated.Breaker Immediately Placed in Proper Position
ML17250A3269 June 1980Monthly Operating Rept for May 1980Boric Acid
ML17250A3383 June 1980RO 80-05:on 800603,during Performance of Safety Injection Valve Position Verification Procedure,Discovered Breaker for A-loop Accumulator Discharge Valve MOV-865 Was in Closed Position.Breaker Placed in Proper Position,
ML17250A39611 July 1980RO 80-06:on 800711,chemical Analysis Indicated Boric Acid Storage Tanks Below Tech Specs for Vol & Percent Weight Boric Acid.Cause Not Stated.Orderly Power Reduction & Batching Operations Begun to Restore Tanks to SpecsBoric Acid
Backfit
ML17250A41514 July 1980RO 80-06:on 800714,chemical Analysis Indicated Boric Acid Storage Tanks Out of Spec for Vol & % Weight of Boric Acid. Caused by Inadvertent Dilution of Concentration Determining Chemical Reagents.Tanks Restored to Required SpecsBoric Acid
ML17250A46231 July 1980Draft SEP Review of NRC Safety Topic VIII-2 Associated W/ Electrical Instrumentation & Control Portions of Engineered Safety Feature Sys Control Logic & Design for Ginna Nuclear Power Plant.Safe Shutdown
ML17250A53321 May 1980Operator Requalification Program, Procedure A-102.14, Revision 3Fuel cladding
ML17250A6926 October 1980Monthly Operating Rept for Sept 1980