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Issue date | Title | Topic | |
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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 Adjustment | 25 May 1977 | 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 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 Recalibr | 20 October 1976 | 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 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 Cracking | 8 June 1977 | 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 Cracking | Boric 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 Replaced | 27 May 1977 | 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 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 Rept | 24 February 1982 | 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 Rept | |
ML17059A361 | 6 July 1994 | Emergency Action Level Verification & Validation Rept. | Earthquake |
ML17244A343 | 24 January 1979 | LER 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 | |
ML17244A485 | 15 March 1979 | Annual Financial Rept 1978. | Temporary Modification |
ML17244A521 | 8 May 1979 | Monthly Operating Rept for Apr 1979 | Boric Acid |
ML17244A541 | 29 May 1979 | Offsite Dose Calculating Manual | |
ML17244A587 | 2 July 1979 | Inservice Insp Program for 1980-89 (App B of QA Manual) | Hydrostatic Nondestructive Examination Liquid penetrant |
ML17244A765 | 9 August 1979 | Monthly Operating Rept for Jul 1979 | |
ML17244A797 | 31 December 1978 | Annual Operating Rept 1978 | Boric Acid Shutdown Margin Fire Barrier Hydrostatic Backfit |
ML17244A817 | 12 September 1979 | Monthly Operating Rept for Aug 1979 | Boric Acid |
ML17244A820 | 31 August 1979 | Discusses RO 79-17 Re Boric Acid Storage Tanks Out of Spec for Vol & % Weight of Boric Acid.Tanks Restored to within Specs | Boric Acid Backfit |
ML17244A867 | 31 August 1979 | Sixty-Day Response to IE Bulletin 79-14, 'Seismic Analysis for As-Built Safety-Related Piping Sys.' | Boric Acid |
ML17244A868 | 31 August 1979 | Piping & Piping Analysis Drawing List. Attachment 1 to 60-day Response to IE Bulletin 79-14 | Boric Acid |
ML17249A194 | 10 October 1979 | Monthly Operating Rept for Sept 1979 | |
ML17249A200 | 10 October 1979 | LER 79-018/03L-0:on 790913,output Breaker to Bus 16 Did Not Close.Caused by Overcurrent Relay Contact Lacking Continuity.Relay Inspected & Actuated | |
ML17249A290 | 15 November 1979 | App C to QA Manual Re Revised Inservice Pump & Valve Testing Program for May 1979-Dec 1980 | Safe Shutdown Boric Acid |
ML17249A296 | 19 November 1979 | Discussion of TMI Lessons Learned Short-Term Requirements. | Anticipated operational occurrence |
ML17249A329 | 6 December 1979 | Design Analysis Adequacy of Station Electric Distribution Sys Voltages. | |
ML17249A331 | 3 December 1979 | Ro: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 | |
ML17249A345 | 31 October 1979 | Steam Generator Water Hammer Technical Evaluation. | |
ML17249A362 | 11 December 1979 | RO 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 Cause | Liquid penetrant Backfit |
ML17249A370 | 31 December 1979 | Fuel & LOCA Evaluation of Mixed Oxide Fuel Assemblies. | |
ML17249A372 | 3 July 1979 | Plant Transient Analysis, Revision 1 | Boric Acid Shutdown Margin |
ML17249A373 | 28 November 1979 | Addendum to Criticality Analysis for Fuel Storage Racks to Address Storage of Mixed Oxide Fuel Assemblies. | |
ML17249A374 | 14 December 1979 | Cycle 10 SAR W/Mixed Oxide Assemblies. | Boric Acid Shutdown Margin |
ML17249A380 | 31 December 1979 | Safe Shutdown - Fire Study. | Safe Shutdown Boric Acid Fire Barrier Fire Watch |
ML17249A451 | 28 December 1979 | Discussion of TMI Lessons Learned Short-Term Requirements. | Boric Acid Reactor Vessel Water Level Anticipated operational occurrence Emergency Lighting Earthquake |
ML17249A483 | 9 January 1980 | Monthly Operating Rept for Dec 1979 | Boric Acid |
ML17249A510 | 23 January 1980 | Design Analysis,Rcs Subcooling Margin Monitoring Sys Error Analysis. | |
ML17249A573 | 8 February 1980 | Monthly Operating Rept for Jan 1980 | |
ML17249A603 | 10 October 1979 | Design Criteria,Spent Fuel Cooling Sys, Revision 1 | Safe Shutdown Earthquake Operating Basis Earthquake Spent Fuel Pool Instrumentation Earthquake |
ML17249A768 | 7 March 1980 | Monthly Operating Rept for Feb 1980 | |
ML17249A829 | 10 April 1980 | Monthly Operating Rept for Mar 1980 | |
ML17249A847 | 14 April 1980 | RO 80-003:eddy Current Exams Conducted to Detect Potential Tube Defects.Based on Results,Pulling Initiated to Remove Tube W/Abnormal Absolute Signal | Backfit |
ML17249A898 | 8 May 1980 | Monthly Operating Rept for Apr 1980 | |
ML17249A973 | 31 December 1979 | Design 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 |
ML17250A304 | 7 May 1980 | RO 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 | |
ML17250A309 | 29 February 1980 | Metallurgical Investigation of Cracks in Pressurizer Nozzle-to-Safe-End Weld of Robert Emmett Ginna Nuclear Power Generating Station. | Liquid penetrant |
ML17250A318 | 3 June 1980 | RO 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 | |
ML17250A326 | 9 June 1980 | Monthly Operating Rept for May 1980 | Boric Acid |
ML17250A338 | 3 June 1980 | RO 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, | |
ML17250A396 | 11 July 1980 | RO 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 Specs | Boric Acid Backfit |
ML17250A415 | 14 July 1980 | RO 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 Specs | Boric Acid |
ML17250A462 | 31 July 1980 | Draft 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 |
ML17250A533 | 21 May 1980 | Operator Requalification Program, Procedure A-102.14, Revision 3 | Fuel cladding |
ML17250A692 | 6 October 1980 | Monthly Operating Rept for Sept 1980 |