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Issue date | Title | Topic | |
---|---|---|---|
ML20199G199 | 19 November 1997 | Corrected Page 4-12 to WCAP-14723, Farley Nuclear Plant Units 1 & 2 Power Uprate Project NSSS Licensing Rept | |
ML20148M784 | 30 June 1997 | Non-proprietary Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for AL Power Farley Nuclear Plant Units 1 & 2, Rev 1 | |
ML20212D262 | 30 April 1997 | Rev 1 to WCAP-14689, Farley,Units 1 & 2,Heatup & Cooldown Limit Curves for Normal Operation & PTLR Support Documentation | Anticipated operational occurrence Hydrostatic |
ML20135C973 | 31 January 1997 | Non-proprietary Version of WCAP-14723, Farley Nuclear Plant Units 1 & 2 Power Uprate Project NSSS Licensing Rept | |
ML20133G601 | 31 January 1997 | Specific Application of Laser Welded Sleeves for Farley Units 1 & 2 Sg | |
ML20133G590 | 31 January 1997 | Rev 4 to W Series 44 & 51 SG Generic Sleeving Rept,Laser Welded Sleeves | |
ML20149L911 | 6 November 1996 | Nonproprietary Class 3 SG Sleeving Integration Rept for Jm Farley Units 1 & 2 | |
ML20128M541 | 8 October 1996 | L* Tube Plugging Criteria for Tubes W/Degradation in Tubesheet Roll Expansion Region of Farley Unit 2 Sg | Safe Shutdown Earthquake |
ML20135B826 | 30 September 1996 | RCS Flow Verification Using Elbow Taps at Westinghouse 3- Loop Pwrs | Fuel cladding |
ML20212D255 | 30 June 1996 | Jm Farley,Units 1 & 2,Radiation Analysis & Neutron Dosimetry Evaluation | |
ML20087E831 | 31 August 1995 | Elimination of Pressure Sensor Response Time Testing Requirements,Wog Program MUHP-3040 Rev 1 | Reverse polarity |
ML20069K292 | 31 March 1994 | Nonproprietary Steam Generator Lower Level Tap Relocation Assessment for Jm Farley Nuclear Plant Units 1 & 2 | Shutdown Margin Finite Element Analysis |
ML20072F366 | 31 December 1993 | Elimination of Pressure Sensor Response Time Testing Requirements | |
ML20114B501 | 31 August 1992 | Nonproprietary Response to NRC Questions on Farley SG Tube Alternate Plugging Criteria Presentation Matls | |
ML20114B513 | 31 August 1992 | Nonproprietary PWR SG Tube Repair Limits:Technical Support Document for Outside Diameter Stress Corrosion Cracking at Tube Support Plates Final Rept | Boric Acid Anticipated operational occurrence Nondestructive Examination |
ML20101G290 | 31 March 1992 | Nonproprietary Preliminary Data on Voltage/Burst/Leakage of 3/4 Inch Diameter Tubing for ODSCC at Tsps | |
ML20092M947 | 29 February 1992 | Steam Generator Tube Alternate Plugging Criteria Presentation Matls | |
ML20094J968 | 29 February 1992 | Nonproprietary Jm Farley Units 1 & 2 SG Tube Plugging Criteria for Outer Diameter Stress Corrosion Cracking at Tube Support Plates | |
ML20090B951 | 28 February 1992 | Nonproprietary Rev 2 to RTD Bypass Elimination for Licensing Rept for Jm Farley Nuclear Plant,Units 1 & 2, Table 2.1-1 (Replacement Page 15) | |
ML20092J128 | 31 December 1991 | Nonproprietary WCAP-13139, Steam Generator Tube Support Plate Alternate Plugging Criteria Summary | |
ML20086A042 | 31 October 1991 | Nonproprietary Addl Info Supporting SG TSP Criteria for Jm Farley,Units 1 & 2 | Boric Acid |
ML20086A061 | 31 October 1991 | Rev 1 to WCAP-12872, Jm Farley Units 1 & 2 SG Tube Plugging Criteria for ODSCC at Tsp | Non-Destructive Examination Earthquake |
ML20082T438 | 30 September 1991 | Nonproprietary Addl Info in Support of Eliminating Pressurizer Surge Line Rupture from Structural Design Basis for Jm Farley Plant Units 1 & 2 | |
ML20082S746 | 31 August 1991 | Nonproprietary Jm Farley Nuclear Plant Units 1 & 2 Response to NRC Request for Addl Info on Steam Generator Flow Area Reduction Due to Combined LOCA & SSE Loads | Safe Shutdown Earthquake Earthquake |
ML20092L191 | 31 July 1991 | Rev 2 to Handbook on Flaw Evaluation for Joseph Farley Units 1 & 2 Steam Generators & Pressurizers | |
ML20073P126 | 31 May 1991 | Allowable Outage Time Study for RHR Valves for Farley Nuclear Plant,Units 1 & 2 | |
ML20079D603 | 31 May 1991 | Westinghouse Revised Thermal Design Procedure Instrument Uncertainity Methodology for Alpr,Farley Nuclear Plant,Units 1 & 2 (for RTD Bypass Loops) | |
ML20079D607 | 31 May 1991 | Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for Alpr,Farley Nuclear Plant,Units 1 & 2 (for RTD Bypass Loop Elimination) | |
ML20073J989 | 30 April 1991 | Nonproprietary Technical Justification for Eliminating Pressurizer Surge Line Rupture from Structural Design Basis for Farley Units 1 & 2 | Safe Shutdown Safe Shutdown Earthquake Pressure boundary leak |
ML20066J566 | 31 January 1991 | Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Jm Farley Units 1 & 2 Nuclear Power Plants | |
ML20066L050 | 31 January 1991 | Nonproprietary Rev 2 to WCAP 12614, RTD Bypass Elimination Licensing Rept for Jm Farley Nuclear Plant Units 1 & 2 | Shutdown Margin Non-Destructive Examination Hydrostatic Flow Induced Vibration |
ML20066L317 | 31 January 1991 | Nonproprietary WCAP-12856, Structural Evaluation of Farley Units 1 & 2 Pressurizer Surge Lines,Considering Effects of Thermal Stratification | |
ML20066E509 | 31 December 1990 | Nonproprietary Steam Generator Tube Plugging Limits Presentation Matls | |
ML20197H665 | 30 November 1990 | Nonproprietary WCAP-12764, Steam Generator Tube Collapse Considerations Presentation Matls | |
ML20058E385 | 26 October 1990 | Rev 1 to RTD Bypass Elimination Licensing Rept for Jm Farley Nuclear Plant Units 1 & 2 | |
ML20058E355 | 31 August 1990 | Rev 0 to Alabama Power Jm Farley Unit 1 Increased Steam Generator Tube Plugging & Reduced Thermal Design Flow Licensing Rept | |
ML20059D485 | 16 August 1990 | Steam Generator Sleeving Rept Laser Welded Sleeves Jm Farley Units 1& 2 | Non-Destructive Examination Liquid penetrant Flow Induced Vibration |
ML20058E366 | 31 July 1990 | Median Signal Selector for Westinghouse 7300 Series Process Instrumentation - Application to Westinghouse Three Loop Plants Employing RTD Bypass Elimination,Alabama Light Co, Jm Farley Unit 1 | |
ML20059D437 | 31 July 1990 | Alabama Power Jm Farley Unit 2 Increased Steam Generator Tube Plugging & Reduced Thermal Design Flow Licensing Rept | Boric Acid Shutdown Margin Operating Basis Earthquake Earthquake Fuel cladding Flow Induced Vibration |
ML20062F978 | 31 July 1990 | Rev 1 to WCAP-12213, Handbook on Flaw Evaluation for J Farley Units 1 & 2 Steam Generators & Pressurizers | Hydrostatic |
ML20062F976 | 30 September 1989 | Nonproprietary WCAP-12447, Background & Technical Basis: Handbook on Flaw Evaluation for Farley Units 1 & 2 Main Coolant Sys & Components | |
ML20247N032 | 31 July 1989 | Nonproprietary Jm Farley Unit 2 Engineering Evaluation of Weld Joint Crack in 6-Inch Safety Injection & RHR Piping | |
ML20058N818 | 31 December 1988 | Safety Evaluation Supporting More Negative Eol Moderator Temp Coefficient Tech Spec for Jm Farley Nuclear Plant Units 1 & 2 | |
ML20153D705 | 31 July 1988 | Joseph Farley Unit 1 & 2 Evaluation for Tube Vibration Induced Fatigue | Flow Induced Vibration |
ML20153D662 | 30 April 1988 | Background & Technical Basis for Handbook on Flaw Evaluation for Jm Farley Nuclear Plant Units 1 & 2 Reactor Vessel Beltline & Nozzle to Shell Welds | |
ML20210D283 | 30 April 1987 | Rev 1 to Jm Farley Units 1 & 2 Steam Generator Sleeving Rept (Mechanical Sleeves) | Hydrostatic Finite Element Analysis |
ML20210D304 | 30 April 1987 | Rev 2 to Tubesheet Region Plugging Criterion for Alabama Power Co Farley Nuclear Station Unit 2 Steam Generators | Boric Acid Finite Element Analysis |
ML20210T571 | 30 June 1986 | Rev 2 to Heatup & Cooldown Limit Curves for Alabama Power Co,Joseph M Farley Unit 1 Reactor Vessel | Hydrostatic |
ML20155A323 | 28 February 1986 | Rev 1 to Heatup & Cooldown Limit Curves for Jm Farley Unit 2 Reactor Vessel | Hydrostatic |
ML20137K818 | 31 January 1986 | Jm Farley Units 1 & 2 Reactor Vessel Fluence & Ref Temp for Pressurized Thermal Shock Evaluations |