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 Issue dateTitleTopic
ML20217P63529 September 1999Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear StationsSafe Shutdown Earthquake
Operating Basis Earthquake
Earthquake
ML20207H75628 June 1999Pressure Temp Limits Rept (Ptlr)Hydrostatic
Pressure and Temperature Limits Report
ML20207H76228 June 1999Pressure Temp Limits Rept (Ptlr)Hydrostatic
Pressure and Temperature Limits Report
ML20204H9943 March 1999Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear StationsSafe Shutdown
Boric Acid
High Radiation Area
Safe Shutdown Earthquake
Hydrostatic
Operating Basis Earthquake
Nondestructive Examination
Earthquake
Control of Heavy Loads
Fuel cladding
Liquid penetrant
Overexposure
Affidavit
Depleted uranium
ML20207H7675 October 1998Rv Weld Chemistry & Initial Rt Ndt
ML20236U47523 July 1998SG Eddy Current Insp Rept Cycle 7 Refueling Outage (B2R07)Hydrostatic
ML20198J5647 January 1998Unit 2 Pressure & Temp Limits ReptHydrostatic
Pressure and Temperature Limits Report
ML20198J5067 January 1998Pressure Temp Limits Rept (Ptlr)Hydrostatic
Pressure and Temperature Limits Report
ML20198J5207 January 1998Pressure Temp Limits Rept (Ptlr)Hydrostatic
Pressure and Temperature Limits Report
ML20198J5537 January 1998Unit 1 Pressure & Temp Limits ReptHydrostatic
Pressure and Temperature Limits Report
ML20199E8803 November 1997Revised Byron Unit 2 Pressure Temperature Limits Rept (PTLR)Hydrostatic
Pressure and Temperature Limits Report
ML20199E8753 November 1997Revised Byron Unit 1 Pressure Temperature Limits Rept (Ptlr)Hydrostatic
Pressure and Temperature Limits Report
ML20217G61722 July 1997Operability Assessment Process Form
ML20141K02421 May 1997Pressure & Temp Limits ReptHydrostatic
Pressure and Temperature Limits Report
ML20141K04321 May 1997Pressure & Temp Limits ReptHydrostatic
Pressure and Temperature Limits Report
ML20141K01821 May 1997Pressure & Temp Limits ReptHydrostatic
Pressure and Temperature Limits Report
ML20141K03721 May 1997Pressure & Temp Limits ReptHydrostatic
Pressure and Temperature Limits Report
ML20148P88116 May 1997Spent Fuel Rack Criticality Analysis Using Soluble B CreditBoric Acid
Safe Shutdown Earthquake
Earthquake
ML20141F71415 May 1997Operability Assessment Process Form
ML20134M31313 November 1996Revised SG Tube Rupture Analysis for Byron/Braidwood
ML20134N80131 October 1996Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron
ML20134N31331 October 1996Sys Design Description for Containment SpraySafe Shutdown
Boric Acid
Ultimate heat sink
Safe Shutdown Earthquake
Coatings
Operating Basis Earthquake
Earthquake
ML20129F89230 September 1996Circumferential Indication Summary Rept
ML20129G38831 August 1996Unit-1 EOC 7B Interim Plugging Criteria Rept
ML20113B09530 June 1996Interim Plugging Criteria Return to Power Rept
ML20101E76531 March 1996Unit - 1 EOC 7A Interim Plugging Criteria Rept
ML20095G06931 December 1995Interim Plugging Criteria Return to Power Rept
ML20093G71712 October 1995Rev 0 to PSA-B-95-18, RELAP5M3 Comparison of Model Boiler 2 MSLB from Hzp Test
ML20093G88211 October 1995Rev 0 to PSA-B-95-17, Calculation of Byron 1/Braidwood 1 D4 SG Tube Support Plate Loads w/RELAP5M3
ML20092A9731 September 1995Independent Verification of Byron/Braidwood D4 SG Tube Support Plate Differential Pressures During Mslb
ML20091M87125 August 1995Rept of Independent Assessment of Calculation of TSP Forces
ML20078P1556 February 1995Probability of Detection by Bobbin Insp
ML20078G83525 January 1995Probability of Detection by Bobbin Insp
ML20078F18620 January 1995Refuel Outage B1R05 RHR HX Nozzles Ultrasonic Indication Summary
ML20078G94319 January 1995EOC 6 Interim Plugging Criteria ReptNondestructive Examination
ML20078R11615 November 1994Non-proprieatry NFSR-0090, Response to Nuclear Regulatory Staff Request for Addl Info on VIPRE/WRB-2 DNBR Thermal Limit for Westinghouse 17x17 Ofa & Vantage 5 FuelB.5.b Mitigating Strategies
Flow Induced Vibration
ML20149H15930 June 1994Spent Fuel Rack Criticality Analysis Considering Boraflex Gaps & ShrinkageShutdown Margin
ML20127L0098 September 1992Rev 0,to VIPRE/WRB-2 DNBR Thermal Limit for Westinghouse 17x17 Ofa & Vantage 5 Fuel
ML20087E0459 January 1992UHS Design Basis Reconstitution Final ReptSafe Shutdown
Ultimate heat sink
ML20077D06715 November 1991Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper TubesheetBoric Acid
ML20082K76422 August 1991Simulator Initial Certification Rept,Sept 1991
ML20064N80227 July 1991Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation
ML20101F5633 July 1991Byron/Braidwood Unit 1 Rhr/Safety Injection Piping Water Hammer Acoustic AnalysisStroke time
L-90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation31 October 1990Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation
ML20042E91331 March 1990Nonproprietary Rev 1 to Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants.
ML20246D68714 August 1989Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks
ML19327B40131 July 1989Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel.
ML20247H07130 June 1989Description & Verification Summary of Computer Program, GappipeEarthquake
ML20246D67130 June 1989Criticality Analysis of Byron/Braidwood Fresh Fuel Racks
ML20247H07922 June 1989App to Description & Verification Summary of Computer Program,Gappipe