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	Issue date	Title	Topic
ML20217P635	29 September 1999	Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations	Safe Shutdown Earthquake Operating Basis Earthquake Earthquake
ML20204H994	3 March 1999	Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations	Safe 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
ML20207H767	5 October 1998	Rv Weld Chemistry & Initial Rt Ndt
ML20198J564	7 January 1998	Unit 2 Pressure & Temp Limits Rept	Hydrostatic Pressure and Temperature Limits Report
ML20198J553	7 January 1998	Unit 1 Pressure & Temp Limits Rept	Hydrostatic Pressure and Temperature Limits Report
ML20198P659	31 December 1997	.0 Volt IPC Full Cycle Operation Technical Basis Supplement to 'Braidwood Unit 1 Cycle 7 Interim Plugging Criteria Rept,Aug 1997.'
ML20210P861	31 August 1997	Cycle 7 Interim Plugging Criteria Rept
ML20141K037	21 May 1997	Pressure & Temp Limits Rept	Hydrostatic Pressure and Temperature Limits Report
ML20141K043	21 May 1997	Pressure & Temp Limits Rept	Hydrostatic Pressure and Temperature Limits Report
ML20148P881	16 May 1997	Spent Fuel Rack Criticality Analysis Using Soluble B Credit	Boric Acid Safe Shutdown Earthquake Earthquake
ML20141G636	15 May 1997	Interim Plugging Criteria Return to Power Rept
ML20138H000	28 April 1997	Locked Tube Tts Circumferential Indication Root Cause Determination Evaluation
ML20134M313	13 November 1996	Revised SG Tube Rupture Analysis for Byron/Braidwood
ML20134N313	31 October 1996	Sys Design Description for Containment Spray	Safe Shutdown Boric Acid Ultimate heat sink Safe Shutdown Earthquake Coatings Operating Basis Earthquake Earthquake
ML20134N801	31 October 1996	Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron
ML20116H146	1 August 1996	Cycle Length Assessment Rept Addendum	Nondestructive Examination
ML20112B852	17 May 1996	Cycle Length Assessment Rept Suppl
ML20117J049	8 May 1996	At&T Round Cell Nuclear Util User'S Council Charter
ML20106G589	30 April 1996	Training Dept Braidwood Simulator 1996 Certification Rept
ML20100R737	29 February 1996	Cycle 6 Interim Plugging Criteria 90 Day Rept
ML20094K610	30 November 1995	Interim Plugging Criteria Return to Power Rept
ML20093G717	12 October 1995	Rev 0 to PSA-B-95-18, RELAP5M3 Comparison of Model Boiler 2 MSLB from Hzp Test
ML20093G882	11 October 1995	Rev 0 to PSA-B-95-17, Calculation of Byron 1/Braidwood 1 D4 SG Tube Support Plate Loads w/RELAP5M3
ML20092A973	1 September 1995	Independent Verification of Byron/Braidwood D4 SG Tube Support Plate Differential Pressures During Mslb
ML20091M871	25 August 1995	Rept of Independent Assessment of Calculation of TSP Forces
ML20084V210	9 June 1995	Interim Plugging Criteria 90 Day Rept	Boric Acid
ML20078P155	6 February 1995	Probability of Detection by Bobbin Insp
ML20078R116	15 November 1994	Non-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 Fuel	B.5.b Mitigating Strategies Flow Induced Vibration
ML20077N013	30 September 1994	Rev 2 Evacuation Time Estimates within Plume Exposure Pathway Emergency Planning Zone for Braidwood Nuclear Generating Station
ML20149H159	30 June 1994	Spent Fuel Rack Criticality Analysis Considering Boraflex Gaps & Shrinkage	Shutdown Margin
ML20106G596	2 June 1993	Simulator Malfunction Cause & Effects	Safe Shutdown Boric Acid Fire Barrier Nuclear Accident Reporting System
ML20128E887	30 November 1992	Environmental Qualification of Okonite Tape Splice (T-95/No 35) Under Local Submergence for Power & Control Applications, Calculation Rept
ML20127L009	8 September 1992	Rev 0,to VIPRE/WRB-2 DNBR Thermal Limit for Westinghouse 17x17 Ofa & Vantage 5 Fuel
ML20064N802	27 July 1991	Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation
ML20101F563	3 July 1991	Byron/Braidwood Unit 1 Rhr/Safety Injection Piping Water Hammer Acoustic Analysis	Stroke time
ML20065D660	28 February 1991	Heatup & Cooldown Limit Curves for Normal Operation Braidwood Unit 2 (Capsule U)	Hydrostatic
L-90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation	31 October 1990	Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation
ML20065D650	31 August 1990	Heatup & Cooldown Limit Curves for Braidwood Unit 1 Reactor Veesel (Capsule U)	Stroke time Hydrostatic
ML20042E913	31 March 1990	Nonproprietary Rev 1 to Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants.
ML20246D687	14 August 1989	Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks
ML19327B401	31 July 1989	Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel.
ML20247E452	13 July 1989	Units 1 & 2 Suppl 1 to Response to NRC Concern 7
ML20247E481	11 July 1989	Units 1 & 2 Suppl 1 to Sargent & Lundy Rept Dtd 890630, Response to NRC Concern 8,Environ Qualification of Class 1E Control Circuits Terminated at Marathon 1,600 Nuc Terminal Boxes	Safe Shutdown
ML20247E467	30 June 1989	Units 1 & 2 Response to NRC Concern 8, Environ Qualification of Class 1E Control Circuits Terminated at Marathon 1,600 Nuc Terminal Boxes
ML20247H071	30 June 1989	Description & Verification Summary of Computer Program, Gappipe	Earthquake
ML20246D671	30 June 1989	Criticality Analysis of Byron/Braidwood Fresh Fuel Racks
ML20247E445	26 June 1989	Units 1 & 2 Response to NRC Concern 7
ML20247H079	22 June 1989	App to Description & Verification Summary of Computer Program,Gappipe
ML20247N062	31 May 1989	Production Training Dept,Braidwood,Malfunctions & Initial Conditions
ML20248C005	31 May 1989	Engineering Study on Control Room Integrity Test Requirement	Fire Protection Program

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