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	Issue date	Title	Topic
ML20101N485	31 March 1996	Nonproprietary Version of Suppl 1 to Power Uprate SAR for BSEP Units 1 & 2	Safe Shutdown Power Uprate
ML20094P968	30 September 1995	Power Uprate Safety Analsis Rept for BSEP Units 1 & 2	Safe Shutdown Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Ultimate heat sink Anticipated operational occurrence Hydrostatic Probabilistic Risk Assessment Temporary Modification Abnormal operational transient Flow Accelerated Corrosion Feedwater Controller Failure Stress corrosion cracking Fuel cladding Biofouling Power Uprate Overspeed trip
ML20115D203	31 August 1995	Rev 2 to RPV Power Uprate Stress Rept Reconciliation for Brunswick Units 1 & 2 Power Plants	Power Uprate
ML20072F271	30 June 1994	Info on Reactor Vessel Matl Surveillance Program Brunswick Steam Electric Plant Unit 1
ML20072F286	30 June 1994	Info on Reactor Vessel Matl Surveillance Program Brunswick Steam Electric Plant Unit 1
ML20072F290	30 June 1994	Info on Reactor Vessel Matl Surveillance Program Brunswick Steam Electric Plant Unit 2
ML20046C385	31 July 1993	Core Spray Crack Analysis for Bsep,Unit 1.	Offsite Dose Calculation Manual Temporary Modification Design basis earthquake Process Control Program Stress corrosion cracking Flow Induced Vibration Thermal fatigue
ML20097E687	30 November 1991	Feedwater Sparger Circumferential Cracking Evaluation for Brunswick Units 1 & 2	Finite Element Analysis Stress corrosion cracking Liquid penetrant
ML20078B321	31 May 1991	Nonproprietary Rev 1 to Brunswick Steam Electric Plant,Unit 1 Feedwater Nozzle Fracture Mechanics Analysis	Finite Element Analysis
ML20012A172	23 February 1990	Core Spray Line Crack Growth Analysis Update for Brunswick Steam Electric Plant Unit 2.	Stress corrosion cracking Thermal fatigue
ML20247G056	31 December 1986	Reactor Cavity Neutron Dosimetry Program for Brunswick Unit 2
ML20126H336	31 March 1985	Rev 1 to Design Rept for Recirculation & Reactor Water Cleanup Sys Weld Overlay Repairs & Flaw Analysis at Brunswick Steam Electric Plant,Unit 1	Non-Destructive Examination Weld Overlay Nondestructive Examination Stress corrosion cracking Liquid penetrant Unidentified leakage
ML20087H571	31 March 1984	Amend 1 to Verification of Carolina Power & Light Ref BWR Thermal-Hydraulic Methods Using Fibwr Code	Shutdown Margin Feedwater Controller Failure Water rod
ML20083H640	23 December 1983	Nonproprietary Amend 1 to Topical Rept NF-1583.03-1, Methods of PRESTO-B Three-Dimensional,BWR Core Simulation Code
ML20083H594	22 December 1983	Nonproprietary Amend 1 to Topical Rept NF-1583.02-1, Methods of Record LWR Fuel Assembly Burnup Code	Water rod
ML20083H572	22 December 1983	Amend 1 to Topical Rept NF-1583.01-1, Description & Validation of Steady-State Analysis Methods for Bwrs. W/Nine Oversize Figures.Aperture Cards Are Available in PDR
ML20069A999	28 February 1983	Description & Validation of Steady-State Analysis Methods for Bwrs	Shutdown Margin Power change
ML20069B003	28 February 1983	Nonproprietary Methods of Record - LWR Fuel Assembly Burnup Code	Water rod
ML20069B012	28 February 1983	Nonproprietary Methods of PRESTO-B - Three-Dimensional,LWR Core Simulation Code	Shutdown Margin
ML20063E048	31 July 1982	Core Spray Crack Analysis at Brunswick Steam Electric Plant,Unit 2	Stress corrosion cracking Flow Induced Vibration Thermal fatigue
ML20076E156	31 October 1981	Mark I Containment Program Plant-Unique Load Definition, Brunswick Steam Electric Plant:Units 1 & 2
ML20053E394	30 September 1981	Single-Loop Operation.	Abnormal operational transient Fuel cladding
ML19257A791	31 October 1979	Mark I Containment Program Structural Acceptance Criteria, Plant Unique Analysis Application Guide, Revision 1,for Task 3.1.3	Safe Shutdown Safe Shutdown Earthquake Hydrostatic Operating Basis Earthquake Finite Element Analysis Earthquake Pressure Boundary Leakage
ML20083K111	31 December 1978	LOCA Rept
ML19322A061	28 December 1978	Mark I Containment Program Load Definition Rept. Provides Info to Define Hydrodynamic Loads Produced on Containment Sys of Domestic Mark I Plants During Locas,Safety/Relief Valve Discharges & Related Dynamic Events	Reactor Vessel Water Level Stroke time Hydrostatic Earthquake Coast down Subsequent actuation
ML19261A845	30 November 1978	Info on Reactor Vessel Matl Surveillance Program.
ML20073A669	30 June 1976	Assurance of Acceptance Scram Through CRD Speed Analysis	Shutdown Margin

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