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Issue date | Title | Topic | |
---|---|---|---|
ML14357A042 | 31 December 2014 | NUREG-1437 - Supp 54, Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Byron Station, Units 1 and 2. | License Renewal |
ML15062A428 | 31 March 2015 | NUREG-1437 Supplement 55 Draft Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 55 Regarding Braidwood Station, Units 1 and 2, Draft Report for Comment | License Renewal |
ML15196A263 | 31 July 2015 | NUREG-1437 Supplement 54, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 54, Regarding Byron Station, Units 1 and 2, Final Report | License Renewal |
ML15314A814 | 30 November 2015 | NUREG-1437, Suppl 55, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Braidwood Station, Units 1 and 2 Final Report. | License Renewal |
ML15350A038 | 31 December 2015 | NUREG-2190, Vol 1, Safety Evaluation Report, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. | License Renewal |
ML15350A041 | 31 December 2015 | NUREG-2190 V2 - Safety Evaluation Report, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. | Boric Acid Ultimate heat sink Fire Barrier Anticipated operational occurrence Safe Shutdown Earthquake Weld Overlay Coatings Operating Basis Earthquake Nondestructive Examination VT-2 Incorporated by reference Finite Element Analysis B.5.b Aging Management Pressure and Temperature Limits Report Flow Accelerated Corrosion Stress corrosion cracking Integrated leak rate test Eddy Current Testing Moisture barrier License Renewal Earthquake Control of Heavy Loads Liquid penetrant Flow Induced Vibration Power Uprate Measurement Uncertainty Recapture Thermal fatigue |
ML16021A423 | 31 January 2016 | NUREG-2187, Vol. 1, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models-Byron Unit 1. Chapters 1 to 8, Appendices a to C. | Safe Shutdown Reactor Vessel Water Level Loop seal Mission time Hydrostatic Probabilistic Risk Assessment Operator Manual Action Significance Determination Process Fuel cladding Power Uprate Measurement Uncertainty Recapture |
ML16022A062 | 31 January 2016 | NUREG-2187, Vol. 2, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models-Byron Unit 1. Appendices D to G. | Probabilistic Risk Assessment Significance Determination Process |