Reference Fuel Design Compliance with Acceptance Criteria 4D-1/2STP 3 & 4 Final Safety Analysis Report 4D Reference Fuel Design Compliance with Acceptance CriteriaThe information in this appendix of the reference ABWR DCD, including all subsections and tables, is incorporated...
Decrease in Reactor Coolant Inventory 15.6-1STP 3 & 4 Final Safety Analysis Report Tier 215.6 Decrease in Reactor Coolant InventoryThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the ...
Digital Instrumentation and Control Design Verification for Safety-Related Systems 7DS-1STP 3 & 4 Final Safety Analysis Report Tier 27DS Digital Instrumentation and Control Design Verification for Safety-Related SystemsThe purpose of this appendix is to consolidate informatio...
Offsite Radiological Monitoring Program 11.6-1/2STP 3 & 4 Final Safety Analysis Report Tier 211.6 Offsite Radiological Monitoring ProgramThe existing offsite radiological monitoring program for STP 1 & 2 is described in the STP Offsite Dose Calculation Manual, which has been ...
Systems Integration 18.6-1STP 3 & 4 Final Safety Analysis Report18.6 Systems IntegrationThe information in this section of the reference ABWR DCD, including all subsections, is incorporated by reference with the following departure and a supplement.STD DEP T1 3.4-118.6.1 Saf...
Measurement Against Goals 19.6-1/2STP 3 & 4 Final Safety Analysis Report19.6 Measurement Against GoalsThe information in this section of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with the following departure. STD DEP Admin 19.6...
Containment Systems 6.2-1STP 3 & 4 Final Safety Analysis Report 6.2 Containment SystemsThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, as modified by the STP Nuclear Operating Company Application to Amend the Design C...
Remote Shutdown System 18.5-1/2STP 3 & 4 Final Safety Analysis Report18.5 Remote Shutdown SystemThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 09
Basic Geologic and Seismic Information 2.5S.1-125STP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-37 Structure Contour Map of Stratum C (Silty Sand)Rev. 09 2.5S.1-126 Basic Geologic and Seismic InformationSTP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-38 Structure Co...
All Other Instrumentation Systems Required for Safety 7.6-1STP 3 & 4 Final Safety Analysis Report7.6 All Other Instrumentation Systems Required for SafetyThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated...
Supporting Analysis for Emergency Operation Information and Controls 18H-1STP 3 & 4 Final Safety Analysis Report18H Supporting Analysis for Emergency Operation Information and ControlsThe information in this appendix of the reference ABWR DCD, including all subsections and ta...
Turbine Service Water System 4.6-1/2STP 3 & 4 Tier 14.6 Turbine Service Water SystemThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 09
Emergency Procedure Guidelines 18A-1STP 3 & 4 Final Safety Analysis Report18A Emergency Procedure GuidelinesThe information in this appendix of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departure.ST...
Enclosure 2 List of Attendees Fuel Rack Design Analysis Audit Held on April 8-9, 2014 NAME ORGANIZATION Samir Chakrabarti NRC Huan Li NRC Jessica Umaña NRC Diego Saenz NRC Rich Morante BNL James Fisicaro TANE Dick Bense NINA Scott Head NINA Steve Thomas NINA Chuck Bullard H...
Comments on STP Nuclear Operating Company’s Draft Request for Exemption from Certain Requirements of the Fitness for Duty Rule for Managing Fatigue. Following are our preliminary comments on draft request for exemption from requirements of 10 CFR Part 26, regarding managing f...
Debris Coolability and Core Concrete Interaction 19EC-1/2STP 3 & 4 Final Safety Analysis Report 19EC Debris Coolability and Core Concrete InteractionThe information in this appendix of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by ...
Containment and Environmental Control Systems 2.14-1STP 3 & 4 Tier 12.14 Containment and Environmental Control SystemsThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following dep...
Reactor Service Water System 4.5-1/2STP 3 & 4 Tier 14.5 Reactor Service Water SystemThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 05
Turbine Service Water System 4.6-1/2STP 3 & 4 Tier 14.6 Turbine Service Water SystemThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 05
Makeup Water Preparation System 4.3-1/2STP 3 & 4 Tier 14.3 Makeup Water Preparation SystemThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 12
Increase in Reactor Pressure 15.2-1STP 3 & 4 Final Safety Analysis Report15.2 Increase in Reactor PressureThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departures and ...
Transient and Accident Classification 15.1S-1/2STP 3 & 4 Final Safety Analysis Report15.1S Transient and Accident ClassificationAs specified by Regulatory Guide 1.206 the design differences from the certified design that could impact the STP 3 & 4 transient and safety analysi...
PRA as a Design Tool 19.7-1STP 3 & 4 Final Safety Analysis Report 19.7 PRA as a Design ToolThe information in this section of the reference ABWR DCD, including all subsections, is incorporated by reference with the following departures. STD DEP T1 3.4-1STD DEP 19.7-1STP DEP 1...