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. 10 2.5S.1-126 Basic Geologic and Seismic InformationSTP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-38 Structure Co...
Decrease in Reactor Coolant System Flow Rate 15.3-1/2STP 3 & 4 Final Safety Analysis Report15.3 Decrease in Reactor Coolant System Flow RateThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference ...
Probability Analysis of Pressure Regulator Downscale Failure 15D-1/2STP 3 & 4 Final Safety Analysis Report15D Probability Analysis of Pressure Regulator Downscale FailureThe information in this appendix of the reference ABWR DCD, including all subsections, tables, and figures...
Design Goals and Design Bases 18.2-1/2STP 3 & 4 Final Safety Analysis Report18.2 Design Goals and Design BasesThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 10
Tunnels 3.12-1/2STP 3 & 4 Final Safety Analysis Report3.12 TunnelsThe information in this section of the reference ABWR DCD, including all subsections, is incorporated by reference with no departures or supplements.Rev. 10
Requirements for Further Technical Information 1.5-1/2STP 3 & 4 Final Safety Analysis Report1.5 Requirements for Further Technical InformationThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 10
Operational Radiation Protection Program 12.5S-1STP 3 & 4 Final Safety Analysis Report12.5S Operational Radiation Protection ProgramNuclear Energy Institute Report No. NEI 07-03A, “Generic FSAR Template Guidance for Radiation Protection Program Description” provides the Opera...
Implementation Requirements for Hardware/Software Development 7B-1/2STP 3 & 4 Final Safety Analysis Report7B Implementation Requirements for Hardware/Software DevelopmentThe information in this appendix of the reference ABWR DCD, including all subsections, is incorporated by ...
STP 3 & 4 2.0-1/2SLs2.02.0 SAFETY LIMITS (SLs)The information in this section of the reference ABWR DCD, including all subsections, is incorporated by reference with the following departure.STD DEP 16.2-12.2 SL ViolationsWith any SL violation, the following actions shall be ...
Requirements for Determination of ABWR Site Acceptability 2.2-1/2STP 3 & 4 Final Safety Analysis Report2.2 Requirements for Determination of ABWR Site AcceptabilityThe information in this section of the reference ABWR DCD, including all subsections and tables, is incorporated...
Not Used 3J-1/2STP 3 & 4 Final Safety Analysis Report3J Not UsedThe information in this appendix of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 10
Data Communication Systems 7.9S-1STP 3 & 4 Final Safety Analysis Report7.9S Data Communication Systems7.9S.1 DescriptionThis section addresses both the essential (safety-related) and non-essential (nonsafety-related) data communication functions, as specified in RG 1.206, th...
Fuel Licensing Acceptance Criteria 4B-1/2STP 3 & 4 Final Safety Analysis Report 4B Fuel Licensing Acceptance CriteriaThe information in this appendix of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with no departures or supplement...
Diverse Instrumentation and Control Systems 7.8S-1/2STP 3 & 4 Final Safety Analysis Report7.8S Diverse Instrumentation and Control SystemsSubsection 7C.5 addresses diversity of the instrumentation and control systems.Rev. 11
Spent Fuel Pool Geometry and Dose Rate Calculation 12B-1STP 3 & 4 Final Safety Analysis Report12B Spent Fuel Pool Geometry and Dose Rate CalculationThis Appendix provides site-specific information regarding the Spent Fuel Pool (SFP) geometry and methodology used to generate S...
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. 11
Additional Bypass Leakage Considerations 6E-1/2STP 3 & 4 Final Safety Analysis Report 6E Additional Bypass Leakage ConsiderationsThe information in this appendix of the reference ABWR DCD, including all subsections, is incorporated by reference with no departures or supplemen...
Technical Specifications and Emergency Operation Requirements 2.4S.14-1STP 3 & 4 Final Safety Analysis Report2.4S.14 Technical Specifications and Emergency Operation RequirementsThe following site-specific supplement addresses COL License Information Item 2.22. For STP 3 & 4,...
Decrease in Reactor Coolant Inventory 15.6-1STP 3 & 4 Final Safety Analysis Report15.6 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 followi...
Maintenance Rule Program 17.6S-1/2STP 3 & 4 Final Safety Analysis Report 17.6S Maintenance Rule ProgramNuclear Energy Institute Report No. NEI 07-02A, Rev.0 (Corrected), dated November 2010, "Generic FSAR Template Guidance for Maintenance Rule Program Description for Plants L...
Engineered Safety Feature Systems, Instrumentation and Control 7.3-1STP 3 & 4 Final Safety Analysis Report7.3 Engineered Safety Feature Systems, Instrumentation and ControlThe information in this section of the reference ABWR DCD, including all subsections and figures, is inc...
Piping Design Review 3.12S-1/2STP 3 & 4 Final Safety Analysis Report3.12S Piping Design ReviewGE transmitted Revision 4 of the reference ABWR DCD to the NRC via letter dated March 28, 1997. The section titled "Introduction for Design Control Document" contains in tabular form...
Basic Geologic and Seismic Information 2.5S.1-129STP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-41 Structure Contour Map of Stratum H (Silty Sand)Rev. 11 2.5S.1-130 Basic Geologic and Seismic InformationSTP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-42 Site Vicinit...
Reactor Power Conversion System 3.2-1STP 3 & 4 Environmental Report3.2 Reactor Power Conversion SystemThe proposed plant will consist of STP 3 & 4 and their auxiliaries. The power source of each unit is an Advanced Boiling Water Reactor (ABWR) reactor design. The reference AB...
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...