Control Rod Licensing Acceptance Criteria 4C-1/2STP 3 & 4 Final Safety Analysis Report 4C Control Rod Licensing Acceptance CriteriaThe information in this appendix of the reference ABWR DCD, including all subsections, is incorporated by reference with the following standard d...
Severe Accidents 7.2-1STP 3 & 4 Environmental Report7.2 Severe AccidentsAs stated in NUREG-1555, “Severe accidents are those involving multiple failures of equipment or function and, therefore, the likelihood of occurrence is lower for severe accidents than for Design Bases A...
Control Rod Licensing Acceptance Criteria 4C-1/2STP 3 & 4 Final Safety Analysis Report 4C Control Rod Licensing Acceptance CriteriaThe information in this appendix of the reference ABWR DCD, including all subsections, is incorporated by reference with the following standard d...
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. 07
Design Development and Validation Testing 18G-1/2STP 3 & 4 Final Safety Analysis Report18G Design Development and Validation TestingThe information in this appendix 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 Report7DS Digital Instrumentation and Control Design Verification for Safety-Related SystemsThe purpose of this appendix is to consolidate information regar...
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...
STP 3 & 4 3.0-1LCO Applicability3.03.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITYThe information in this section of the reference ABWR DCD, including all subsections, is incorporated by reference with the following departure.STP DEP 16.3-1LCO 3.0.6 When a supported ...
Not Used 19G-1/2STP 3 & 4 Final Safety Analysis Report19G Not UsedThe information in this appendix of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 07
Control Systems Not Required for Safety 7.7-1STP 3 & 4 Final Safety Analysis Report7.7 Control Systems Not Required for SafetyThe information in this section of the reference ABWR DCD, including all subsections and figures, as modified by the STP Nuclear Operating Company App...
Yard Structures and Equipment 2.16-1/2STP 3 & 4 Tier 12.16 Yard Structures and EquipmentThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with no departures or supplements.Rev. 07
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. 07
Engineered Safety Feature Materials 6.1-1STP 3 & 4 Final Safety Analysis Report 6.1 Engineered Safety Feature MaterialsThe information in this section of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with the following supplements....
Response to TMI Related Matters 1A-1STP 3 & 4 Final Safety Analysis Report1A Response to TMI Related MattersThe information in this appendix of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with the following departures and supplem...
Basic Geologic and Seismic Information 2.5S.1-107STP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-19 Quaternary Deposits of the Gulf Coastal PlainRev. 07 Basic Geologic and Seismic Information 2.5S.1-108STP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-20 Regional Gravi...
Radioactive Release from Subsystems and Components 15.7-1STP 3 & 4 Final Safety Analysis Report15.7 Radioactive Release from Subsystems and ComponentsThe information in this section of the reference ABWR DCD, including all subsections, figures and tables, is incorporated by r...
PRA as a Design Tool 19.7-1STP 3 & 4 Final Safety Analysis Report19.7 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 19...
System Evaluation for ISLOCA 3MA-1STP 3 & 4 Final Safety Analysis Report3MA System Evaluation for ISLOCAThe information in this appendix of the reference ABWR DCD, including all subsections, is incorporated by reference with the following standard departures.STD DEP T1 2.4-1S...
Accident and Analysis 15.0-1/2STP 3 & 4 Final Safety Analysis Report15.0 Accident and AnalysisThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following supplements.15.0.5 COL Lic...
Control and Instrument Systems 2.2-1STP 3 & 4 Tier 12.2 Control and Instrument SystemsThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departures.STD DEP T1 2.2-1 (Table ...
SRP 6.5.1, Table 6.5.1-1 Compliance Assessment 6B-1/2STP 3 & 4 Final Safety Analysis Report 6B SRP 6.5.1, Table 6.5.1-1 Compliance AssessmentThe information in this appendix of the reference ABWR DCD is incorporated by reference with the following departure.STD DEP 7.1-1 Adso...
Purpose and Summary 19.1-1/2STP 3 & 4 Final Safety Analysis Report19.0 Response to Severe Accident Policy Statement19.1 Purpose and SummaryThe information in this section of the reference ABWR DCD, including all subsections, as modified by the STP Nuclear Operating Company A...
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...
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 ...
Engineered Safety Feature Materials 6.1-1STP 3 & 4 Final Safety Analysis Report 6.1 Engineered Safety Feature MaterialsThe information in this section of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with the following supplements....