DHR Reliability Study 19QB-1/2STP 3 & 4 Final Safety Analysis Report19QB DHR Reliability StudyThe information in this appendix of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with the following departure. STD DEP 5.4-1 19QB.5 Dec...
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...
Source Terms 11.1-1/2STP 3 & 4 Final Safety Analysis Report11.0 Radioactive Waste Management11.1 Source TermsThe information in this section of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with no departures or supplementsthe fol...
Summary Description 5.1-1STP 3 & 4 Final Safety Analysis Report5.0 Reactor Coolant System and Connected Systems5.1 Summary DescriptionThe information in this section of the reference ABWR DCD, including all subsections and figures, as modified by the STP Nuclear Operating Co...
ATWS Performance Evaluation 15E-1STP 3 & 4 Final Safety Analysis Report15E ATWS Performance EvaluationThe information in this appendix of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departures.STD DEP...
Transportation of Radioactive Materials 3.8-1STP 3 & 4 Environmental Report3.8 Transportation of Radioactive MaterialsOperation of STP 3 & 4 would require transportation of unirradiated fuel, irradiated fuel (spent nuclear fuel), and radioactive waste. The subsections that f...
Reactivity and Power Distribution Anomalies 15.4-1STP 3 & 4 Final Safety Analysis Report15.4 Reactivity and Power Distribution AnomaliesThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with...
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...
Summary Description 5.1-1STP 3 & 4 Final Safety Analysis Report5.0 Reactor Coolant System and Connected Systems5.1 Summary DescriptionThe information in this section of the reference ABWR DCD, including all subsections and figures, as modified by the STP Nuclear Operating Co...
ABWR Shutdown Risk Assessment 19Q-1STP 3 & 4 Final Safety Analysis Report19Q ABWR Shutdown Risk AssessmentThe information in this appendix of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departures and...
Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) 14.3S-1/2STP 3 & 4 Final Safety Analysis Report14.3S Inspections, Tests, Analyses and Acceptance Criteria (ITAAC)The selection criteria and methodology provided in Section 14.3 of the reference ABWR DCD for the cert...
Flooding Protection Requirements 2.4S.10-1STP 3 & 4 Final Safety Analysis Report2.4S.10 Flooding Protection RequirementsThe following supplement addresses COL License Information Item 2.19.As discussed in Section 2.4S.2, the design basis flood elevation in the STP 3 & 4 power...
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. 11
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Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) 14.3S-1/2STP 3 & 4 Final Safety Analysis Report14.3S Inspections, Tests, Analyses and Acceptance Criteria (ITAAC)The selection criteria and methodology provided in Section 14.3 of the reference ABWR DCD for the cert...
Piping Design 3.3-1/2STP 3 & 4 Tier 13.3 Piping DesignThe information in this section of the reference ABWR DCD, including all tables, is incorporated by reference with no departures or supplements.Rev. 05
Containment Hydrodynamic Loads 3B-1STP 3 & 4 Final Safety Analysis Report3B Containment Hydrodynamic LoadsThe information in this appendix of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departures.STD...
Summary of Analysis Supporting Fire Protection Design Requirements 9B-1/2STP 3 & 4 Final Safety Analysis Report9B Summary of Analysis Supporting Fire Protection Design RequirementsThe information in this appendix of the reference ABWR DCD, including all subsections, tables an...
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...
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....
Nuclear Fuel 2.8-1/2STP 3 & 4 Tier 12.8 Nuclear FuelThe information in this section of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with no departures or supplements.Rev. 05
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...
LOCA Inventory Curves 15F-1/2STP 3 & 4 Final Safety Analysis Report15F LOCA Inventory CurvesThe information in this appendix of the reference ABWR DCD, including all subsections and figures, is incorporated by reference with no departures or supplements.Rev. 05
November 1, 2010 MEMORANDUM TO: Edwin M. Hackett, Executive Director Advisory Committee on Reactor Safeguards FROM: David B. Matthews, Director /F. Akstulewicz for/ Division of New Reactor Licensing Office of New Reactors SUBJECT: STP UNITS 3 AND 4, COMBINED LICENSE ...