Core Cooling Systems 2.4-1STP 3 & 4 Tier 12.4 Core Cooling 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 2.4-1 (Figure 2.4.1a, Table 2.4.1...
Design Considerations Reducing Sabotage Risk 19C-1/2STP 3 & 4 Final Safety Analysis Report19C Design Considerations Reducing Sabotage RiskDesign changes and site-specific information were reviewed against the information in this section. No conclusions in SSAR Chapter 19C we...
Seismic Capacity Analysis 19H-1STP 3 & 4 Final Safety Analysis Report19H Seismic Capacity AnalysisThe 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 T1 2...
GE Topical Reports and Other Documents 1.6-1STP 3 & 4 Final Safety Analysis Report1.6 GE Topical Reports and Other DocumentsThe information in this section of the reference ABWR DCD, including all tables, is incorporated by reference with the following supplement. Table 1.6-...
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. 09
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...
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...
SLs 2.0 STP 3 & 4 2.0-1 Rev. 10 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 5.41 MPaG or core flow < 10% rated core flow: THERMAL POWER shall be ≤ 25% RTP. 2.1.1.2 With the reactor steam dome pressure ≥ ...
Guidelines for LBB Application 3E-1/2STP 3 & 4 Final Safety Analysis Report3E Guidelines for LBB ApplicationThe information in this appendix of the reference ABWR DCD, including all subsections, tables and figures, is incorporated by reference with the following departure and...
Components and Subsystem Design 5.4-1STP 3 & 4 Final Safety Analysis Report5.4 Components and Subsystem DesignThe information in this section of the reference ABWR DCD, including all subsections, tables and figures, is incorporated by reference with the following departures a...
Human Factors Engineering 3.1-1/2STP 3 & 4 Tier 13.1 Human Factors EngineeringThe information in this section of the reference ABWR DCD, including all tables and figures, is incorporated by reference with no departures or supplements.Rev. 09
Other Features of Steam and Power Conversion 10.4-1STP 3 & 4 Final Safety Analysis Report10.4 Other Features of Steam and Power ConversionThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures is incorporated by reference wit...
Source Term Sensitivity Studies 19.5-1/2STP 3 & 4 Final Safety Analysis Report19.5 Source Term Sensitivity StudiesThe information in this section of the reference ABWR DCD, including all subsections, is incorporated by reference with no departures or supplements.Rev. 10
Seismic Capacity Analysis 19H-1STP 3 & 4 Final Safety Analysis Report19H Seismic Capacity AnalysisThe 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 T1 2...
Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-1/2STP 3 & 4 Final Safety Analysis Report 4A Typical Control Rod Patterns and Associated Power Distribution for ABWRThe information in this appendix of the reference ABWR DCD, including all subsections...
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...
Not Used 3F-1/2STP 3 & 4 Final Safety Analysis Report3F Not UsedThe information in this appendix of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 10
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...
Interlock Systems Important to Safety 7.6S-1/2STP 3 & 4 Final Safety Analysis Report7.6S Interlock Systems Important to SafetySubsections 7.4.1.3 (items 7 and 11), 7.6.1.3, 7.6.2.3, and Table 7.4-1 address interlock functions important to safety.Rev. 10
Reliability Assurance Program During Design Phase 17.3-1/2STP 3 & 4 Final Safety Analysis Report 17.3 Reliability Assurance Program During Design PhaseThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by...
Regulatory Guide 1.52, Section C, Compliance Assessment 9C-1/2STP 3 & 4 Final Safety Analysis Report9C Regulatory Guide 1.52, Section C, Compliance AssessmentThe information in this appendix of the reference ABWR DCD, including all subsections, is incorporated by reference wi...
ABWR Human-System Interface Design Implementation Process 18E-1STP 3 & 4 Final Safety Analysis Report18E ABWR Human-System Interface Design Implementation ProcessThe information in this appendix of the reference ABWR DCD, including all subsections, tables and figures, is inco...
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 ...
Anticipated Transients Without Scram 15.8-1/2STP 3 & 4 Final Safety Analysis Report15.8 Anticipated Transients Without ScramThe information in this section of the reference ABWR DCD, including all subsections, is incorporated by reference with no departures or supplements.Rev...
Radioactive Waste Management System 3.5-1STP 3 & 4 Environmental Report3.5 Radioactive Waste Management System Radioisotopes are produced during the normal operation of nuclear reactors, through the processes of fission and activation. Fission products may enter the reactor c...