Turbine Generator 10.2-1STP 3 & 4 Final Safety Analysis Report10.2 Turbine GeneratorThe information in this section of the reference ABWR DCD, including all subsections, tables and figures, is incorporated by reference with the following departures and supplements.STD DEP T1 ...
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. 07
Probabilistic Evaluations 19D-1/2STP 3 & 4 Final Safety Analysis Report19D Probabilistic Evaluations The information in this appendix of the reference ABWR DCD, including all subsections, is incorporated by reference with no departures or supplements.Rev. 07
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...
Offsite Power System 4.2-1/2STP 3 & 4 Tier 14.2 Offsite Power SystemThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 08
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...
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 Temperature 15.1-1/2STP 3 & 4 Final Safety Analysis Report15.1 Decrease in Reactor Coolant TemperatureThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the f...
Power Cycle Systems 2.10-1STP 3 & 4 Tier 12.10 Power Cycle SystemsThe 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. 05 2.10-2 Power Cycle Systems STP 3...
Regulatory Guide 1.52, Section C, Compliance Assessment 6A-1/2STP 3 & 4 Final Safety Analysis Report 6A Regulatory Guide 1.52, Section C, Compliance AssessmentThe information in this appendix of the reference ABWR DCD is incorporated by reference with no departures or supplem...
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...
Containment Ultimate Strength 19FA-1/2STP 3 & 4 Final Safety Analysis Report 19FA Containment Ultimate StrengthThe information in this appendix of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 05
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...
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...
Ice Effects 2.4S.7-1STP 3 & 4 Final Safety Analysis Report2.4S.7 Ice EffectsThe following site-specific supplement addresses COL License Information Item 2.16.2.4S.7.1 Ice Conditions and Historical Ice FormationThe potential impact of ice effects on the STP 3 & 4 site was an...
Instrumentation and Control 3.4-1STP 3 & 4 Tier 13.4 Instrumentation and ControlThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departure. STD DEP T1 3.4-1 (Figure 3.4a,...
Functional Design of Reactivity Control System 4.6-1STP 3 & 4 Final Safety Analysis Report 4.6 Functional Design of Reactivity Control SystemThe information in this section of the reference ABWR DCD, including all subsections and figures, is incorporated by reference with the...
Flooding Protection Requirements 2.4S.10-1/2STP 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 pow...
Potable and Sanitary Water System 4.4-1/2STP 3 & 4 Tier 14.4 Potable and Sanitary Water SystemThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 05
ABWR Shutdown Risk Assessment 19Q-1STP 3 & 4 Final Safety Analysis Report 19Q 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 an...
Differences Between BWROG EPG Revision 4 and ABWR EPG 18B-1STP 3 & 4 Final Safety Analysis Report 18B Differences Between BWROG EPG Revision 4 and ABWR EPGThe information in this appendix of the reference ABWR DCD, including all subsections and tables, is incorporated by refe...
Basic Geologic and Seismic Information 2.5S.1-109STP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-19 Quaternary Deposits of the Gulf Coastal PlainRev. 05 Basic Geologic and Seismic Information 2.5S.1-110STP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-20 Regional Gravi...
Quality Assurance During the Operations Phase 17.2-1/2STP 3 & 4 Final Safety Analysis Report 17.2 Quality Assurance During the Operations PhaseThe information in this section of the reference ABWR DCD is incorporated by reference with the following site-specific supplement.Th...
SAFEGUARDS INFORMATIONSeptember 25, 2003Mr. Stephen A. ByrneSenior Vice President, Nuclear OperationsSouth Carolina Electric and Gas CompanyVirgil C. Summer Nuclear StationHwy 215 North at Bradham BoulevardJenkinsville, SC 29065SUBJECT: ORDERS MODIFYING LICENSE FOR REVISED DE...
November 22, 2002
Mr. Harold B. Ray
Executive Vice President
Southern California Edison Company
San Onofre Nuclear Generating Station
P.O. Box 128
San Clemente, CA 92674-0128
SUBJECT: BULLETIN 2002-01, “REACTOR PRESSURE VESSEL HEAD DEGRADATION
AND REACTOR COOLANT PRESSURE B...