's*a!-,( IcsAIID com.SPorg{N(.AI*f s.YJanuary 16, 1980 g$y'h Yp )3T!%[~p e 'dYMr. Melbert Schwarz, Jr., EsquireBaker and Botts i-riOne Shell Plaza -!Houston, Texas 77002s' -/r, ;!'IIRe: Docket Nos. 50-49850-499iDear Mr. Schwarz:Citizens Concerned About Nuclear Power, Inc. and ...
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...
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...
Increase in Reactor Pressure 15.2-1STP 3 & 4 Final Safety Analysis Report15.2 Increase in Reactor PressureThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departures and ...
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...
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 ...
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...
Ultimate Heat Sink 4.1-1/2STP 3 & 4 Tier 14.1 Ultimate Heat SinkThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 06
Detailed Design of the Operator Interface System 18.7-1/2STP 3 & 4 Final Safety Analysis Report 18.7 Detailed Design of the Operator Interface SystemThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 06
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...
Seismic Design 3.7-1STP 3 & 4 Final Safety Analysis Report3.7 Seismic DesignThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departure and supplements.STD DEP 1.8-1STD DE...
Plant Nuclear Safety Operational Analysis (NSOA) 15A-1STP 3 & 4 Final Safety Analysis Report15A Plant Nuclear Safety Operational Analysis (NSOA)The information in this appendix of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by refer...
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...
Onsite Power Systems 8.3-1STP 3 & 4 Final Safety Analysis Report8.3 Onsite Power SystemsThe 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 ...
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 the following departures or supplements.STD DEP T1 2.10-1 (Figure ...
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. 06
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. 09
PRA as a Design Tool 19.7-1STP 3 & 4 Final Safety Analysis Report 19.7 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 1...
Planning, Development, and Design 18.3-1/2STP 3 & 4 Final Safety Analysis Report18.3 Planning, Development, and DesignThe information in this section of the reference ABWR DCD, including all subsections, is incorporated by reference with no departures or supplements.Rev. 08
Initial Test Program 3.5-1/2STP 3 & 4 Tier 13.5 Initial Test ProgramThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 08
Emergency Core Cooling Systems 6.3-1STP 3 & 4 Final Safety Analysis Report 6.3 Emergency 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 a...
LCO Applicability 3.0 STP 3 & 4 3.0-1 Rev. 08 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7. LCO 3.0.2 Upon dis...
Quality Assurance Program Guidance 17.5S-1/2STP 3 & 4 Final Safety Analysis Report 17.5S Quality Assurance Program GuidanceThe Quality Assurance Program Description has been submitted as a separate document titled “STP 3 & 4 Quality Assurance Program Description.”Rev. 08
Containment Ultimate Strength 19F-1/2STP 3 & 4 Final Safety Analysis Report 19F Containment Ultimate StrengthThe information in this appendix of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with no departures or suppleme...
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...