Radiation Protection 3.2-1STP 3 & 4 Tier 13.2 Radiation ProtectionThe information in this section of the reference ABWR DCD, including all tables and figures, is incorporated by reference with the following departures.STD DEP T1 2.14-1 (Figure 3.2i)STD DEP T1 3.4-1 (Figure 3....
Turbine Service Water System 4.6-1/2STP 3 & 4 Tier 14.6 Turbine Service Water SystemThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 07
Nuclear Steam Supply Systems 2.1-1/2STP 3 & 4 Tier 12.1 Nuclear Steam Supply SystemsThe 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 2.1-22.1.1 Reac...
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...
Diverse Instrumentation and Control Systems 7.8S-1/2STP 3 & 4 Final Safety Analysis Report7.8S Diverse Instrumentation and Control SystemsSubsection 7C.5 addresses diversity of the instrumentation and control systems.Rev. 08
2.5S.1-118 Basic Geologic and Seismic InformationSTP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-28 Site Area Geological Map (0.6-mile radius)Rev. 05 Basic Geologic and Seismic Information 2.5S.1-119STP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-29 STP Site Specific...
Basic Geologic and Seismic Information 2.5S.1-90STP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-2 Site Vicinity Topographic Map (25-mile radius)Rev. 05 2.5S.1-91 Basic Geologic and Seismic InformationSTP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-3 Site Area Topogra...
Nuclear Steam Supply Systems 2.1-1/2STP 3 & 4 Tier 12.1 Nuclear Steam Supply SystemsThe 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 2.1-22.1.1 Reac...
Fault Trees 19QA-1STP 3 & 4 Final Safety Analysis Report 19QA Fault TreesThe information in this appendix of the reference ABWR DCD, including all subsections, is incorporated by reference with no departures or supplements.Rev. 05
Seismic Margins Analysis 19I-1STP 3 & 4 Final Safety Analysis Report19I Seismic Margins AnalysisThe information in this appendix of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departure and supplement...
PRA-Based Reliability and Maintenance 19K-1STP 3 & 4 Final Safety Analysis Report 19K PRA-Based Reliability and MaintenanceThe information in this Appendix of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with the following departu...
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 ...
Not Used 19J-1/2STP 3 & 4 Final Safety Analysis Report 19J Not UsedThe information in this appendix of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 05
Probabilistic Evaluations 19D-1/2STP 3 & 4 Final Safety Analysis Report 19D 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. 05
Maintenance Rule Program 17.6S-1STP 3 & 4 Final Safety Analysis Report17.6S Maintenance Rule ProgramNuclear Energy Institute Report No. NEI 07-02A, Rev.0, dated March 2008, "Generic FSAR Template Guidance for Maintenance Rule Program Description for Plants Licensed Under 10 C...
Emergency Operation Information and Controls 18F-1STP 3 & 4 Final Safety Analysis Report 18F Emergency Operation Information and ControlsThe information in this appendix of the reference ABWR DCD, including all tables, is incorporated by reference with the following departure...
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...
Basic Geologic and Seismic Information 2.5S.1-136STP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-46 Field Survey Elevation Profiles Rev. 05 2.5S.1-137 Basic Geologic and Seismic InformationSTP 3 & 4 Final Safety Analysis ReportFigure 2.5S.1-47 Cross Section C-Cā Along So...
Health Physics Program 12.5-1/2STP 3 & 4 Final Safety Analysis Report12.5 Health Physics ProgramThe information in this section of the reference ABWR DCD, including all subsections, is incorporated by reference with the following supplements.12.5.3.1 Radiation Protection Pro...
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...
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BIOLOGICAL OPINIONEffects to the Indiana Bat (Myotis soda/is) andNorthern Long-eared Bat (Myotis septentrionalis)from the Construction and Operationof the Bell Bend Nuclear Power PlantLuzerne County, PennsylvaniaPrepared by:U.S. Fish and Wildlife ServicePennsylvania Field Offi...
On this page:Publication InformationAbstractDownload complete documentNUREG CP-0194, Volume 2 (PDF - 25.59 MB)Publication InformationDate Published: July 2010Prepared by: David Stroup Felix Gonzalez Hugh WoodsU.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Rese...
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