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...
Corium Shield 19ED-1/2STP 3 & 4 Final Safety Analysis Report 19ED Corium ShieldThe information in this appendix of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with no departures or supplements.Rev. 05
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...
Design Reliability Assurance Program 3.6-1/2STP 3 & 4 Tier 13.6 Design Reliability Assurance ProgramThe information in this section of the reference ABWR DCD, including all tables, is incorporated by reference with no departures or supplements.Rev. 05
High Pressure Nitrogen Gas Supply System 6.7-1/2STP 3 & 4 Final Safety Analysis Report 6.7 High Pressure Nitrogen Gas Supply SystemThe information in this section of the reference ABWR DCD, including all subsections, tables and figures, is incorporated by reference with no de...
Severe Accident Mitigation Alternatives 7.3-1STP 3 & 4 Environmental Report7.3 Severe Accident Mitigation Alternatives As described in ER Section 7.2, GE performed a generic severe accident analysis for the ABWR as part of the design certification process (Reference 7.3-1). ...
Instrumentation and Control Systems and Platforms 7.1S-1STP 3 & 4 Final Safety Analysis Report7.1S Instrumentation and Control Systems and PlatformsThis supplemental section provides information for safety-related and nonsafety-related instrumentation and control (I&C) system...
Introduction 19.2-1STP 3 & 4 Final Safety Analysis Report 19.2 IntroductionThe information in this section of the reference ABWR DCD, including all subsections, and tables, is incorporated by reference with the following departure and supplements.STD DEP Admin (Table 19.2-1)1...
Design Basis Accidents 7.1-1STP 3 & 4 Environmental Report7.0 Environmental Impacts of Postulated Accidents Involving Radioactive MaterialsThis chapter assesses the environmental impacts of postulated accidents involving radioactive materials. Section 7.1 evaluates design ba...
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...
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...
Wind and Tornado Loadings 3.3-1STP 3 & 4 Final Safety Analysis Report3.3 Wind and Tornado LoadingsThe information in this section of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with the following departure and supplements.STD DEP...
Containment Systems 6.2-1STP 3 & 4 Final Safety Analysis Report 6.2 Containment 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...
Abbreviations and Acronyms Used in the ABWR Certified Design Material Appendix B-1STP 3 & 4 Tier 1Appendix B Abbreviations and Acronyms Used in the ABWR Certified Design MaterialThe information in this appendix of the reference ABWR DCD is incorporated by reference with no de...
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...
Additional Bypass Leakage Considerations 6E-1/2STP 3 & 4 Final Safety Analysis Report 6E Additional Bypass Leakage ConsiderationsThe information in this appendix of the reference ABWR DCD, including all subsections, is incorporated by reference with no departures or supplemen...
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...
Heating, Ventilating and Air Conditioning System 4.10-1/2STP 3 & 4 Tier 14.10 Heating, Ventilating and Air Conditioning SystemThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 05
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. 05
WI Department of Energy W hngtnDC 20585 2 9 1993 Mr. Joseph J. Holonich, Director Repository Licensing and Quality Assurance Project Directorate Division of High-Level Waste Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washin...
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 2, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P.O. Box 88, Mail Code 800 Jenkinsville, SC 29065 SUBJECT: VI...
DOCKET NUIE MMM , League of Women X oters of Soh caro a P.O. Box 8453 Columbia, SC 29202 "00 GUT 2i P 5' 9 October 17, 2000 To: Secretariy U.S. Nuclear Regulatory Commission Washington, DC 20555 From: Mary T. Kelly, Associate Director, LWVSC 4018 Sandwood Drive Columbia, SC 29...
,ACCELERATED DISTBJBUTION DEMONSTRATION SYSTEM~~, ~REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9404140222 DOC.DATE: 94/04/08 NOTARIZED: YES DOCKETFACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528STN-50-529 Palo Verde Nuclear Station...
o3i-3,..MAY 2 61988In Reply Refer To:Dockets: 50-49850-499Houston Lighting & Power CompanyATTN: J. H. Goldberg, Group VicePresident,' Nuclear~P.O. Box 1700Houston, Texas .77001Gentlemen:Attached is a copy of the Federal Emergency Management Agency (FEMA),Region VI letter dated...
NRC INSPECTION MANUAL CIPBCCIB MANUAL CHAPTER 2503 CONSTRUCTION INSPECTION PROGRAM: INSPECTIONS OF INSPECTIONS, TESTS, ANALYSES AND ACCEPTANCE CRITERIA (ITAAC) RELATED WORK Issue Date: 10/03/07 i 2503 TABLE OF CONTENTS 250...