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Category:Final Safety Evaluation Report (FSER)
MONTHYEARML18271A1322018-09-28028 September 2018 APR1400 Final Safety Evaluation Report, Appendix B - References ML18274A4032018-09-28028 September 2018 Korea Hydro & Nuclear Power Co., Ltd - Review Results to Final Safety Evaluation Report for Six Chapters ML18043A8872018-09-28028 September 2018 APR1400 Chapter 9, Auxiliary Systems, Final Safety Evaluation Report ML18044A1852018-09-28028 September 2018 APR1400 Chapter 10, Steam and Power Conversion System, Final Safety Evaluation Report ML18067A2922018-09-28028 September 2018 APR1400 Chapter 4, Reactor, Final Safety Evaluation Report ML18078A0162018-09-28028 September 2018 APR1400 Chapter 11, Radioactive Waste Management, Final Safety Evaluation Report ML18081A5052018-09-28028 September 2018 APR1400 Chapter 12, Radiation Protection, Final Safety Evaluation Report ML18082A2982018-09-28028 September 2018 APR1400 Chapter 2, Site Characteristics, Final Safety Evaluation Report ML18176A0512018-09-28028 September 2018 APR1400 Chapter 15, Accident and Transient Analyses, Final Safety Evaluation Report ML18197A2192018-09-28028 September 2018 APR1400 Chapter 8, Electric Power, Final Safety Evaluation Report ML18211A5692018-09-28028 September 2018 APR1400 Chapter 5, Reactor Coolant System and Connecting Systems, Final Safety Evaluation Report ML18212A0922018-09-28028 September 2018 APR1400 Chapter 6, Engineered Safety Systems, Final Safety Evaluation Report ML18215A2402018-09-28028 September 2018 APR1400 Chapter 17, Quality Assurance and Reliability Assurance, Final Safety Evaluation Report ML18215A2412018-09-28028 September 2018 APR1400 Chapter 7, Instrumentation and Controls, Final Safety Evaluation Report ML18215A2422018-09-28028 September 2018 APR1400 Chapter 3, Design of Structures, Systems, Components, and Equipment, Final Safety Evaluation Report ML18227A0612018-09-28028 September 2018 APR1400 Chapter 16, Technical Specifications, Final Safety Evaluation Report ML18261A1612018-09-28028 September 2018 APR1400 Chapter 13, Conduct of Operations, Final Safety Evaluation Report ML18264A1412018-09-28028 September 2018 APR1400 Chapter 1, Introduction and General Discussion, Final Safety Evaluation Report ML18269A1742018-09-28028 September 2018 APR1400 Chapter 18, Human Factors Engineering, Final Safety Evaluation Report ML18269A2422018-09-28028 September 2018 APR1400 Final Safety Evaluation Report, Appendix C - Acronyms ML18270A0722018-09-28028 September 2018 APR1400 Final Safety Evaluation Report, Table of Contents ML18270A3942018-09-28028 September 2018 APR1400 Final Safety Evaluation Report, Appendix D - Principal Contributors ML18270A4522018-09-28028 September 2018 APR1400 Final Safety Evaluation Report, Appendix E - Index of Nrc'S RAIs ML18271A1212018-09-28028 September 2018 APR1400 Final Safety Evaluation Report, Appendix a - Chronology ML18215A2392018-09-28028 September 2018 APR1400 Chapter 19, Probabilistic Risk Assessment and Severe Accident Evaluation, Final Safety Evaluation Report ML18264A1302018-09-21021 September 2018 Enclosure 3 - Markup of the APR1400 Chapter 6 - FSER ML18264A1292018-09-21021 September 2018 Enclosure 2 - Markup of the APR1400 Chapter 5 - FSER ML18264A1282018-09-21021 September 2018 Enclosure 1 - Markup of the APR1400 Chapter 4 - FSER 2018-09-28
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Fuel Assembly Description
Fuel Rod Description
Burnable Absorber Rod Description Control Element Assembly Description Design Evaluation
Code of Federal Regulations Design Bases ********
Description and Design Drawings Design Evaluation
Evaluation of Design Bases
Nuclear Design Description
Operating Strategy
Fuel Assemblies and Core Loading Patterns Power Distributions
Reactivity Coefficients
Reactivity Control Provisions and Requirements
Reactor Criticality During Refueling
Stability Criteria
Analytical Methods DIT and ROCS Code Suite
Legacy Library
Use of ENDF/B-IV Nuclear Data Library in DIT and ROCS
Methodology for the CPCS
Reactor Vessel Fluence Methodology and Calculation
Fluence Calculation Method
Fluence Bias Determination Method
Fluence Parameter Uncertainties Overall Fluence Uncertainty Vessel Surveillance
Calculated Vessel Fluence
Initial Test Program
Thermal-Hydraulic Design of the Reactor Core
Core Thermal-Hydraulic Calculations
Reactor Core Instrumentation Requirements
4.5.1.1 Introduction
4.5.1.2 Summary of Application
4.5.1.3 Regulatory Basis
4.5.1.4 Technical Evaluation Materials Specifications
Austenitic Stainless Steel Components
Other Materials
Cleaning and Cleanliness Controls
4.5.1.5 Combined License Information Items 4.5.1.6 Conclusions Introduction Summary of Application
Materials Specifications
Controls on Welding Nondestructive Examination Fabrication and Processing of Austenitic Stainless Steel Components
Other Materials Other Degradation Mechanisms
Regulatory Basis
Materials Specifications, Selection, and Heat Treatment Controls on Welding Nondestructive Examination Austenitic Stainless Steels
Other Materials Technical Evaluation Materials Specifications
Controls on Welding Nondestructive Examination Fabrication and Processing of Austenitic Stainless Steel Components Other Materials Other Degradation Mechanisms Combined License Information Items Conclusions
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Information for Control Rod Drive System
Evaluation of the Control Rod Drive System
Testing and Verification of the Control Rod Drive System
Information for Combined Performance of the Reactivity Control Systems Evaluation of Combined Performance of the Reactivity Control Systems