ANS 15.21 : 2012
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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FORMAT AND CONTENT FOR SAFETY ANALYSIS REPORTS FOR RESEARCH REACTORS
21-08-2023
12-01-2013
1. Introduction
1.1 Scope
1.2 Definitions
1.3 Application
1.3.1 Purpose
1.3.2 Format
1.3.3 Style
1.3.4 International System of Units (SI)
1.3.5 SAR Table of Contents
1.3.6 SAR Appendices
1.3.7 Significant Figures
1.3.8 Abbreviations
1.3.9 References
1.3.10 Security
1.3.11 Procedures
1.3.12 Organizations
1.3.13 Specifications
2. Safety Analysis Report Contents
2.1 Chapter 1, Introduction
2.2 Chapter 2, Site Characteristics
2.3 Chapter 3, General Design of Buildings and Structures
2.4 Chapter 4, Reactor
2.5 Chapter 5, Reactor Coolant System and Connected Systems
2.6 Chapter 6, Engineered Safety Features
2.7 Chapter 7, Instrumentation and Controls
2.8 Chapter 8, Electric Power
2.9 Chapter 9, Auxiliary Systems
2.10 Chapter 10,Experimental Facilities and Utilization
2.11 Chapter 11,Operational Radiological Safety
2.12 Chapter 12,Conduct of Operations
2.13 Chapter 13,Accident Analysis
2.14 Chapter 14,Technical Specifications (or Equivalent Document)
2.15 Chapter 15,Quality Assurance Program
2.16 Chapter 16,Decontamination and Decommissioning
3. References
Appendices
Appendix A Table of Contents for a Research Reactor
Safety Analysis Report
Appendix B Glossary of Definitions Found in Research Reactor
Standards (ANS-15 Series)
Appendix C Selected Initiating Events for Research
Reactor Accident Analysis
Appendix D References Related to Research Reactor
Safety Analysis Reports
Gives the criteria for the format and content for safety analysis reports (SARs) for research reactors.
DocumentType |
Standard
|
PublisherName |
American Nuclear Society
|
Status |
Superseded
|
SupersededBy | |
Supersedes |
ANS 15.7-1977(R1986) | SITE EVALUATION, RESEARCH REACTOR |
ANS 15.16 : 2015 | EMERGENCY PLANNING FOR RESEARCH REACTORS |
ANS 15.4 : 2016 | SELECTION AND TRAINING OF PERSONNEL FOR RESEARCH REACTORS |
ANS 15.10-1994 | DECOMMISSIONING OF RESEARCH REACTORS |
ANS 15.15-1978(R1986) | SAFETY SYSTEMS OF RESEARCH REACTORS, CRITERIA FOR THE REACTOR |
ANS 15.11 : 2016 | RADIATION PROTECTION AT RESEARCH REACTOR FACILITIES |
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