NuScale US600 Safety Evaluations
The NRC's Safety Evaluations with Open Items (Review Phase 2) in conjunction with its review of the NuScale Design Certification application submitted by NuScale Power, LLC can be accessed in the Agencywide Documents Access and Management System (ADAMS) via Accession No. ML19191A196.
The NRC's Advanced Safety Evaluations with No Open Items (Review Phase 4) can be accessed in ADAMS via Accession No. ML19192A011. A staff Non-Concurrence Process (NCP) for Phase 4 can be accessed in ADAMS via Accession No. ML20049A058.
The NRC approved NuScale topical reports, along with NRC staff's safety evaluations, can be accessed in ADAMS via Accession No. ML20197A370.
The NRC's Final Safety Evaluations Reports (Review Phase 6) can be accessed in ADAMS via package Accession No. ML20023A318, which also contains documents for a staff NCP.
Specifically, the following table provides access to the Final Safety Evaluation Report (with No Open Items) that the NRC has issued in conjunction with its completion of the review of NuScale Design Certification application submitted by NuScale Power, LLC. The table lists safety evaluation reports on all 21 DCA Chapters along with an abstract, a Table of Contents, and six Appendices.
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Chapter |
Description |
Date |
|
Abstract |
8/28/2020 |
TOC |
Table of Contents |
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1 |
Introduction and General Discussion |
8/28/2020 |
2 |
Site Characteristics and Site Parameters |
8/28/2020 |
3 |
Design of Structures, Systems, Components and Equipment |
8/28/2020 |
4 |
Reactor |
8/28/2020 |
5 |
Reactor Coolant System and Connecting Systems |
8/28/2020 |
6 |
Engineered Safety Features |
8/28/2020 |
7 |
Instrumentation and Controls |
8/28/2020 |
8 |
Electric Power |
8/28/2020 |
9 |
Auxiliary Systems |
8/28/2020 |
10 |
Steam and Power Conversion System |
8/28/2020 |
11 |
Radioactive Waste Management |
8/28/2020 |
12 |
Radiation Protection |
8/28/2020 |
13 |
Conduct of Operations |
8/28/2020 |
14 |
Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria |
8/28/2020 |
15 |
Transient and Accident Analysis |
8/28/2020 |
16 |
Technical Specifications |
8/28/2020 |
17 |
Quality Assurance and Reliability Assurance |
8/28/2020 |
18 |
Human Factors Engineering |
8/28/2020 |
19 |
Probabilistic Risk Assessment and Severe Accident Evaluation |
8/28/2020 |
20 |
Mitigation of Beyond-Design-Basis Events |
8/28/2020 |
21 |
Multi-Module Design Considerations |
8/28/2020 |
Appendix A |
Chronology |
8/28/2020 |
Appendix B |
References |
8/28/2020 |
Appendix C |
Acronyms |
8/28/2020 |
Appendix D |
Principal Contributors |
8/28/2020 |
Appendix E |
Index of NRC's Requests for Additional Information |
8/28/2020 |
Appendix F |
Report by the Advisory Committee on Reactor Safeguards |
8/28/2020 |