NuScale 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 8/28/2020
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

Page Last Reviewed/Updated Tuesday, December 01, 2020