Application Documents for the NuScale US600 Design
The U.S. Nuclear Regulatory Commission (NRC) considers public involvement in, and information about, our activities to be a cornerstone of strong, fair regulation of the nuclear industry. As such, the NRC believes that nuclear regulation should be transacted as openly and candidly as possible to maintain and enhance the public's confidence. Ensuring appropriate openness explicitly recognizes that the public must be informed about, and have a reasonable opportunity to participate meaningfully in, the NRC's regulatory processes. Toward that end, this page provides access to documents and correspondence with NuScale related to the design certification application activities regarding the NuScale small modular reactor (SMR) design.
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Design Certification Application
The applicant submitted its design certification application in 10 "Parts" as listed in the table below.
The applicant's final safety analysis report (FSAR) - Part 2 of the application - provides information to support the NRC's approval and certification of the standard NuScale SMR design, under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 52 (10 CFR Part 52), "Licenses, Certifications, and Approvals for Nuclear Power Plants." The FSAR is divided into two "Tiers:"
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The Tier 1 material, which is derived from the more-detailed Tier 2 documents, provides high-level information on the plant design. As such, it includes the principal performance characteristics and safety functions of the plant's structures, systems, and components (SSCs). It also includes inspections, tests, analyses, and acceptance criteria (ITAAC) to provide reasonable assurance that the as-built plant will operate in conformance with the combined license (COL), the provisions of the Atomic Energy Act, and applicable NRC regulations. In addition, the Tier 1 documents identify significant site parameters and requirements for significant interfaces between the standard NuScale SMR design and those aspects of the plant design that are site-specific.
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The Tier 2 documents provide more detailed information on the plant design. This information is to be approved, but not certified, by the NRC.
| Part |
Chapter |
Title |
Revision |
| 1 |
|
General and Financial Information |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 2 |
|
Final Safety Analysis Report |
|
| Tier 1 |
| 1-5 |
Certified Design Descriptions and Inspections, Tests, Analyses, & Acceptance Criteria (ITAAC) |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| Tier 2 |
| 1 |
Introduction and General Description of the Plant |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 2 |
Site Characteristics and Site Parameters |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 3 |
Design of Structures, Systems, Components and Equipment |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 4 |
Reactor |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 5 |
Reactor Coolant System and Connecting Systems |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 6 |
Engineered Safety Features |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 7 |
Instrumentation and Controls |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 8 |
Electric Power |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 9 |
Auxiliary Systems |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 10 |
Steam and Power Conversion System |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 11 |
Radioactive Waste Management |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 12 |
Radiation Protection |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 13 |
Conduct of Operations |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 14 |
Initial Test Program and Inspections, Tests, Analyses, and Acceptance Criteria |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 15 |
Transient and Accident Analyses |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 16 |
Technical Specifications |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 17 |
Quality Assurance and Reliability Assurance |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 18 |
Human Factors Engineering |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 19 |
Probabilistic Risk Assessment and Severe Accident Evaluation |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 20 |
Mitigation of Beyond-Design-Basis Events |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 21 |
Multi-Module Design Considerations |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 3 |
|
Applicants Environmental Report - Standard Design Certification
The applicant's environmental report presents an evaluation of severe accident mitigation design alternatives (SAMDA) for the NuScale SMR design. This evaluation addresses the costs and benefits of the SAMDA, as well as the bases for not incorporating the SAMDA in the NuScale SMR design.
|
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 4 |
|
Generic Technical Specifications |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 5 |
|
Emergency Plans |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 6 |
|
Security Plans |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 7 |
|
Exemptions |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 8 |
|
License Conditions; Inspections, Tests, Analyses & Acceptance Criteria (ITAAC) |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 9 |
|
Withheld Information |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
| 10 |
|
Quality Assurance Program Description |
Rev. 5
Rev. 4
Rev. 3
Rev. 2
Rev. 1
Rev. 0 |
Standard Design Approval SDA-600
On July 13, 2020, NuScale Power, LLC, (NuScale) submitted a letter (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20195C766), requesting approval of the NuScale design as described in the NuScale DCA, under Subpart E, “Standard Design Approvals,” of 10 CFR Part 52, upon completion of NRC staff’s review and issuance of the Final Safety Evaluation Report.
In response to the NuScale letter, the NRC provided the standard design approval (SDA) on September 11, 2020, for the NuScale reactor standard design (ADAMS Accession No. ML20247J564). The SDA is for the NuScale plant consisting of up to 12 nuclear power modules, with each module having an output of 50MWe, for a total output of up to 600MWe (gross).
The SDA allows the NuScale design to be referenced in an application for a construction permit or operating license under Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities,” or an application for a combined license or manufacturing license under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.” However, this SDA does not constitute a commitment to issue a permit, design certification (DC), or license, or in any way affect the authority of the Commission, the Atomic Safety and Licensing Board, or other presiding officers in any proceeding under 10 CFR Part 2, “Rules of Practice for Domestic Licensing Proceedings and Issuance of Orders.”
The Advisory Committee on Reactor Safeguards (ACRS) also concluded that the SDA for the 600 MWe NuScale design should be issued.
The duration of this SDA is 15 years in accordance with 10 CFR 52.147, “Duration of design approval.” If the NuScale design is subsequently certified, then this SDA will be updated, as needed, to conform to any changes resulting from the DC certification rulemaking.
Applicant Documents
This section lists, in chronological order, the years in which the applicant submitted documents to support the U.S. Nuclear Regulatory Commission (NRC) staff's review of the application. You may click on a year in the list below to see a listing of the documents that were submitted in that year.
2000s: 2020 | 2019 | 2018 | 2017 | 2016
NRC Documents
This section lists, in chronological order, the years in which the staff of the U.S. Nuclear Regulatory Commission (NRC) sent documents to the applicant in association with the application. You may click on a year in the list below to see a listing of the documents that were sent in that year.
2000s: 2020 | 2019 | 2017