Spotlight
SMR-300
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On this page:
Project Overview
The SMR-300 is an advanced, passively safe, pressurized light water nuclear power plant with 300 MW(e) rated net electric output. The SMR-300 is designed with forced circulation utilizing two cold legs each with a vertically mounted reactor coolant pump, two hot legs, and a single once-through steam generator (OTSG) with an integral pressurizer stacked on top of the OTSG. The use of reactor coolant pumps during normal operation is necessary to produce the rated power; however, the design utilizes passive, gravity driven safety systems that do not rely on pumps, external water, external power, or operator action. The annular reservoir, the large body of water situated between the containment structure and containment enclosure structure, serves as the SMR‑300 ultimate heat sink.
Pre-Application Documents for the SMR-300 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 correspondences related to the pre-application activities with SMR, LLC, a Holtec International Company, regarding its initial design, SMR-160, and its uprated design, SMR-300.
On this page:
- Topical Reports for the SMR-300 Design
- White Papers for the SMR-300 Design
- Public Meeting Materials and Meeting Summaries for the SMR-300 Design
- Correspondences related to the SMR-300 Design
- Clarification Questions related to the SMR-300 Design
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Topical Reports for the SMR-300 Design
The following table provides access to topical reports that SMR (Holtec) has submitted for NRC staff review and approval. Information regarding public meetings on the topical report are listed in the Public Meeting Materials and Meeting Summaries for the SMR-300 Design:
Submittal Date | Title | Topical Report Submittal ADAMS Accession No. | Staff Final Safety Evaluation Report ADAMS Accession No. |
|---|---|---|---|
06/06/25 | HI-224198, "SMR-300 Design Basis Accident Radiological Consequences Analysis Methodology Licensing Topical Report" | Revision 0: ML25157A143 | Under review |
06/11/24 | HI-2230875, "Holtec PSA Risk Significance Determination Methodology Licensing Topical Report" | Revision 0: ML24163A399 -A Version: ML25051A209 | Complete Final Safety Evaluation |
09/28/23 | HI-2230815, “Quality Assurance Program for Holtec International’s Small Modular Reactor Design and Construction” | Revision 0: Revision 1: ML24110A088 Revision 2: ML24155A285 | Complete |
During the review of the topical reports (TRs), the NRC staff may issue requests for additional information (RAIs) that are needed to determine the acceptability of methods and approaches described in each TR. The applicant's responses to RAIs may result in revisions to a TR and the issuance of TR supplement that incorporates all changes. Only the latest revision of the TR is listed above.
Additional information can be obtained from ADAMS using a search by docket number 99902049.
White Papers for the SMR-300 Design
The following table provides access to White Papers that SMR (Holtec) has submitted for NRC staff review and feedback:
Submittal Date | Title | White Paper ADAMS Accession No. | Staff Feedback or Assessment ADAMS Accession No. |
|---|---|---|---|
09/06/24 | SMR, LLC – Planned SMR-300 LWA Exemption Request and LWA Application Contents | Proprietary | Under review |
11/08/23 | SMR, LLC, White Paper, “Soil Structure Interaction Analysis” | ||
09/26/23 | SMR, LLC, 160-USNRC-064, “Limited Work Authorization Requirements Applicable to SMR, LLC” | ||
08/25/23 | SMR, LLC/Mitsubishi Electric Corp., JEXK-0143-1049-P(R0), “Two Division Safety System Compliance with Applicable Rules and Regulations” | Proprietary | |
08/11/23 | SMR, LLC/Mitsubishi Electric Corp., JEXK-0143-1050-P(R0), “Functional Independence Evaluation Based on ISG-04” | Proprietary | |
07/13/23 | SMR, LLC JEXK-0143-1048-P, "Diversity Evaluation Based on NUREG/CR-6303." | Proprietary | |
06/14/23 | SMR, LLC Report HI-2210328, "HFE Functional Requirements Analysis and Function Allocation for Chemical and Volume Control System" | Proprietary | |
01/23/23 | SMR, LLC, SMR-160 Hazard Analysis for l&C System Methodology Report No. Hl‑2230060, Rev. 0 | ML23023A006, part of ML23023A002 | |
12/19/22 | SMR, LLC, Preapplication Meeting Materials for January 25, 2023 | ||
12/19/22 | SMR-160 Reactor Coolant Makeup White Paper | ||
11/01/22 | Enclosure 2: SMR-160 PDHR and SOHR Containment Isolation White Paper Report No. HI-2220845, Rev. O (Redacted) | ML22305A511, part of ML22305A508 | |
11/01/22 | SMR, LLC, SMR-160 GDC 40 Compliance White Paper Report No. Hl-2220836 Rev. O | ||
10/14/22 | SMR, LLC, Hl-2220583, Rev. 1, SMR-160 I&C Architecture White Paper | ML22287A012, part of ML22287A008 | |
10/06/22 | Enclosure 3: HI-2220717, "SMR-160 Spent Fuel Pool Makeup White Paper" | ||
09/13/22 | HI-2188193, Revision 1, "SMR 160 Control Rod Assembly Design Criteria Document" |
The prospective applicant may choose to receive NRC feedback on its White Papers during a public meeting. The NRC feedback provided during the public meeting is documented in the meeting summary.
Additional information can be obtained from ADAMS using a search by docket number 99902049.
Public Meeting Materials and Meeting Summaries for the SMR-300 Design
Meeting Date | Meeting Topic | Meeting Materials ADAMS Accession No. | Meeting Summary ADAMS Accession No. |
|---|---|---|---|
06/26/25 | Combustible Gas Control Considerations for the SMR-300 In-Containment Spent Fuel Pool | Pending | |
05/08/25 | SMR-300 PSAR Fire Analyses Plan | ||
04/28/25 | Update on Palisades Site Characterization Work Supporting the SMR-300 Environmental Report | Pending | |
03/19/25 | Overview of Proposed Exemption for Emergency Preparedness Requirements | ||
02/18/25 | Radiological Consequences Topical Report Pre-Submittal Meeting | ||
02/13/25 | Environmental Impacts of Postulated Accidents | Pending | |
12/12/24 | SMR Holtec Risk Significance Topical Report – Limitations & Conditions | ||
10/01/24 | Control Rod Drive System Testing | ||
09/23/24 | Modularity Design Philosophy | ||
09/19/24 | Integral and Separate Effects Testing Scaling | ||
09/10/24 | Nuclear Codes – Verification & Validation | ||
08/13/24 | Cyber Security | ||
07/24/24 | Reliability Assurance Program | ||
07/19/24 | Limited Work Authorization Scope and Licensing Strategy | ||
07/11/24 | Environmental Qualification | ||
06/05/24 | Proprietary Information from 05/24/24 SMR-300 Design Overview Meeting: Instrumentation & Control, Human Factors and Electrical Engineering | See 05/08/24 Meeting Materials: ML24122C699 | |
05/31/24 | Quality Assurance Program Topical Report – Clarification of Remote Source Verification | Topical Report: | |
05/08/24 | SMR-300 Design Overview | ||
05/01/24 | Update on Risk Significance Topical Report Submission | ||
04/10/24 | Chapter 15 Analysis | CANCELLED | |
04/03/24 | Initial Environmental and Site Characterization | ||
03/27/24 | Quality Assurance Program Description Topical Report – Revised Information Needs | ||
02/26/24 | Fire Protection Program | ||
02/07/24 | GDC 17 – Electric Power Systems | ||
02/26/24 | Quality Assurance Program Description Topical Report – Information Needs | ||
02/07/24 | Chapter 16 Technical Specification Development | ||
01/26/24 | Quality Assurance Program Description | ||
11/08/23 | Soil Structure Interaction Analysis | ||
11/01/23 | Limited Work Authorization Process | ||
10/04/23 | Applicability of Three-Mile Island Action Items to the SMR-160 Design | ||
09/27/23 | SMR-160 Fuel Management | ||
09/20/23 | Dual Unit Simulator Fidelity for the SMR-160 Design | ||
09/13/23 | Applicability of IEEE 603 to the SMR-160 Design | ||
08/23/23 | SMR-160 Conformance with DI&C ISG-04 – Highly Integrated Control Rooms | ||
08/09/23 | Update on SMR-160 Seismic Methodology | Meeting rescheduled to 11/01/23 | |
07/26/23 | SMR-160 Defense-in-Depth and Diversity (D3) | ||
07/12/23 | SMR-160 Emergency Planning Zone Methodology | ||
06/20/23 | Human Factors Engineering Programs | ||
06/07/23 | Anticipated Transients without Scram | ||
04/19/23 | Chapter 13 – Operational Programs | ||
03/22/23 | Main Control Room Staffing | ||
03/08/23 | Simulator, Operator Training/Qualifications, and Operating Experience Reviews | ||
02/15/23 | Fire Protection | ||
02/08/23 | Instrumentation & Control Hazards Analysis | ||
01/25/23 | Parts of a Construction Permit Application, and Table of Contents of the Preliminary Safety Analysis Report and Environmental Report | ||
01/11/23 | Reactor Coolant Makeup System Design and General Design Criterion 33 | ||
12/06/22 | Quality Assurance Guidance | None | |
11/30/22 | Closed System Isolation Valves Design (General Design Criterion 57) | ||
11/16/22 | Passive Containment Heat Removal System (General Design Criterion 40) | ||
10/27/22 | Technical Specifications | None | |
10/18/22 | Spent Fuel Pool Makeup | ||
10/18/22 | Reactivity Control and Materials Aspects of the Control Rod Drive System | ||
10/04/22 | White Paper: Instrumentation and Control Architecture | ||
09/27/22 | Seismic Analysis Method | ||
09/13/22 | Control Rod Drive System |
Future public meetings may be found through the calendar on the main NRC public site.
Additional information can be obtained from ADAMS using a search by docket number 99902049.
Correspondences related to the SMR-300 Design
The following table provides access to letters and other pre-application correspondence between SMR, LLC, a Holtec International Company, and NRC regarding the SMR (Holtec) design.
Date | Description |
|---|---|
U.S. Nuclear Regulatory Commission Staff Response to SMR, LLC (A Holtec International Company) Presentation on the 10 CFR 50.160 Emergency Preparedness Rule for the SMR-300 Design | |
SMR, LLC, Regulatory Engagement Plan, HI-2240423, Revision 5 | |
SMR, LLC, Regulatory Engagement Plan, HI-2240423, Revision 4 | |
SMR, LLC, Regulatory Engagement Plan, HI-2240423, Revision 3 | |
SMR, LLC, Regulatory Engagement Plan, HI-2240423, Revision 2 | |
SMR, LLC, Regulatory Engagement Plan, HI-2240423, Revision 1 | |
SMR, LLC, Regulatory Engagement Plan, HI-2240423, Revision 0 | |
2-13-2024 - Email to A. Brenner, SMR (Holtec) re - Collaborative Activities with the United Kingdom Office of Nuclear Regulation on the SMR (Holtec) Design (Project No. 99902049) |
Clarification Questions related to the SMR-300 Design
The following table provides access to clarification questions between SMR (Holtec) and the NRC staff.
Date | Topic |
|---|---|
NRC Staff Response to Questions re: Guidance for Multi-unit Probabilistic Safety Analysis (Project 99902049) | |
NRC Staff Response to Questions re: Seismic Methodology (Project 99902049) | |
NRC Staff response to Question re: Seismic Probabilistic Risk Assessment for a Construction Permit Application (Project 99902049) | |
NRC Staff Response to Questions re: Electrical Separation for the SMR-160 design (99902049) | |
NRC Staff Questions and SMR (Holtec) Responses re: July 19, 2023, Public Meeting Materials - SMR-160 Code Verification and Validation and Evaluation Methodologies (99902049) | |
NRC Staff Response to Questions on IEEE 603-1991 and Completion of Protective Action (Project 99902049) | |
NRC Staff Response to Questions re: Quality Assurance for the SMR-160 Design (99902049) | |
NRC Staff Response to Clarification Question re: RHR System Classification (99902049) | |
NRC Staff response to Follow-up Question re: Polar Crane Analysis for the SMR-160 design (Project Number 99902049) | |
NRC Staff response to Question re: Manual Initiation of Protective Action for the SMR-160 design (Project Number 99902049) | |
NRC staff response to SMR-160 question re: Polar Crane Analysis (Project 99902049) | |
NRC Staff Response to SMR (Holtec) Questions re: NonSafety Structures. | |
NRC Staff Response to Follow-up Questions re: Water Source for Fire Protection | |
NRC Staff Response to SMR (Holtec) Questions re: Radwaste Management (RG 1.143) | |
NRC Staff Response to SMR (Holtec) Question re: Wet Bulb Temperature | |
NRC Staff Response to Follow-up Questions after the November 30 Public Meeting re: Closed Systems Isolation Valves | |
NRC Staff Response to Follow-up Questions regarding the Scope of PRA and Turbine Missiles (RG 1.115) | |
NRC Staff Response to Question regarding "Equivalent Materials" for the SMR-160 Design | |
NRC Staff Response to Question regarding Water Source for Fire Protection | |
NRC Technical Paper re: Passive SMRs presented at IAEA Conference | |
NRC Staff Response to SMR (Holtec) Clarification Question re: Aircraft Impact Assessment | |
NRC Staff Response to SMR (Holtec) Clarification Question re: Turbine Missiles | |
NRC Staff response to questions re: Common-Cause Failure, Common Mode-Failure, and Level/Pressure/Temperature Transmitters | |
NRC Staff Response to Questions re: SECY-94-084 | |
NRC Staff Response to Questions re: Aircraft Impact Analysis | |
NRC Staff Response to Follow-Up Question re: CRDS (SRP 3.9.4) | |
NRC Staff Response to Clarification Question regarding Codes and Standards | |
NRC Staff Responses to Clarification Questions regarding Containment Stress Limits (SRP 3.9.3) | |
NRC Staff Responses for Some Questions Supporting the Oct 18 SFP Public Meeting | |
NRC Staff Response to the Clarification Question regarding Software for Structural Analysis | |
NRC Staff Response to the Clarification Question regarding Piping Design and Analysis for the SMR-160 Design |
Page Last Reviewed/Updated Monday, November 03, 2025
Page Last Reviewed/Updated Monday, November 03, 2025