Spotlight
SMR-160
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On this page:
Project Overview
The SMR-160 is a pressurized water reactor (PWR) with passive safety systems designed by SMR, LLC, a Holtec International Company. The reactor, steam generator, and spent fuel pool are located in containment with the reactor core well below grade. The SMR-160 has a rated electrical output of 160 MWe.
Pre-Application Documents for the SMR-160 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.
On this page:
- Topical Reports for the SMR-160 Design
- White Papers for the SMR-160 Design
- Public Meeting Materials and Meeting Summaries for the SMR-160 Design
- Correspondences related to the SMR-160 Design
- Clarification Questions related to the SMR-160 Design
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Topical Reports for the SMR-160
The following table provides access to topical reports that SMR (Holtec) has submitted for NRC staff review and approval:
Submittal Date | Title | Topical Report Submittal ADAMS Accession No. | Staff Final Safety Evaluation Report ADAMS Accession No. |
|---|---|---|---|
09/28/23 | HI-2230815, Rev. 0, “Quality Assurance Program for Holtec International’s Small Modular Reactor Design and Construction” | Under Review | |
03/04/21 | HI-2201064, Rev. 2, "Elimination of the Large Break Loss of Coolant Accident (LOCA) and Establishment of LOCA Acceptance Criteria" | Withdrawn | |
06/04/14 | HI-2135649-NP, Quality Assurance Program |
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-160 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. |
|---|---|---|---|
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 | |
05/23/23 | SMR, LLC Report Hl-2230397 Rev. 0, SMR-160 LOCA Exemption Request Language and Acceptance Criteria White Paper for May 25, 2023 | Proprietary | |
05/11/23 | SMR, LLC Report HI-2210473, Revision 0, "SMR-160 PSA Risk Significance Determination Methodology" | Proprietary | |
03/29/23 | SMR, LLC Report Hl-2230279 Rev. 0, LOCA Exemption Update White Paper (P) | ||
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" | ||
10/03/22 | SMR, LLC Basis for Future LOCA Exemption Request for October 19, 2022 | ||
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-160 Design
Meeting Date | Meeting Topic | Meeting Materials ADAMS Accession No. | Meeting Summary ADAMS Accession No. |
|---|---|---|---|
10/25/23 | Risk Determination Methodology Topical Report | ||
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 | ||
08/30/23 | Follow-up on RG 1.99 Limitations | ||
08/23/23 | SMR-160 Conformance with DI&C ISG-04 – Highly Integrated Control Rooms | ||
08/09/23 | Update on SMR-160 Seismic MethodologyUpdate on SMR-160 Seismic Methodology | Meeting rescheduled to 11/01/23 | |
07/26/23 | SMR-160 Defense-in-Depth and Diversity (D3) | ||
07/19/23 | SMR-160 Verification & Validation of Codes | ||
07/12/23 | SMR-160 Emergency Planning Zone Methodology | ||
06/28/23 | Applicability of 10 CFR Part 50, Appendix K – Emergency Core Cooling System Evaluation Models | ||
06/20/23 | Human Factors Engineering Programs | ||
06/07/23 | Anticipated Transients without Scram | ||
05/25/23 | Follow-up to Loss-of-Coolant Accident Analysis Update No. 1 | ||
05/17/23 | SMR-160 Risk Topics | ||
05/10/23 | Fuel Qualification and Testing | ||
05/03/23 | SMR-160 Design Overview (Proprietary) | ||
04/19/23 | Chapter 13 – Operational Programs | ||
05/04/23 | Loss-of-Coolant Accident Analysis Update No. 1 | ||
03/22/23 | Main Control Room Staffing | ||
03/08/23 | Simulator, Operator Training/Qualifications, and Operating Experience Reviews | ||
02/22/23 | Reactor Pressure Vessel Embrittlement | ||
02/21/23 | Chapter 15 Analysis | ||
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 | |
12/05/22 | SMR-160 Passive Core Cooling System Design for Non-Loss-of-Coolant-Accident Analyses (Regulatory Treatment of Nonsafety Systems) | ||
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 | |
10/19/22 | Potential Loss-of-Coolant Accident Analysis Exemption | ||
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 | ||
08/31/22 | Loss-of-Coolant Accident Topics |
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-160 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 |
|---|---|
SMR, LLC Regulatory Engagement Plan, Revision 7 (Project No. 99902049) | |
SMR, LLC Regulatory Engagement Plan, Revision 6 (Project No. 99902049) | |
SMR, LLC, Submittal of Regulatory Engagement Plan, Revision 5 | |
SMR, LLC, Submittal of Regulatory Engagement Plan, Revision 4 | |
SMR, LLC Regulatory Engagement Plan, Revision 3 (Project No. 99902049) | |
SMR, LLC, Online Reference Portal Information Access Agreement (Project No. 99902049) | |
SMR, LLC Update to Voluntary Response to NRC Regulatory Issue Summary 2020-02 and Proposed Regulatory Engagement Plan, Revision 2 (Project No. 99902049) | |
SMR, LLC Proposed Regulatory Engagement Plan, Revision 1 (Project No. 99902049) | |
SMR, LLC, Submittal of Voluntary Response to NRC Regulatory Issue Summary 2020-02 | |
SMR Inventec, LLC Establishment of a Safeguards Information (SGI) Program and Request for SGI Use and Storage Approval | |
Voluntary Response to Regulatory Issue Summary (RIS) 2013-18 (Non-Proprietary) | |
Voluntary Response to Regulatory Issue Summary (RIS) 2012-12 (Non-Proprietary) |
Clarification Questions related to the SMR-160 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) | |
Clarification Question Regarding Potential SECY Timeline Required for Potential FOAK Exemption (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 (Holtec) Follow-up Question re: RCS Flow Instrumentation (Project 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 Questions regarding RG 1.99 Revision 2, Radiation Embrittlement of Reactor Vessel Materials (Project No. 99902049) | |
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 Staff Response to Clarification Question re: Reactor Coolant System Flow Instrumentation | |
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 Friday, November 07, 2025
Page Last Reviewed/Updated Friday, November 07, 2025