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Project Overview
The staff of the U.S. Nuclear Regulatory Commission (NRC) is currently engaged in pre-application activities for the GEH BWRX-300 small modular reactor (SMR), including the review of numerous licensing topical reports (LTRs) describing the design approaches and methodologies for the BWRX-300 SMR in advance of a 10 CFR Part 50 or Part 52 application. The BWRX-300 is a ~300 MWe water-cooled, natural circulation SMR with passive safety systems. As the tenth evolution of the Boiling Water Reactor (BWR), the BWRX-300 represents the simplest, yet most innovative BWR design since GE began developing nuclear reactors in 1955. The design of the BWRX-300 is based on the U.S. NRC-licensed, 1,520 MWe Economic Simplified BWR and is designed to provide clean, flexible baseload electricity generation.
Topical Reports and White Papers for the GEH BWRX-300 SMR Design
The following table provides access to topical reports that GEH has submitted for NRC staff review and approval:
| Submittal Date |
Title |
Topical Report or White Paper Submittal ADAMS Accession No. |
Staff Final Safety Evaluation Report or White Paper Feedback
Accession No. |
Approved version of Licensing Topical Report
(“-A”) |
| 12/31/2019 |
NEDO–33910P-A, Revision 2, BWRX–300, "Reactor Pressure Vessel Isolation and Overpressure Protection." |
ML20174A577 |
ML20176A449 |
ML23167A086 |
| 03/31/2020 |
NEDO-33911P-A, Revision 3, BWRX–300, "Containment Performance." |
ML20248H573 |
ML21008A371 |
ML22007A024 |
| 03/31/2020 |
NEDO-33912P-A Revision 1, BWRX–300, "Reactivity Control." |
ML20248H544 |
ML20275A373 |
ML21060B579 |
| 09/25/2020 |
NEDC–33922P-A, Revision 3, BWRX–300, "Containment Evaluation Method (GOTHIC Application to BWRX–300)" |
ML20269A472 |
ML22040A004 |
ML22168A014 |
| 01/20/2021 |
NEDO-33914-A, Revision 2, BWRX-300, “Advanced Civil Construction and Design Approach Licensing Topical Report.” |
ML21020A137 |
ML22020A036 |
ML22168A010 |
| 10/14/2022 |
BWRX-300 White Paper NEDO-33988, Revision 0, BWRX-300 Steel-Plate Composite (SC) Containment Vessel (SCCV) and Reactor Building Structural Design |
ML22287A177 |
ML23005A034 |
Not Applicable |
| 12/07/2022 |
BWRX-300 White Paper NEDO-33989, Revision 0, BWRX-300 Safety Strategy |
ML22341A058 |
ML23023A143 |
Not Applicable |
| 08/18/2023 |
NEDO-33926,
Revision 1, BWRX-300, Steel-Plate Composite Containment Vessel (SCCV) and Reactor Building (RB) Structural Design |
ML23230B215 |
Draft SER and RAIs Target Date
December 2023 |
Final – A License TR Target Date August 2024 |
| 2023/ 2024 |
NEDC-33934,
Draft LTR "Readiness Assessment"
ML23166A876 |
TBD |
TBD |
TBD |
During the course of its review of the License TRs, the NRC staff may issue requests for additional information (RAIs) that is needed to determine the acceptability of methods and approaches described in each License TR. The applicant's responses to RAIs may result in revisions to an License TR and the issuance of an License TR supplement that incorporates all changes.
Additional information can be obtained from ADAMS (99900003).
Page Last Reviewed/Updated Monday, October 23, 2023