The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Topical Reports for the NuScale US460 Standard Design Approval

NuScale SDAA Topical Reports
Topical Report Title Status
TR-0118-58005-P-A
 
Improvements in Frequency Domain Soil-Structure-Fluid Interaction Analysis, Revision 2 Approved (-A) version Issued on 12/18/2020
TR-0420-69456-A
 
Control Room Staffing Plan, Revision 1 Approved (-A) version issued on 6/2/2021
TR-0920-71621-A
 
Building Design and Analysis Methodology  for Safety-Related Structures, Revision 1 Approved (-A) version Issued on 3/3/2022
TR-108553-P-A
 
“Framatome Fuel and Structural Response Methodologies Applicability to NuScale: Supplement 1 to TR-0116-20825-P-A, Revision 1 and Supplement 1 to TR-0716-50351-P-A, Revision 1,” Revision 0 Approved (-A) version Issued on 11/28/2022
TR-0116-21012-P-A "Applicability Range Extension of NSP4 Critical Heat Flux Correlation, Supplement 1 to TR-0116-21012-P-A, Revision 1," TR-107522, Revision 1 Approved (-A) version Issued on 4/28/2023
MN-122626-A
 
Quality Assurance Program Description, Revision 1 Approved (-A) version Issued on 2/02/2024
TR-108601-A
 
“Statistical Subchannel Analysis Methodology, Supplement 1 to TR-0915-17564-P-A, Revision 2, Subchannel Analysis Methodology," TR-108601-P, Revision 4 Approved (-A) version Issued on 4/15/2024
TR-0716-50350
 
Rod Ejection Accident Methodology, Revision 3 ACRS review completed
TR-124587
 
Extended Passive Cooling and Reactivity Control Methodology, Revision 0 Under review
TR submitted on 1/5/2023
Next step – NRC issues Advanced SE
TR-0516-49416
 
Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4 Under review
TR submitted on 1/5/2023
Next step – NRC issues Advanced SE
TR-0516-49422
 
Loss-of-Coolant Accident Evaluation Model, Revision 3 Under review
TR submitted on 1/8/2023
Next step – NRC issues Advanced SE
TR-131981
 
Methodology for the Determination of the Onset of Density Wave Oscillations (DWO), Revision 1 Under review
TR submitted on 7/17/2023
Next step – NRC issues Advanced SE
NuScale Generic Topical Reports
TR-0915-17772-P-A
 
Methodology for Establishing the Technical Basis for Plume Exposure Emergency Planning Zones at NuScale Small Modular Reactor Plant Sites, Revision 3 Approved (-A) version Issued on 10/26/2022
TR-141299-P
 
NuScale Power Plant Design Capability to Mitigate Beyond-Design-Basis Events Defined by 10 CFR 50.155, Revision 1 Under review
TR submitted on 9/11/2023
Next step – NRC issues Advance SE
TR-145417-P
 
NuScale US460 Fuel Storage Rack Design Topical Report, Revision 0 Under review
TR submitted on 10/9/2023
Next step – NRC issues Advance SE

Page Last Reviewed/Updated Tuesday, December 17, 2024