United States Nuclear Regulatory Commission - Protecting People and the Environment

Advisory Committee on Reactor Safeguards (ACRS) 2020 Letter Reports

This page includes links to files in non-HTML format. See Plugins, Viewers, and Other Tools for more information.

Date Title Response
08/04/2020 Safety Evaluation, Revision 2 for Topical Report, "Uranium Oxycarbide (UCO) Tristructural Isotropic (TRISO) Coated Particle Fuel Performance: Topical Report EPRI-AR-1(NP)."  
07/29/2020 Report on the Safety Aspects of the NuScale Small Modular Reactor  
07/29/2020 NuScale Area of Focus – Boron Redistribution  
06/23/2020 Review of NEI 96–07, Appendix D, Revision 1, and NRC Draft Regulatory Guide 1.187 Revision 2 Addressing Application Of 10 CFR 50.59 To Digital I&C Modifications  
06/01/2020 Safety Evaluation of the Kairos Topical Report Kp–TR–005–P, Revision 1, "Reactor Coolant for the Kairos Power Fluoride Salt-Cooled High Temperature Reactor" 07/02/2020
06/01/2020 NuScale Areas of Focus – Probabilistic Risk Assessment And Emergency Core Cooling System Valve Performance 07/01/2020
05/27/2020 Safety Evaluation For Topical Report KP–TR–006-P, Revision 1, "Scaling Methodology For The Kairos Power Testing Program" 07/02/2020
04/30/2020 Report on the Safety Aspects of the Subsequent License Renewal Application Review of the Surry Power Station, Units 1 and 2 06/01/2020
04/29/2020 NuScale Chapter 15: Open Item Closure and Area of Focus Reviews – Return to Criticality And Boron Distribution 05/22/2020
04/28/2020 NuScale Combustible Gas Monitoring 05/18/2020
04/13/2020 Biennial Review and Evaluation of NRC Safety Research Program 05/19/2020
03/26/2020 Safety Evaluation Report of the NuScale Power, LLC, Topical Report TR–0716–50350, Revision 1, "Rod Ejection Accident Methodology" 04/09/2020
03/25/2020 Safety Evaluation Report for Topical Report TR–0516–49416, Revision 2, "Non-Loss-of-Coolant Accident Analysis Methodology" 04/27/2020
03/25/2020 NuScale Power, LLC, Design Certification Application - Safety Evaluation for Topical Report, "Loss-of-Coolant Accident Evaluation Model," TR-0516-49422, Revision 1 04/14/2020
03/24/2020 NuScale Area of Focus – Helical Tube Steam Generator Design 04/24/2020
03/10/2020 Assessment of the Quality of Selected NRC Research Projects by the Advisory Committee on Reactor Safeguards - FY 2019 04/16/2020
Page Last Reviewed/Updated Wednesday, August 12, 2020