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Home NRC Library Document Collections Advisory Committee on Reactor Safeguards Letter Reports

Advisory Committee on Reactor Safeguards (ACRS) 2020 Letter Reports

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Date Title Response
12/18/2020 Safety Evaluation for Topical Report NEDC-33912P, "BWRX-300 Reactivity Control  
12/16/2020 Design Review Guide (DRG): Instrumentation And Controls For Non-Light-Water Reactor (Non-LWR) Reviews) 01/25/2021
11/23/2020 Final Draft Revision 8 Of Standard Review Plan Branch Technical Position 7-19, "Guidance For Evaluation Of Defense-In-Depth And Diversity To Address Common Cause Failure Due To Latent Defects In Digital Safety Systems" 12/18/2020
11/23/2020 Letter to Margaret M. Doane from Matthew W. Sunseri regarding NuScale Topical Report, TR-0118-58005, Rev. 1, "Improvements in Frequency Domain Soil-Structure-Fluid Interaction Analysis" No Response
Required
11/23/2020 Letter to Margaret M. Doane from Matthew W. Sunseri regarding Revision 3 to RG 1.200, "Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities"  
11/23/2020 Letter to Margaret M. Doane from Matthew W. Sunseri regarding Safety Evaluation for Framatome Inc., TR ANP-10323P, Rev 1, "Galileo Fuel Rod Thermal-Mechanical Methodology for Pressurized Water Reactors"  
11/04/2020



10/19/2020		 ACRS Review Of Staff Response To The Advisory Committee On Reactor Safeguards Letter On NuScale Power, LLC, Area Of Focus – Boron Redistribution

Boron Dilution Events in the NuScale Power Module – Recommendations for Consideration in Reviewing Possible Accidents from Deborated Conditions		 No Response Required
10/21/2020 10 CFR Part 53 Licensing and Regulation of Advanced Nuclear Reactors 11/24/2020
10/06/2020 Final Safety Evaluation Report for Topical Report, Framatome Topical Report ANP-10337, Revision 0, Supplement 1P, Revision 0, "Deformable Spacer Grid Element"  
10/05/2020 Safety Evaluation for Topical Report NEDC-33910P, "BWRX-300 Reactor Pressure Vessel (RPV) Isolation and Overpressure Protection"  
10/02/2020 Observations and Lessons-Learned from ACRS Licensing Reviews Relevant to Future Advanced Reactor Applications 11/12/2020
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)." 08/26/2020
07/29/2020 Report on the Safety Aspects of the NuScale Small Modular Reactor 08/25/2020
07/29/2020 NuScale Area of Focus – Boron Redistribution 08/25/2020
07/22/2020 Regulatory Guide (RG) 1.236, Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod Drop Accidents 08/24/2020
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 Monday, March 8, 2021