| 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 |