| Date |
Title |
Response |
| 12/20/2019 |
Safety Evaluation Of The NuScale Power, LLC Topical Report TR- 0915-17565, Revision 3, "Accident Source Term Methodology," And Source Term Area Of Focus Review For The NuScale Small Modular Reactor |
01/27/2020 |
| 12/19/2019 |
Safety Evaluation For Global Nuclear Fuel - Americas, LLC, Licensing Topical Report NEDE-33885P Revision 0, "GNF CRDA Application Methodology" |
|
| 12/19/2019 |
Report on the Safety Aspects of the Subsequent License Renewal Application Review of the Peach Bottom Atomic Power Station, Units 2 and 3 |
01/16/2020 |
| 11/27/2019 |
Assessment of the Continued Adequacy of Revision 2 of Regulatory Guide 1.99 |
12/23/2019 |
| 11/26/2019 |
Safety Evaluation for Brunswick Steam Electric Plant, Units 1 and 2 to Support Review of the License Amendment Request Regarding Application of Framatome Methodologies for Transition to Atrium 11 Fuel |
01/15/2020 |
| 11/26/2019 |
Interim Letter: The NRC Staff's Safety Evaluation Report with No Open Items for Chapters 8 and 18 and the Advanced Accumulator Topical Report Related to the Certification of the US-APWR Design |
|
| 11/26/2019 |
NUREG/KM-0013, "Credibility Assessment Framework For Critical Boiling Transition Models - A Generic Safety Case To Determine The Credibility Of Critical Heat Flux And Critical Power Models, Draft Report For Comment" |
01/15/2020 |
| 11/04/2019 |
Review of Advanced Reactor Computer Code Evaluations |
01/31/2020 |
| 11/04/2019 |
Safety Evaluation of Topical Report ANP-10346P, Revision 0, "ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA" |
11/27/2019 |
| 10/31/2019 |
Advanced Boiling Water Reactor Design Certification Renewal |
|
| 10/17/2019 |
ACRS Activities to Support NRC Transformation |
|
| 10/07/2019 |
Review Of Draft SECY Paper, "Population – Related Siting Considerations For Advanced Reactors" |
11/06/2019 |
| 10/07/2019 |
Report on the Safety Aspects of the Subsequent License Renewal Application of the Turkey Point Nuclear Generating Units 3 and 4 |
10/27/2019 |
| 09/26/2019 |
Safety Evaluation of Westinghouse Topic Report WCAP-17794-NP, Rev. 0, "10X10 SVEA Fuel Critical Power Experiments and New CPR Correlation: D5 for SVEA-96 OPTIMA3 |
10/31/2019 |
| 09/25/2019 |
Proposed Focus Area Review Approach of the Advanced Safety Evaluation Report with No Open Items for the Design Certification Application of the NuScale Small Modular Reactor |
10/31/2019 |
| 09/24/2019 |
Safety Evaluation Of The NuScale Topical Report TR-0716-50351, Revision 0, "NuScale Applicability Of AREVA Method For The Evaluation Of Fuel Assembly Structural Response To Externally Applied Forces" |
10/31/2019 |
| 09/20/2019 |
Safety Evaluation Of The Nuscale Topical Report TR-0516-49417-P, Revision 0, "Evaluation Methodology For Stability Analysis Of The Nuscale Power Module" |
10/31/2019 |
| 08/02/2019 |
Interim Letter – Chapters 3, 6, 15 And 20 of the NRC Staff's Safety Evaluation Report With Open Items Related to the Design Certification Application Review of the Nuscale Small Modular Reactor |
09/13/2019 |
| 06/27/2019 |
Response to Chapter 2, "Site Characteristics and Site Parameters," And Chapter 17, "Quality Assurance and Reliability Assurance" of the U.S. Nuclear Regulatory Commission Staff's Safety Evaluation Report with Open Items Related to the Certification of the NuScale Power, LLC, Small Modular Reactor |
08/05/2019 |
| 06/20/2019 |
Review of Nuclear Energy Institute (NEI) 96-07, Appendix D, "Supplemental Guidance for Application of 10 CFR 50.59 To Digital Modifications," Dated November 2018, and The NRC's Associated Draft Revision 2 to Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59 Changes, Tests and Experiments" |
07/16/2019 |
| 06/19/2019 |
Interim Letter – Chapter 3, Section 3.9.2, and Chapters 14, 19 and 21 of the NRC Staff's Safety Evaluation Report with Open Items Related to the Design Certification Application Review of the NUSCALE Small Modular Reactor |
06/24/2019 |
| 05/30/2019 |
Interim Letters: Chapters 4 and 5 of the NRC Staff's Safety Evaluation Report with Open Items Related to the Design Certification Application Review of the NuScale Small Modular Reactor |
06/19/2019 |
| 05/03/2019 |
Assessment of the Quality of Selected NRC Research Projects by the Advisory Committee on Reactor Safeguards – FY 2018 |
|
| 04/17/2019 |
Interim Letter: Chapters 9, 10, 11, 12 and 16 of the NRC Staff's Safety Evaluation Report with Open Items Related to the Design Certification Application Review of the NuScale Small Modular Reactor |
05/10/2019 |
| 04/17/2019 |
ACRS Review of Applications for Operation in the Expanded Power to Flow Domain |
|
| 03/21/2019 |
Interim Letter: Chapters 13 And 18 Of The NRC Staff's Safety Evaluation Report With Open Items Related To The Design Certification Application Review Of The NuScale Small Modular Reactor |
04/17/2019 |
| 03/19/2019 |
Draft SECY Paper and Guidance Documents to Implement a Technology-Inclusive, Risk-Informed, and Performance-Based Approach to Inform the Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors |
04/18/2019 |
| 03/07/2019 |
EDO Response to ACRS Letter of September 26, 2018 On Chapters 7 and 8 of the NRC Staff's Safety Evaluation Report with Open Items Related to the Certification of the Nuscale Small Modular Reactor |
04/10/2019 |
| 02/28/2019 |
Non-Power Production or Utilization Facilities Proposed License Renewal Rulemaking |
|
| 02/22/2019 |
Safety Evaluation for ANP-10332P, Revision 0, Aurora-B: An Evaluation Model for Boiling Water Reactors; Application to Loss-of-Coolant Accident Scenarios |
03/21/2019 |
| 02/21/2019 |
Interim Letter: Chapters 2 And 17 Of The NRC Staff's Safety Evaluation Report With Open Items Related To The Certification Of The NuScale Small Modular Reactor |
04/17/2019 |
| 01/09/2019 |
Early Site Permit – Clinch River Nuclear Site |
02/04/2019 |