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Advisory Committee on Reactor Safeguards (ACRS) 2018 Letter Reports
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| Date | Title | Response |
|---|---|---|
| 12/19/2018 | Report On The Safety Aspects Of The License Renewal Application For The Seabrook Station, Unit 1 | |
| 12/14/2018 | Seabrook Station Unit 1 - License Renewal Application: Review of Licensee Program Addressing Alkali-Silica Reaction | 01/11/2019 |
| 11/21/2018 | Report on the Safety Aspects of the License Renewal Application for the Waterford Steam Electric Station, Unit 3 | 12/20/2018 |
| 11/15/2018 | Report on the Safety Aspects of the License Renewal Application for River Bend Station, Unit 1 | 12/20/2018 |
| 11/08/2018 | Draft Digital Instrumentation & Controls Interim Staff Guidance, Digital I&C-ISG-06, "Licensing Process," Revision 2 | 12/21/2018 |
| 10/24/2018 | Regulatory Guides | No Response Required |
| 10/19/2018 | Draft Proposed Rule, "Emergency Preparedness for Small Modular Reactors and Other New Technologies" | 11/09/2018 |
| 09/26/2018 | Safety Evaluation of the NuScale Power, LLC Topical Report TR-0915-17564-P, Revision 1, "Subchannel Analysis Methodology" | 10/15/2018 |
| 09/26/2018 | Chapters 7 and 8 of the NRC Staff's SER with Open Items Related to the Certification of the NuScale Small Modular Reactor | 10/30/2018 |
| 09/13/2018 | Regulatory Guides | No Response Required |
| 07/26/2018 | Report on the Safety Aspects of the APR1400 Pressurized Water Reactor | 07/30/2018 |
| 07/19/2018 | Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus License Amendment Request | 08/14/2018 |
| 07/18/2018 | Draft Digital Instrumentation & Controls Interim Staff Guidance, Digital I&C-ISG-06, Licensing Process, Revision 2 | 09/11/2018 |
| 06/15/2018 | Long-Term Core Cooling for the Apr1400 | 07/13/2018 |
| 06/15/2018 | Safety Evaluation Of The Nuscale Power, LLC Topical Report Tr-0616-48793, Revision 0, "Nuclear Analysis Codes And Methods Qualification" And Safety Evaluation Of The Nuscale Power, LLC Topical Report Tr-0116-21012, Revision 1, "Nuscale Power Critical Heat Flux Correlations" | 06/29/2018 |
| 06/15/2018 | Safety Evaluation for Topical Report APR1400-F-A-TR-12004-P, Revision 1, "Realistic Evaluation Methodology for Large-Break Loss of Coolant Accident of the APR1400." | 07/13/2018 |
| 05/10/2018 | Functional Containment Performance Criteria for Non-Light Water Reactor Designs | 06/27/2018 |
| 04/12/2018 | Safety Evaluation for WCAP-17938-P, Revision 2, "AP 1000 In-Containment Cables and Non-Metallic Insulation Debris Integrated Assessment" | 06/07/2018 |
| 03/26/2018 | Safety Evaluation for Topical Report APR1400-F-M-TR-13001, Revision 1, "Plus 7 Fuel Design for the APR1400" | 06/11/2018 |
| 03/26/2018 | Safety Evaluation for ANP-10333P, Revision 0, & Aurora-B: an Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA) | 04/27/2018 |
| 03/26/2018 | Regulatory Guide 1.232, Guidance for Developing Principal Design Criteria for Non-Light-Water Reactors | 05/09/2018 |
| 02/26/2018 | Biennial Review and Evaluation of the NRC Safety Research Program | 06/20/2018 – Letter 06/20/2018 – Enclosure |
| 02/21/2018 | Nuscale Power Exemption Request From 10 CFR Part 50, Appendix A, General Design Criterion 27, "Combined Reactivity Control Systems Capability" | 03/19/2018 |
| 01/23/2018 | ACRS Assessment of the Quality of Selected NRC Research Projects – FY 2017 |
Page Last Reviewed/Updated Tuesday, September 08, 2026
Page Last Reviewed/Updated Tuesday, September 08, 2026