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

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  

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Page Last Reviewed/Updated Friday, March 13, 2020