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Alert

Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

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 Thursday, July 17, 2025

Page Last Reviewed/Updated Thursday, July 17, 2025