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Advisory Committee on Reactor Safeguards (ACRS) 2017 Letter Reports
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| Date | Title | Response |
|---|---|---|
| 11/16/2017 | State-of-the-Art Reactor Consequence Analysis (SOARCA) Project: Sequoyah Integrated Deterministic and Uncertainty Analyses | 12/22/2017 |
| 11/06/2017 | Report on the Safety Aspects of the Construction Permit for Northwest Medical Isotopes, LLC, Radioisotope Production Facility | 12/08/2017 |
| 10/20/2017 | Revision 3 to Regulatory Guide 1.174 | 11/20/2017 |
| 10/20/2017 | Safety Evaluation of the Nuscale Power, LLC Topical Report TR-0116-20825-P, "Applicability of AREVA Fuel Methodology for the Nuscale Design," Revision 1 | 11/21/2017 |
| 10/19/2017 | Safety Evaluation for Topical Report ANP-10300p, Revision 0, "Aurora-B: an Evaluation Model for Boiling Water Reactors; Application to Transient And Accident Scenarios" | 02/26/2018 |
| 10/11/2017 | Regulatory Guide | No Response Required |
| 09/25/2017 | Interim Letter: Chapters 7 and 18 of the NRC Staff's Safety Evaluation Report with Open Items Related to the Certification of the APR1400 Design | 11/02/2017 |
| 07/27/2017 | Safety Evaluation for WCAP-17642-P, Revision 1, "Westinghouse Performance Analysis and Design Model (PAD5)" | 09/19/2017 |
| 07/26/2017 | Report on the Safety Aspects of the License Renewal Application for South Texas Project, Units 1 and 2 | 08/21/2017 |
| 07/26/2017 | Safety Evaluation of the NuScale Power, LLC Topical Report TR-0815-16497-P, "Safety Classification of Passive Nuclear Power Plant Electrical Systems," Rev. 1 | 09/11/2017 |
| 07/26/2017 | Interim Letter: Chapters 3, 4, 9 and 15 of The NRC Staff's Safety Evaluation Report With Open Items Related To The Certification Of The APR1400 Design | 09/07/2017 |
| 06/21/2017 | Draft Proposed Rulemaking 10 CFR 73.53, "Requirements for Cyber Security at Nuclear Fuel Cycle Facilities," Related Parts 70, 73, and 40, and Draft Regulatory Guide DG-5062, "Cyber Security Programs for Nuclear Fuel Cycle Facilities" | 08/31/2017 |
| 06/21/2017 | Proposed Revision to NUREG-1530, "Reassessment of NRC's Dollar Per Person-Rem Conversion Factor Policy" | 07/21/2017 |
| 06/21/2017 | Interim Letter: Chapters 6, 12, 13, 14, 16, 17, and 19 of the NRC Staff’s Safety Evaluation Report with Open Items Related to the Certification of the APR1400 Design | 08/10/2017 |
| 06/19/2017 | Browns Ferry Power Station Units 1, 2, and 3 Extended Power Uprate License Amendment Request | 07/21/2017 |
| 06/19/2017 | Draft Safety Evaluation of PWROG-14001-P, Revision 1, "PRA Model for the Generation III Westinghouse Shutdown Seal" | 07/24/2017 |
| 05/19/2017 | Consequential Steam Generator Tube Rupture | 06/27/2017 |
| 05/18/2017 | Safety Evaluation of License Amendment Request by South Texas Project Nuclear Operating Company to Adopt a Risk-Informed Resolution of Generic Safety Issue-191 | 06/16/2017 |
| 04/24/2017 | Safety Evaluation of the NuScale Power, LLC Licensing Topical Report TR-1015-18653-P, Revision 1, Design of the Highly Integrated Protection System Platform | 05/31/2017 |
| 04/18/2017 | Draft NUREG/BR-0058, Revision 5, U.S. Nuclear Regulatory Commission Guidance on Performing Regulatory and Cost-Benefit Analyses | 05/03/2017 |
| 04/18/2017 | Report on Subsequent License Renewal | 05/19/2017 |
| 03/21/2017 | NRC Non-Light Water Reactor Vision & Strategy – Near-Term Implementation Action Plans and Advanced Reactor Design Criteria | 05/10/2017 |
| 03/20/2017 | Interim Comments on Draft NUREG/BR-0058, Revision 5, "U.S. Nuclear Regulatory Commission Guidance on Performing Cost-Benefit Analyses" | 05/03/2017 |
| 03/20/2017 | Proposed Revision to NUREG-1530, "Reassessment of NRC's Dollar Per Person-REM Conversion Factor Policy" | 05/01/2017 |
| 02/28/2017 | Safety Evaluation of APR1400 Topical Report, "KCE-1 Critical Heat Flux Correlation for PLUS7 Thermal Design" | 03/30/2017 |
| 02/22/2017 | Revision of Regulatory Guidance for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components | 03/24/2017 |
| 02/21/2017 | Interim Letter: Chapters 2, 5, 8, 10, and 11 of the NRC Staff's Safety Evaluation Report with Open Items Related to the Certification of the APR1400 Design | 03/31/2017 |
| 02/21/2017 | Safety Evaluation of Topical Report, "Fluidic Device Design for the APR1400 | 03/31/2017 |
| 02/14/2017 | Response to the December 15, 2016 Staff Letter Regarding "Draft Final Rule on Mitigation of Beyond-Design-Basis Events and Associated Regulatory Guidance" | 03/17/2017 |
| 01/11/2017 | ACRS Assessment of the Quality of Selected NRC Research Projects - 2016 | No Response Required |
| 12/13/2016 | Closure of Fukushima Recommendations Related to Evaluation of Natural Hazards Other Than Seismic and Flooding, Periodic Confirmation of Natural Hazards, and Real-Time Radiation Monitoring | 01/17/2017 |
Page Last Reviewed/Updated Thursday, August 27, 2026
Page Last Reviewed/Updated Thursday, August 27, 2026