Document: NRC Regulatory Guide
Document ID: acab976c-e936-49be-8c59-865767973599
Document Type: regulatory_guide
Title: Guidance for a Technology-Inclusive Content of Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2319/ML23194A194.pdf
Revision Date: 2023-09
Chapter: 
Section ID: RG-1.253
CFR Part: 
CFR Title: 

Content:
iews,” August 31, 2010. (ML1025210405) 15. NRC, SRM-SECY-11-0024, “Staff Requirements—SECY-11-0024—Use of Risk Insights to Enhance the Safety Focus of Small Modular Reactor Reviews,” May 11, 2011. (ML111320551) 16. NRC, DANU-ISG-2022-01, “Review of Risk-Informed, Technology-Inclusive Advanced Reactor Applications-Roadmap,” Washington, DC, April 2022. (ML22048B546) 17. NRC, NUREG 0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” Washington, DC 18. NRC, “Nuclear Regulatory Commission International Policy Statement,” Federal Register, Vol. 79, No. 132, July 10, 2014, pp. 39415–39418 (79 FR 39415). 19. NRC, Management Directive (MD) 6.6, “Regulatory Guides,” Washington, DC. 20. International Atomic Energy Agency (IAEA) Specific Safety Requirements (SSR), No. SSR-2/1, “Safety of Nuclear Power Plants: Design,” Vienna, Austria, 2016. 21 NRC, NUREG-0933, Resolution of Generic Safety Issues (Formerly entitled "A Prioritization of Generic Safety Issues") (NUREG-0933, Main Report with Supplements 1–35), available at https://www.nrc.gov/sr0933/index.html 22. NRC, RG 1.247 for trial use, “Acceptability of Probabilistic Risk Assessment Results for Non-Light-Water Reactor Risk-Informed Activities,” Washington, DC. 23. American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) RA-S-1.4-2021, “Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants,” New York, NY, 2021. 24. NEI 20-09, “Performance of PRA Peer Reviews Using the ASME/ANS Advanced Non-LWR PRA Standard,” Washington DC, May 2021. (ML21125A284) 25. 10 CFR Part 100, “Reactor Site Criteria.” 26. NRC, DANU-ISG-2022-02, “Site Information,” Washington, DC. (ML22048B541) DG-1404, Revision 1, Page 32 27. 10 CFR 50.150, “Aircraft impact assessment.” 28. NRC, RG 1.217, Revision 0, “Guidance for the Assessment of Beyond-Design-Basis Aircraft Impacts,”