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:
d that the NRC staff considers acceptable for use in satisfying the regulations at 10 CFR 50.150. RG 1.217 endorses the industry guidance document NEI 07-13, Revision 8P, “Methodology for Performing Aircraft Impact Assessments for New Plant Designs,” issued April 2011 (Ref. 29). The ARCAP Roadmap ISG contains guidance for NRC staff on aircraft impact assessments and may be informative for applicants. (2) Mitigation of Beyond-Design-Basis Events (MBDBE) (10 CFR 50.155, “Mitigation of beyond-design-basis events” (Ref. 30)): One of the primary lessons learned from the accident at the Fukushima Dai-ichi nuclear power plant in Japan was the significance of the challenge presented by a loss of multiple SR systems after a beyond-design-basis external event. As a result of lessons learned from the Fukushima Dai-ichi accident, the NRC amended its regulations to establish requirements for nuclear power reactor applicants and licensees for mitigating beyond- design-basis events (i.e., 10 CFR 50.155(b)(1)). DG-1404, Revision 1, Page 20 In the case of the Fukushima Dai-ichi accident, the loss of all alternating current power led to loss of core cooling, and ultimately to core damage and a loss of containment integrity. The design basis for U.S. nuclear plants includes bounding analyses with margin for external events expected at each site. Extreme external events (e.g., seismic events or external flooding, etc.) beyond those accounted for in the design basis, while unlikely, could present challenges to nuclear power plants. The following documents provide guidance on implementation of the regulations at 10 CFR 50.155 and applicants using NEI 21-07, Revision 1, to develop their applications should use the following documents: • RG 1.226, “Flexible Mitigation Strategies for Beyond-Design-Basis Events” (Ref. 31), identifies methods and procedures the NRC staff considers acceptable for nuclear power reactor applicants and licensees to use to demonstrate compliance with