Document: NRC Regulatory Guide
Document ID: 769c53ca-7692-4fdf-9301-9fd64e37aa8f
Document Type: regulatory_guide
Title: Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2110/ML21105A439.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.91
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CFR Title: 

Content:
(NRC) staff finds acceptable for evaluating postulated accidental explosions at nearby facilities and transportation routes. It describes the calculation of minimum safe distance based on estimates of Trinitrotoluene (TNT)-equivalent mass of potentially explosive materials, the calculation of exposure rates based on potentially explosive cargo transportation frequencies, and the calculation of blast load effects. This guidance also contains information on methodologies for assessing thermal effects or radiative heat flux exposure caused by explosions and fires to structures. This guide describes methods acceptable to the NRC staff for determining if the risk of damage at the site caused by an accidental explosion at a nearby facility or on a transportation route is sufficiently high to warrant a detailed investigation to ensure safety-related systems, structures, and components (SSCs) are unaffected. Acceptable methods for evaluating structural adequacy when an investigation is warranted are also described. This guide considers the effects of air blasts from explosions on highways, railways, water routes, pipelines, and nearby fixed facilities. Applicability This guidance applies to applicants and reactor licensees subject to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 1); 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 2); and 10 CFR Part 100, “Reactor Site Criteria” (Ref. 3). Though the guidance primarily reflects past reviews of large light-water nuclear power plant applications, this RG may also provide useful guidance to fuel cycle, spent fuel storage, and waste disposal facilities. DG-1388, Page 2 Applicable Regulations • Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50 establishes the minimum requirements for the principal design criteria for water-cooled nuclear power plants. The