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
CFR Part: 
CFR Title: 

Content:
rfaces. f. Analysis showing that the structure can resist missiles can be accomplished using the methodology from “A Review of Procedures for the Analysis and Design of Concrete Structures to Resist Missile Impact Effects,” by R.P Kennedy, 1976 (Ref. 18), for concrete structures, and “Impact Effect of Fragments Striking Structural Elements,” by R.A. Williamson and R.. Alvy, 1973 (Ref. 19), for steel structures. Additional information on missile effects over safety-related structural barriers can be found in NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” Chapter 3.5.3, “Barrier Design Procedures” (Ref. 20). 4. Regarding guidance on the thermal effects or radiative heat flux exposure on power plant structures, the information in NUREG/CR-3330 (Ref. 21), 49 CFR Part 192.903 (Ref. 22), and American Society of Mechanical Engineers (ASME) B31.8S (Ref. 23) is acceptable for determining the potential impact of radiative heat flux on power plant structures exposed to explosions and fires. Baker 2005 (Ref. 24), provides information for hazardous materials other than natural gas. If the calculated radiative heat flux is found to be acceptable, no further consideration need be given to the effects of explosions or fires from these sources in facility design. DG-1388, Page 11 D. IMPLEMENTATION The NRC staff may use this RG as a reference in its regulatory processes, such as licensing, inspection, or enforcement. However, the NRC staff does not intend to use the guidance in this RG to support NRC staff actions in a manner that would constitute backfitting as that term is defined in 10 CFR 50.109, “Backfitting,” and as described in NRC Management Directive 8.4, “Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests,” (Ref. 25) nor does the NRC staff intend to use the guidance to affect the issue finality of an approval under 10 CFR Part 52, “Licenses,