Document: NRC Regulatory Guide
Document ID: 239cc7c1-f2cb-46cc-945d-8009db28aa6c
Document Type: regulatory_guide
Title: General Site Suitability Criteria for Nuclear Power Stations + HISTORY - HISTORY 12/2023 – DG-4034 , Proposed Revision 4 12/2011 – DG-4021 , Proposed Revision 3 02/1995 – DG-4004, Second Proposed Revision 2 11/1992 – DG-4003, Proposed Revision 2 (Rev. 4)
Source: NRC Regulatory Guide Division 4
Source URL: https://www.nrc.gov/docs/ML2312/ML23123A090.pdf
Revision Date: 2023-10
Chapter: 
Section ID: RG-4.7
CFR Part: 
CFR Title: 

Content:
ressure from explosion of flammable vapor clouds, fires, or release of toxic vapors exist, the suitability of the site should be determined through detailed evaluation of the potential hazard. RG 1.91 describes a method acceptable to the NRC staff for determining distances from a plant to a railway, highway, and navigable waterway, or a pipeline carrying hazardous chemicals beyond which any possible explosion on these routes or pipeline is not likely to adversely affect plant operation or to prevent a safe shutdown. Section 3.5.1.6 of NUREG-0800 and DOE-STD-3014-2006 describe methods acceptable to the NRC staff for assessing potential aircraft hazards. The acceptability of a site depends on establishing that (1) an accident at a nearby industrial, military, or transportation facility will not result in radiological consequences that exceed the dose specified in 10 CFR 50.34, or (2) such an accident poses no undue risk because the annual frequency of DG-4034, Page 27 its occurring is sufficiently low (less than about 1x10-7 per year). The identification of design-basis events resulting from the presence of hazardous materials or activities near the plant or plants is acceptable if it includes all postulated types of accidents for which it is estimated that the expected rate of occurrence of exposures resulting in radiological doses above those in 10 CFR 50.34(a)(1) (as it relates to the requirements of 10 CFR Part 100) exceeds the order of magnitude of 1x10-7 per year, which is the NRC staff objective, as described in Sections 2.2.1–2.2.3 of NUREG-0800 and in Section C of RG 1.91. The frequency of occurrence of initiating events leading to potential consequences in excess of the dose specified in 10 CFR 50.34(a)(1), 10 CFR 52.17(a)(1), and 10 CFR 52.79(a)(1) should be estimated using assumptions that are as realistic as practicable. Because the events under consideration are of such low probability, valid statistical data are often not available to permit accurate