Document: NUREG-0800
Document ID: 1a1e8dec-a4fe-47ea-b26f-caf30796f404
Document Type: srp
Title: - 2.2.2  IDENTIFICATION OF POTENTIAL HAZARDS IN SITE VICINITY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070220.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.2.1
CFR Part: 
CFR Title: 

Content:
ing primary review branch.10 II. ACCEPTANCE CRITERIA 10 CFR Part 100 § 100.10 requires that site acceptance be based on the consideration of factors 11 relating to the proposed reactor design and the characteristics peculiar to the site. One of the factors involves the use characteristics of the site environs. In accordance with 10 CFR Part 50, §50.34, the applicant is required to submit in the preliminary and final safety analysis reports (PSAR and FSAR) information needed for evaluating these factors. Guidelines for specific information requirements are described in Chapter 2, Sections 2.2.1 and 2.2.2 of Regulatory Guide (RG) 1.70.12 The information submitted by the applicant is adequate and meets the 10 CFR Part 50, §50.34 and 10 CFR 100, §100.10 requirements and RG 1.70 guidelines if it satisfies the following criteria: 1. Data in the SAR safety analysis report (SAR) adequately describe the locations and 13 distances of industrial, military, and transportation facilities in the vicinity of the plant, and is in agreement with data obtained from other sources, when available. 2. Descriptions of the nature and extent of activities conducted at the site and in its vicinitynearby facilities, including the products and materials likely to be processed, 14 stored, used, or transported, are adequate to permit identification of possible hazards in subsection III of this SRP section. 3. Sufficient statistical data with respect to hazardous materials are provided to establish a basis for evaluating the potential hazard to the plant. Technical Rationale The technical rationale for application of acceptance criteria for the evaluation of potential accidents is discussed in the following paragraphs:15 Compliance with 10 CFR 100.10 requires that evaluation of reactor sites include factors related to proposed reactor designs as well as to characteristics peculiar to individual sites. Through its design, construction, and operation, a reactor should reflect an extremely low