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:
3, 3.5.1.5, or 3.5.1.6, as appropriate. For design certification reviews, the above review procedures are used to verify that the design as set forth in the standard SAR (including inspections, tests, analyses, and acceptance criteria (ITAAC); site interface requirements; and COL action items) meets the acceptance criteria given in subsection II.25 IV. EVALUATION FINDINGS The reviewer verifies that the information submitted by the applicant is in accordance with 10 CFR Part 50, §50.34 requirements and within RG 1.70 guidelines such that compliance with 10 CFR Part 100, §100.10 can be evaluated. The information is sufficiently complete and adequate if it can support conclusions of the following type, to be used in the staff's safety evaluation report (SER):26 The applicant has provided information in the SAR on potential site hazards in accordance with the requirements of 10 CFR 50, §50.34 and Regulatory Guide 1.70. The nature and extent of activities involving potentially hazardous materials which are conducted at nearby industrial, military, and transportation facilities have been evaluated to identify any such activities which have the potential for adversely affecting plant safety-related structures. Based on evaluation of information contained in the SAR, as well as information independently obtained by the staff, it is concluded that all potentially hazardous activities on site and in the vicinity of the plant have been 27 identified. The hazards associated with these activities have been reviewed and are discussed in Sections ______ and ______ of this SER. If the activities are identified as being potentially hazardous, the evaluations described in Standard Review Plan SRP Sections 2.2.3, 3.5.1.5, and 3.5.1.6 are performed with respect to the inherent capability of the plant or special plant design measures to prevent radiological releases in excess of the 10 CFR Part 100 guidelines. For design certification reviews the findings will also summarize, to the