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:
clude 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 probability for 2.2.1-3 DRAFT Rev. 3 - April 1996 accidents that could result in release of significant quantities of radioactive fission products. In addition, the site's location and engineered features included as safeguards against the hazardous consequences of an accident should ensure a low risk of public exposure. When determining the acceptability of a site for a reactor, the use characteristics of the site environs (including those in the exclusion area and the low population zone) should be considered. Onsite or nearby facilities that could pose a risk to safe reactor operation include (1) onsite storage and use of compressed or liquid hydrogen and propane and (2) industrial, transportation, or military facilities that could involve the use of hazardous materials (e.g., oil or toxic chemicals) or pose other risks (e.g., a barge collision with an intake structure or an airplane crash at the site). On the basis of the information provided in SRP Section 2.2.1 - 2.2.2, potential accidents regarded as design basis events are determined and reviewed under SRP Section 2.2.3. Design basis events on site or in the vicinity of the nuclear plant are defined as accidents with a probability of occurrence of about 10 per year or greater and with potential consequences -7 serious enough to affect the safety of the plant to the extent that 10 CFR Part 100 guidelines could be exceeded. Where unfavorable physical characteristics exist, the proposed site may be found acceptable if the facility design includes appropriate and adequate engineering safeguards to compensate for the observed deficiencies. RG 1.91 provides guidance for evaluating 16 postulated explosions on transportation routes near nuclear plants. Meeting these requirements provides assurance that the plant is