Document: NUREG-0800
Document ID: 16e4170c-5e48-458a-8460-e22ce0296238
Document Type: srp
Title: EXCLUSION AREA AUTHORITY AND CONTROL
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550024.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.1.2
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CFR Title: 

Content:
operation could result in exposures above the 10 CFR Part 100 guidelines. The staff will correspond with the NRC legal staff, as required, to determine the legal sufficiency of applicant’s proposed controls. The review of public radiation exposure at the exclusion area boundary in the unlikely event of a serious release of radioactive material is addressed under SRP Section 13.3 and Chapter 15. 3. For DC applications and COL applications referencing a DC rule or DC application, review of the site parameters in the Design Control Document (DCD) Tier 1 and Chapter 2 of the DCD Tier 21 submitted by the applicant is performed under SRP Section 2.0, “Site Characteristics and Site Parameters.” Review of site characteristics and site-related design parameters in an ESP or in COL applications referencing an ESP is also performed under Section 2.0. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 2 For applicants before January 10, 1997 the requirements are identified in 10 CFR 100.10 and 10 CFR 100.11. 2.1.2-3 Revision 3 - March 2007 1. 10 CFR Part 50 and 10 CFR Part 52, as they relate to including in the safety analysis report (SAR) a detailed description and safety assessment of the site on which the facility is to be located (10 CFR 50.34(a)(1), 10 CFR 52.17(a)(1), and 10 CFR 52.79(a)(1)). 2. 10 CFR Part 100, as it relates to the following: A. Defining an exclusion area and setting forth requirements regarding activities in that area (10 CFR 100.3) B. Addressing and evaluating factors that are used in determining the acceptability of the site as identified in 10 CFR 100.20(b)2 C. Determining an exclusion area such that certain dose limits would not be exceeded in the event of a postulated fission product release as identified in 10 CFR 50.34(a)(1) as it relates to site