Document: NUREG-0800
Document ID: cf5af21e-7865-41fe-bc4c-b83bfde7ea75
Document Type: srp
Title: SITE LOCATION AND DESCRIPTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070205.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.1.1
CFR Part: 
CFR Title: 

Content:
rmation has been provided to determine general population doses from normal liquid and gaseous releases.5 An applicant for a standard design certification may postulate values for site parameters as a basis for plant design.6 Review Interfaces 1. The EGCB performs the following reviews as part of its primary review responsibility under the SRP sections indicated:7 a. ECGB reviews the applicant's authority to control activities in the exclusion area as part of its primary responsibility for implementation of SRP Section 2.1.2. b. The ECGB reviews the population distribution in the exclusion area and the low population zone as part of its primary responsibility for implementation of SRP Section 2.1.3. c. The ECGB reviews industrial, military, and transportation facilities within or near the exclusion area as part of its primary responsibility for implementation of SRP Section 2.2.3. d. The ECGB coordinates and performs the review of site parameters postulated for design in a standard design certification application as part of its primary review responsibility for SRP Section 2.3.6.8 2. The EGCB will coordinate other branch evaluations that interface with the overall review of site location and description as follows:9 a. The Plant Systems Branch (SPLB) considers the boundaries of the restricted area as part of its primary responsibility for implementation of SRP Sections 11.1, 11.2, and 11.3. b. The Emergency Preparedness and Radiation Protection Branch (PERB) considers activities in the exclusion area as part of its primary responsibility for implementation of SRP Section 13.3 and Section 15. II. ACCEPTANCE CRITERIA Information included in this SAR section should allow three types of safety analyses to be conducted. The first addresses exposure of the public to radiation at the boundary of the restricted area of the plant. The second addresses the consequences in the unlikely event that a serious release of radioactive material should occur. The third addresses the