Document: NUREG-0800
Document ID: d1955890-9bdd-4d92-be3b-aee2bad19249
Document Type: srp
Title: PHYSICAL SECURITY - EARLY SITE PERMIT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070720310.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.6.3
CFR Part: 
CFR Title: 

Content:
ion of proposed owner-controlled area (OCA) and PA vehicle checkpoint. 2. A description of the physical land characteristics to indicate that adequate distances exist between vital equipment and vital areas and the probable location of a security boundary. 3. A description of the site characteristics that may require measures in order to control approaches to the facility (e.g., barge slips within the OCA, transportation routes, cliffs, depressions, hills, mounds, open waterways, and roadway or railroad that penetrate the OCA boundary) 4. A description of nearby facilities and pipelines to identify potential hazards in the site vicinity. 5. A description of planned culverts (greater than 254 square inches in cross-section area) that extend from outside to inside the proposed PA, the area for power block structures, and/or the area for safety related water sources (e.g., cooling towers). Review Interface Other SRP sections interface with this section as follows: 1. Review of the adequacy of the physical security hardware Inspection, Test, Analysis, and Acceptance Criteria (PS-ITAAC) as performed under SRP Section 14.3.12 - Physical Security Hardware. 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: 1. 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities" 13.6.3-3 March 2007 2. 10 CFR Part 52, "Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants" 3. 10 CFR 73.1 (a)(1), "Radiological Sabotage" 4. 10 CFR 73.55, "Requirements for physical protection of licensed activities in nuclear power reactors against radiological sabotage" and Appendices B, C, G and H 5. 10 CFR Part 74, "Material Control and Accounting of Special Nuclear Material" 6. 10 CFR Part 100, "Reactor Site Criteria" 7. 10 CFR 100.21,