Document: NUREG-0800
Document ID: 496a8650-7c3b-4111-a527-d49e2f61ae5c
Document Type: srp
Title: PHYSICAL SECURITY—COMBINED LICENSE AND OPERATING REACTORS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1729/ML17291B265.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.6.1
CFR Part: 
CFR Title: 

Content:
of Applications; Technical Information in Final Safety Analysis Reports,” 10 CFR 52.79(a)(35)(i) and (ii) and 10 CFR 52.79(a)(36)(i) through (v), which require that an applicant or licensee meet all applicable requirements in 10 CFR Part 73. 2. 10 CFR 52.80(a), which requires that a COL application contain the proposed ITAAC, including those applicable to emergency planning which the licensee shall perform, and also contain the acceptance criteria necessary and sufficient to provide reasonable assurance that if the ITAAC are performed and the acceptance criteria are met, the facility will have been constructed and will operate in conformance with the COL, the provisions of the Atomic Energy Act of 1954 (as amended), and NRC regulations. The certified design (i.e., rule), in part, provides a portion of the final design and specification of physical security systems and associated ITAAC that are incorporated by reference in a COL application to meet this requirement. 13.6.1-8 Revision 2 – August 2018 3. Where a COL or an OL cites a certified design, 10 CFR Part 52, Subpart B, “Standard Design Certification,” Section 10 CFR 52.47, “Contents of Applications; Technical Information,” identifies required design information specific to standards set out in 10 CFR Part 73. The designs of physical security systems, along with their design bases, within a certified design are incorporated by reference and therefore not included in the scope of the COL or OL licensing review. 4. 10 CFR 50.33 and 10 CFR 50.34 define the requirements for applying for a construction permit for a utilization facility, which include a preliminary safety analysis report that address site-evaluation based on requirements of 10 CFR Part 100,”Reactor Site Criteria,” with summary descriptions and discussions of the facility (10 CFR 50.34(a)(2)), a preliminary plan for organization, training, and conduct of operations and an FSAR and security plans (10 CFR 50.34(c) , 10 CFR 50.34(d), and