Document: NUREG-0800
Document ID: 0abe910e-a8ee-47e5-aad0-5cb695cb55a7
Document Type: srp
Title: PHYSICAL SECURITY—COMBINED LICENSE AND OPERATING REACTORS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1022/ML102230082.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.6.1
CFR Part: 
CFR Title: 

Content:
e requirements for performing criminal history checks of individuals granted unescorted access to a nuclear power facility or SGI. This SRP section reviews access authorization as part of the physical security plan. 14. 10 CFR Part 73, Appendix B, Section VI, establishes the requirements for selecting, training, qualifying, and equipping security personnel responsible for protecting nuclear facilities against the DBT of radiological sabotage (see Appendix II). Security personnel qualified in accordance with Appendix B are an integral part of the physical security plan 13.6.1-10 Revision 1 - October 2010 required by 10 CFR 73.55 and are reviewed under this SRP section. Compliance with the requirements of Appendix B, Section VI to 10 CFR Part 73 provides assurance that security personnel are adequately prepared to identify, respond to, and repel threats to the nuclear facility and material. 15. 10 CFR Part 73, Appendix C, Section II, establishes the requirements for a safeguards contingency plan (see Appendix III). The safeguards contingency plan is a documented plan to provide guidance to licensee personnel responding to threats, thefts, or radiological sabotage relating to nuclear facilities. The safeguards contingency plan is an integral part of the response capabilities and requirements of the physical security plan developed in accordance with 10 CFR 73.55 and reviewed under this SRP section. Compliance with Appendix C, Section II to 10 CFR Part 73 provides assurance that a licensee is adequately prepared to respond to perceived dangers of nuclear material theft or radiological sabotage. III. REVIEW PROCEDURES The scope of the review of a COL application is dependent on whether the COL applicant references a DC, an ESP, an LWA, or other NRC approvals (e.g., manufacturing license, site suitability report, or topical report). The reviewer should then review Tier I information for the design, including the postulated site parameters, interface criteria, and ITAAC.