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:
ystems (10 CFR 73.22(g)) J. removal of the “safeguards information” designation (10 CFR 73.22(h)) K. destruction of matter containing safeguards information (10 CFR 73.22(i)) 4. 10 CFR 73.55(a) is satisfied when descriptions of engineered controls, operational requirements, and management systems, as well as organization descriptions, provide sufficient details to meet these criteria, including specifying a schedule for program implementation: A. Each nuclear power reactor licensee, licensed under 10 CFR part 50, will implement the requirements of 10 CFR 73.55 through its Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Cyber Security Plan referred to collectively hereafter as ‘‘security plans” by March 31, 2010. (10 CFR 73.55(a)(1)). B. Current applicants for an operating license under 10 CFR part 50, or combined license under 10 CFR part 52 who have submitted their applications to the Commission prior to the effective date of this rule must amend their applications to include security plans (10 CFR 73.55(a)(1)). C. The physical security plan identifies and describes in sufficient detail how site- specific conditions are accounted for in meeting the requirements of 10 CFR 73.55 and identifies the licensee as the entity responsible for maintaining a physical protection program and implementing security plans and written procedures (10 CFR 73.55(a)(2) and 10 CFR 73.55(a)(3)). The site-specific conditions include the site characteristics, parameters, and any restrictions to or impediments on developing security plans (as addressed in a referenced early site permit or construction permit, if applicable). D. A specific license condition is provided for the implementation of a reactor security program (in accordance with the requirements of 10 CFR 73.55 and all applicable sections of 10 CFR Part 73) for a nuclear power reactor before fuel is allowed onsite (in the protected area) for an operating license issued under the