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:
tore SGI, (3) physically protect SGI in transit, (4) implement internal and external controls for transit and correspondence, (5) perform inspections, audits, and evaluation of the SGI program and its implementation, (6) establish conditions for access to SGI, including application of a “need to know,” (7) control reproduction and dissemination of SGI, (8) meet requirements for protecting SGI on electronic systems, (9) meet the requirements to remove the SGI designation, and (10) meet the requirements to destroy SGI. C. If the applicant’s or licensee’s plans to protect SGI are in accordance with protection procedures employed by the NRC (e.g., Management Directive 12.7, “NRC Safeguards Information Security Program”), they are acceptable as methods of protection against unauthorized disclosure. 8. 10 CFR 73.23, “Protection of Safeguards Information—Modified Handling: Specific Requirements” is either not applicable to, or outside the scope of review for, a nuclear power reactor license application under 10 CFR Part 50 or 10 CFR Part 52. 9. The following regulatory requirements are not within the scope of review of a nuclear power reactor license application under 10 CFR Part 50 or 10 CFR Part 52: A. 10 CFR 73.24, “Prohibitions” B. 10 CFR 73.25, “Performance Capabilities for Physical Protection of Strategic Special Nuclear Material in Transit” 13.6.1-44 Revision 2 – August 2018 C. 10 CFR 73.26, “Transportation Physical Protection Systems, Subsystems, Components, and Procedures” D. 10 CFR 73.27, “Notification Requirements” E. 10 CFR 73.28, “Security Background Checks for Secure Transfer of Nuclear Materials” F. 10 CFR 73.35, “Requirements for Physical Protection of Irradiated Reactor Fuel (100 Grams or Less) in Transit” G. 10 CFR 73.37, “Requirements for Physical Protection of Irradiated Reactor Fuel in Transit” H. 10 CFR 73.45, “Performance Capabilities for Fixed Site Physical Protection Systems.” I. 10 CFR 73.46,