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:
wer uses SRP Section 14.3.12 to determine the adequacy of the PS-ITAAC. The referenced SRP sections contain the specific acceptance criteria and review procedures. II. ACCEPTANCE CRITERIA Requirements The NRC bases its acceptance criteria on the relevant requirements of the following regulations: 1. 10 CFR Part 26, “Fitness for Duty Programs” 2. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities” 3. 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” 4. 10 CFR 73.1, “Purpose and Scope” 5. 10 CFR 73.2, “Definitions” 6. 10 CFR 73.21, 10 CFR 73.22, and 10 CFR 73.23, “Protection of Safeguards Information” 7. 10 CFR 73.55, “Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage” 8. 10 CFR 73.56, “Personnel Access Authorization Requirements for Nuclear Power Plants” 9. 10 CFR 73.57, “Requirements for Criminal History Checks of Individuals granted Unescorted access to a Nuclear Power Facility or Access to Safeguards Information by Power Reactor Licensees” 13.6.1-4 Revision 1 - October 2010 10. 10 CFR 73.58, “Safety/Security Interface Requirements for Nuclear Power Reactors” 11. 10 CFR 73.70, “Records” 12. 10 CFR Part 73, Appendix B, Section VI, “Nuclear Power Reactor Training and Qualification Plan for Security Personnel Performing Security Program Duties” 13. 10 CFR Part 73, Appendix C, Section II, “Nuclear Power Plant Safeguards Contingency Plans” SRP Acceptance Criteria Specific SRP acceptance criteria that meet the relevant requirements of the above regulations are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, the NRC requires an applicant or an operating reactor licensee to identify differences between the design features, analytical techniques, and procedural measures proposed for its