Document: NUREG-0800
Document ID: ef3f5f75-7632-40a4-900f-67ff5fbbf623
Document Type: srp
Title: PHYSICAL SECURITY - DESIGN CERTIFICATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070720289.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.6.2
CFR Part: 
CFR Title: 

Content:
otection of licensed activities in nuclear power reactors against radiological sabotage" and Appendices B, C, G and H. 5. 10 CFR Part 74, "Material Control and Accounting of Special Nuclear Material." 6. 10 CFR Part 100, "Reactor Site Criteria." Although there are no Commission regulations governing the contents of a DC application with respect to security, there are several regulatory guidance documents that can be applied. They are as follows: 7. Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, November 1978. 8. Regulatory Guide 1.91, Evaluations of Explosions Postulated to Occur at Transportation Routes Near Nuclear Power Plants, February 1978. 9. Regulatory Guide 4.7, General Site Suitability Criteria for Nuclear Power Stations, April 1998. 10. Regulatory Guide 5.12, General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials, November 1973. 11. Regulatory Guide 5.65, Vital Area Access Controls, Protection of Physical Security Equipment and Key and Lock Controls, September 1986. 12. Regulatory Guide 5.7, Entry/Exit Control for Protected Areas, Vital Areas, and Material Access Areas, Revision 1, May 1980. 13. Regulatory Guide 5.44, Perimeter Intrusion Alarm Systems, Revision 3, October 1997. 14. Information Notice No. 86-83: Underground Pathways into Protected Areas, Vital Areas, and Controlled Access Areas, September 19, 1986. 15. Regulatory Information Summary 2005-04, Guidance on the Protection of Unattended Openings that Intersect a Security Boundary or Area, April 14, 2005. 16. Regulatory Guide 5.29, Material Control and Accounting for Nuclear Power Reactors. 17. American National Standards Institute (ANSI) N15.8, Nuclear Material Control Systems for Nuclear Power Plants, 1974. 13.6.2-4 March 2007 SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations identified above are as follows for the review