Document: NUREG-0800
Document ID: 6958f90f-4bf5-4fe1-9ae7-49439fd2deca
Document Type: srp
Title: PHYSICAL SECURITY HARDWARE - INSPECTIONS, TESTS, ANALYSES, AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1603/ML16032A050.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3.12
CFR Part: 
CFR Title: 

Content:
ACCEPTANCE CRITERIA REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of physical security hardware Secondary - Licensing organization and cognizant review organization according to the Standard Review Plan (SRP) sections identified in this SRP 1. The SRP Section14.3, “Inspections, Tests, Analyses and Acceptance Criteria,” provides guidance for the review of the inspections, tests, analyses, and acceptance criteria (ITAAC) for an early site permit (ESP), a design certification (DC), or a combined license (COL) application submitted under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” and is intended to be used in tandem with this SRP section. This review approach ensures that the complete scope of the design is addressed and that the COL ITAAC are necessary and sufficient to provide the assurances stated in 10 CFR 52.97(b). I. AREAS OF REVIEW Refer to SRP Section14.3, Section I, “Areas of Review,” for general ITAAC review guidance for an ESP, a DC, or a COL application. 14.3.12-2 Draft Revision 2 - June 2016 This section of the SRP specifically addresses ITAAC related to physical security hardware (PS-ITAAC). Physical security hardware includes, but is not limited to, communication systems, assessment and alarm systems, locks, personnel access control, physical equipment barriers, and surveillance devices. ITAAC information is contained in the Final Safety Analysis Report (FSAR) of a COL application or Tier 1 information from the design control document (DCD) of a DC application. The staff of the U.S. Nuclear Regulatory Commission (NRC) will review PS-ITAAC for the facility’s physical security system to determine whether the designs and specifications for PS-ITAAC are in accordance with the regulatory requirements of 10 CFR Part 73, “Physical Protection of Plants and Materials,” which are applicable for a nuclear power plant. The NRC staff