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
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CFR Title: 

Content:
rements of 10 CFR Part 73 will be met. The scope of technical review includes key standards and criteria for the design of, and operational requirements for, physical protection as set forth in 10 CFR 73.55, “Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors against Radiological Sabotage,” along with other applicable sections of 10 CFR Part 73. The reviewer should use the information provided as licensing bases, which include engineering controls (i.e., PSS) and administrative controls (operational requirements) for the design of a physical protection system (i.e., detection, assessment, communications, and response for interdiction and neutralization), to determine how an applicant (or a licensee) meets the performance requirement of 10 CFR 73.55(b) to protect against the design basis threat (DBT) for radiological sabotage. The information contained in the licensing documents also includes details on management systems and organizations. 2. The application must provide information that is sufficiently detailed to describe how regulatory requirements for PSS are met and how operational requirements for physical protection systems provide protection against the DBT of radiological sabotage as established by the performance and prescriptive design requirements of 10 CFR 73.55(b). The scope of the technical review includes the descriptions of the design bases for PSS that are relied on by the physical protection system and the descriptions of administrative controls and management systems that address operational requirements, training and qualification of personnel, and safeguards contingency planning. This information establishes the licensing bases for the physical protection program and provides the bases for the Commission’s determination of whether a nuclear power plant would be adequately protected and operated in accordance with NRC regulatory requirements. 3. As stated in SECY-11-0024, “Use of Risk Insights To