Document: NUREG-0800
Document ID: fd099646-2b48-49c1-9d0b-a36844679790
Document Type: srp
Title: ACCESS AUTHORIZATION - OPERATIONAL PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1522/ML15226A009.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.6.4
CFR Part: 
CFR Title: 

Content:
I, and III. The NRC considers that the site-specific information in the most recent revision of the NRC-endorsed NEI 03-12 generic security plan template (site-specific bracketed text) describes a PSP that meets the level of detail required for submitted security plans. For example: a. Each licensee should meet the general performance objective of providing reasonable assurance that malicious acts during nuclear power plant construction cannot later reasonably result, directly or indirectly, in radiological sabotage as defined by 10 CFR 73.2, “Definitions.” Licensees should accomplish this objective by designing an AA program to deter and detect malicious acts. The purpose of this program is to implement site-specific measures that will deter malicious acts against security- and safety-related systems, structures, and components (SSCs) or other malicious activities during construction that could be used to commit or facilitate acts of radiological sabotage, as defined by 10 CFR 73.2, and to detect malicious acts after lockdown of security- and safety-related SSCs. b. To achieve the general performance objectives, as construction activities near completion, the design of the construction security program should provide for the deterrence and detection of malicious acts to security- and safety-related SSCs before and after final placement of each SSC. This includes the implementation of the lockdown procedures. Although licensees are not required to meet the standards of 10 CFR 73.1(a)(1) for protection against the design-basis threat during the construction phase, licensees should ensure that the capability to deter and detect malicious acts directed against security- and safety-related SSCs is maintained until all construction activities have ended and the transition to the requirements of 10 CFR 73.55 is complete prior to nuclear fuel on site (in the protected area) or after the plant becomes operational. c. The licensee shall implement measures to transition