Document: NUREG-0800
Document ID: c422c59e-3da0-4294-a2cc-0e84c5c8422e
Document Type: srp
Title: to ensure that the Access Authorization Operational Program and associated milestones
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1212/ML12125A098.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.6.4
CFR Part: 
CFR Title: 

Content:
after the plant becomes operational. c. The licensee shall implement measures to transition to the requirements of 10 CFR 73.55. To accomplish this, the licensee should design transition procedures to implement AA measures before the construction and installation of security- and safety-related SSCs (i.e., those SSCs necessary for the safe shutdown of the reactor after the reactor becomes operational) and progressively increase those measures after the placement of security- and safety-related SSCs in their final location where they will be operated. Placement of security- and safety-related SSCs is further characterized as the scheduled onsite in-place setting, installing, or erecting of security- and safety-related SSCs in the controlled access construction area where the SSCs will be operated after the nuclear power plant is operational. The Commission does not intend for the licensee to implement an AA measures as early as the pouring of foundations for the areas encompassing security- and 13.6.4-7 Draft Revision 0 – December 2012 safety-related SSCs. However, the Commission does intend that the licensee will implement these measures before beginning the placement of security- or safety-related systems, equipment, or components inside the controlled access construction area. Areas external to the licensee’s controlled access construction area (such as laydown areas, prestaging areas, batch areas, and offsite manufacturing and fabrication facilities) are not within the scope, unless the construction security plan designates these areas as being included in the controlled access construction areas. d. To satisfy the requirements of 73.56, licensee should delineate in procedures and plans the AA measures for the protection of security- and safety-related SSCs, as well as measures for transitioning to the physical protection program required by 10 CFR 73.55(b)(1) and AA program required by 10 CFR 73.56 as applicable to an operating reactor. Licensees should