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:
nted unescorted access to a nuclear power facility or Safeguards Information (SGI). This SRP section reviews AA as part of the physical security plan. 13.6.4-13 Revision 0 – October 2016 III. REVIEW PROCEDURES The scope of the review of a COL application is dependent on whether the COL applicant references an ESP, a LWA, or other NRC approvals (e.g., manufacturing license, site suitability report, or topical report). The reviewer will select material from the procedures described below, as may be appropriate for a particular case. The reviewer verifies that the licensee’s AA program is adequately described. The reviewer will select material from the procedures described below, as may be appropriate for a particular case. The reviewer verifies that the licensee’s security program is fully described in the PSP, for COL applicants, that implementation milestones have been identified. For COL applicants, implementation of AA programs will be inspected in accordance with NRC Inspection Manual Chapter IMC-2504, “Construction Inspection Program Inspection of Construction and Operational Programs.” For operating reactor licensees, implementation of AA programs will be inspected in accordance with NRC Inspection Manual Chapter IMC-2201, “Security Inspection Program for Commercial Nuclear Power Reactors.” When conducting the review of the AA program the reviewer should determine whether the AA program conforms to required regulations as described above in Section I and Section II above. Site-specific information should be reviewed and evaluated in accordance with the requirements of 10 CFR 73.56. Those sites that fall under an existing NRC-approved AA program would be considered acceptable if the full operational program is applied to the applicable personnel as described in 10 CFR 73.56. These sites would still need to provide a description of their intent to use the operating reactor plant AA program at the construction site(s) and whether a change is made to