Document: NUREG-0800
Document ID: f7325000-a180-4044-b13a-03240a730ff7
Document Type: srp
Title: REACTOR OPERATOR REQUALIFICATION PROGRAM; REACTOR OPERATOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0701/ML070100636.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.2.1
CFR Part: 
CFR Title: 

Content:
nce that only trained and qualified licensed individuals possessing the required knowledge, skills, and abilities will be assigned to, and will conduct, licensed activities. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 1. Preparation for the review of Section 13.2.1 of the SAR should include familiarization with 10 CFR 50.54 items i through m; 10 CFR 55.4, 55.31, 55.41, 55.43, 55.45, 55.46, and 55.59; 10 CFR 50.34(f)(2)(i); Regulatory Guides 1.8 and 1.149; and NUREGs-0711 and -1021. 2. The reviewer then determines, based upon the foregoing, the overall acceptability of the applicant's licensed operator training plans. 3. Operational Programs. The reviewer verifies that the Reactor Operator Requalification Program and Reactor Operator Training Program are fully described and that implementation milestones have been identified. The reviewer verifies that the program and implementation milestones are included in FSAR Table 13.x. The implementation of the Reactor Operator Training Program is included in the license condition on operational programs and implementation. Implementation of this program will be inspected in accordance with NRC Inspection Manual Chapter IMC-2504, "Construction Inspection Program - Non-ITAAC Inspections." 4. For review of a DC application, the reviewer should follow the above procedures to verify that the design, including requirements and restrictions (e.g., interface requirements and site parameters), set forth in the final safety analysis report (FSAR) meets the acceptance criteria. DCs have referred to the FSAR as the design control