§ 53.805 Facility licensee requirements related to generally licensed reactor operators.
(a) Licensees for self-reliant-mitigation facilities that have not yet certified the permanent cessation of operations and permanent removal of fuel from the reactor vessel as described under § 53.1070 must demonstrate compliance with the following requirements:
(1) Ensure that, in addition to being qualified to perform those items identified by the facility-specific systems approach to training conducted under § 53.815, generally licensed reactor operators are qualified to safely and competently—
(i) Perform administrative tasks, including compliance with technical specifications, and perform operability determinations;
(ii) Implement maintenance and configuration controls;
(iii) Comply with radioactive release limitations;
(iv) Understand plant operating data, including reactor parameters, and evaluate emergency conditions;
(v) Initiate a reactor shutdown from necessary locations;
(vi) Dispatch and direct operations and maintenance personnel;
(vii) Implement any applicable responsibilities under the facility emergency plan; and
(viii) Make required notifications to local, State, participating Tribal, and Federal authorities.
(2) Develop, implement, and maintain facility technical specifications that provide the necessary administrative controls to ensure the implementation of the requirements in this section.
(3) Develop, implement, and maintain the generally licensed reactor operator training, examination, and proficiency programs required under § 53.815.
(4) Ensure that generally licensed reactor operators are subject to the facility's generally licensed reactor operator training, examination, and proficiency programs required under § 53.815. Ensure that generally licensed reactor operators are subject to and comply with the applicable programmatic requirements for personnel required under 10 CFR parts 26 and 73. An individual that is not in compliance with any of these programs is not qualified to be in a position that may involve the manipulation of the controls of the commercial nuclear plant.
(5) Report annually to the NRC the identity of all generally licensed reactor operators at the commercial nuclear plant, including all additions and deletions since the previous report.
(6) Ensure that the facility design continues to meet the criteria of § 53.800.
(b) [Reserved]