Document: NUREG-0800
Document ID: 854dac6a-4d16-4de2-b039-2eafedc512e4
Document Type: srp
Title: REACTOR OPERATOR REQUALIFICATION PROGRAM; REACTOR OPERATOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1500/ML15006A035.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.2.1
CFR Part: 
CFR Title: 

Content:
training program is to be established, implemented, and maintained 18 months prior to fuel load. The application includes the following: a. A commitment to meet the guidelines of Regulatory Guide (RG) 1.8, “Qualification and Training of Personnel for Nuclear Power Plants.” b. A commitment to meet the guidelines of RG 1.149, “Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations," for its simulation facilities. c. A commitment to conduct formal licensed operator classroom, on-the-job training, and simulator training before and after initial fuel load. d. For COL applicants, a commitment to meet the guidelines of Nuclear Energy Institute (NEI) 06-13A, “Template for an Industry Training Program Description.” e. The licensed operator training program description should contain the following elements: (i) The subject matter of each licensed operator training course. (ii) The duration (approximate number of weeks) of each licensed operator training course. (iii) The organization teaching the course or supervising instruction of each licensed operator training course, and the qualifications of the instructors and supervisors. 13.2.1-3 Revision 4 – August 2016 (iv) The titles of the positions for which each licensed operator training course is intended. (v) A chart showing the proposed schedule for licensing personnel prior to criticality. The schedule should be relative to the expected fuel load date and should also display the preoperational test period. (vi) To the extent applicable to the facility, the subjects in the reactor operator training program will include the following: (a) Fundamentals of reactor theory, including fission process, neutron multiplication, source effects, control rod effects, criticality indications, reactivity coefficients, and poison effects. (b) General design features of the core, including core structure, fuel elements, control rods, core instrumentation, and coolant flow. (c) Mechanical