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:
technical specifications and their bases. (c) Facility procedures required to obtain authority for design and operating changes in the facility. (d) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions. (e) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. (f) Procedures and limitations involved in initial core loading, alterations in core configuration, control rod programming, and determination of various internal and external effects on core reactivity. (g) Fuel-handling facilities and procedures. (viii) To the extent applicable to the facility, reactor operators and senior reactor operators are required to demonstrate an understanding of and the ability to perform the following: (a) Performance of pre-startup procedures, including operating those controls associated with plant equipment that could affect reactivity. (b) Manipulation of console controls as required to operate the facility between shutdown and designated power levels. (c) Identification of annunciators and condition-indicating signals and, where appropriate, performance of necessary remedial actions. (d) Identification of the instrumentation systems and a description the 13.2.1-5 Revision 4 – August 2016 significance of the instrument reading. (e) Safe control of the facility. (f) Performance of control manipulations to obtain desired operating results during normal, abnormal, and emergency situations. (g) Safe operation of the facility heat-removal systems and identification of the relationship of the proper operation of these systems to the operation of the facility. (h) Safe operation of the facility auxiliary and emergency systems, including operation of those controls associated with plant equipment that could affect reactivity or the release of radioactive materials to the environment. (i) Demonstration or description of the