Document: NUREG-0800
Document ID: e813bec5-8bbc-4d19-89e4-7d41652e196c
Document Type: srp
Title: REACTOR OPERATOR REQUALIFICATION PROGRAM; REACTOR OPERATOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1331/ML13311B565.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.2.1
CFR Part: 
CFR Title: 

Content:
are performed. Control manipulations and plant evolutions to be performed: (a) Plant or reactor startups to include a range that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established. (b) Plant shutdown. (c) Manual control of steam generators or feedwater or both during startup and shutdown. (d) Boration or dilution during power operation. (e) Significant (≥10 percent) power changes in manual rod control or recirculation flow. (f) Reactor power change of 10 percent or greater where load change is performed with load limit control or where flux, temperature, or speed control is on manual (for high-temperature gas-cooled reactors (HTGR)). 13.2.1-7 Draft Revision 4 – August 2014 (g) Loss of coolant, including: (1) Significant PWR steam generator leaks. (2) Inside and outside primary containment. (3) Large and small, including leak-rate determination. (4) Saturated reactor coolant response (PWR). (h) Loss of instrument air (if simulated, plant specific). (i) Loss of electrical power (or degraded power sources). (j) Loss of core coolant flow/natural circulation. (k) Loss of feedwater (normal and emergency). (l) Loss of service water, if required for safety. (m) Loss of shutdown cooling. (n) Loss of component cooling system or cooling to an individual component. (o) Loss of normal feedwater or normal feedwater system failure. (p) Loss of condenser vacuum. (q) Loss of protective system channel. (r) Mispositioned control rod or rods (or rod drops). (s) Inability to drive control rods. (t) Conditions requiring use of emergency boration or standby liquid control system. (u) Fuel cladding failure or high activity in reactor coolant or offgas. (v) Turbine or generator trip. (w) Malfunction of an automatic control system that affects reactivity. (x) Malfunction of reactor coolant pressure/volume control system. (y) Reactor trip. (z) Main steam line break (inside or outside containment). (aa) Nuclear instrumentation failure. 13.2.1-8