Document: NUREG-0800
Document ID: ddaa3c7d-ce79-4a3f-aaae-4e4436ab7bc1
Document Type: srp
Title: NUCLEAR DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740003.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.3
CFR Part: 
CFR Title: 

Content:
ation on reactivity coefficients in the form of curves covering the full applicable range of the variables. The difference between intra- and inter- assembly moderator coefficients, as discussed in RG 1.206, needs to be discussed. 4.3-3 Revision 3 - March 2007 B. The applicant’s presentation of uncertainty analyses for nominal values, including the magnitude of the uncertainty and the justification of the magnitude by examination of the accuracy of the methods used in calculations (safety analysis report (SAR) Section 4.3.3), and comparison where possible with reactor experiments. For comparisons to experiments, it is important for the applicant to show that the experiments are applicable and relevant. C. The applicant’s combination of nominal values and uncertainties to provide suitably conservative values for use in reactor steady-state analysis (primarily control requirements SAR Section 4.3.2.4), stability analyses (SAR Section 4.3.2.7), and the transient and accident analyses presented in SAR Chapter 15. 4. The areas concerning reactivity control requirements and control provisions. These are: A. The control requirements and provisions for control necessary to compensate for long-term reactivity changes of the core. These reactivity changes occur because of depletion of the fissile material in the fuel, depletion of burnable poison in some of the fuel rods, and buildup of fission products and transuranic isotopes. B. The control requirements and provisions for control needed to compensate for the reactivity change caused by changing the temperature of the reactor from the hot zero power condition to the cold shutdown condition. C. The control requirements and provisions for control needed to compensate for the reactivity effects caused by changing the reactor power level from full power to zero power. D. The applicant needs to provide tables and discussions on control requirements and provisions at beginning of life (BOL), end of life (EOL), and