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:
should be included in these distributions and factors. C. The translation of the design power distributions into operating power distributions, including instrument-calculation correlations; operating procedures and measurements; and necessary limits on these operations. D. The requirements for instruments, the calibration and calculations involved in their use, and the uncertainties involved in translation of instrument readings into power distributions. E. Limits and setpoints for actions, alarms, or scram for the instrument systems and demonstration that these systems can maintain the reactor within design power distribution limits. F. Measurements in previous reactors and critical experiments and their use in the uncertainty analyses and the measurements to be made on the reactor under review, including startup confirmatory tests and periodically required measurements. G. The translation of design limits, uncertainties, operating limits, instrument requirements, and setpoints into technical specifications. 3. The areas concerning reactivity coefficients. These are: A. The applicant’s presentation of calculated nominal values for the reactivity coefficients, such as the moderator coefficient, which involves primarily effects from density changes and takes the form of temperature, void, or density coefficients; the Doppler coefficient; and power coefficients. The range of reactor states to be covered includes the entire operating range from cold shutdown through full power and the extremes reached in transient and accident analyses. It includes the extremes of time in cycle and an appropriate range of control rod insertions for the reactor states. The applicant needs to demonstrate that the coefficients used are conservative. The applicant should provide information 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