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:
REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of the assessment of reactor physics, neutronics, and nuclear design Secondary - None I. AREAS OF REVIEW The review of the nuclear design of the fuel assemblies, control systems, and reactor core is carried out to aid in confirming that fuel design limits will not be exceeded during normal operation or anticipated operational transients and that the effects of postulated reactivity accidents will not cause significant damage to the reactor coolant pressure boundary or impair the capability to cool the core and to assure conformance with the requirements of General Design Criteria (GDC) 10, 11, 12, 13, 20, 25, 26, 27, and 28. The specific areas of review are as follows: 1. Confirmation that design bases are established as required by the appropriate GDC. 2. The areas concerning core power distribution, including the following: 4.3-2 Revision 3 - March 2007 A. The presentation of expected power distributions including normal and extreme cases for steady-state and allowed load-follow transients and covering a full range of reactor conditions of time in cycle, allowed control rod positions, and possible fuel burnup distributions. Predictions and calculations, by the applicant, are needed and required by the staff. B. The presentation of the core power distributions as axial, radial, and local distributions and peaking factors to be used in the transient and accident analyses. As discussed in Regulatory Guide (RG 1.206), power distributions within fuel pins is also required. These within-pin power distributions are important for pressurized-water reactor (PWR) and boiling-water reactor (BWR) applications as they affect isotopic buildup/burnup. The effects of phenomena such as fuel densification 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