Document: NUREG-0800
Document ID: a2d035da-992b-42e8-894f-787a019b437d
Document Type: srp
Title: NUCLEAR DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070410.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.3
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Content:
REVIEW RESPONSIBILITIES Primary - Core Performance Branch (CPB) Reactor Systems Branch (SRXB)1 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 10, 11, 12, 13, 20, 25, 26, 27, and 28. The review of the nuclear design under this SRP section, the review of the fuel system design under SRP Section 4.2, the review of the thermal and hydraulic design under SRP Section 4.4, and the review of the transient and accident analyses under the SRP section for Chapter 15 of the applicant's safety analysis report (SAR), are all necessary in order to confirm that the requirements defined above are met.2 The specific areas of interest in the nuclear design include: 1. Confirmation that design bases are established as required by the appropriate General Design Criteria. DRAFT Rev. 3 - April 1996 4.3-2 2. The areas concerning core power distribution. These are: a. The presentation of expected or possible 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. 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. 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