Document: NUREG-0800
Document ID: 8da52d2b-9980-4076-8056-2cafebb25ed6
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550060.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
d is proposed), the staff or consultants, under the direction of the primary review organization, perform independent analyses. These analyses verify the design or establish the range of applicability and associated accuracy of the new method; the reviewer ensures it is applied accordingly. 6. The reviewer evaluates the functional requirements for instrumentation used in monitoring those thermal-hydraulic parameters important to safety, such as in-core power distribution and coolant temperature measurements. Chapter 7 of the SAR or DCD for new plants and the review requirements in SRP Section 7 should detail the instrumentation design and logic. 7. The reviewer evaluates the design of software used in core protection systems and establishes its acceptability by comparing it with previously approved designs and assessing any differences with regard to system performance and safety functions effects. Consistency of the core protection algorithms and logic functions with the thermal-hydraulic analyses should be verified, along with the program for implementing the software. The reviewer bases confirmation of adequate software implementation on documented testing that verifies the acceptability of the software calculational systems, the proper integration of software and hardware systems, and the acceptable static and dynamic operation of the integrated system when compared to the predictions of the thermal-hydraulic design analyses. The reviewer should consult with the organization responsible for the review of the design acceptability of the hardware portion of the core protection systems. 8. The reviewer establishes that the thermal-hydraulic design and its characterization by minimum critical heat flux ratio (MCHFR) or DNBR have been accomplished and are presented in a manner that accounts for all possible reactor operating states as determined from operating maps. In this regard, the reviewer confirms that the power distribution assumptions of SAR or DCD Section