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
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CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of thermal and hydraulic design for Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs) Secondary - Organization responsible for the review of heat transfer correlations I. AREAS OF REVIEW The objectives of the review are to confirm that the thermal and hydraulic design of the core and the reactor coolant system (RCS) (1) uses acceptable analytical methods, (2) is equivalent to or is a justified extrapolation from proven designs, (3) provides acceptable margins of safety from conditions that would lead to fuel damage during normal reactor operation and anticipated operational occurrences (AOOs), and (4) is not susceptible to thermal-hydraulic instability. The specific areas of review are as follows: 1. This SRP section describes the normal review of thermal and hydraulic design (i.e., a design for a plant similar in core and RCS design to previously reviewed plants). The review of new prototype plants, new critical heat flux (CHF) or critical power ratio (CPR) correlations, and new analysis methods require additional independent audit analyses. The required analyses may be in the following form: A. Independent computer calculations to substantiate reactor vendor analyses. B. Reduction and correlations of experimental data to verify processes or phenomena which are applied to reactor design. 4.4-2 Revision 2 - March 2007 C. Independent comparisons and correlations of data from experimental programs. These reviews also include analyses of experimental techniques, test repeatability, and data reduction methods. 2. The review evaluates the proposed technical specifications regarding safety limits and limiting safety system settings to ascertain that they are consistent with the power-flow operating map for boiling-water reactor (BWR) plants or the temperature-power operating map for pressurized-water reactor (PWR) plants. 3. For new plant applicants, the review determines the