Document: NUREG-0800
Document ID: 145ec0f9-012b-4669-9627-ed1b1d0cce95
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070412.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
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Content:
REVIEW RESPONSIBILITIES Primary - Core PerformanceReactor Systems Branch (CPBSRXB)1 Secondary - Instrumentation and Control System Branch (ICSB) Human Factors Engineering Branch (HFEB) Procedures and Test Review Branch (PTRB)None2 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) has been accomplished using acceptable analytical methods; is equivalent to or is a justified extrapolation from proven designs; provides acceptable margins of safety from conditions which would lead to fuel damage during normal reactor operation and anticipated operational transients occurrences ; and is not susceptible to thermal-hydraulic 3 instability. This SRP section describes the normal review of thermal and hydraulic design, i.e., that for a plant similar in core and primary coolant system 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 that additional independent audit 4 analyses be performed. The required analyses may be in the following form: 1. Independent computer calculations to substantiate reactor vendor analyses. 2. Reduction and correlations of experimental data to verify processes or phenomena which are applied to reactor design. DRAFT Rev. 2 - April 1996 4.4-2 3. Independent comparisons and correlations are made of data from experimental programs. These reviews also include analyses of experimental techniques, test repeatability, and data reduction methods. The review includes evaluation of the proposed technical specifications regarding safety limits and limiting safety system settings, to ascertain that these 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. For new plant applicants, the review determines the acceptability