Document: NUREG-0800
Document ID: 54e3d49d-900d-4fe8-9297-2fc04501e4e0
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340664.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
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Content:
ety analysis report (SAR) to the documents referenced by the applicant or in this SRP section to determine conformance to the bounds established by such documents. The reviewer must confirm that void, pressure drop, and heat transfer correlations used to estimate fluid conditions (flow, pressure, quality) are within the ranges of applicability specified by their authors or in previous staff reviews, that the analysis methods are used in the manner specified by the developers or in previous staff reviews, that the reactor design falls within the ranges of applicability specified for accepted analysis methods, and that the design is within the criteria specified in II, above, and is not an unexplained or unwarranted extrapolation of other thermal-hydraulic designs. The review does not routinely involve calculations by the staff. However, the reviewer should ensure that those applications based on statistical design methodologies Include the coefficients required by the statistical model and define the parameter ranges for which the coefficients are applicable. Uncer- tainties in computer codes, correlations, design methods, and set point methodologies should be quantified and the method(s) of accounting for these uncertainties in the design procedures should be discussed. For example the sensitivity factors and their ranges of applicability must be reviewed for those plants utilizing the Westinghouse "Improved Thermal Design Procedure," (Ref. 19). On occasion, e.g., if a new design or new design method is proposed, independent analyses are performed by the staff or by consultants under the direction of CPB. These analyses verify the design or establish the range of applicability and associated accuracy of the new method and the reviewer ensures it is applied accordingly. The reviewer is to establish that the thermal-hydraulic design and its characterization by MCHFR or DNBR have been accomplished and are presented in a manner which accounts for all possible reactor