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:
nts identified in Subsection II. For DC and COL applications submitted uder Part 52, the level of information reviewed should be consistent with that of a FSAR submitted in an OL application. However, verification that the as-built facility conforms to the approved design is performed through the ITACC process. 1. The reviewer must understand currently acceptable thermal and hydraulic design practice for the reactor type under review. This understanding can be most readily gained from (1) topical reports describing CHF correlations, system hydraulic models and tests, and core subchannel analysis methods, (2) standard texts and other technical literature which establish the methodology and the nomenclature of this technology, and (3) documents that summarize current staff positions concerning acceptable design methods. 2. Much of the review described below is generic in nature and is not performed for each plant. The reviewer compares the core design and operating parameters to those of previously reviewed plants and then devotes the major portion of the review effort to those areas in which the application is not identical to previously reviewed plants. 3. The reviewer compares the information in the applicant’ s SAR or DCD for new plants to the documents referenced by the applicant or included in this SRP section to determine conformance to the bounds established by such documents. The reviewer confirms that (1) the 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, (2) the analysis methods are used in the manner specified by their developers or in previous staff reviews, (3) the reactor design falls within the ranges of applicability specified for accepted analysis methods, and (4) the design is within the criteria specified in Subsection II, above, and is not an unexplained or unwarranted extrapolation of