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
CFR Part: 
CFR Title: 

Content:
de that the proposed test programs are adequate for the core and reactor coolant system. . If the core or the reactor coolant system differs significantly from that of previously reviewed designs, the impact of the proposed changes on the preoper- ational and initial startup testing programs are reviewed at the construction permit stage. This effort should particularly evaluate the need for any special design features required to perform acceptable test programs. The proposed-technical specifications that relate to the core and the reactor coolant system are evaluated. This evaluation is to cover all of the safety limits and bases that could affect the thermal and hydraulic performance of the core. The limiting safety system .settings are reviewed to ascertain that acceptable margins exist between the values at which reactor trip occurs automatically for each parameter (or combinations of parameters) and the safety limits. The reviewer confirms that the limiting safety system settings and limiting conditions for operation, as they relate to the reactor coolant system, do not permit operation with any expected combination of parameters that would not satisfy criterion 1 of section II. For example, the limiting condition of operation must assure that the reactor coolant pumps have adequate net positive suction head for all expected modes of operation. IV. EVALUATION FINDINGS The reviewer verifies that the SAR contains sufficient information and his review supports the following kinds of statements and conclusions, which should be included in the staff's safety evaluation report. The following paragraph is applicable to both a CP and OL: The thermal-hydraulic design of the core for the plant was reviewed. The scope of review included the design criteria, preliminary core design, and the steady state analysis of the core thermal-hydraulic performance.* The review concentrated on the differences between the proposed core design (and criteria) and those designs and