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:
de 1.68. The reviewer assures that the applicant has provided sufficient information to clearly identify the test objectives, methods of testing, and acceptance criteria. The test scope should include verification of any safety analysis codes or methods that could affect the thermal-hydraulic evaluations and that have not been previously verified. The initial startup test should also include a description of plans for a signature analysis to determine alarm settings for the loose parts monitoring system, as well as a description of test programs for evaluation, qualification, and calibration of ICC instrumentation. 4.4-12 Revision 2 - March 2007 The reviewer evaluates the proposed test programs to determine whether they provide reasonable assurance that the core and RCS will satisfy functional requirements. As an alternative to this detailed evaluation, the reviewer may compare the core and RCS design to that of previously reviewed plants. If the design is essentially identical and the proposed test programs are essentially the same as performed previously on other plants, the reviewer may conclude that the proposed test programs are adequate for the core and RCS. If the core or the RCS differs significantly from that of previously reviewed designs, the impact of the proposed changes on the preoperational and initial startup testing programs are reviewed at the COL stage. This effort should particularly evaluate the need for any special design features required to perform acceptable test programs. 18. The reviewer evaluates the proposed technical specifications that relate to the core and the RCS. This evaluation covers all 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