Document: NUREG-0800
Document ID: c1cdbeda-5248-4d81-880d-2950ea4b0e03
Document Type: srp
Title: - 15.4.5-2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550007.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.4
CFR Part: 
CFR Title: 

Content:
nces meet the acceptance criteria given in Subsection II below. Furthermore, the results of the AOOs are reviewed to ascertain that the values of pertinent system parameters are within ranges expected for the type and class of reactor under review. Review Interfaces Other SRP sections interface with this section as follows: 1. General information on transient and accident analyses is provided in SRP Section 15.0. 2. Design basis radiological consequence analyses associated with design basis accidents are reviewed under SRP Section 15.0.3. 3. Values of the parameters in the analytical models of the reactor core are reviewed for compliance with plant design and specified operating conditions, acceptance criteria for fuel cladding damage limits are determined, and the core physics, fuel design, and core thermal-hydraulics data in the SAR analysis are reviewed under SRP Sections 4.2, 4.3, and 4.4.