Document: NUREG-0800
Document ID: 94ab38ac-ddfc-4ba1-ae38-bc25ffa6e976
Document Type: srp
Title: – 15.4.5
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070716.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.4
CFR Part: 
CFR Title: 

Content:
ure, core average temperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions), steam line pressure, containment pressure, pressure relief valve flow rate, and flow rate from the reactor coolant system to the containment system (if applicable) are reviewed. Time-related variations of the following parameters are reviewed: – reactor power; – heat fluxes (average and maximum); – reactor coolant system pressure; – minimum DNBR (PWR) or CPS (BWR); – core and recirculation loop coolant flow rates (BWR); – coolant conditions (inlet temperature, core average temperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions); – steam line pressure; – containment pressure; – pressure relief valve flow rate; and – flow rate from the reactor coolant system to the containment system (if applicable).37 The values of the more important of these parameters for the core flow increase transientsAOOs are compared with those predicted for other similar plants to see that they are within the range expected. For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report, including inspections, tests, analysis, and acceptance criteria (ITAAC), site interface requirements and combined license action items, meet the acceptance criteria given in subsection II. SRP Section 14.3 (proposed) contains procedures for the review of certified design material (CDM) for the standard design, including the site parameters, interface criteria, and ITAAC.38 IV. EVALUATION FINDINGS The reviewer verifies that the SAR contains sufficient information and that thehis review 39 supports the following kinds of statements and conclusions which should be included in the staff's safety