Document: NUREG-0800
Document ID: 1877a6e5-f5a2-4394-bd63-c323831e96d0
Document Type: srp
Title: INTRODUCTION - TRANSIENT AND ACCIDENT ANALYSES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML2231/ML22319A149.pdf
Revision Date: 2023-07
Chapter: 15
Section ID: 15.0
CFR Part: 
CFR Title: 

Content:
eactor coolant inventory, including total inventory, and coolant level in various locations in the RCS • Secondary (power conversion) system parameters, including steam flow rate, steam pressure and temperature, feedwater flow rate, feedwater temperature, and steam generator inventory • ECCS flow rates and pressure differentials across the core, as applicable • Containment pressure • Relief and/or safety valve flow rate • Flow rate from the RCS to the containment system, if applicable 8 “Suitably conservative” means the input values used for parameters and initial conditions represent either 1) an appropriately conservative set of possible conditions, or 2) realistic conditions in concert with an appropriate treatment of the associated uncertainties and variabilities. 15.0-12 Draft Revision 4 – July 2023 • Pressurizer water volume (for PWRs) In addition, the discussion of the results should emphasize the margins between the predicted values of various core parameters, as well as the values of those parameters that would represent limiting acceptable conditions. II. ACCEPTANCE CRITERIA Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR Part 20, “Standards for Protection Against Radiation” 2. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities” (especially 10 CFR 50.46 and Appendix A) 3. 10 CFR Part 100, “Reactor Site Criteria” 4. 10 CFR Part 52, “Early Site Permits; Standard Design Certification; and Combined Licenses for Nuclear Power Plants” The following GDC from Appendix A to 10 CFR Part 50 are relevant to SRP Section 15: 1. GDC 10, as it relates to the RCS being designed with appropriate margin to ensure that specified acceptable fuel design limits are not exceeded during normal operations including AOOs. 2. GDC 12, as it relates to the reactor core and associated coolant, control, and protection systems being designed to assure that