Document: NUREG-0800
Document ID: 25cb3efc-9642-430d-a72f-52decd59b34f
Document Type: srp
Title: INTRODUCTION - TRANSIENT AND ACCIDENT ANALYSES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710376.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0
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Content:
sed the bases (including the degree of conservatism) used to select the numerical values of the input parameters. iii. Results. The reviewer ensures that the applicant has presented the results of the analyses, including key parameters as a function of time during the course of the transient or accident. The following are examples of parameters that should be included: • Neutron power • Thermal power • Heat fluxes, average and maximum • RCS pressure • DNBR or CPR, as applicable • Core and recirculation loop coolant flow rates for BWRs • Coolant conditions, including inlet temperature, core average temperature (for PWRs), core average steam volume fraction (for BWRs), average exit and hot channel exit temperatures, and steam volume fractions • Temperatures, including maximum fuel centerline temperature, maximum clad temperature, or maximum fuel enthalpy • Reactor 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 • 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. 15.0-11 Revision 3 - March 2007 Review Interfaces Other SRP sections interface with this section as follows: 1. Design basis radiological consequence analyses associated with design basis accidents are reviewed under SRP Section 15.0.3. The specific acceptance criteria and review procedures are contained in the referenced SRP section. II. ACCEPTANCE