Document: NUREG-0800
Document ID: ed948426-dd77-4047-be5e-2b7ab22de3f5
Document Type: srp
Title: FEEDWATER SYSTEM PIPE BREAK INSIDE AND OUTSIDE CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550009.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.8
CFR Part: 
CFR Title: 

Content:
whether the values of pertinent system parameters, addressed in subsection II of this Standard Review Plan (SRP) section, are within expected ranges. The parameters of importance for these transients include: A. reactor coolant system (RCS) pressure, B. steam generator pressure, C. fluid temperatures, D. fuel and clad temperatures, E. break discharge flow rate, F. steamline and feedwater flow rates, G. safety and relief valve flow rates, H. pressurizer and steam generator water levels, I. mass and energy transfer within the containment (for breaks inside containment), J. reactor power, K. total core reactivity, L. hot and average channel heat flux, and M. minimum departure from nucleate boiling ratio (DNBR). 2. Methods of thermal and hydraulic analysis, the postulated sequence of events, including analyses to determine the time of reactor trip and time delays prior and subsequent to initiation of reactor protection system (RPS) actions. The analytical thermal/hydraulic methods are reviewed for whether the mathematical modeling and computer codes have been reviewed and accepted by the staff. If a referenced analytical method has not been reviewed, the reviewer requests an evaluation of the new analytical model. The parameter values in the analytical model, the initial conditions of the core, and all nuclear design parameters are reviewed. This review includes: 15.2.8-3 Revision 2 - March 2007 A. power level, B. power distribution, C. Doppler coefficients, D. moderator temperature coefficients, E. void coefficients, F. reactor kinetics, G. departure from nucleate boiling correlations, and H. control rod worth. 3. The response of the reactor coolant and auxiliary systems, the functional and operational characteristics of RPS effects on the sequence of events, and all operator actions required to secure and maintain the reactor in a safe shutdown condition. The sequence of events described in the applicant's safety analysis report (SAR) is reviewed for the performance