Document: NUREG-0800
Document ID: c1d42ca1-cc58-40db-812c-918554bfa81b
Document Type: srp
Title: FEEDWATER SYSTEM PIPE BREAKS INSIDE AND OUTSIDE CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070704.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.8
CFR Part: 
CFR Title: 

Content:
prior and subsequent to initiation of reactor protection system (RPS) actions, 8 3. the assumed response of the reactor coolant and auxiliary systems, the functional 9 and operational characteristics of the reactor protection system(RPS) in terms of its effects on the sequence of events, and all operator actions required to secure and maintain the reactor in a safe shutdown condition. The results of the analyses are reviewed to ensure that the values of pertinent system parameters, discussed in subsection II below, are within expected ranges. The parameters of importance for these transients include: 1. reactor coolant systemRCS pressure, 2. steam generator pressure, 3. fluid temperatures, 4. fuel and clad temperatures, 5. break discharge flow rate, 6. steamline and feedwater flow rates, 7. safety and relief valve flow rates, 8. pressurizer and steam generator water levels, 9. mass and energy transfer within the containment (for breaks inside containment), 10. reactor power, 11. total core reactivity, 12. hot and average channel heat flux, and 13. minimum departure from nucleate boiling ratio (DNBR). 10 The sequence of events described in the applicant's safety analysis report (SAR) is reviewed by both RSBSRXB and ICSBHICB. The RSBSRXB and HICB reviewers concentrates on the 11 12 15.2.8-3 DRAFT Rev. 2 - April 1996 need for the reactor protection system(RPS), the engineered safety systems (ESS), and operator 13 action to secure and maintain the reactor in a safe conditions. The analytical methods are reviewed by RSBSRXB to ascertain whether the mathematical modeling and computer codes have been previously reviewed and accepted by the staff. If a referenced analytical method has not been previously reviewed, the reviewer requests initiation of a generic evaluation of the new analytical model. RSBSRXB also reviews the values of all the parameters used in the analytical model. CPBSRXB also reviews the initial conditions of 14 15 the core and all nuclear design