Document: NUREG-0800
Document ID: 3b714304-f91e-4999-917a-7d27866735e3
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350117.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
. The results of the analyses are reviewed to ensure that pertinent system parameters are within expected ranges. The parameters of importance for these transients include reactor coolant system (RCS) pressure, steam generator pressure, fluid temperatures, clad temperatures, discharge flow rates, steam line and feedwater flow rates, safety and relief valve flow rates, pressurizer and steam generator water levels, reactor power, total core reactivity, hot and average channel heat flux, and minimum departure from nucleate boiling ratio (DNBR). The sequence of events described in the applicant's safety analysis report (SAR) is reviewed by both RSB and ICSB. The RSB reviewer concentrates on the capability of the reactor protection system, the engineered safety systems, and operator action to secure and maintain the reactor in a safe condition. In addition, the RSB will coordinate other branches' evaluations that interface with the overall review of the steam system piping failures as follows: the Auxiliary Systems Branch (ASB) reviews the auxiliary feedwater system to verify its ability to function following a steam line break given a single active component failure with either onsite or offsite power as part of its primary review responsibility for SRP Section 10.4.9. RSB reviews the auxiliary feed- water system to verify that the flow provided is acceptable for controlling the transient following a steam line break. The Mechanical Engineering Branch (MEB) reviews the effects of blowdown loads, including Jet propulsion piping and component supports as part of its Primary review responsibility for SRP Sections 3.6.2 and 3.9. In addition, MEB reviews the design bases for safety and relief valves in SRP Section 3.9.3. The Containment Systems Branch (CSB) evaluates the response of the containment to ruptures of steam lines with regard to the effects of pressure and temperature on the containment functional capabilities as part of its primary review responsibility for SRP