Document: NUREG-0800
Document ID: 42e7682f-df25-4a6a-94f4-7d44ea029702
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070677.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
m designs are diverse and may require both automatic and manual actuation, preoperational tests should be specified to identify any necessary operator actions and to establish times required for their completion. d. The variations with time during the transient of the neutron power, heat fluxes (average and maximum), total core reactivity, reactor coolant system pressure, minimum DNBR; coolant conditions (inlet temperature core average temperature and average exit and hot channel exit temperatures, fuel rod conditions (maximum fuel center-line temperature, maximum clad temperature, or maximum fuel enthalpy), steam generator pressure, containment pressure, relief and/or safety valve flow rates, discharge flow rate, steam line and feedwater flow rates and pressurizer and steam generator water levels are reviewed. Time-related variations of the following parameters are reviewed: – reactor power; – heat fluxes (average and maximum); – total core reactivity; – reactor coolant system pressure; – minimum DNBR; – coolant conditions (inlet temperature core average temperature and average exit and hot channel exit temperatures; – fuel rod conditions (maximum fuel center–line temperature, maximum clad temperature, or maximum fuel enthalpy); – steam generator pressure; – containment pressure; – relief and/or safety valve flow rates; – discharge flow rate; – steam line and feedwater flow rates; and – pressurizer and steam generator water levels.52 15.1.5-11 DRAFT Rev. 3 - April 1996 The values of the more important of these parameters for the steam line break accident (as listed in subsection I) are compared with those predicted for other similar plants to see that they are within the range expected. 2. To the extent deemed necessary, the reviewer evaluates the effect of single active failures of systems and components that may affect the course of the accident. For new applications, loss of offsite power should not be treated as a single active