Document: NUREG-0800
Document ID: 7ed8e5d3-fcfd-49cc-84ad-3b25caba06af
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550006.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
studies, and models proposed by the applicant are evaluated. C. Analytical models should be sufficiently detailed to simulate the reactor coolant (primary), steam generator (secondary), and auxiliary systems. The reviewer evaluates the following functional requirements: i. Reactor trip signal: credit taken for any reactor trip signal is reviewed by Instrument and Control to confirm that, under accident conditions, the instrumentation and control systems are capable of the assumed response. ii. Emergency core cooling system (ECCS): credit taken for actuation of the ECCS is reviewed by Instrument and Control to verify the ability of the instrumentation and control systems to respond as assumed. iii. Auxiliary feedwater system: the availability of the auxiliary feedwater system to supply adequate auxiliary feedwater flow to the intact steam generators during the accident and the subsequent shutdown condition is evaluated. This is done by Plant Systems as to availability of the system and by Reactor Systems as to capability to effect an orderly shutdown. Since auxiliary feedwater system 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. In the case of AP1000 the safety related function of decay heat removal is performed by the PRHR. 15.1.5-10 Revision 3 - March 2007 D. 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; –