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:
-pressure transient, the likely result of a large feedwater line break. Assumptions for pressurizer spray performance if credited should be reviewed as well as heat transfer by condensation within the pressurizer steam space. Test data examples which might be useful in validation of pressurizer models are in “The Pressure Response of a PWR Pressurizer During an Insure Transient,” Transactions of the American Nuclear Society, 1983 Annual Meeting, Detroit, MI, June 12-16, 1983. 3. Credit taken for a reactor trip signal or for ESS actuation should be reviewed for the ability of the instrumentation and control systems to respond as assumed under accident conditions. 4. The AFWS ability to supply adequate feedwater flow to the unaffected steam generators during the accident and subsequent shutdown is evaluated as to availability and capability to effect an orderly shutdown. As AFWS designs are diverse and may require both automatic and manual actuation, pre-operational tests should be specified for any necessary operator actions and for the maximum times for their completion. To the extent necessary, the reviewer evaluates the effect of system and component single, active failures that may alter the course of the accident. For new applications, the LOOP is not a single, active failure but an addition to a single, active failure as addressed in subsection II.6.D of this SRP section. This phase of the review uses the system review procedures described in the SRP sections for SAR Chapters 5, 6, 7, 8, and 10. During the transient the variations with time of parameter listed in Sections 15.X.X.3(C) and 15.X.X.4(C) of the Standard Format, Regulatory Guide 1.70, are reviewed. The more important of these parameters for the feedwater line break accident (as listed in subsection I of this SRP section) are compared to those predicted for other similar plants for whether they are within the expected range. 5. The reviewer confirms that the amount of secondary coolant expelled