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:
ve failures of systems and components that may alter the course of the accident. For new applications, the LOOP is not considered a single active failure, but considered in addition to a single active failure as discussed in subsection II, assumption d. This phase of the review uses 51 the system review procedures described in the standard review plan sections for Chapters 5, 6, 7, 8, and 10 of the SAR. The variations with time during the transient of parameters listed in Sections 15.X.X.3(C) and 15.X.X.4(C) of the Standard Format, (Ref. 2)Regulatory Guide 1.70,52 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 to see that they are within the expected range. The reviewer confirms that the amount of secondary coolant expelled from the system has been calculated conservatively by evaluating the applicant's methods and assumptions, by comparison with an acceptable analysis performed on another plant of similar design, or by comparison with staff calculations for typical plants which will be available from RSBSRXB on request. The reviewer confirms that a commitment has been made in the SAR to conduct preoperational tests to verify that valve discharge rates and response times, including, for example, opening and closing times (delay times) for main feedwater, auxiliary feedwater, turbine and main steam isolation valves, and steam generator and pressurizer relief and safety valves, has been conserva- tively modeled in the accident analyses. In addition, preoperational testing should include verification of reactor trip delay times, startup delay times for actuation of the auxiliary feedwater systemAFWS, safety injection signal delay time, and delay times for delivery of any high concentration boron injection required to bring the plant to a safe shutdown condition. Using the information developed in the review, the AEBPERB