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:
n 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 from the system is calculated conservatively by evaluation of the applicant's methods and assumptions, by comparison with an acceptable analysis on another plant of similar design, or by comparison with staff calculations. The reviewer confirms an SAR commitment to conduct pre-operational tests to verify that valve discharge rates and response times (e.g., opening and closing times (delay times) for main feedwater, auxiliary feedwater, turbine and main steam isolation, and steam generator, pressurizer relief, and safety valves) are modeled conservatively in the accident analyses. In addition, pre-operational testing should include verification of reactor trip delay times, startup delay times for AFWS actuation, 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. 6. Using the information developed in the review, the reviewer evaluates the radiological consequences of the design-basis feedwater line break. This evaluation is based on a qualitative comparison to the results of the design-basis steam line break or on a detailed analysis using the approach described in the SRP Section 15.0.3. 15.2.8-11 Revision 2 - March 2007 7. AFWS reliability and operability are reviewed for compliance with 10 CFR 50.34(f)(1)(ii) and 10 CFR 50.34(f)(2)(xii) as to AFWS performance requirements following feedwater piping failures. (See SRP Acceptance Criteria for AP1000 applicability). Reactor RCP seal reliability and integrity during loss of alternating-current power and loss of coolant to the seals (e.g., a result of containment isolation) are reviewed for compliance with 10 CFR 50.34(f)(1)(iii). (See SRP Acceptance Criteria for AP1000 applicability). 8. For review of a DC