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:
iew procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements The basic objective of the review of feedwater system pipe break events is to confirm that the reactor primary system is maintained in a safe status for break sizes up to and including a break equivalent in area to the double-ended rupture of the largest feedwater line. Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. General Design Criterion (GDC) 13, as to the availability of instrumentation to monitor variables and systems over their anticipated ranges to assure adequate safety, and of 15.2.8-5 Revision 2 - March 2007 appropriate controls to maintain these variables and systems within prescribed operating ranges. 2. GDC 17, as to onsite and offsite electric power systems for safety-related SSCs to function. The safety function for each power system (assuming the other system is not functioning) must be of sufficient capacity and capability so design conditions of the reactor coolant pressure boundary are not exceeded and the core is cooled in postulated accidents. 3. GDCs 27 and 28, as to the RCS design with appropriate margin so acceptable fuel design limits are not exceeded and core cooling capability is maintained. 4. GDC 31, as to RCS design with sufficient margin so the boundary is nonbrittle and the probability of fracture propagation is minimized. 5. GDC 35, as to design of the RCS and its auxiliaries for abundant emergency core cooling. 6. 10 CFR Part 100, as to calculated doses at the site boundary. SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations identified above are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical