Document: NUREG-0800
Document ID: 0b93bfa1-19be-488b-8c78-a6c71cf3b42e
Document Type: srp
Title: MASS AND ENERGY RELEASE ANALYSIS FOR POSTULATED
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0535/ML053560191.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1.3
CFR Part: 
CFR Title: 

Content:
LOCA potentially causes the greatest pressure surge and release of fission products when compared to any other accident. Since it is the most severe challenge expected, containment must be designed to definitively withstand this accident. Following GDC 50 will ensure that containment integrity is maintained under the most severe accident conditions thus precluding the release of radioactivity to the environment. 2. Appendix K to 10 CFR 50 provides required and acceptable features of evaluation models used to analyze various circumstances applicable to the ECCS. Section I.A of Appendix K provides a comprehensive list of LOCA heat (energy) sources and the reactor operating history assumptions associated with those heat sources. Since the mass and energy release analysis for postulated LOCAs is used to design containment and containment subcompartments such that they will withstand the worst case LOCA, it is critical that all potential energy sources are taken into account. Following 10 CFR 50 Appendix K will ensure that containment and containment subcompartments are designed to accommodate all energy sources for the worst case LOCA, thus precluding the potential release of radioactivity to the environment following such a LOCA. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. The reviewer confirms, with the lead reviewer for SRP Section 3.6.2, the validity of the applicant's analysis of pipe break size, type and locations for subcompartments containing high energy lines by using elevation and plan drawings of the containment showing the routing of lines containing high