Document: NUREG-0800
Document ID: a4ef36de-b662-41f6-9e66-96e4b7197298
Document Type: srp
Title: MASS AND ENERGY RELEASE ANALYSIS FOR POSTULATED
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0601/ML060150002.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1.3
CFR Part: 
CFR Title: 

Content:
neral Electric: M3CPT (Reference 11), NEDO-20533 (Reference 12), and | SHEX (Reference 13, 14, and 15). | | Westinghouse: WCAP-8312 (Reference 16), SATAN-V (Reference 1), WCAP- | 10325 (Reference 17), SATAN-VI (Reference 18), and WREFLOOD (Reference | 19). | | Theses codes and methods have been referenced in licensee submittals and on | a case by case basis have been found to be acceptable for these purposes. | | Other methods will be acceptable if they are found to be conservative for these | calculations. | | C. 10 CFR 52.47(a)(1)(vi) provides the requirement for ITAAC for design certification | reviews | | D. 10 CFR 52.97(b)(1) provides the requirement for ITAAC for combined license reviews | | Technical Rationale | The technical rationale for application of the above acceptance criteria to the mass and energy | release analysis for postulated LOCAs is discussed in the following paragraphs. | | 1. GDC 50 requires the containment structure and associated heat removal system to be | designed with margin to accommodate any LOCA such that the containment design leak | rate is not exceeded. A 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