Document: NUREG-0800
Document ID: 9e785a38-4746-4e32-949d-a145ddb95511
Document Type: srp
Title: MASS AND ENERGY RELEASE ANALYSIS FOR POSTULATED
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070491.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1.4
CFR Part: 
CFR Title: 

Content:
onsibility of other branches, the acceptance criteria and their methods of application are contained in the referenced SRP section of the corresponding primary branch. II. ACCEPTANCE CRITERIA The SCSB acceptance criteria is based on meeting the requirements of General Design Criterion 9 (GDC) 50, with respect to providing sufficient conservatism conservation in the mass and 10 energy release analysis for postulated PWR secondary system pipe ruptures to assure that the containment design margin is maintained. Specific criteria necessary to meet the relevant requirements of GDC 50 are as follows: 1. Sources of Energy The sources of energy that should be considered in analyses of steam and feedwater line break accidents include: the stored energy in the affected steam generator's metal, including the vessel tubing, feedwater line, and steam line; the stored energy in the water contained within the affected steam generator; the stored energy in the feedwater transferred to the affected steam generator prior to closure of the isolation valves in the feedwater line; the stored energy in the steam from the unaffected steam generator(s) prior to the closure of the isolation valves in the steam generator crossover lines; and the energy transferred from the primary coolant to the water in the affected steam generator during blowdown. The steam line break accident should be analyzed for a spectrum of pipe break sizes and various plant conditions from hot standby to 102% of full power. Only the 102% power condition need be analyzed provided the applicant can demonstrate that the feedwater flows and fluid inventory are greatest at full power. 6.2.1.4-3 DRAFT Rev. 2 - April 1996 2. Mass and Energy Release Rate Calculations In general, calculations of the mass and energy release rates during a steam or feedwater line break accident should be done in a manner that is conservative from a containment response standpoint; i.e., that maximizes the post-accident containment pressure and