Document: NUREG-0800
Document ID: b8d2b8f5-432a-4c0a-81ab-20231f7d0f28
Document Type: srp
Title: PROBABILISTIC RISK ASSESSMENT AND SEVERE ACCIDENT EVALUATION FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1508/ML15089A068.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.0
CFR Part: 
CFR Title: 

Content:
t’s assessment of the seismic capacity of the 19.0-4 Revision 3 – December 2015 containment structure in meeting the expectation documented in SECY-93-087, Section II.N. The staff also reviews the applicant’s assessment of the structural effects of postulated containment phenomenological challenges such as direct containment heating and ex-vessel explosions loads on the containment. The review and evaluation focus on the structural performance of the containment boundary as the ultimate barrier to radionuclide releases to the environment in a severe accident. COL Action Items and Certification Requirements and Restrictions. For a DC application, the review will also address COL action items and requirements and restrictions (e.g., interface requirements and site parameters). For a COL application referencing a DC, a COL applicant must address COL action items (referred to as COL license information in certain DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. Review Interfaces The organization responsible for structural engineering supports the review of the PRA and severe accident evaluation in two main areas: the applicant’s evaluation of seismic contributors (specifically the seismic hazard analysis and estimation of seismic capacities (acceleration at which there is high confidence in low probability of failure [HCLPF]) and the applicant’s analysis of containment performance. This organization provides written input to the SER. Acceptance criteria for these sections are outlined below. The review of an applicant’s degree of compliance with requirements of 10 CFR 50.44, “Combustible Gas Control for Nuclear Power Reactors,” is conducted with guidance in SRP Section 6.2.5 and performed in coordination with the review of containment performance under severe accident conditions. Other organizations that use the