Document: NUREG-0800
Document ID: edf4b0e7-a6b1-4168-a057-45a70ca5524d
Document Type: srp
Title: ADEQUACY OF DESIGN FEATURES AND FUNCTIONAL CAPABILITIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1227/ML12276A112.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.5
CFR Part: 
CFR Title: 

Content:
5-10 Revision 0 – April 2013 (i) the reactor core remains cooled or the containment remains intact; and (ii) spent fuel pool cooling or spent fuel pool integrity is maintained. • The applicant has performed an AIA reasonably formulated to identify design features and functional capabilities to show, with reduced use of operator action, that the acceptance criteria in the AIA rule are met. For standard design certification, standard design approvals, and manufacturing license reviews, the findings will also summarize the staff’s evaluation of the COL action/information items proposed by the applicant that are relevant to this SRP section. For combined licensee reviews, the findings will also summarize the staff’s evaluation of how the COL applicant addressed those COL action/information items included in the design certification document referenced in its application that are relevant to this SRP section. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff’s evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of license applications, standard design certifications and standard design approvals submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission=s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.” 2. 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.” 3. NEI 07-13,