Document: 10 CFR Part 52
Document ID: e9c3b096-4c13-4284-8ed2-18c06d0500ef
Document Type: cfr
Title: Contents of applications; technical information in final safety analysis report.
Source: 10 CFR Part 52
Source URL: https://www.ecfr.gov/current/title-10/part-52/section-52.157
Revision Date: 
Chapter: 
Section ID: 52.157
CFR Part: 52
CFR Title: 10

Content:
oposed ITAAC required by § 52.158(a) ; ( 22 ) A representative conceptual design for a nuclear power facility using the manufactured reactor, to aid the NRC in its review of the final safety analysis required by this section and to permit assessment of the adequacy of the interface requirements in paragraph (f)(20) of this section; ( 23 ) For light-water reactor designs, a description and analysis of design features for the prevention and mitigation of severe accidents, e.g., challenges to containment integrity caused by core-concrete interaction, steam explosion, high-pressure core melt ejection, hydrogen combustion, and containment bypass; ( 24 ) [Reserved] ( 25 ) If the reactor is to be used in modular plant design, a description of the possible operating configurations of the reactor modules with common systems, interface requirements, and system interactions. The final safety analysis must also account for differences among the configurations, including any restrictions that will be necessary during the construction and startup of a given module to ensure the safe operation of any module already operating; ( 26 ) A description of the management plan for design and manufacturing activities, including: ( i ) The organizational and management structure singularly responsible for direction of design and manufacture of the reactor; ( ii ) Technical resources directed by the applicant, and the qualifications requirements; ( iii ) Details of the interaction of design and manufacture within the applicant's organization and the manner by which the applicant will ensure close integration of the architect engineer and the nuclear steam supply vendor, as applicable; ( iv ) Proposed procedures governing the preparation of the manufactured reactor for shipping to the site where it is to be operated, the conduct of shipping, and verifying the condition of the manufactured reactor upon receipt at the site; and ( v ) The degree of top level management oversight and technical