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:
§ 52.157 Contents of applications; technical information in final safety analysis report. The application must contain a final safety analysis report containing the information set forth below, with a level of design information sufficient to enable the Commission to judge the applicant's proposed means of assuring that the manufacturing conforms to the design and to reach a final conclusion on all safety questions associated with the design, permit the preparation of construction and installation specifications by an applicant who seeks to use the manufactured reactor, and permit the preparation of acceptance and inspection requirements by the NRC: ( a ) The principal design criteria for the reactor to be manufactured. Appendix A of 10 CFR part 50 , “General Design Criteria for Nuclear Power Plants,” establishes minimum requirements for the principal design criteria for water-cooled nuclear power plants similar in design and location to plants for which construction permits have previously been issued by the Commission and provides guidance to applicants in establishing principal design criteria for other types of nuclear power units; ( b ) The design bases and the relation of the design bases to the principal design criteria; ( c ) A description and analysis of the structures, systems, and components of the reactor to be manufactured, with emphasis upon the materials of manufacture, performance requirements, the bases, with technical justification therefor, upon which the performance requirements have been established, and the evaluations required to show that safety functions will be accomplished. The description shall be sufficient to permit understanding of the system designs and their relationship to safety evaluations. Items such as the reactor core, reactor coolant system, instrumentation and control systems, electrical systems, containment system, other engineered safety features, auxiliary and emergency systems, power conversion systems, radioactive