Document: 10 CFR Part 52
Document ID: 020ef942-5abe-41d1-bb67-8c0291bd7dfb
Document Type: cfr
Title: Contents of applications; technical information.
Source: 10 CFR Part 52
Source URL: https://www.ecfr.gov/current/title-10/part-52/section-52.47
Revision Date: 
Chapter: 
Section ID: 52.47
CFR Part: 52
CFR Title: 10

Content:
s to be met by those portions of the plant for which the application does not seek certification. These requirements must be sufficiently detailed to allow completion of the FSAR; ( 26 ) Justification that compliance with the interface requirements of paragraph (a)(25) of this section is verifiable through inspections, tests, or analyses. The method to be used for verification of interface requirements must be included as part of the proposed ITAAC required by paragraph (b)(1) of this section; and ( 27 ) A description of the design-specific probabilistic risk assessment (PRA) and its results. ( 28 ) For applications for standard design certifications which are subject to 10 CFR 50.150(a) , the information required by 10 CFR 50.150(b) . ( b ) The application must also contain: ( 1 ) The proposed inspections, tests, analyses, and acceptance criteria that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a facility that incorporates the design certification has been constructed and will be operated in conformity with the design certification, the provisions of the Act, and the Commission's rules and regulations; and ( 2 ) An environmental report as required by 10 CFR 51.55 . ( c ) This paragraph applies, according to its provisions, to particular applications: ( 1 ) An application for certification of a nuclear power reactor design that is an evolutionary change from light-water reactor designs of plants that have been licensed and in commercial operation before April 18, 1989, must provide an essentially complete nuclear power plant design except for site-specific elements such as the service water intake structure and the ultimate heat sink; ( 2 ) An application for certification of a nuclear power reactor design that differs significantly from the light-water reactor designs described in paragraph (c)(1) of this section or uses simplified, inherent, passive, or