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:
he Atomic Energy Act, and the NRC regulations. 5. 10 CFR 52.158(a)(1) requires that a manufacturing license application contain the proposed inspections, tests, and analyses that the licensee who will be operating the reactor shall perform, and the 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: (1) the reactor has been manufactured in conformity with the manufacturing license; the provisions of the Atomic Energy Act, and the Commission's rules and regulations; and (2) the manufactured reactor will be operated in conformity with the approved design and any license authorizing operation of the manufactured reactor. Standard Review Plan Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC regulations identified above are as follows for the review described in this SRP section. The 19.5-4 Revision 0 – April 2013 SRP is not a substitute for the NRC regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria, and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. 1. Regulatory Guide (RG) 1.217, Revision 0, “Guidance for the Assessment of Beyond-Design-Basis Aircraft Impacts,” endorses the guidance in Nuclear Energy Institute (NEI) 07-13, Revision 8, “Methodology for Performing Aircraft Impact Assessments for New Plant Designs,” (ref. 3) as an acceptable method for use in satisfying the NRC requirements in 10 CFR 50.150(a) regarding the assessment of aircraft impacts for new nuclear power reactors. The NRC will review the information contained in the application and reach conclusions as to whether the applicant