Document: NUREG-0800
Document ID: 2b698949-d53d-40f7-bf3c-6935d411fb3f
Document Type: srp
Title: -12
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1404/ML14043A231.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.3
CFR Part: 
CFR Title: 

Content:
Revision 3 – April 2014 A. The applicant's proposed design and service loadings, and combinations thereof, are reviewed for completeness and for appropriate designation of corresponding design and service stress limits. B. The combination of design and service loadings, including procedures for combination, proposed by the applicant for each Code-constructed item, are reviewed to determine if they are adequate. This aspect of the review is made by comparison with the loading combinations and procedures for combination set forth in Appendix A. Deviations from the position are evaluated on a case-by-case basis by questions addressed to the applicant to determine the rationale and justification for exceptions. A final determination is based on engineering judgment and agency experience with prior applications. C. The design and service stress limits selected by the applicant for each set of design and service loading combinations are reviewed to determine if they meet those specified in Appendix A. The criteria to ensure piping component functional capability are reviewed to determine their adequacy in meeting the objectives set forth in Appendix A. Deviations from the position may be permitted provided justification is presented by the applicant. The acceptability determination is based on considerations of adequate margins of safety. In SECY-93-087, “Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs,” dated April 2, 1993, the staff discussed eliminating the operating-basis earthquake (OBE) from the design bases when the OBE is established at less than or equal to one third of the safe-shutdown earthquake (SSE). In the associated Staff Requirements Memorandum (SRM) dated July 21, 1993, the Commission approved the staff’s recommendations associated with eliminating the OBE from the design bases. Appendix S to 10 CFR Part 50, “Earthquake Engineering Criteria for Nuclear Power Plants,” first