Document: NUREG-0800
Document ID: 4851d1d8-cf40-4a04-920b-1e59a44d3f2e
Document Type: srp
Title: SPECIAL TOPICS FOR MECHANICAL COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1608/ML16088A068.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.1
CFR Part: 
CFR Title: 

Content:
e criteria met, the facility has been constructed and will operate in conformity with the combined license, the provisions of the AEA, and the NRC’s regulations. SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations identified above are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC’s 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. To meet the requirements of GDCs 1, 2, 14, 15, and 10 CFR Part 50, Appendix S the applicant should provide a complete list of transients to be used in the design and fatigue analysis of all Code Class 1 components, component supports, reactor core support structures, and reactor vessel internal components within the reactor coolant pressure boundary. The number of events for each transient and the number of load and stress cycles per event and for events in combination should be included. All transients, such as startup and shutdown operations, power level changes, emergency and recovery conditions (including, for new applications, natural convection cooldown), switching operations (i.e., startup or shutdown of one or more coolant loops), control system or other system malfunctions, component malfunctions, transients from single operator errors, inservice hydrostatic tests, seismic events as determined from the criteria specified in Appendix S to 10 CFR Part 50, and design-basis events contained in the Code-required “Design Specifications” for the components of the reactor coolant pressure boundary, should be specified. The section of the applicant’s SAR on transients