Document: NUREG-0800
Document ID: 0bc22ae4-5c52-4b2a-bb94-6d323cffe8b8
Document Type: srp
Title: SPECIAL TOPICS FOR MECHANICAL COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070335.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.1
CFR Part: 
CFR Title: 

Content:
the reactor coolant system being designed with sufficient margin to assure ensure that 18 the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated operational occurrences. 5E. 10 CFR Part 50, Appendix B, as it relates to design quality control. 6F. 10 CFR Part 100, Appendix A, as it relates to the suitability of the plant design bases for mechanical components established in consideration of site seismic characteristics. Specific criteria necessary to meet the relevant requirements of the regulations listed above are as follows: 1. To meet the requirements of GDC General Design Criteria 1, 2, 14, 15, 19 and 10 CFR Part 100, Appendix A, the applicant shall provide a complete list of transients to be used in the design and fatigue analysis of all Code Class 1 and CS components, supports and reactor internals 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 shall 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 20 (i.e., startup or shutdown of one or more coolant loops), control system or other system malfunctions, component malfunctions, transients resulting from single operator errors, inservice hydrostatic tests, seismic events as determined from the criteria specified in Appendix A to 10 CFR Part 100, and design basis events, that are contained in the Code-required "Design Specifications" for the components of the reactor coolant pressure boundary shall be specified, including reactor internals and core support structures. The section of the applicant's SAR which pertains to transients will be acceptable if the transient conditions selected for equipment fatigue evaluation are based upon a conservative