Document: NUREG-0800
Document ID: 76e2cd41-eada-4a81-bc9e-1df5cf439180
Document Type: srp
Title: SPECIAL TOPICS FOR MECHANICAL COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1422/ML14227A637.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.1
CFR Part: 
CFR Title: 

Content:
mperature and pressure conditions caused by those transients. To a large extent the selection of these specific transient conditions is based upon engineering judgment and experience. Some guidance on the selection of these transients and combinations can be found in SRP Section 3.9.3. Transients and consequent loads and load combinations with appropriate specified design and service limits should provide a complete basis for design of the reactor coolant pressure boundary for all conditions and events expected over the service lifetime of the plant. The staff should consider the number of transients appropriate for the design life of the plant. Also, environmental conditions to which equipment safety-related or risk-significant equipment will be exposed (e.g., chemistry of the coolant water) should be considered to minimize the degradation of materials due to corrosion. 2. To meet the requirements of 10 CFR Part 50, Appendix B and GDC 1, a list of computer programs used in dynamic and static analyses to determine the structural and functional integrity of seismic Category I components, ASME BPV Code and non-Code components should be provided. For each program, as a minimum, the following information should be provided to demonstrate its applicability and validity: 3.9.1-5 Draft Revision 4 – August 2015 A. The author, program source, dated version, and facility. B. A description and the extent and limitation of its application. C. The computer program solutions to a series of test problems demonstrated to be compatible with solutions obtained from any one of sources (i) through (iv) within the acceptable margin using benchmark problems acceptable to the staff (e.g., NUREG/CR-1677, “Piping Benchmark Problems.” Volumes I and II): (i) Hand calculations (ii) Analytical results published in relevant engineering literature (iii) Acceptable experimental tests (iv) A similar computer program previously accepted by NRC or acceptable to the staff (e.g., commercial