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:
icants include seismic events in the design basis and in their postulated design transients. Pursuant to GDC 2, the reviewer evaluates whether mechanical components are designed to withstand the loads generated by natural phenomena. The reviewer also verifies whether the applicant has provided a list of postulated design transients with consideration of seismic events. The requirements of GDC 2 provide reasonable assurance that SSCs important to safety have the capability to withstand the effects of natural phenomena and to perform their intended functions. 3. GDC 14 requires that the reactor coolant pressure boundary be designed, fabricated, erected, and tested so as to have an extremely low probability of abnormal leakage, rapidly propagating failure, and of gross rupture. 4. GDC 15 requires that the reactor coolant system and its auxiliary, control, and protection systems be designed with sufficient margin to assure that the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated operational occurrences. 5. GDC 14 and GDC 15 apply to this review because SSCs important to safety are exposed to postulated transients anticipated during the design life of the plant. If SSCs are to perform their design functions there must be adequate assurance that mechanical components will remain functional under all postulated combinations of normal operating conditions, anticipated operational occurrences, postulated pipe breaks, and seismic events. 6. Compliance with the requirements of GDC 14 and GDC 15 provides reasonable assurance that the design transients and consequent loads and load combinations with the appropriate specific design and service limits for ASME Code Class 1 components, component supports, reactor core support structures, and reactor vessel internal components form a complete basis for the design of the reactor coolant pressure 3.9.1-7 Draft Revision 4 – August 2015