Document: NUREG-0800
Document ID: 7024eeeb-1819-4d56-9b72-fb63eab3836b
Document Type: srp
Title: and 3.9.3.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1006/ML100620981.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.2
CFR Part: 
CFR Title: 

Content:
thstand the effects of natural phenomena and will perform their intended safety function. 4. Compliance with GDC 4 requires that nuclear power plant SSCs important to safety be designed to accommodate the effects of, and be compatible with, environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including LOCAs. In addition, these SSCs must be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids, that may result from equipment failures and from events and conditions outside the nuclear power unit. SRP Section 3.8.3 provides methods acceptable to the staff, including load combinations, acceptance criteria, standards, and codes to assure compliance with GDC 4. Meeting these requirements and criteria provide assurance that the containment internal structures will withstand loads from internal events, such as those described above, and from external sources such as earthquakes, thus decreasing the probability that these events will damage containment internal structures. Meeting these requirements and criteria provide assurance that the internal structures of the containment will function as designed, be capable of maintaining their structural integrity, and perform their intended safety function. 5. Compliance with GDC 5 prohibits the sharing of structures important to safety among nuclear power units unless it can be shown that such sharing will not significantly impair their ability to perform their safety functions, including, in the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units. The requirements of GDC 5 are imposed to ensure that the use of common structures in multiunit plants will not significantly affect the orderly and safe shutdown and cooldown in one plant in the event of an accident in another. The load combination equations combine loads from normal operation and design-basis accidents so that