Document: NUREG-0800
Document ID: d51db4b1-0b68-4e27-8107-a41ccdbd671a
Document Type: srp
Title: ASME CODE CLASS 1, 2, AND 3 COMPONENTS, COMPONENT SUPPORTS,
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070337.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.3
CFR Part: 
CFR Title: 

Content:
is guidance is designed to be in compliance with GDC 2. Meeting the requirements of GDC 2 provides assurance that components and structures important to safety are capable of performing their intended safety functions.69 (4) Compliance with GDC 4 requires that the nuclear power plant structures and components important to safety be designed to accommodate the effects of and be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents. SRP Section 3.9.3 provides guidance for the staff's review of the subject components and structures which are important to safety. This guidance includes consideration of loading effects and the resulting stresses (computed in accordance with the ASME B&PV Code) associated with normal operation, maintenance, testing, and postulates accidents, including loss-of-coolant accidents. This guidance is designed to be in compliance with GDC 4. Meeting the requirements of GDC 4 provides assurance that components and structures important to safety are capable of performing their intended safety functions.70 (5) Compliance with 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 gross rupture. SRP Section 3.9.3 provides guidance for the staff's review of ASME Class 1 components and component supports, including core support structures. This guidance cites the requirements of the ASME B&PV Code to compute stresses and stress limits that are based on the loads and load combinations described in the SRP section. Meeting these requirements provides additional assurance that components that are part of the reactor coolant pressure boundary will be designed so as to have an extremely low probability of abnormal leakage, rapidly propagating failure, and gross rupture. This guidance is designed to be in