Document: NUREG-0800
Document ID: f5ae448a-20e3-4127-90a9-888a9b291921
Document Type: srp
Title: REACTOR VESSEL INTEGRITY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340640.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.3
CFR Part: 
CFR Title: 

Content:
de new or novel concepts unless they are substantiated by a com- prehensive justification showing that no aspects of the design will compro- mise the overall integrity of the vessel in any manner. The design details must be adequate to permit all required inspections and to provide required access to all areas requiring inservice inspec- tion in conformance with Section XI of the Code, as detailed in SRP Section 5.2.4, "Reactor Coolant Pressure Boundary Inservice Inspection and Testing." This satisfies the requirements of GDC 32 and §50.55a regarding inservice inspection. If the neutron radiation exposure of the reactor vessel becomes high enough that the predicted value of the adjusted reference temperature of the mate- rial exceeds 2001F, the design must be adequate to permit in-place annealing of the vessel to restore ductility and toughness, in accordance with Appendix G, "Fracture Toughness Requirements," of 10 CFR Part 50. This satisfies the fracture toughness requirement of GDC 31. 2. Materials of Construction The basic acceptance criteria for the materials used in the construction of the reactor vessel, and the regulations that they satisfy, are detailed in SRP Section 5.2.3, "Reactor Coolant Pressure Boundary Materials," and in SRP Section 5.3.1, "Reactor Vessel Materials." These criteria are the requirements of Appendix G, 10 CFR Part 50, as augmented by Sections III and IX of the Code. The materials must be compatible with the design requirements. Accept- ability is based on standard practice and engineering judgement, with consideration being given to such factors as material form, size-related variations in properties, and nonisotropic characteristics. Although many materials are acceptable for reactor vessels according to Section IlI of the Code, the special considerations relating to fracture toughness and radiation effects effectively limit the basic materials that are currently acceptable for most parts of reactor vessels to SA 533 Gr B C1 1, SA