Document: NUREG-0800
Document ID: 6cdd237d-c5b3-4a09-8753-54cfe1fea503
Document Type: srp
Title: REACTOR VESSEL MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190007.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.1
CFR Part: 
CFR Title: 

Content:
not damage or deteriorate the materials, alter their properties, accelerate effects associated with aging, or increase the susceptibility to failure mechanisms such as stress corrosion cracking. This reduces the likelihood that degradation and/or failure of the reactor vessel could cause substantial reduction in capability to contain reactor coolant inventory, reduction in capability to confine fission products, or interference with core cooling. 8. 10 CFR Part 50, Appendix G, establishes requirements for the fracture toughness of pressure-retaining components of the RCPB made of ferritic materials. The reactor vessel is an integral part of the RCPB. Application of these requirements to the RCPB materials provides a method of satisfying the requirements of GDC 14 and 31 related to fracture prevention. The rationale for these requirements is as discussed in Items 3 and 4 above. 9. 10 CFR Part 50, Appendix H, establishes the reactor vessel material surveillance program requirements. The surveillance program monitors the changes in fracture toughness properties of ferritic materials in the reactor vessel belt-line, resulting from exposure to neutron irradiation and the thermal environment. Data from the surveillance program is utilized in complying with 10 CFR Part 50, Appendix G requirements for establishing pressure-temperature limits and corrective actions (such as vessel annealing) if fracture toughness criteria can not be met. The structural integrity of the reactor vessel material is essential in assuring support of internal reactor components, confinement of reactor coolant, and a barrier to the release of fission products. Compliance with 10 CFR Part 50, Appendix H, provides assurance that changes to the reactor vessel materials resulting from the operational environment will be monitored, and that appropriate actions will be taken if significant changes occur in the material fracture toughness that may affect the integrity of the reactor vessel, and thus its