Document: NUREG-0800
Document ID: bf62536e-58c7-4cb0-a51f-5c5ce2c21d6b
Document Type: srp
Title: DRAFT Rev. 2 - April
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070423.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.2.9
CFR Part: 
CFR Title: 

Content:
g to assess their structural and leak-tight integrity, and a material surveillance program for the reactor pressure vessel. The reactor vessel material surveillance program monitors the reactor vessel beltline materials for changes in fracture toughness resulting from exposure to neutron irradiation and the thermal environment. The specific material surveillance program requirements are established in 10 CFR 50, Appendix H and the data is utilized to determine compliance of the irradiated material with the fracture toughness requirements and criteria of 10 CFR 50, Appendix G. Compliance with GDC 32 provides assurance that degradation potentially affecting RCPB integrity is detected prior to fracture. Further, a materials surveillance program assures that the reactor vessel materials maintain of sufficient toughness thereby reducing the probability of reactor vessel failures. 6. 10 CFR 50.60 establishes that all light-water nuclear power reactors must meet the fracture toughness and material surveillance requirements set forth in 10 CFR 50, Appendix G and Appendix H. Compliance with the requirements of this rule and the associated Appendices provide assurance regarding the structural integrity of the RCPB and specifically the reactor vessel. The rationale for compliance with this rule is discussed in Technical Rationale items 3, 4, 8 and 9 of this subsection. 7. 10 CFR 50, Appendix B, Criterion XIII, requires that measures be established to control the cleaning of material and equipment to prevent damage or deterioration. Regulatory Guide 1.37 provides regulatory positions relevant to compliance with Appendix B. Application of cleaning requirements to the reactor vessel materials provides assurance that contaminants to which they could be exposed will 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