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:
in the fracture toughness of material in the reactor vessel belt-line caused by exposure to neutron radiation have been assessed properly, and adequate safety margins against the possibility of vessel failure are provided as the material surveillance requirements of ASTM E-185 and Appendix H to 10 CFR Part 50, are met. Compliance with these requirements assures that the surveillance program constitutes an acceptable basis for monitoring radiation-induced changes in the fracture toughness of the reactor vessel material and satisfies the requirements of GDC 32 and 10 CFR 50.60 regarding an appropriate material surveillance program for the reactor vessel. 11. Integrity of the reactor vessel studs and fasteners is assured by conformance with the recommendations of RG 1.65. Compliance with these recommendations satisfies the quality standards requirements of GDC 1, GDC 30, and 10 CFR 50.55a; the prevention of RCPB fracture requirement of GDC 31; and the requirements of Appendix G to 10 CFR Part 50, as detailed in the provisions of the ASME Code, Sections II and III. Accordingly, the staff concludes that the plant design is acceptable and meets the requirements of GDC 1, 4, 14, 30, and 31 of Appendix A of 10 CFR Part 50; the requirements of Appendices B and G of 10 CFR Part 50; and the requirements of 10 CFR 50.55a of 10 CFR Part 50. Revision 2 - March 2007 5.3.1-20 For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. The staff will use this SRP section in