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:
used provide assurance that austenitic stainless steel components will be properly cleaned onsite. The controls satisfy Appendix B of 10 CFR Part 50 regarding controls for onsite cleaning of materials and components. 8. Fracture toughness of the reactor vessel and its appurtenances is controlled by conformance with Appendix G to 10 CFR Part 50, which specifies ASME Code provisions and supplementary requirements of Appendix G to 10 CFR Part 50. The fracture toughness tests required by the ASME Code and by Appendix G to 10 CFR Part 50 provide reasonable assurance that adequate safety margins against the possibility of non-ductile behavior or rapidly propagating fracture can be established for all pressure- retaining components of the reactor coolant boundary. The use of Appendix G of the Code as a guide in establishing safe operating procedures, the use of the results of the fracture toughness tests performed in accordance with the Code and NRC regulations, and the implementation of the material surveillance program in accordance with 10 CFR Part 50 Appendix G and Appendix H, will provide adequate safety margins during operating, testing, maintenance, and postulated accident conditions for the service life of the reactor vessel. Compliance with the provisions of Appendix G to 10 CFR Part 50, satisfies the requirements of GDC 14, GDC 31, 10 CFR 50.55a, and 10 CFR 50.60 regarding prevention of fracture of the RCPB. 9. The applicant described the Reactor Vessel Material Surrveillance Program and its implementation in conformance with 10 CFR 50.60 and 10 CFR 50, Appendix H. The Reviewer ensures the Reactor Vessel Material Surveillance Program and associated implementation milestones are included within the license condition on operational program implementations. 10. Changes 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