Document: NUREG-0800
Document ID: d4acff25-51e1-4891-b590-9ad78ef4833e
Document Type: srp
Title: REACTOR VESSEL MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340633.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.1
CFR Part: 
CFR Title: 

Content:
Review Plan Section 5.2.3, "Reactor Coolant Pressure Boundary Materials," are considered applicable to welding of the reactor vessel and its components. The reviewer verifies that any special welding control or special welding process is able to conform to the qualification requirements of the Code, Section IX, or that justification is made for this deviation. The reviewer also reviews the controls (before, during, and after welding of austenitic stainless steel) to avoid contamination and sensitization that could increase the possibility of stress corrosion cracking in austenitic stainless steel. Additionally, controls to avoid underclad cracking during weld cladding of the reactor vessel are reviewed. 5. Fracture Toughness The information submitted by the applicant relative to tests for fracture toughness is reviewed for conformance with the Code, Section III, paragraph NB-2300, and Appendix G of 10 CFR Part 50. These tests include Charpy V-notch impact tests and dropweight tests. A description of the tests is reviewed, and the location of the test speci- mens and their orientation are verified. 5.3.1-9 Rev. 1 - July 1981 Information regarding calibration of instruments and equipment is reviewed for conformance to Code Section III, paragraph NB-2300. In the event that none of the fracture toughness tests has been performed, the preliminary safety analysis report (PSAR) must contain a statement of the applicant's intention to perform this work in accordance with Code Section III, NB-2300 and Appendix G of 10 CFR Part 50. The final safety analysis report (FSAR) is reviewed to ensure that all the impact tests shown in NB-2300 have been performed. The results of the tests shall be in accordance with the acceptance criteria shown in subsection II.5 of this SRP section. For those plants that were designed and constructed prior to the effective date of Appendix G, 10 CFR Part 50, some of the fracture toughness require- ments of Appendix G may not be explicitly met. The