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:
scribed in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (hereafter “the Code”), Section III, are reviewed. Attention is directed towards calibration methods, instrumentation, methods of application, sensitivity, reliability, and standards used. 4. Special Controls and Special Processes Used for Ferritic Steels and Austenitic Stainless Steels. Information on special controls and special processes for welding ferritic steels and austenitic stainless steels is reviewed, and their adequacy is assessed. The extent to which the controls and processes deviate from Code rules is reviewed. Information on welding of safe-ends during the fabrication of dissimilar metal joints is given particular attention and details of the methods, processes, and materials used are reviewed. Controls for abrasive work (e.g., grinding) on austenitic stainless steel surfaces are also reviewed with respect to the potential for material contamination and excessive surface cold-working. 5. Fracture Toughness. Fracture toughness of the ferritic materials used for reactor vessels and appurtenances thereto is reviewed to ensure that such components will behave in a non-brittle manner and that the probability of rapidly propagating fracture will be minimized under operating, maintenance, and testing conditions and during anticipated operational occurrences. The review includes the descriptions of the fracture toughness tests performed on all ferritic materials used for the reactor vessel and appurtenances thereto, and includes Charpy V-notch impact test specimens, drop- weight test specimens, and any other test specimens included by the applicant. The test procedures specified by the applicant are reviewed and their adequacy is confirmed. The composition of ferritic materials employed for the reactor vessel is reviewed and the amount of residual elements such as copper and phosphorus is checked. The results of impact tests performed on base material, weld