Document: NUREG-0800
Document ID: 4a46b35d-2e81-4517-9716-154b19f57049
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190006.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.3
CFR Part: 
CFR Title: 

Content:
in low-alloy steel components clad with stainless steel. Welding processes that generate excessive heating and promote base metal coarsening cause underclad cracking of certain steels. These variables are reviewed. C. The requirements for nondestructive examination of ferritic wrought seamless tubular products used for ASME Class 1 components of nuclear power plants are specified in Paragraphs NB-2550 through NB-2570, ASME Boiler and Pressure Vessel Code (hereafter “the Code”), Section III, “Rules for Construction of Nuclear Facility Components.” The methods of examination specified for nondestructive examination are reviewed. 4. Fabrication and Processing of Austenitic Stainless Steel. Austenitic stainless steels in a variety of product forms (including several stabilized product forms) are used for construction of pressure-retaining components in the reactor coolant pressure boundary. Unstabilized austenitic type stainless steels, which include American Iron and Steel Institute (AISI) Types 304 and 316, are more frequently used. Because these compositions are susceptible to stress corrosion cracking when exposed to certain environmental conditions, process controls must be exercised during all stages of component manufacturing and reactor construction to avoid severe sensitization of the material and to minimize exposure of the stainless steel to contaminants that could lead to stress corrosion cracking. 5.2.3-4 Revision 3 - March 2007 Item 4.C is reviewed by the organization responsible for chemical engineering issues and on request it will review corrosion testing data. A. Sensitization is caused by intergranular precipitation of chromium carbide in austenitic stainless steels that are exposed to temperatures in the approximate range of 430EC to 820EC (800EF to 1500EF). Precipitation of the chromium carbide at the grain boundaries increases with increasing carbon content and exposure time. Control of the application and processing of stainless steel is