Document: NUREG-0800
Document ID: b17adfa2-7bfa-4f7d-9b7b-7a5df200327f
Document Type: srp
Title: REACTOR INTERNAL AND CORE SUPPORT MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340586.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.5.2
CFR Part: 
CFR Title: 

Content:
taff responsible for the review of applications to construct and operate nuclear power plants. These Uocuwent amre made available to the public as part of the Commission's policy to Inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate, to accommodate comments and to reflect new Inform- don and experience. Comments and suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Washington. D.C. - The adequacy and suitability of the materials specified for the above applica- tions are reviewed in terms of their mechanical properties, stress corrosion resistance, and fabricability. 2. Controls on Welding The review includes the controls on welding of materials used for reactor internals. 3. Nondestructive Examination of Wrought Seamless Tubular Products and Fittings The review includes information submitted by the applicant on the nondestructive examinations procedures used for inspection of each product form. 4. Austenitic Stainless Steel Austenitic stainless steel is primarily used for the construction of the reactor internal and core support structures. Unstabilized austenitic stainless steel, such as Types 304 and 316, is normally specified. Since 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 sensitization of the material, and to minimize exposure of