Document: NUREG-0800
Document ID: 61ddad5b-f914-4192-b39f-6f00ffa2e3c5
Document Type: srp
Title: REACTOR INTERNAL AND CORE SUPPORT STRUCTURE MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190005.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.5.2
CFR Part: 
CFR Title: 

Content:
t be completed until after the completion of this section. 4.5.2-8 Revision 3 - March 2007 IV. EVALUATION FINDINGS The reviewer verifies that the applicant has provided sufficient information and that the review and calculations (if applicable) support conclusions of the following type to be included in the staff's safety evaluation report. The reviewer also states the bases for those conclusions. 1. The staff concludes that the materials used for the reactor internals and core support structures are acceptable and meet the requirements of 10 CFR 50.55a and 10 CFR Part 50, Appendix A, General Design Criterion 1. This conclusion is based upon the following considerations: The applicant has selected, and identified by specification, materials for the reactor internals and core support structures that satisfy the requirements of Subsubarticle NG-2120 of Section III, Division 1 and Tables 2A, 2B and 4 of Section II of the ASME Code. For materials not in accordance with ASME Code provisions, the applicant has selected materials of construction that are approved for use by NRC-accepted ASME Code Cases, as identified in Regulatory Guide 1.84, or that have otherwise been demonstrated acceptable for the application. As proven by extensive tests and satisfactory performance, the specified materials are compatible with the expected environment and corrosion is expected to be negligible. The applicant has demonstrated that the design, fabrication, and testing of the materials used in the reactor internals and core support structures are of high quality standards and are adequate to assure structural integrity. The controls imposed upon austenitic stainless steel components satisfy the positions of Regulatory Guide 1.44, “Control of the Use of Sensitized Stainless Steel,” and the related criteria provided in SRP Section 5.2.3, “Reactor Coolant Pressure Boundary Materials.” The controls imposed on the reactor coolant chemistry provide reasonable assurance that the reactor