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:
REVIEW RESPONSIBILITIES Primary - Organization responsible for review of component integrity issues related to reactor vessel internals Secondary - Organization responsible for the review of materials engineering issues related to flaw evaluation and welding I. AREAS OF REVIEW Section 50.55a, “Codes and Standards,” of 10 CFR Part 50, and General Design Criterion (GDC) 1 of Appendix A to 10 CFR Part 50 require that structures, systems, and components (SSCs) important to safety be designed, fabricated, and tested to quality standards commensurate with the importance of the safety function to be performed. The purpose of this standard review plan (SRP) section is to review and evaluate the adequacy of the materials selected for the construction of the reactor internal and core support structures, as defined in NG-1120 of Section III of the ASME Boiler and Pressure Vessel Code (hereafter “the Code”), and to assure that the reactor internal and core support structures meet these regulations. The reactor internal and core support structures reviewed under this SRP section include all structures and components within the pressure vessel other than the fuel and control assemblies, and instrumentation. This SRP section covers the material, component design, fabrication and inspection to assure structural integrity in compliance with Section 50.55a and General Design Criterion 1 of Appendix A to 10 CFR Part 50. 4.5.2-2 Revision 3 - March 2007 The following areas in the applicant's safety analysis report (SAR) relating to reactor internal and core support structure materials are reviewed; specific areas of review are as follows: 1. Materials. The review includes the acceptability of the materials, including weld materials, to be used for the reactor internals and core support structures. The adequacy and suitability of the materials specified for the reactor internals and core support structures are reviewed in terms of their fracture toughness, stress corrosion