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:
tion. Nondestructive examinations shall be in accordance with the requirements of ASME Code, Section III, Division 1, Subarticle NG-2500. The nondestructive examination acceptance criteria shall be in accordance with the requirements of ASME Code, Section III, Division 1, Subarticle NG-5300. 4. Austenitic Stainless Steels. The acceptance criteria for this area of review are given in SRP Section 5.2.3, subsections II.2 and II.4.a, b, d, and e. Regulatory Guide 1.44 provides acceptance criteria for preventing intergranular corrosion of stainless steel components. In conformance with this guide, furnace sensitized material should not be allowed. Methods described in this guide should be followed for cleaning and protecting austenitic stainless steel from contamination during handling, storage, testing, and fabrication, and for determining the degree of sensitization that occurs during welding. 5. Other Materials. All materials used for reactor internals and core support structures must be selected for compatibility with the reactor coolant, as specified in Subsubarticles NG-2160 and NG-3120 of Section III, Division 1 of the ASME Code. The tempering temperature of martensitic stainless steels and the aging temperature of precipitation- hardened stainless steels should be specified to provide assurance that these materials will not deteriorate in service. Acceptable heat treatment temperatures are 565EC - 595EC (1050EF - 1100EF) for aging of Type 17-4 PH and 565EC (1050EF) for tempering of Type 410 stainless steel. Other materials shall have similar appropriate heat treat and fabrication controls in accordance with strength and compatibility requirements. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: GDC 1 and 10 CFR 50.55a require that SSCs be designed, fabricated, erected, constructed, tested, and inspected to quality standards