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:
nation of Wrought Seamless Tubular Products and Fittings Examination shall be in accordance with the requirements of ASME Code Section III, NG-2500. The acceptance criteria shall be in accordance with the requirements of ASME Code Section III, NG-5300. 4. Austenitic Stainless Steels The acceptance criteria for this area of review are given in SRP Section 5.2.3, "Reactor Coolant Pressure Boundary Materials." Regulatory Guide 1.44, "Control of the Use of Sensitized Stainless Steel," describes acceptance criteria for preventing intergranular corrosion of stain- less steel components. Furnace sensitized material should not be allowed, and 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. Regulatory Guide 1.31, "Control of Ferrite Content in Stainless Steel Weld Metal," describes acceptable criteria for assuring the integrity of welds in stainless steel components. 5. Other Materials All materials used for reactor internals must be selected for their compatibility with the reactor coolant, as described in Subarticles NG-2160 and NG-3120 of Section III of the 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 deteri- orate in service. Acceptable heat treatment temperatures are aging at 10501F - 11001F for Type 17-4 PH and tempering at 1050'F for Type 410 stainless steel. Other materials shall have similar appropriate heat treat and fabrication controls in accordance with strength and compatibility requirements. III. REVIEW PROCEDURES The reviewer will select and emphasize material from the procedures described below, as may be appropriate for a particular case. For the areas of review described in subsection I of this SRP