Document: NUREG-0800
Document ID: 2adccc8f-d828-4baf-b696-6ee4f776837b
Document Type: srp
Title: REACTOR INTERNAL AND CORE SUPPORT MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070416.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.5.2
CFR Part: 
CFR Title: 

Content:
54 examination by either radiographic or ultrasonic examination is acceptable. 4. Austenitic Stainless Steel The materials and fabrication procedures used for reactor internals are reviewed. The areas of review and review procedures followinclude those spelled outdescribed in SRP 55 Section 5.2.3, "Reactor Coolant Pressure Boundary Materials.". Environmental 56 conditions must be controlled and welding procedures must be such that the probability of sensitization and microfissuring is reduced. With respect to verification of the degree of sensitization that occurs during welding, SRP Section 4.5.1, subsection III.2 identifies an acceptable alternate method to the methods described in Regulatory Guide 1.44. In 57 addition, the reviewer verifies that the material and reactor coolant compositions have been selected to assure compatibility, and that the fabrication and cleaning controls imposed on stainless steel components are designed to prevent contamination with chloride and fluoride ions. 5. Other Materials The material specifications and fabrication procedures are reviewed to verify that the heat treatment and welding controls are appropriate for the material. The reviewer verifies that the fabrication and cleaning controls will preclude contamination of nickel base alloys by chloride ions, fluoride ions, or lead. 4.5.2-7 DRAFT Rev. 3 - April 1996 Operating experience has indicated that certain nickel-chromium-iron alloys (e.g. Inconel) are susceptible to cracking due to corrosion. Inconel 690 alloy has improved corrosion resistance in comparison to Inconel alloy 600 previously used in reactor applications. Where nickel-chromium-iron alloys are proposed for use, the reviewer verifies that an acceptable technical basis is either identified (based upon demonstrated satisfactory use in similar applications) or presented by the applicant to support use of the material. Particular review emphasis is placed upon the corrosion resistance and stress corrosion cracking