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:
inless Steel The materials and fabrication procedures used for reactor internals are reviewed. The areas of review and review procedures follow those spelled out in SRP Section 5.2.3, "Reactor Coolant Pressure Boundary Materials." Environmental conditions must be controlled and welding procedures must be such that the probability of sensitization and microfissuring is reduced. In 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. 6. Additional Information Request If the information contained in the SAR does not comply with the appropriate acceptance criteria, or if the information provided is inadequate to establish such compliance, the reviewer prepares a request for additional information for transmittal to Project Management. Such requests not only identify the additional information required, but also specify the changes needed in the SAR or the plant Technical Specifications to meet acceptance criteria. Subse- quent amendments received in response to these requests are reviewed for compliance with the acceptance criteria. IV. EVALUATION FINDINGS The reviewer verifies that sufficient and adequate information has been provided to satisfy the requirements of the SRP section, and that his evaluation supports conclusions of the following type, to be included in the staff's safety evaluation report: 4.5.2-4 Rev. 2 - July 1981 The staff concludes that the materials used for the construction of the reactor internal