Document: NUREG-0800
Document ID: 4a46b35d-2e81-4517-9716-154b19f57049
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190006.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.3
CFR Part: 
CFR Title: 

Content:
tal conditions (e.g., exposure to the reactor coolant). In addition the reviewer verifies that acceptable augmented inspection requirements have been proposed based on operating experience and service conditions. For all RCPB environments, particular review emphasis is placed upon the corrosion resistance and stress corrosion cracking resistance properties of the proposed nickel-chromium-iron alloy(s). Where cast austenitic stainless steels are proposed for use in the RCPB, the reviewer verifies that the material specifications ensure adequate fracture toughness over the design life to support use of the material under the expected environmental conditions (e.g., exposure to the reactor coolant operating temperatures). 2. Compatibility of Materials with the Reactor Coolant. The reviewer verifies that the following information is provided at each respective stage of the review process: A. At the construction permit stage of review: (1) A list of the materials of construction of the components of the reactor coolant pressure boundary that are exposed to the reactor coolant, including a description of material compatibility with the coolant, contaminants, and radiolytic products to which the materials may be exposed in service. (2) A list of the materials of construction of the RCPB, and a description of material compatibility with external insulation and with the environment in the event of reactor coolant leakage. (3) The fabrication and cleaning controls imposed on stainless steel components to minimize contamination with chloride and fluoride ions. B. At the operating license stage of the review process: 5.2.3-16 Revision 3 - March 2007 (1) The items listed under Subsection III.2.A above are reviewed to provide assurance that any changes are noted that may have occurred during the period between the submittal of the preliminary and final safety analysis reports. C. For design certification and COL applications under 10 CFR Part 52, the reviewer verifies the