Document: NUREG-0800
Document ID: fbf00155-ed67-4c5f-bb08-246909eb564a
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340601.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.3
CFR Part: 
CFR Title: 

Content:
e nuclear power plants. These documents are made available to the public as part of the Commission's policy to Inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them Is not required. The standard review plan sections are keyed to the Standard Format and content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate. to accommodate comments and to reflect new Informa- tion and experience. Comments and suggestions for improvement will be considered end should be sent to the U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Washington. D.C. 2055 Similarly, a review by MTEB is made of possible uses of austenitic stain- less steels in the sensitized condition. The use of austenitic stainless steels in any condition in boiling water reactors (BWR's) requires special attention because of the oxygen content of BWR coolant. 3. Fabrication and Processing of Ferritic Materials Items 3.a, 3.b, and 3.c are reviewed by MTEB. a. The fracture toughness properties of ferritic materials used for pressure-retaining components of the reactor coolant pressure boundary are reviewed. The fracture toughness tests performed on all ferritic materials used for pressure-retaining RCPB components (i.e., vessels, pumps, valves, and piping) are reviewed. The test procedures used for Charpy V-notch impact and dropweight testing are reviewed. Fracture toughness of the material is characterized by its reference temperature, RTNDT. This temperature is the higher of the nil- ductility temperature (NDT) from the dropweight test or the temperature that is 600F below the temperature at which Charpy V-notch impact test data are 50 ft-lbs and 35 mils lateral expansion., b. The