Document: NUREG-0800
Document ID: 93695235-ba5b-4bfb-be93-d9aec2460bd0
Document Type: srp
Title: STEAM AND FEEDWATER SYSTEM MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190016.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.3.6
CFR Part: 
CFR Title: 

Content:
ant. GDC 35 also requires that the system will have containment capabilities to assure that the emergency core cooling function can be accomplished, assuming a single failure. For pressure- containing components of a critical nature, their containment capability, i.e., their structural integrity, including freedom from brittle fracture, can only be assured by 10.3.6-4 Revision 3 - March 2007 requiring minimum fracture toughness performance of the materials of which they are fabricated. This is a standard industrial practice which is frequently used in construction codes of significant steel structures. 4. 10 CFR Part 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," which establishes quality assurance requirements for the design, construction, and operation of those SSCs of nuclear power plants that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. 5. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and will operate in accordance with the design certification, the provisions of the Atomic Energy Act, and the NRC's regulations; 6. 10 CFR 52.80(a), which requires that a COL application contain the proposed inspections, tests, and analyses, including those applicable to emergency planning, that the licensee shall perform, and the acceptance criteria that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, the facility has been constructed and will operate in conformity with the combined license, the provisions of the Atomic Energy Act,