Document: NUREG-0800
Document ID: 495c2b41-2832-4900-9000-040f3ae8c835
Document Type: srp
Title: STEAM GENERATOR MATERIALS AND DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1614/ML16147A289.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.2.1
CFR Part: 
CFR Title: 

Content:
0, “Quality of Reactor Coolant Pressure Boundary,” requires, in part, that components which are part of the RCPB shall be designed, fabricated, erected, and tested to the highest quality standards practical. 6. GDC 31, “Fracture Prevention of Reactor Coolant Pressure Boundary,” requires, in part, that the RCPB shall be designed with sufficient margin to ensure that—when stressed under operating, maintenance, testing, and postulated accident conditions—the 5.4.2.1-5 Revision 4 - July 2016 boundary behaves in a nonbrittle manner and the probability of rapidly propagating fracture is minimized. 7. 10 CFR 50.55a(c), 10 CFR 50.55a(d), and 10 CFR 50.55a(e) generally require certain grouping of components, including those compromising the RCPB or SSPB, to meet the requirements of Section III of the ASME Code. 8. Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50 applies to the steam generator materials. Of particular note is Criterion XIII, which requires, in part, that measures shall be established to control the handling, storage, shipping, cleaning, and preservation of material and equipment in accordance with work and inspection instructions to prevent damage or deterioration. 9. Appendix G, “Fracture Toughness Requirements,” to 10 CFR Part 50 requires, in part, that RCPB pressure-retaining components that are made of ferritic materials meet ASME Code requirements for fracture toughness during system hydrostatic tests and any condition of normal operation, including anticipated operational occurrences. 10. 10 CFR 52.47(b)(1) requires, in part, that a DC application contain the proposed 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 DC is built and will be operated in conformity with the DC, the provisions of the Atomic Energy Act, and the