Document: NUREG-0800
Document ID: bf62536e-58c7-4cb0-a51f-5c5ce2c21d6b
Document Type: srp
Title: DRAFT Rev. 2 - April
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070423.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.2.9
CFR Part: 
CFR Title: 

Content:
C) 1 and 30, as they relate to quality standards for design, 17 fabrication, erection, and testing of structures, systems and components; 3B. General Design Criterion 4, as it relates to compatibility of components with environmental conditions; 4C. General Design Criterion 14, as it relates to prevention of rapidly propagating fractures of the RCPB; 5D. General Design Criterion 31, as it relates to material fracture toughness; 6E. General Design Criterion 32, as it relates to the requirements for a materials surveillance program; 5.3.1-5 DRAFT Rev. 2 - April 1996 1F. Section10 CFR Part 50, § 50.55a, as it relates to quality standards for design, and 18 determination and monitoring of fracture toughness; G. 10 CFR Part 50, §50.60, "Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation," as it relates to reactor coolant pressure boundary fracture toughness and material surveillance requirements of 10 CFR 50, Appendix G and Appendix H;19 7H. 10 CFR Part 50, Appendix B, Criterion XIII, as it relates to onsite material cleaning 20 21 control; 8I. 10 CFR Part 50, Appendix G, as it relates to materials testing and acceptance criteria 22 for fracture toughness; and 9J. 10 CFR Part 50, Appendix H, as it relates to the determination and monitoring of 23 fracture toughness. Specific criteria necessary to meet the relevant requirements of 10 CFR Part 50, § 50.55a; GDC 1, 4, 14, 30, 31, and 32; and Appendices B, G, and H the Commissions regulations identified above are as follows for each review described in subsection I of this SRP section: 24 1. Material Specifications The requirements of GDC 1 and 30 and §10 CFR 50.55a regarding quality standards 25 are met by compliance with the provisions of the ASME Code, Section III, for material specifications, as detailed below: a. Acceptable material specifications for the reactor vessel and its appurtenances are those listed in the Code, Section III, Appendix I, and are