Document: NUREG-0800
Document ID: 91fee075-c567-438d-bf9f-47be3177b457
Document Type: srp
Title: ENGINEERED SAFETY FEATURES MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070453.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.1.1
CFR Part: 
CFR Title: 

Content:
dix I of Section III, Division 1 of the ASME Code, and 99 Parts A, B, and C of Section II of the Code, and the staff position that the yield strength of cold-worked stainless steels shall be less than 620 MPa (90,000 psi). Fracture 100 toughness of the ferritic materials meets the requirements of the Code. The controls on the use and fabrication of the austenitic stainless steel of the systems satisfy the requirementspositions of Regulatory Guide 1.31, "Control of Ferrite 101 DRAFT Rev. 2 - April 1996 6.1.1-16 Content of Stainless Steel Weld Metal," and Regulatory Guide 1.44, "Control of the Use of Sensitized Stainless Steel." Fabrication and heat treatment practices performed in accordance with these requirementspositions provide added assurance that the 102 probability of stress corrosion cracking will be reduced during the postulated accident time interval. For BWRs, to assure adequate resistance against intergranular stress corrosion cracking, susceptible austenitic stainless steel piping appropriately conforms with the positions of Attachment A of Generic Letter 88-01 or the recommendations of NUREG-0313, Revision 2, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping."103 Conformance with the Codes and Regulatory Guides and with the staff positions mentioned above, constitute an acceptable basis for meeting the requirements of General Design Criteria 1, 4, 14, 35, and 41; Appendix B to 10 CFR Part 50, and 10 CFR Part 50, §50.55a, in which the systems are to be designed, fabricated, and erected so that the systems can perform their function as required. 2. General Design Criteria 1, 14, and 31 and Appendix B to 10 CFR Part 50 have been met with respect to assuring that the reactor coolant pressure boundary and associated 104 auxiliary systems have an extremely low probability of leakage, of rapidly propagating failures and of gross rupture. The controls placed on concentrations of leachable impurities in