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:
UREG-0313, Revision 2, because the controls used 102 5.3.1-19 DRAFT Rev. 2 - April 1996 provide assurance that welded components will not be contaminated nor sensitized prior to and during the welding process. These controls satisfy the quality standards requirement of GDC 1, GDC 30, and §10 CFR 50.55a and the 103 GDC 4 requirement relative to material compatibility. b. The controls regarding onsite cleaning and cleanliness control of austenitic stainless steel are in conformance with the recommendations of Regulatory Guide 1.37, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants," because the controls used provide assurance that austenitic stainless steel components will be properly cleaned onsite. The controls satisfy Appendix B of 10 CFR Part 50 regarding controls for onsite cleaning of materials and components. 8. Fracture toughness of the reactor vessel and its appurtenances is controlled by conformance with Appendix G, to 10 CFR Part 50, which specifies ASME Code 104 provisions and supplementary requirements of Appendix G, to 10 CFR Part 50. The 105 fracture toughness tests required by the ASME Code and by Appendix G of to 10 CFR Part 50 provide reasonable assurance that adequate safety margins against the 106 possibility of non-ductile behavior or rapidly propagating fracture can be established for all pressure-retaining components of the reactor coolant boundary. The use of Appendix G of the Code as a guide in establishing safe operating procedures, andthe use of the results of the fracture toughness tests performed in accordance with the Code and NRC regulations, and the implementation of the material surveillance program in accordance with 10 CFR 50 Appendix G and Appendix H, will provide adequate safety margins during operating, testing, maintenance, and postulated accident conditions for the service life of the reactor vessel. Compliance with the provisions of Appendix G, to 10