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:
ovide 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 CFR 107 Part 50, satisfies the requirements of GDC 14, GDC 31, and §10 CFR 50.55a, and 10 108 109 CFR 50.60 regarding prevention of fracture of the reactor coolant pressure boundary. 110 9. Changes in the fracture toughness of material in the reactor vessel beltline caused by exposure to neutron radiation have been assessed properly, and adequate safety margins against the possibility of vessel failure are provided as the material surveillance requirements of ASTM E- 185 and Appendix H, to 10 CFR Part 50, are met. 111 112 Compliance with these documents assures that the surveillance program constitutes an acceptable basis for monitoring radiation-induced changes in the fracture toughness of the reactor vessel material and satisfies the requirements of GDC 32 and 10 CFR 50.60113 regarding an appropriate material surveillance program for the reactor vessel. 10. Integrity of the reactor vessel studs and fasteners is assured by conformance with the recommendations of Regulatory Guide 1.65, "Materials and Inspections for Reactor Vessel Closure Studs." Compliance with these recommendations satisfies the quality standards requirements of GDC 1, GDC 30, and §10 CFR 50.55a; the prevention of 114 fracture of the RCPB requirement of GDC 31; and the requirements of Appendix G, to 10 CFR Part 50, as detailed in the provisions of the ASME Code, Sections II and III. 115 For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff's evaluation of inspections, DRAFT Rev. 2 - April 1996 5.3.1-20 tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP