Document: NUREG-0800
Document ID: 6cdd237d-c5b3-4a09-8753-54cfe1fea503
Document Type: srp
Title: REACTOR VESSEL MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190007.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.1
CFR Part: 
CFR Title: 

Content:
0 CFR Part 50 and 10 CFR 50.61(b)(2) (for PWRs) shall be met. i. SRP Section 5.3.2 discusses the requirements of paragraphs IV.A.2 and of Appendix G in detail. ii. The acceptance criteria discussed in paragraph IV.A.1 of Appendix G states that reactor vessel belt-line materials shall have a minimum upper shelf energy of 102 J (75 ft-lbs) as determined from Charpy V-notch impact tests on unirradiated specimens in accordance with paragraph NB-2331(a) of the Code, Section III. Reactor vessel belt-line materials must also maintain an upper shelf energy no less than 68 J (50 ft-lb) throughout the life of the vessel. These two requirements do not apply, however, if it is demonstrated to the Commission by appropriate data and analyses based on other types of tests that lower values of upper shelf fracture energy are adequate. C. The neutron radiation embrittlement effects on reactor vessel materials shall be determined in accordance with 10 CFR Part 50, Appendix G, Section III, and RG 1.99, “Radiation Embrittlement of Reactor Vessel Materials.” 6. Material Surveillance. The material surveillance acceptance criteria are the requirements of Section III of Appendix H of 10 CFR Part 50. Complying with the acceptance criteria satisfies the requirements of GDC 32 regarding an appropriate material surveillance program for the reactor vessel. Section III of Appendix H requirements are: A. No material surveillance program is required for reactor vessels for which it can be conservatively demonstrated by analytical methods applied to experimental data and tests performed on comparable vessels, making appropriate allowances for all uncertainties in the measurements, that the peak neutron fluence (E > 1 MeV) at the end of the design life of the vessel will not exceed 1017 n/cm2. Revision 2 - March 2007 5.3.1-9 B. Reactor vessels constructed of ferritic materials which do not meet the conditions in paragraph a. shall have their belt-line regions monitored by a surveillance program