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:
aterials shall have a minimum uppershelf energy as determined from Charpy V-notch impact tests on unirradiated specimens in accordance with paragraph NB-2322a of the 59 Code, Section III, of 102 J (75 ft-lbs) , and must maintain an upper shelf 60 energy no less than 68 J (50 ft-lb) throughout the life of the vessel unless 61 it is demonstrated to the Commission by appropriate data and analyses based on other types of tests that lower values of uppershelf fracture energy are adequate. c. The neutron radiation embrittlement effects on reactor vessel materials shall be determined in accordance with 10 CFR 50, Appendix G, Section V, and Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials." 5.3.1-9 DRAFT Rev. 2 - April 1996 Reactor vessel beltline materials for which either the predicted Charpy upper shelf energy at end of life is below 68 J (50 ft-lb), or the predicted adjusted reference temperature at end of life exceeds 93 C (200 F), must be designed to allow thermal annealing for the recovery of the material toughness properties. Alternatively, the requirements of 10 CFR 50, Appendix G, paragraph V.C may be met.62 6. Material Surveillance The material surveillance acceptance criteria are the requirements of Section II 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 II 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 that have been verified by 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/cm . 2 b. Reactor vessels constructed of ferritic materials which do not meet these conditions shall