Document: NUREG-0800
Document ID: 866c6ef6-2f4a-45c7-9e71-43e1f66a8422
Document Type: srp
Title: Draft Revision 3– July 2018
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1807/ML18071A066.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5
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Content:
alue obtained was less than 61 J (45 ft-lbs), the RTNDT may be estimated as 11 °C (20 °F) above the test temperature. 1.2 Estimation of Charpy V-Notch Upper Shelf Energies For the beltline region of reactor vessels, the upper shelf toughness must account for the effects of neutron radiation. Reactor vessel beltline materials must have Charpy upper shelf energy, in the transverse direction for base material and along the weld for weld material in accordance with the ASME Code, of no less than 102 J (75 ft-lbs) initially and must maintain Charpy upper shelf energy throughout the life of the vessel of no less than 68 J (50 ft-lbs). Beltline materials are defined to be those materials directly surrounding the effective height of the active core and adjacent materials estimated to receive a neutron fluence of 1 x 1017 n/cm2 (E > 1.0 MeV) or higher. This definition, which is derived from the definition of beltline in 10 CFR 50.61 and considers the neutron fluence zone of interest as defined in Appendix H(III)(a), 10 CFR Part 50, is consistent with NRC BTP 5-3-4 Draft Revision 3 – July 2018 Regulatory Issue Summary 2014-11, “Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components.” If Charpy upper shelf energy values were not obtained, conservative estimates should be made using results of tests on specimens from the first surveillance capsule removed. If tests were only made on longitudinal specimens, the values should be reduced to 65 percent of the longitudinal values to estimate the transverse properties. The predicted end-of-license (EOL) Charpy upper shelf energy and adjusted reference temperature for the reactor vessel materials must meet the requirements of 10 CFR Part 50, Appendix G, paragraph IV.A. Reactor vessel materials that do not meet the specified EOL acceptance criteria should be reviewed through an equivalent margins analysis in accordance with the same paragraph of 10 CFR