Document: NUREG-0800
Document ID: d4acff25-51e1-4891-b590-9ad78ef4833e
Document Type: srp
Title: REACTOR VESSEL MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340633.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.1
CFR Part: 
CFR Title: 

Content:
DT is the higher of TNOT and (Tcv - 60?F). (4) When a Cv impact test has not been performed at (TNDT + 60?F), or when the Cv impact test at (TNDT + 60'F) does not exhibit a minimum of 50 ft-lbs and 35 mils lateral expansion, a temperature representing a minimum of 50 ft-lbs and 35 mils lateral expansion may be obtained from a full Cv impact curve developed from the minimum data points of all the Cv impact tests performed. b. In addition to the above criteria, the requirements of paragraphs IV.A.2 and 3 and IV.B of Appendix G of 10 CFR Part 50 shall be met. (1) Standard Review Plan Section 5.3.2, "Pressure-Temperature Limits," discusses the requirements of paragraphs IV.A.2 and 3 of Appendix G in detail. (2) The acceptance criteria discussed in paragraph IV.B of Appendix G states that reactor vessel beltline materials shall have a minimum upper-shelf energy as determined from Charpy V-notch impact tests on unirradiated specimens in accordance with paragraph NB-2322a | of the Code, Section III, of 75 ft-lbs unless 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. 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 5.3.1-6 Rev. 1 - July 1981 that have been verified by experimental data and tests performed on comparable vessels, making appropriate allowances for all uncertain- ties 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. b. Reactor vessels constructed