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:
s reviewed to ensure that such components will behave in a nonbrittle manner and that the probability of rapidly propagating fracture will be minimized under operating, maintenance, and testing condi- tions and during anticipated operational occurrences. The review includes the descriptions of the fracture toughness tests performed on all ferritic materials used for the reactor vessel and appurtenances thereto, and includes Charpy V-notch impact test specimens, dropweight test specimens, and any other test specimens included by the applicant. The test procedures specified by the applicant are reviewed and their ade- quacy is confirmed. The composition of ferritic materials employed for the reactor vessel is reviewed and the amount of residual elements such as copper and phosphorus is checked. The results of impact tests performed on base material, weld metal, and heat-affected zones are reviewed, and the scope of the testing is checked, particularly in the area of the reactor vessel beltline region, where radiation effects on the material are most significant. Fracture toughness of the materials employed is characterized by its ref- erence temperature, RTNDT. This temperature is the higher value of the nil-ductility temperature (NDT) from the dropweight test, or the temperature that is 60?F below the temperature at which Charpy V-notch impact test data meet a specified toughness level. The information submitted is checked to ensure that the RTNDT of the materials is included with the data and test results for impact testing. 6. Material Surveillance | Reactor vessel material surveillance must be performed to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region of water-cooled power reactors, resulting from exposure to neutron irradiation and the thermal environment. Under the surveillance programs, fracture toughness test data are obtained from material specimens withdrawn periodically from the reactor