Document: NRC Regulatory Guide
Document ID: a2b67b51-f5fe-4c86-a879-f0e439601f7f
Document Type: regulatory_guide
Title: Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003740052.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.162
CFR Part: 
CFR Title: 

Content:
al effects, if any, on containment and the biological shield. Maxi mum concrete temperatures should be based on exist ing design limits or provisions of Section III, Division 2, of the ASME Boiler and Pressure Vessel Code (Ref. 15). If the design temperature limits or the ASME Boiler and Pressure Vessel Code limits for the adjacent concrete structure are projected to be ex ceeded during the annealing operation, an acceptable maximum temperature for the concrete must be estab fished using appropriate test data. Test data on proper ties should address irradiated concrete of appropriate type and exposures to time-temperature conditions that bound the expected conditions of the concrete during annealing. The structural analysis should evaluate, for the complete annealing cycle, residual deformations, re sidual stresses, elastic-plastic-creep effects (Ref. 16), distortions, bending, piping displacements, effects of thermal gradients (axial, azimuthal, and through wall), and restraints on the vessel, including nozzles and flange and attached piping. Any potential interfer ence with other equipment, components, or supports should be evaluated. This section should specify the limiting parameters established by these analyses, in cluding maximum temperature, maximum stress, and limiting heatup and cooldown rates. 1.5 Thermal Annealing Operating Conditions This section of the report should describe the pro posed thermal annealing operating conditions, includ ing bounding conditions of temperature and time, and heatup and cooldown schedules. The annealing parameters should be selected to provide sufficient re covery of fracture toughness to satisfy the require ments of 10 CFR 50.60 and 10 CFR 50.61, or any other objective identified in the application, for the proposed post-anneal period of operation. The anneal ing parameters should be compatible with design stress limits of the reactor and any other component or 1.162-6 K K structure expected to experience significant