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:
d instrumentation should be discussed in the operating plan. The temperature con trol system should be able to control temperatures suf ficiently to avert adverse effects from thermal gradients during heatup, annealing, and cooldown operations. 1.8 ALARA Considerations This section of the report should describe the steps to be taken to minimize occupational exposure, in 1.162-7 accordance with the "as low as is reasonably achiev able" (ALARA) principle and the provisions of 10 CFR 20.1206. Special training of the personnel who will actually perform the annealing operations should be described. Equipment and procedures for monitor ing and control of airborne radioactive particles during the operation should be identified. This section should specifically address precautions to be taken to avoid excessive exposure from radiation streaming when the reactor internals are being removed and stored, when the reactor coolant is removed from the reactor, and when the heating equipment is being moved into and out of the reactor vessel. It should also describe steps taken to minimize occupational exposure from radio active waste processing, radioactive materials decon tamination, and radioactive waste shipment. 1.9 Summary of the Thermal Annealing Operating Plan The Thermal Annealing Report should contain a summary of the Thermal Annealing Operating Plan that includes the highlights of each section, the key pa rameters of annealing, and the major conclusions of the plan. The projected percent recovery and the pro jected reembrittlement rate should be identified, as well as the projected end-of-license values of RTNDT and Charpy upper-shelf energy after annealing. 2. REQUALIFICATION INSPECTION AND TEST PROGRAM The inspection and test program to requalify the annealed reactor vessel should include the detailed monitoring, inspections, and tests proposed to demon strate that the limitations in the operating plan on tem peratures, heat treatment times, temperature profiles, and