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:
ng Plan and relevant portions of the Requalification Inspection and Test Program. The licensee may restart its reactor after the NRC places a summary of its inspection of the ther mal annealing in the Public Document Room and the NRC holds a public meeting on the thermal annealing. 5.3.2 Licensee Elects To Take Credit for any Recovery If the partial annealing was otherwise performed in accordance with the Thermal Annealing Operating Plan and relevant portions of the Requalification In spection and Test Program and the licensee elects to take full or partial credit for the partial annealing, the licensee must confirm in writing to the Director, NRR, that the partial annealing was otherwise performed in compliance with the Thermal Annealing Operating Plan and relevant portions of the Requlification In spection and Test Program. The licensee may restart its reactor after the NRC places a summary of its in spection of the thermal annealing in the NRC Public Document Room and the NRC holds a public meeting on the thermal annealing. 5.3.3 Termination, Not in Compliance If the partial annealing was not performed in ac cordance with the Thermal Annealing Operating Plan and relevant portions of the Requalification Inspection and Test Program, the licensee is to submit a summary of lack of compliance with the Thermal Annealing Op erating Plan and the Requalification Inspection and Test Program and a justification for subsequent opera tion, to the Director of NRR. Any changes to the facil ity as described in the updated final safety analysis re port that are attributable to the noncompliances and constitute unreviewed safety questions, and any changes to the technical specifications that are re quired as a result of the noncompliances, must also be identified. If no unreviewed safety questions or changes to technical specifications are identified, the licensee may restart its reactor after the NRC places a summary of its inspection of the thermal annealing in the Public Doc