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:
the Thermal Annealing Plan, and prior to restart, the NRC will (1) briefly document whether the thermal an nealing was performed in compliance with the licens ee's Thermal Annealing Operating Plan and the Re qualification Inspection and Test Program, with the documentation to be placed in the NRC Public Docu ment Room, and (2) hold a public meeting on the an nealing. The purposes for the public meeting are to (1) permit the licensee to explain the results of the reactor vessel annealing to the NRC and the public, (2) allow the NRC to discuss its inspection of the reac tor vessel annealing, and (3) provide an opportunity for the public to comment to the NRC on the thermal annealing. The licensee may restart its reactor after the meeting has been completed, unless the NRC orders otherwise. Within 45 days of the licensee's written con firmation that the thermal annealing was completed in accordance with the Thermal Annealing Operating Plan and the Requalification Inspection and Test Pro gram, the NRC staff will complete full documentation of the NRC's inspection of the licensee's annealing process and place the documentation in the NRC Pub lic Document Room. 1.162-17 5.2 Annealing Completed, Not in Compliance If the thermal annealing was completed but not performed in accordance with the Thermal Annealing Operating Plan and the Requalification Inspection and Test Program, including the bounding conditions of the temperature and times, the licensee must submit a summary of lack of compliance and a justification for subsequent operations. The licensee must also identify any changes to the facility that are attributable to the noncompliances that constitute unreviewed safety questions and any changes to the technical specifica tions that are required for operation as a result of the noncompliances. This identification does not relieve the licensee from complying with applicable require ments of the Commission's regulations and the operat ing license; and if these