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:
nreviewed Safety Questions and Technical Specification Changes. The rule also provides three methods for deter mining the percent recovery. When surveillance speci-. mens are available from a credible surveillance pro gram, the percent recovery for the reactor vessel is required to be determined by using a test program that applies the actual annealing conditions to the irra diated surveillance specimens. If surveillance speci mens are not available, the applicant may elect to de termine the percent recovery by testing materials removed from the reactor vessel beltline region. The third method permits uses of a generic computational method if adequate justification is provided. Use of the procedure described in this regulatory guide in Sec tion 3.1.3, "Computational Methods," is considered appropriate justification for this application. Upon completion of the thermal annealing and the associated tests and analyses, the applicant must con firm in writing to the Director of the Office of Nuclear Reactor Regulation (NRR) that the thermal anneal was performed in accordance with the Thermal Annealing Operating Plan and the Requalification Inspection and Test Program. Within 15 days of the licensee's written confirmation that the thermal annealing was com pleted in accordance with the Thermal Annealing 1.162-3 Plan, and prior to restart, the NRC will (1) briefly doc ument whether the thermal annealing was performed in compliance with the licensee's Thermal Annealing Operating Plan and the Requalification Inspection and Test Program, placing the documentation in the NRC Public Document Room, and (2) hold a public meeting to permit the licensee to explain the results of the reac tor vessel annealing to the NRC and the public, allow the NRC to discuss its inspection of the reactor vessel annealing, and 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