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:
meeting are (1) for the licensee to explain to the NRC and the public the re sults of the reactor pressure vessel annealing, (2) for the NRC to discuss its inspection of the reactor vessel annealing, and (3) for the NRC to receive public com ments on the annealing. 7.3 NRC Inspection Report Within 45 days of NRC's receipt of a licensee's submittals described in Section 5 of this regulatory guide, the NRC staff will fully document its inspection of the licensee's annealing process and place this docu mentation in the NRC Public Document Room. 1-. 1.162-20 K REFERENCES 1. U. Potapovs, J. R. Hawthorne, and C. Z. Serpan, Jr., "Notch Ductility Properties of SM-1A Reac tor Pressure Vessel Following the In-Place Annealing Operation," Nuclear Applications, Vol. 5, No. 6, pp. 389-409, 1968. 2. A. Fabry et al., "Annealing of the BR-3 Reactor Pressure Vessel," in Proceedings of the Twelfth Water Reactor Safety Research Information Meeting, NUREG/CP-0058, Vol. 4, pp. 144-175, NRC, January 1985.1 3. N. M. Cole and T. Friderichs, "Report on An nealing of the Novovoronezh Unit 3 Reactor Ves sel in the USSR," NUREG/CR-5760 (MPR Associates, Inc., MPR-1230), NRC, July 1991. 4. W. L. Server, "In-Place Thermal Annealing of Nuclear Reactor Pressure Vessels," NUREG/ CR-4212 (EG&G Idaho, Inc., EGG-MS-6708), NRC, April 1985. 5. T. R. Mager, "Feasibility of and Methodology for Thermal Annealing an Embrittled Reactor Ves sel," EPRI NP-2712, Vol. 2, Electric Power Research Institute, Palo Alto, CA, November 1982.2 6. T. R. Mager et al., "Thermal Annealing of an Embrittled Reactor Vessel, Feasibility and Meth odology," EPRI NP-6113-SD, Electric Power Research Institute, Palo Alto, CA, January 1989.2 7. J. R. Hawthorne and A. L. Hiser, "Investigations of Irradiation-Anneal-Reirradiation (IAR) Prop erties Trends of RPV Welds-Phase 2, Final Re port," NUREG/CR-5492 (Materials Engineering Associates, Inc., MEA-2088), NRC, January 1990.1 8. E. D. Eason et al., "Models for Embrittlement Recovery Due