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:
t Branch (T-6 F 33), U.S. Written comments may be submitted to the Rules Review and Directives Branch, DFIPS, ADM, U.S. Nuclear Regulatory Commission, Washing ton, DC 20658-0001. The guides are issued in the following ten broad divisions: 1. Power Reactors 6. Products 2. Research and Test Reactors 7. Transportation 3. Fuels and Materials Facilities 8. Occupational Health 4. Environmental and Siting 9. Antitrust and Financial Review 5. Materials and Plant Protection 10. General Single copies of regulatory guides may be obtained free of charge by writ the Office of Administration, Attention: Distribution and Services tion, U.S. Nuclear Regulatory Commission. Washington, OC 20655-0001. or by fax at (301)415-2260. Issued guides may also be purchased from the National Technical Infor mation Service on a standing order basis. Details on this service may be obtained by writing NTIS, 6285 Port Royal Road, Springfield, VA 22161. REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.162 (Draft was Issued as DG-1027) FORMAT AND CONTENT OF REPORT FOR THERMAL ANNEAUNG OF REACTOR PRESSURE VESSELS Nuclear Regulatory Commission, Washington, DC 20555-000 1; and to the Desk Officer, Office of Infor mation and Regulatory Affairs, NEOB-10202 (3150-0011), Office of Management and Budget, Washington, DC 20503. B. DISCUSSION BACKGROUND Criterion 31 of Appendix A, "General Design Cri teria for Nuclear Power Plants," to 10 CFR Part 50 requires that: The reactor shall be designed with sufficient margin to assure that when stressed under op erating, maintenance, testing, and postulated accident conditions, (1) the boundary behave in a nonbrittle manner and (2) the probability of rapidly propagating fracture is minimized. A major concern in this regard is that the material properties of reactor vessels degrade progressively when exposed to neutron radiation during service, re sulting in a loss in fracture toughness and ductility. To maintain adequate toughness and preclude