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:
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 to Annealing of Reactor Pressure 1Copies are available for inspection or copying for a fee from the NRC Public Document Room at 2120 L Street NW., Washing ton, DC; the PDR's mailing address Is Mail Stop LL-6, Wash ington, DC 20555-0001; telephone (202)634-3273; fax (202)634-3343. Copies may be purchased at current rates from the U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328 (telephone (202) 512-1800) or from the National Technical Information Service by writing NTIS at 5285 Port Royal Road, Springfield, VA 22161. > 2Copies may be purchased from EPRI's Research Reports Cen ter, P.O. Box 50490, Palo Alto, CA 94303 (telephone (415)965-4081). Vessel Steels," NUREG/CR-6327 (MCS 950302), May 1995.3 9. American Society for Testing and Materials, "Recommended Guide for In-Service Annealing of Water-Cooled Nuclear Reactor Vessels," ASTM E 509-86, Philadelphia, 1986. 10. NRC, "Additional Requirements for Yankee Rowe Pressure Vessel Issues," SECY-91-333, October 22, 1991.3 11. NRC, "Action Plans To Implement the Lessons Learned from the Yankee Rowe Reactor Vessel Embrittlement Issue," SECY-92-283, Au gust 14, 1992.3 12. NRC, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," NUREG-0800, June 1987.1 13. American Society of Mechanical Engineers, "Rules for Construction of Nuclear Power Plants," Section III, Division 1, Subsection NB, of ASME Boiler and Pressure Vessel Code, New York, 1993. 14. American Society for Testing and Materials, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactors," ASTM E 185-82, Philadelphia, 1982. 15. American Society of Mechanical Engineers, "Nuclear Power Plant Components," Section III, Division 2, of the ASME Boiler and Pressure Vessel