Document: NRC Regulatory Guide
Document ID: 2704425a-c58a-45c4-93ab-8761721c3e7a
Document Type: regulatory_guide
Title: Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003740038.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.161
CFR Part: 
CFR Title: 

Content:
tions of the Commission's regulations, the methods descnled in this guide reflecting public comments will be used by tlhe NRC staff in the evaluation of applications fornew licenses and for evaluating compliance with Appendix Gto 10 CFR Part 50. 1.161-11 REFERENCES 1. American Society for Testing and Materials, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vesses," ASTM E 185-79, July 1979.' 2. American Society for Testing and Materials, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactors, ASTM E 185-82, July 1982.' 3. American Society ofMechanical Engineers, Section XI, Division 1, "Rules for Inservice Inspection of Nuclear Power Plant Components,* of the ASVE Boiler and Pressure Vessel Code, New York, through 1988 Addenda and 1989 Edition.2 4. TL Dickson, Genric Analyses for Evalualion ofLow Charpy Upper-Shelf Energy Effects on Safety Margins Against Fracture of Reactor Pressure Vessel Materials," USNRC, NUREG/CR-6023, July 1993.3 5. R. Jdmson, "Resolution of the Task A-II Reactor Vessel Materials Toughness Safety Issue," USNRC, NUREG-0744, Volume I (Revision 1) and Volume 2 (Revision 1), October 1982. 6. Generic Letter No. 82-26, "NUREO-0744 Rev. 1; Pressure Vessel Material Fracture Toughness," Issued by Darrel G. Eisenhut, Director, Division of Licensing NRR, USNRC, November 12, 1982.! 7. Letter from Warren H Bamford, Chairman of the ASME Subgroup on Evaluation Standards for ASME Section XI, to James E. Richardson, USNRC, Subject: Response to NRC Request, A-I l Issue, February 20, 1991.! 8. American Society of Mechanical Engineers, Assessment of Reactor Vessels with Low Upper Shelf Charpy Impact EncrU Levels," Appendix K, A93, pp. 482.1-482.15, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1992 Edition, 1993 Addenda, New York, December 1993. 9. American Society for Testing and Materials, "Standard Test Method for Determining J-R