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:
for demonstrating equivalence to the margins of safety in Appendix 0 of the ASME Code (Ref. 3). Several examples using these proc dures are presented in Appendix A to this guide and in more detail in NUREG/CR-6023 Ref. 4). This regulatory guide contains information collections that are subject to the Paperwork Reduction Act of 1980 (44 U.SC. 3501 et seq.). This regulatory guide has been submit ted to the Office of Management and Budget for review and approval of the information collections. These information collections and record keeping are needed for demonstrating compliance with Appendix 0 to 10 CFR Part 50 for the remaining duratienofthe plants license if Charpy upper-shelf energy ofthe materials in the beitline region may drop, or may have dropped, below the 50 ft-lb regulatory limit The public reporting burden for this collection of information is estimated to average 960 hours per response, including the time for reviewing instructions, semrcing existing data sources, gathering and mAinta;nin the data needed, and completing and reviewing the collection of ifnnation. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for further reducing the reporting burden, to the Information and Records Management Branch (T6F33), U.S. Nulear Regulatory Caomission, Washington DC 20555; and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0011), Office of Management and Budget, Washington, DC 20503. B. DISCUSSION The problem of evaluating materials that do not satisfy the 50 ft-lb upper-shdf enry requirement was recognized by the NRC staff several years ago and was designated Unre solved Safety Issue A-1 1, "Reactor Vessel Materials Tough ness." In 1982, the staffcompleted resolution ofUSI A-l I by issuing NUREG-0744, "Resolution of the Task A-1l Reactor "Vessel Materials Toughness Safety Issue (Ref. 5), which provided methods for evaluating the fracture behavior of