Document: NRC Regulatory Guide
Document ID: 5f4d6577-6c2a-473a-9a76-4033a95dba4c
Document Type: regulatory_guide
Title: Radiation Embrittlement of Reactor Vessel Materials (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003740284.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.99
CFR Part: 
CFR Title: 

Content:
72 298 216 245 275 303 220 248 278 308 223 250 281 313 227 254 285 317 231 257 288 320 D. IMPLEMENTATION The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide. Except in those cases in which an applicant pro- poses an acceptable alternative method for complying with specified portions of the Commission's regulations, the methods described in this guide will be used as follows: 1. The methods described in Regulatory Positions 1 and 2 of this guide will be used by the NRC staff in evaluating all predic- tions of radiation embrittlement needed to implement Appendices G and H to 10 CFR Part 50. 2. Holders of licenses and permits should use the methods described in this guide to predict the effect of neutron radiation on reactor vessel materials as required by Paragraph V .A of Appen- dix G to 10 CFR Part 50, unless they can justify the use of dif- ferent methods. The use of the Revision 2 methodology may result in a modification of the pressure-temperature limits contained in Technical Specifications in order to continue to satisfy the requirements of Section V of Appendix G, 10 CFR Part 50. 3. The recommendations of Regulatory Position 3 are essen- tially unchanged from those used to evaluate construction permit applications docketed on or after June 1, 1977. 1.99-6 j J REFERENCES 1. American Society for Testing and Materials, "Standard Prac- tice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," ASTM E 185-82, July 1982. * 2. G. L. Guthrie, "Charpy Trend Curves Based on 177 PWR Data Points," in "L WR Pressure Vessel Surveillance Dosimetry Im- provement Program," NUREG/CR-3391, Vol. 2, prepared by Hanford Engineering Development Laboratory, HEDL-TME 83-22, April 1984. "'* 3. G. R. Odette et al., "Physically Based Regression Correlations of Embrittlement Data from Reactor Pressure Vessel Surveillance Programs," Electric Power Research