Document: NUREG-0800
Document ID: f5ae448a-20e3-4127-90a9-888a9b291921
Document Type: srp
Title: REACTOR VESSEL INTEGRITY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340640.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.3
CFR Part: 
CFR Title: 

Content:
gnificantly under service conditions; (6) may be annealed to restore the material toughness properties if this becomes necessary; and 5.3.3-6 Rev. 1 - July 1981 - (7) will be subjected to surveillance to account for neutron irradiation damage so that the operating limitations may be adjusted. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regard- ing the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of con- formance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guide. VI. REFERENCZS 1. Standard Review Plan Section 5.2.3, "RCPB Materials." 2. Standard Review Plan Section 5.2.4, "RCPB Inservice Inspection and Testing." 3. Standard Review Plan Section 5.3.1, "Reactor Vessel Materials." 4. Standard Review Plan Section 5.3.2, "Pressure-Temperature Limits." 5. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants." (Criterion 1, "Quality Standards and Records;" Criterion 4, "Environmental and Missile Design Bases;" Criterion 14, "Reactor Coolant Pressure Boundary;" Criterion 30, "Quality of Reactor Coolant Pressure Boundary;" Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary;" and Criterion 32, "Inspection of Reactor Coolant Pressure Boundary.") 6. 10 CFR Part 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." 7. 10 CFR Part 50, Appendix G, "Fracture Toughness Requirements." 8. 10 CFR Part 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements." 9. 10 CFR Part 50, Section 50.55a, "Codes and Standards." 10. ASME Boiler and Pressure Vessel Code, Section III, especially Appendix G,