Document: NUREG-0800
Document ID: 6cdd237d-c5b3-4a09-8753-54cfe1fea503
Document Type: srp
Title: REACTOR VESSEL MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190007.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.1
CFR Part: 
CFR Title: 

Content:
plicable. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. Implementation schedules for conformance to parts of the methods discussed herein are contained in the referenced regulations and regulatory guides. Acceptable repairs and upgrades are described in the referenced generic letter for previously accepted materials and welds that do not meet NUREG-0313, Revision 2 recommendations related to material specifications and post-weld treatments for stress corrosion cracking resistant installations. NUREG-0313, Revision 2 recommendations for stress corrosion cracking resistant installations will be used by the staff for evaluation of reactor vessel attachments and appurtenances in new BWR applications. VI. REFERENCES 1. 10 CFR 50.55a, “Codes and Standards.” 2. 10 CFR 50.60, “Acceptance Criteria for Fracture Prevention Measures for Light water Nuclear Power Reactors for Normal Operation.” 3. 10 CFR 50.61, “Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.” 4. 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 1, “Quality Standards and Records.” 5. 10 CFR Part 50, Appendix A, GDC 4, “Environmental and Dynamic Effects Design Bases.” 6. 10 CFR Part 50, Appendix A, GDC 14, “Reactor Coolant Pressure