Document: NUREG-0800
Document ID: b17adfa2-7bfa-4f7d-9b7b-7a5df200327f
Document Type: srp
Title: REACTOR INTERNAL AND CORE SUPPORT MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340586.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.5.2
CFR Part: 
CFR Title: 

Content:
of the materials and loss of component structural integrity. The material selection, fabrication practices, examination and testing proce- dures, and control practice performed in accordance to these recommendations provide reasonable assurance that the materials used for the reactor internal and core support structure will be in a metallurgical condition to preclude inservice deterioration. Conformance with requirements of the ASME Code and the recommendations of the regulatory guide constitutes an acceptable basis for meeting in part the requirements of General Design Criterion 1 and Section 50.55a of 10 CFR Part 50. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the staff's plan for implementing this section of the Standard Review Plan. Except in those cases in which the applicant proposes an acceptable alternate 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 conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Plants." 4.5.2-5 Rev. 2 - July 1981 2. 10 CFR Part 50, §50.55a, "Codes and Standards." 3. Regulatory Guide 1.31, "Control of Ferrite Content in Stainless Steel Weld Metal." 4. Regulatory Guide 1.44, "Control of the Use of Sensitized Stainless Steel." 5. Regulatory Guide 1.85, "Code Case Acceptability, ASME Section III Materials." 6. ASME Boiler and Pressure Vessel Code, Section II, Parts A, B, and C, Section III, and Section IX, American Society of Mechanical Engineers. 7. SRP Section 5.2.3, "Reactor Coolant Pressure Boundary Materials." 4.5.2-6 Rev. 2 - July 1981