Document: NUREG-0800
Document ID: d4acff25-51e1-4891-b590-9ad78ef4833e
Document Type: srp
Title: REACTOR VESSEL MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340633.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.1
CFR Part: 
CFR Title: 

Content:
require- ments are met. IV. EVALUATION FINDINGS The reviewer verifies that sufficient and adequate information has been provided to satisfy the requirements of the SRP section, and that his evaluation supports 5.3.1-1.0 Rev. 1 - July 1981 the conclusions of the following type, to be ihcluded in the staff's safety evaluation report. The staff concludes that the reactor vessel materials are acceptable and meet the requirements of General Design Criteria 1, 4, 14, 30, 31, and 32 of Appendix A of 10 CFR Part 50; the material testing and monitoring requirements of Appendices B, G, and H of 10 CFR Part 50; and the requirements of §50.55a of 10 CFR Part 50. This conclusion is based on the following: 1. The materials used for construction of the reactor vessel and its appur- tenances have been identified by specification and found to be in confor- mance with Section III of the ASME Code. Special requirements of the applicant with regard to control of residual elements in ferritic materials have been identified and are considered acceptable. Compliance with the above Code provisions for material specifications satisifies the quality standards requirements of GDC 1, GDC 30, and §50.55a. 2. Special processes used for manufacture or fabrication of the reactor vessel and its appurtenances have been identified, and appropriate data reports on each process as required by Section III of the ASME Code have been sub- mitted by the applicant. Since certification has been made by the applicant that the materials and fabrication requirements of Section III of the Code have been complied with, the special processes used are considered acceptable. Compliance with these Code provisions meets the quality standards require- ments of GDC 1, GOC 30, and §50.55a. 3. Special methods used for nondestructive examination of the reactor vessel and its appurtenances have been identified and have been found equivalent or superior to the techniques described in Appendix X of Code Section III.