Document: NUREG-0800
Document ID: bf62536e-58c7-4cb0-a51f-5c5ce2c21d6b
Document Type: srp
Title: DRAFT Rev. 2 - April
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070423.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.2.9
CFR Part: 
CFR Title: 

Content:
n III, for material specifications, as detailed below: a. Acceptable material specifications for the reactor vessel and its appurtenances are those listed in the Code, Section III, Appendix I, and are presented in detail in Code Section II, Parts A, B, and C. The materials must also meet the specifications requirements of 10 CFR Part 50, Appendix G. b. The acceptability of materials not specified in the Code are considered on an individual basis. Their suitability is evaluated on the basis of data submitted in accordance with the requirements of Code Section III, Appendix IV-1400 and 10 CFR Part 50, Appendix G. These data must include information on mechanical properties, weldability, and physical changes of the material. 2. Special Processes Used for Manufacture and Fabrication of Components The requirements of GDC 1 and 30 and §10 CFR 50.55a regarding quality standards 26 are met by compliance with the provisions of the ASME Code, Section III, for fabrication of components. The reactor vessel and its appurtenances are fabricated and installed in accordance with Code Section III, Paragraph NB-4100. The manufacturer or installer of such components is required to certify, by application of the appropriate Code Symbol and completion of an appropriate data report in accordance with Code Section III, Paragraph NA-8000 , that the materials used comply with the requirements of 27 DRAFT Rev. 2 - April 1996 5.3.1-6 NB-2000, and that the fabrication or installation comply with the requirements of NB-4000. 3. Special Methods for Nondestructive Examination The requirements of GDC 1 and 30 and §10 CFR 50.55a regarding quality standards 28 are met by compliance with the ASME Code, Section III, for fabrication nondestructive testing. The acceptance criteria for examination of the reactor vessel and its appurtenances by nondestructive examination are those specified in Code Section III, NB-5000, for normal methods of examination. When special techniques or procedures are