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:
erials have been identified and are considered acceptable. Compliance with the above Code provisions for material specifications satisfies the quality standards requirements of GDC 1, GDC 30, and §10 CFR 50.55a. In addition, the use of 86 austenitic stainless steel in BWR reactor vessel attachments and appurtenances conforms with the staff positions in Generic Letter 88-01 or the recommendations of NUREG-0313, Revision 2.87 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 submitted 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 requirements of GDC 1, GDC 30, and §10 CFR 50.55a. In addition, 88 the use of austenitic stainless steel in BWR reactor vessel attachments and appurtenances conforms with the staff positions in Generic Letter 88-01 or the recommendations of NUREG-0313, Revision 2.89 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. Demonstrations have been made using these special techniques and have satisfied all requirements of the Code. The special methods of nondestructive examination are deemed acceptable. This acceptability based on the Code provisions satisfies the quality standards requirements of GDC 1, GDC 30, and §10 CFR 50.55a. 90 4. Special controls and special welding processes used for welding the reactor vessel and its appurtenances have been identified and found to be qualified in accordance with the requirements of Code Sections III and IX. Qualification in