Document: NUREG-0800
Document ID: 48fcca4d-4efe-4600-b4ca-9911efb87843
Document Type: srp
Title: and 5.2.1.2.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070446.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.1.1
CFR Part: 
CFR Title: 

Content:
hods to be used for removal of surface deposits, sludge, and corrosion products from the tube sheet and the tube/tube support areas. For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report, including inspections, tests, analysis, and acceptance criteria (ITAAC), site interface requirements and combined license action items, meet the acceptance criteria given in subsection II. SRP Section 14.3 (proposed) contains procedures for the review of certified design material (CDM) for the standard design, including the site parameters, interface criteria, and ITAAC.47 IV. EVALUATION FINDINGS The reviewer verifies that sufficient information is provided in accordance with the requirements of this SRP section and that histhe evaluation supports conclusions of the following type, 48 which are to be included, as applicable, in the staff's safety evaluation report: 49 The staff concludes that the steam generator materials specified are acceptable and meet the requirements of GDC 1, 14, 15, and 31, and Appendix B to 10 CFR Part 50. This conclusion is based on the following: 1. The applicant has met the requirements of GDC 1 with respect to codes and standards by assuring that the materials selected for use in Class 1 and Class 2 components will be fabricated and inspected in conformance with codes, standards, and specifications acceptable to the staff. Welding qualification, fabrication, and inspection during manufacture and assembly of the steam generator will be done in conformance with the requirements of Sections III and IX of the ASME Code. 2. The requirements of GDC 14 and 15 have been met to assure that the reactor coolant boundary and associated auxiliary systems have been designed, fabricated, erected, and tested so as to have an extremely low probability of abnormal leakage, of rapid