Document: NUREG-0800
Document ID: 34798f4a-fe75-475a-b41f-ffb023158358
Document Type: srp
Title: 2.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070367.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.2.15
CFR Part: 
CFR Title: 

Content:
rmations are reviewed to determine that they do not exceed the specified limits. 3.9.5-7 DRAFT Rev. 3 - April 1996 Any deviations that have not been adequately justified are identified and findings to that effect are transmitted to the applicant with a request for conformance with the requirements discussed in subsection II, above, or additional technical justification. 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.41 IV. EVALUATION FINDINGS The reviewer verifies that sufficient information has been provided in accordance with this SRP section and that histhe evaluation supports conclusions of the following type, to be included in 42 the staff's safety evaluation report: The staff concludes that the design of reactor internals is acceptable and meets the requirements of General Design Criteria 1, 2, 4, and 10 and 10 CFR Part 50, §50.55a. This conclusion is based on the following: 1. The applicant has met the requirements of GDC 1 and 10 CFR Part 50, §50.55a with respect to designing the reactor internals to quality standards commensurate with the importance of the safety functions to be performed. The design procedures and criteria used for the reactor internals are in conformance with the requirements of Subsection NG of the ASME Code, Section III. 2. The applicant has met the requirements of GDCs 2, 4, and 10 with respect to 43 designing components important to safety to withstand the effects of