Document: NUREG-0800
Document ID: 2adccc8f-d828-4baf-b696-6ee4f776837b
Document Type: srp
Title: REACTOR INTERNAL AND CORE SUPPORT MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070416.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.5.2
CFR Part: 
CFR Title: 

Content:
satisfactory use in similar applications) or presented by the applicant to support use of the material. Particular review emphasis is placed upon the corrosion resistance and stress corrosion cracking resistance properties of the proposed nickel-chromium-iron alloy(s).58 6. Additional Information Request If the information contained in the SAR does not comply with the appropriate acceptance criteria, or if the information provided is inadequate to establish such compliance, the reviewer prepares a request for additional information for transmittal to Project Management. Such requests not only identify the additional information required, but also specify the changes needed in the SAR or the plant Technical Specifications to meet acceptance criteria. Subsequent amendments received in response to these requests are reviewed for compliance with the acceptance criteria. 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.59 IV. EVALUATION FINDINGS The reviewer verifies that sufficient and adequate information has been provided to satisfy the requirements of the SRP section, and that histhe evaluation supports conclusions of the 60 following type, to be included in the staff's safety evaluation report: The staff concludes that the materials used for the construction of the reactor internals and core support structures are acceptable and meet the requirements of General Design 61 Criterion 1 and Section 50.55a of 10