Document: NRC Regulatory Guide
Document ID: 5810150e-ee20-4cd1-b72f-6e918a603f73
Document Type: regulatory_guide
Title: Applications for Nuclear Power Plants (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1523/ML15233A056.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.206
CFR Part: 
CFR Title: 

Content:
n. SECY-91-178 & SRM-91-178 Title: Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for Design Certifications and Combined Licenses Content: SECY-91-178 describes how the ITAAC for design certification, the ITAAC associated with site-specific design information, and certain Tier 2 information could constitute a verification program to be implemented by the combined license holder. The form and content of the ITAAC document is proposed with an example. The SECY also describes how the successful completion of the ITAAC requirements and any other acceptance criteria in the combined license will constitute the basis for the NRC's determination to allow operation of the facility. 6 Excerpt from NEI 15-02, “Industry Guideline for the Development of Tier 1 and ITAAC under 10 CFR Part 52,” Draft A of Revision 0, issued May 2015 (Ref. 88), submitted to NRC for review and discussion on May 27, 2015 (ADAMS Accession No. ML15147A671) (Ref. 89).Although cited by NEI, these documents are available in the NRC Library on the NRC Web site. DG-1325, Page-70 SECY OR SRM NUMBER SECY TITLE/SECY CONTENT SECY-91-210 & SRM-91-210 Title: Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Requirements for Design Review and Issuance of a Final Design Approval (FDA) Content: SECY-91-210 requests Commission guidance on a policy matter related to an industry proposal that would allow the NRC staff to issue standardized plant final design approvals (FDAs) prior to final staff approval of the proposed ITAAC. SECY-92-053 Title: Use of Design Acceptance Criteria during 10 CFR Part 52 Design Certification Reviews Content: SECY-92-053 addresses design acceptance criteria (DAC) for pipe stress analyses, radiation shielding and airborne concentrations, instrumentation and control systems, and control room design details. SECY-92-196 Title: Development of Design Acceptance Criteria (DAC) for the Advanced Boiling Water Reactor (ABWR) Content: SECY-92-196 addresses the proposed