Document: NUREG-0800
Document ID: 5b4fe75c-0560-40a2-9e68-366d25bc7ea0
Document Type: srp
Title: and 7.3.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500552.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
ails are critical to the safety determination, they should be identified as Tier 2* material in the SER and DCD, thereby requiring prior NRC staff approval if changed. For I&C systems, Tier 1 material consists of the certified design description, ITAAC, and interface requirements as defined in 10 CFR 52.47(a)(1)(ii) and (vii). The certified design description is composed of narrative descriptions and schematic drawings needed to describe the significant design features certified by the Staff. Design details and commitments that are important to the NRC's safety determination, but are subject to change (e.g., technology advancement and standard revisions), should be identified as Tier 2* material in the SER and the DCD. For I&C systems, Tier 2* information will normally be limited to computer design, data communication design, setpoint methodology, commercial-grade item dedication, and equipment qualification, including electromagnetic compatibility. Rev. 4 — June 1997 Appendix 7-A BTP HICB-16-8 4. Review Procedures The reviewer should confirm early in the review that the basic types of information outlined above are available to support the review. The review should confirm that the CDM contains an appropriate set of Tier 1 material, and that appropriate Tier 2* material is identified. C. References IEEE Std 603-1991. "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." Memorandum from W. T. Russell to B. A. Boger, et al. "Reviewer Guidance for Design Certification Reviews — Certified Design Descriptions; Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC); Applicant SAR Level of Detail; and Staff SER Documentation." December 28, 1992. Regulatory Guide 1.152. "Criteria for Digital Computers in Safety Systems of Nuclear Power Plants." Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, January 1996. Regulatory Guide 1.70. "Standard Format and Content of Safety Analysis Reports for Nuclear Power