Document: NUREG-0800
Document ID: c958631d-9dc1-4c62-8d33-f6ae0fcc1955
Document Type: srp
Title: PLANT SYSTEMS (Tier 1)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070666.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3.7
CFR Part: 
CFR Title: 

Content:
14.3.1 and 14.3.2, and regarding piping design in SRP Section 14.3.3. 3. The Instrumentation and Controls Branch (HICB) determines the acceptability of Tier 1 information regarding the instrumentation and controls aspects of the design in SRP Section 14.3.5. II. ACCEPTANCE CRITERIA The acceptance criteria for ITAAC are based on meeting 10 CFR 52.97(b)(1), which sets forth the comprehensive requirements for ITAAC. For design certification reviews, the scope of ITAAC is limited to the scope of the certified design as required by 10 CFR 52.47(b). In addition, acceptability is based on meeting the relevant requirements of the following regulations: 1. 10 CFR 50.49 as it relates to environmental qualification of electrical equipment important to safety for nuclear power plants. Applicants must ensure that safety- related, some nonsafety-related, and some post-accident monitoring equipment can perform their intended functions in various anticipated environments. 2. 10 CFR 50.48 as it relates to fire protection for the design. The reviewer should utilize the SRP in its review of Tier 1 to determine the safety significance of SSCs. Other sources include applicable rules and regulations, GDCs, RGs, USIs and GSIs, NRC generic correspondence, PRA, insights from the standard design's safety and severe accident analyses, and operating experience. Tier 1 should be reviewed for consistency with the initial test program described in DCD Tier 2 Chapter 14.2. The reviewer should also use the review checklists provided in Appendix C to SRP Section 14.3 as an aid for establishing consistency and comprehensiveness in his review of the systems. If applicable, the reviewer should utilize regulatory guidance from the Commission for selected policy and technical issues related to particular design. Examples of these are contained in SECY-93-087, "Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor Designs." The SRM related to this is dated