Document: NUREG-0800
Document ID: 3571c656-1693-466b-a77d-6c05b7eed41e
Document Type: srp
Title: REACTOR SYSTEMS - INSPECTIONS, TESTS, ANALYSES, AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070660623.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3.4
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CFR Title: 

Content:
d positions for ensuring consistent and complete treatment of those systems that might be classified as non-safety-related by the designer or applicant but are important to safety or otherwise provide defense-in-depth functions. 4. Applicable regulatory guidance from the Commission for selected policy and technical issues related to particular design should be followed. For the severe accident analyses, the basis for the staff's review for the evolutionary and passive standard designs was the Commission guidance related to SECY-90-016, “Evolutionary Light Water Reactor (LWR) Certification Issues and Their Relationship to Current Regulatory Requirements.” SECY-93-087, “Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor Designs” generically presents guidance and NRC positions on evolutionary and passive LWR design certification issues. For guidance, positions, and issues related to specific designs, guidance is available in such documents as SECY-97-044, “Policy and Key Technical Issues Pertaining to the Westinghouse AP600 Standardized Passive Reactor Design” or SECY-92-137, “Reviews of Inspections, Test, Analyses, and Acceptance Criteria (ITAAC) Requirements for the General Electric (GE) Advanced Boiling Water Reactor (ABWR).” Regarding DAC, SECY-02-059, “Use of Design Acceptance Criteria for the AP1000 Standard Plant Design,” presents staff conclusions on acceptable use of DAC for I&C, control room, and piping design areas, contingent upon Westinghouse’s and the staff’s agreeing on adequate DAC during the design certification review. In SECY-92- 053, “Use of Design Acceptance Criteria During 10 CFR Part 52 Design Certification Process,” the staff noted that DAC is defined as “a set of prescribed limits, parameters, procedures, and attributes upon which the NRC relies, in a limited number of technical areas, in making a final safety determination to support a design certification.”