Document: NUREG-0800
Document ID: 96afb1d6-6ce9-41e4-b4ec-1fc7747bc0b2
Document Type: srp
Title: Revision 8 – January 2021
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML2033/ML20339A647.pdf
Revision Date: 2023-05
Chapter: 7
Section ID: 7
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Content:
s for responding to an event, the reviewer should verify that the applicant’s HFE analysis and assessment demonstrates (e.g., through the process in SRP Chapter 18) that this action is both feasible and reliable. For this, the reviewer should coordinate with the organization responsible for the review of human– system interfaces. 6.5 Justification for Not Correcting Specific Vulnerabilities The reviewer should consider whether the applicant provided justification for not correcting any identified vulnerabilities that the application leaves unresolved. Such justification might include, for example, design attributes (e.g., redundancy, diversity, independence) and diverse actuation or mitigation capabilities, as well as previously NRC-approved credited manual operator actions in the licensing basis to address AOOs or PAs. The staff should review justifications on a case-by-case basis. For example, an applicant might credit the ability of plant operators to identify system leakage using the plant leak detection system before the onset of a large-break pipe rupture. The crediting of such manual operator actions could be justified by appropriate analysis of site-specific factors such as pipe configuration and design, piping fracture mechanics, leak detection system capabilities, and details of manual operator actions and procedures. The reviewer should consider whether evaluation of the applicant’s justifications necessitates a multidisciplinary review in cooperation with other NRC staff. BTP 7-19-34 Revision 8 – January 2021 C. REFERENCES 1. U.S. Code of Federal Regulations (CFR), “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter I, Title 10, “Energy.” 2. CFR, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” Part 52, Chapter I, Title 10, “Energy.” 3. CFR, “Reactor site criteria,” Part 100, Chapter I, Title 10, “Energy.” 4. Institute of Electrical and Electronics Engineers, “The