Document: NUREG-0800
Document ID: fde45fa1-e4ca-4005-b5f6-d1bbefc60c73
Document Type: srp
Title: RELIABILITY ASSURANCE PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070754.pdf
Revision Date: 2023-06
Chapter: 17
Section ID: 17.4
CFR Part: 
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Content:
REVIEW RESPONSIBILITIES Primary - Quality Assurance and Maintenance Branch (HQMB) Secondary - Probabilistic Safety Assessment Branch (SPSB) I. AREAS OF REVIEW1 A reliability assurance program (RAP) will be required for standard design certifications and combined licenses for nuclear power plants licensed under 10 CFR Part 52. Design certification * (DC) applicants and combined license (COL) applicants and holders that reference standard design certifications will be required to have a staff approved RAP. The RAP applies to those plant structures, systems, and components (SSCs) designated as risk significant (significant contributors to plant safety) based on a combination of probabilistic, deterministic, and other approaches (e.g., a probabilistic risk assessment (PRA) for the standard design, and advice from an expert panel). The objectives of the RAP are to provide reasonable assurance of the following: • The plant is designed, constructed, and operated consistent with the assumptions and risk insights for risk-significant SSCs; • Risk-significant SSCs will not degrade to an unacceptable level during plant operations; DRAFT Rev. 0 - April 1996 17.4-2 • The frequency of transients posing challenges to risk-significant SSCs will be minimized; and • SSCs will function reliably when challenged. In SECY-95-132 (Reference 8) the staff documented a two-stage approach to the RAP. The first stage is applied before initial fuel load and is referred to as the design reliability assurance program (D-RAP). The second stage applies to reliability assurance activities for the operations phase of the plant life cycle. Subdivisions of the D-RAP stage are associated with: (1) standard design certification, (2) the COL applicant, and (3) the COL holder. The D-RAP identifies and prioritizes risk-significant SSCs based on probabilistic, deterministic, and other considerations (e.g., the plant-specific PRA). Specifically, in the final safety evaluation reports, NUREG-1462 for