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: 
CFR Title: 

Content:
s that is based on industry experience, analytical models, and applicable requirements. II. ACCEPTANCE CRITERIA6 The D-RAP is described in the standard design certification applicant's standard safety analysis report (SSAR) and the design control document (DCD), including related sections of the PRA. The staff will base its evaluation of each application for a standard design certification or for a COL on the following regulations: A. The Commission approved applicable regulation for RAP, as described in SECY 95-132, Appendix E. (The regulation for each certified design is to be included in a standardized design-specific appendix to 10 CFR Part 52.) B. 10 CFR 50.65 specifies that operators of nuclear power plants shall monitor the performance and condition of SSCs to provide reasonable assurance that specified SSCs are capable of fulfilling their intended functions. C. Appendix B to 10 CFR Part 50 requires that a quality assurance program be provided for the design, construction, and operation of SSCs needed to ensure the safe operation, shutdown, and accident mitigation of a nuclear power plant. To meet the above requirements, the following specific criteria regulation are used: 1. Design Certification D-RAP - The application for Design Certification must contain: a. A description of the RAP used during the design stage, including its scope, purpose, objectives, and essential elements. b. A process for evaluating and prioritizing design structures, systems, and components that is based on risk significance. c. A list of SSCs designated as risk significant. d. For those SSCs designated as risk significant, the following must also be provided: (1) A process for determining dominant failure modes that is based on industry experience, analytical models, and applicable requirements; and (2) Key assumptions and determinations of risk significance that are derived from probabilistic, deterministic, or other methods that consider operations, maintenance, and monitoring