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
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CFR Title: 

Content:
latory Guide 1.160 provides guidance, acceptable to the staff, for implementation of the maintenance rule. Meeting the requirements specified in 10 CFR 50.65 provides assurance that plant SSCs will be properly maintained and capable of performing their intended safety function throughout their service life. 3. Compliance with 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. Appendix B to 10 CFR Part 50 applies to this SRP section because operational reliability assurance activities should be integrated into such programs (e.g., maintenance, surveillance, inservice inspection, inservice testing, and quality assurance). Operational reliability assurance activities related to safety-related SSCs are included in the quality assurance program required under Appendix B to 10 CFR Part 50 and in programs for surveillance, inservice inspection, and inservice testing. 17.4-9 DRAFT Rev. 0 - April 1996 Meeting the quality assurance requirements specified in Appendix B to 10 CFR Part 50 provides assurance that safety related SSCs will be designed, constructed, and operated in a manner that ensures their capability to perform their intended safety function. III. REVIEW PROCEDURES8 The procedures set forth below are used for review of standard design certification applications and COL applications that reference standard design certifications. 1. D-RAP for Standard Design Certification (DC) - An application for a standard design certification should: (a) include a description of the scope, purpose, objectives, and essential elements of the D-RAP; (b) identify and prioritize risk-significant SSCs based on a plant-specific PRA and supplemented by other sources (e.g., deterministic evaluation, industry experience, or an expert panel); and (c) describe the implementation of those portions of the D-RAP