Document: NUREG-0800
Document ID: 4f141c71-35ca-4353-9047-a13efe6d56b7
Document Type: srp
Title: Revision 6 - August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A308.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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Content:
ty, adequacy, and sufficiency, and should be supplemented or modified as necessary to ensure a quality product consistent with the required safety function. 4. GDC 21, “Protection System Reliability and Testability,” requires in part that protection systems be designed for high functional reliability commensurate with the safety function to be performed. 5. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” Criterion III, “Design Control,” requires in part that quality standards be specified and that design control measures shall provide for verifying or checking the adequacy of design. Criterion V, “Instructions, Procedures, and Drawings,” requires in part that activities affecting quality shall be prescribed by “documented…procedures…of a type appropriate to the circumstances…” This BTP outlines such procedures for software. Criterion VI, “Document Control,” requires in part that “measures shall be established to control the issuance of documents…which prescribe all activities affecting quality…These measures shall assure documents, including changes, are reviewed for adequacy and approved for release by authorized personnel…” Criterion VII, “Control of Purchased Material, Equipment, and Services," addresses control of purchased material, equipment, and services. Further, Criterion XI, “Test Control,” requires in part that a test program be established to demonstrate that systems and components will perform satisfactorily in service. A.2 Relevant Guidance The relevant guidance is found in SRP Appendix 7.1-A, and is summarized below. RG 1.28, “Quality Assurance Program Criteria (Design and Construction),” which endorses American Society of Mechanical Engineers (ASME) Nuclear Quality Assurance (NQA)-1, “Quality Assurance Requirements for Nuclear Facility Applications,” and the ASME NQA-1a, “Addenda to ASME NQA-1-2008, Quality Assurance Requirements