Guidance for Addressing Software Common cause Failure In High Safety-Significant Safety Related Digital I&c systems



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References
1.
10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants
2.
10 CFR Part 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
3.
Regulatory Issue Summary (RIS) 2002-22, Supplement 1, Clarification on Endorsement of NEI Guidance in Designing Digital Upgrades in I&C Systems, May 2018.
4.
Draft Revision 8 (August 2020) to Branch Technical Position (BTP) 7-19, Guidance for Evaluation of Defense in Depth and Diversity to Address Common Cause Failure due to Latent Defects in Digital Systems
5.
IEC 61508, Edition 2.0, 2010-04, Functional Safety of Electrical/Electronic/Programmable Electronic Safety Related Systems
6.
EPRI Report 30020011817, Final Report Dated July 2019; Safety Integrity Level (SIL) Certification Efficacy for Nuclear Power
7.
EPRI 2018 Technical Report 3002011816, Digital Engineering Guide, Decision Making Using Systems Engineering
8.
IEC 61513, Edition 2.0, 2011-08, Nuclear Power Plants - Instrumentation and Control Important to Safety - General Requirements for Systems

DRAFT B - August 2020
© NEI 2020. All rights reserved. nei.org 29 Appendix A Connection Between Software CCF First Principles and NRC Regulatory Framework
This Appendix describes the relationship between the first principles of protection against software CCF and the NRC regulatory framework. The first principles are defined in detail in Section 6. For each first principle below the associated NRC regulatory requirements are identified. Note that the regulations listed below may not necessarily apply to all applicants and licensees. The applicability of the regulatory requirements is determined by the plant-specific licensing basis and any proposed changes to the licensing basis associated with the proposed DI&C system under evaluation.

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