Document: NUREG-0800
Document ID: 1add33e8-ea1c-46d8-9e11-29944f57ca8a
Document Type: srp
Title: Revision 6 – August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A184.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
e,” requires that “the effects of natural phenomena, and of normal operating, maintenance, testing, and postulated accident conditions on redundant channels do not result in loss of the protection function.” 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 “where a test program is used to verify the adequacy of a specific feature in lieu of other verifying or checking processes, it shall include suitable qualifications testing of a prototype unit under the most adverse design conditions.” 2. Relevant Guidance If a referenced industry code or standard has been separately incorporated into the U.S. Nuclear Regulatory Commission’s (NRC’s) regulations, licensees and applicants must comply with that code or standard as set forth in the regulations. If the referenced code or standard has been endorsed by the NRC staff in a RG, that code or standard constitutes an acceptable method of meeting the related regulatory requirement as described in the RG. If a referenced code or standard has neither been incorporated into the NRC’s regulations nor endorsed by a RG, licensees and applicants may consider and use the information in the referenced code or standard, if appropriately justified, consistent with current regulatory practice. RG 1.75, “Criteria for Independence of Electrical Safety Systems,” endorses IEEE Std 384, “IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits,” which identifies specific electrical isolation criteria for isolation devices used in instrumentation and control circuits. These isolation criteria form part of the basis for this BTP. Additional guidance on applying the safety system criteria of IEEE Std 603-1991 to computer-based safety systems is provided in IEEE Std 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” as