Document: NUREG-0800
Document ID: 4cca74ec-66e0-4765-9c61-cf547e17c308
Document Type: srp
Title: of the plant safety analysis report (SAR).  Although the NRC did not endorse the annexes of
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A114.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.6
CFR Part: 
CFR Title: 

Content:
f IEEE Std 603-1991. Appendix 7.1-D-22 Revision 1 - August 2016 7. EXECUTE FEATURES FUNCTIONAL AND DESIGN REQUIREMENTS (IEEE Std 7-4.3.2. Clause 7) There is no guidance beyond the requirements of IEEE Std 603-1991. 8. POWER SOURCE REQUIREMENTS (IEEE Std 7-4.3.2, Clause 8) The reviewer should refer to Subsection 8 of SRP Appendix 7.1-C for guidance on implementation of the requirements of IEEE Std 603-1991. 9. SECURE DEVELOPMENT AND OPERATIONAL ENVIRONMENT FOR THE PROTECTION OF DIGITAL SAFETY SYSTEMS Regulatory Guide 1.152 describes digital safety system guidance for the establishment of an SDOE. 10. REFERENCES 1. Electric Power Research Institute, EPRI Topical Report TR-106439, “Guideline on Evaluation and Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Applications,” October 1996. 2. International Electrotechnical Commission, IEC 60880-2-2002, “Software for Computers Important to Safety for Nuclear Power Stations - Part 2, Software Aspects of Defense against Common Cause Failures, Use of Software Tools and of Pre-developed Software.” 3. Institute of Electrical and Electronics Engineers/American Nuclear Society, IEEE/ANS 7-4.3.2-1982, “American Nuclear Society and IEEE Standard Application Criteria for Programmable Digital Computer Systems in Safety Systems of Nuclear Power Generating Stations,” Piscataway, NJ. 4. Institute of Electrical and Electronics Engineers, IEEE Std 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” Piscataway, NJ. 5. Institute of Electrical and Electronics Engineers, IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,” Piscataway, NJ. 6. Institute of Electrical and Electronics Engineers, IEEE Std 379, “IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems,” Piscataway, NJ. 7. Institute of Electrical and Electronics Engineers, IEEE Std 603-1991,