Document: NUREG-0800
Document ID: 5e40cf60-028d-44c3-b9b8-735a6a68a48a
Document Type: srp
Title: Revision 6 - August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A036.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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led plant systems perform as predicted and appropriate measurement and analysis techniques have been used to compensate for the uncertainties introduced by certain design and implementation practices, such as the use of interrupts. This level of review verifies satisfaction of two acceptance criteria groups - performance verification and use of part-scale prototypes. C. REFERENCES 1. Institute of Electrical and Electronic Engineers, IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,” Piscataway, NJ. 2. Institute of Electrical and Electronic Engineers, IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” Piscataway, NJ. BTP 7-21-10 Revision 6 – August 2016 3. Institute of Electrical and Electronic Engineers, IEEE Std 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” Piscataway, NJ. 4. Institute of Electrical and Electronic Engineers, IEEE/EIA 12207.0-1996, “Standard Industry Implementation of International Standard ISO/IEC 12207: 1995 (ISO/IEC 12207) Standard for Information Technology Software Life Cycle Processes,” March 1998. 5. Institute of Electrical and Electronic Engineers, IEEE Std 1012, “IEEE Standard for Software Verification and Validation,” Piscataway, NJ. 6. International Society of Automation, ISA-S67.04, Part I, “Setpoints for Nuclear Safety-Related Instrumentation.” 7. U.S. Nuclear Regulatory Commission, “Data Communications,” NUREG/CR-6082, August 1993. 8. U.S. Nuclear Regulatory Commission, “Reviewing Real-Time Performance of Nuclear Reactor Safety Systems,” NUREG/CR-6083, August 1993. 9. U.S. Nuclear Regulatory Commission, “Setpoints for Safety-Related Instrumentation,” Regulatory Guide 1.105. 10. U.S. Nuclear Regulatory Commission, “Criteria for Use of Computers in Safety Systems of Nuclear Power Plants,” Regulatory Guide 1.152. 11. U.S. Nuclear Regulatory