Document: NUREG-0800
Document ID: c6dbe9ec-b58d-4a77-85ee-47b58571c3c0
Document Type: srp
Title: Revision 6 - August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A200.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
tection Systems for Nuclear Power Generating Stations,” Piscataway, NJ. 3. Institute of Electrical and Electronics Engineers, IEEE Std 498-1990, “IEEE Standard Requirements for the Calibration and Control of Measuring and Test Equipment Used in Nuclear Facilities,” Piscataway, NJ. 4. Institute of Electrical and Electronics Engineers, IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” Piscataway, NJ. 5. 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. 6. International Society of Automation, ISA-S67.04-1994, Part I, “Setpoints for Nuclear Safety-Related Instrumentation Used in Nuclear Power Plants,” Research Triangle Park, NC. 7. International Society of Automation, ISA-S67.04-1994, Part II, “Methodology for the Determination of Setpoints for Nuclear Safety-Related Instrumentation,” Research Triangle Park, NC 8. U.S. Nuclear Regulatory Commission, “Changes in Technical Specification Surveillance BTP 7-12-10 Revision 6 – August 2016 Intervals to Accommodate a 24-Month Fuel Cycle,” Generic Letter 91-04. 9. U.S. Nuclear Regulatory Commission, “Systems Based Instrumentation and Control Inspection,” NRC Inspection Manual, Inspection Procedure 93807, 10. U.S. Nuclear Regulatory Commission, “Setpoints for Safety-Related Instrumentation,” Regulatory Guide 1.105. 11. U.S. Nuclear Regulatory Commission, “Criteria for Use of Computers in Safety Systems of Nuclear Power Plants,” Regulatory Guide 1.152. 12. U.S. Nuclear Regulatory Commission, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” Regulatory Guide 1.174. 13. U.S. Nuclear Regulatory Commission, “An Approach for Plant-Specific, Risk-Informed Decision Making: Technical Specifications,” Regulatory Guide 1.177.