Document: NUREG-0800
Document ID: 1da20040-18d5-4c75-9863-5f578a9d73a5
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550078.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
pecific channels may be inspected to gain further confidence that setpoint calculations are consistent with plant equipment and calibration procedures. NRC Inspection Manual, Procedure 93807, "Systems Based Instrumentation and Control Inspection," provides guidance for such inspections. C. REFERENCES 1. ANSI/NCSL Std. Z540-1-1994, "Calibration Laboratories and Measuring and Test Equipment - General Requirements." 2. IEEE Std. 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations." 3. IEEE Std. 498-1990, "IEEE Standard Requirements for the Calibration and Control of Measuring and Test Equipment Used in Nuclear Facilities." 4. IEEE Std. 603-1991, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." 5. IEEE Std. 7-4.3.2-2003, "IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations." 6. ISA-S67.04-1994, Part I, "Setpoints for Nuclear Safety-Related Instrumentation Used in Nuclear Power Plants." 7. ISA-S67.04-1994, Part II, “Methodology for the Determination of Setpoints for Nuclear Safety-Related Instrumentation." 8. NRC Inspection Manual, Inspection Procedure 93807, "Systems Based Instrumentation and Control Inspection," U.S. Nuclear Regulatory Commission, May 31, 1994. BTP 7-12-9 Revision 5 - March 2007 9. Regulatory Guide 1.105, Revision 3, "Setpoints for Safety-Related Instrumentation," Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999. 10. Regulatory Guide 1.152, Revision 2, “Criteria for Digital Computers in Safety Systems of Nuclear Power Plants,” Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, January 2006. 11. Regulatory Guide 1.174, Revision 1, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, November 2002. 12. Regulatory Guide 1.177, “An