Document: NUREG-0800
Document ID: 5989239b-cda8-4832-8a1c-ff0c221fca34
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A799.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
• Data used to select the trip setpoint, including the source of the data. • Assumptions used to select the trip setpoint (e.g., ambient temperature limits for equipment calibration and operation, potential for harsh accident environment). • Instrument installation details and bias values that could affect the setpoint. • Correction factors used to determine the setpoint (e.g., pressure compensation to account for elevation difference between the trip measurement point and the sensor physical location). • Instrument test, calibration or vendor data, as-found and as-left; with each instrument should be demonstrated to have random drift by empirical and field data and evaluation results should be reflected appropriately in the uncertainty terms, including the setpoint methodology. The design, installation, calibration procedures, and calibration activities for specific 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 Z540-1-1994, “Calibration Laboratories and Measuring and Test Equipment - General Requirements.” 2. GL 91-04, “Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle.” 3. IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” BTP 7-12-9 Draft Revision 6 – August 2015 4. IEEE Std 498-1990, “IEEE Standard Requirements for the Calibration and Control of Measuring and Test Equipment Used in Nuclear Facilities.” 5. IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.” 6. IEEE Std 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.” 7. ISA-S67.04, Part I, “Setpoints for Nuclear