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
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Content:
ent setpoints are initially - and remain - within the technical specification limits. This RG endorses International Society of Automation (ISA)-S67.04, Part I, “Setpoints for Nuclear Safety-Related Instrumentation Used in Nuclear Power Plants.” ISA-S67.04-1994, Part II, “Methodology for the Determination of Setpoints for Nuclear Safety- Related Instrumentation,” provides additional guidance, but RG 1.105 does not endorse or address Part II of ISA-S67.04-1994. NRC Regulatory Issue Summary (RIS) 2006-17, “NRC Staff Position on the Requirements of 10 CFR 50.36, ‘Technical Specifications,’ Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels,” discusses issues that could occur during testing of LSSS. IEEE Std 498-1990, “IEEE Standard Requirements for the Calibration and Control of Measuring and Test Equipment Used in Nuclear Facilities,” and American National Standards Institute (ANSI)/NCSL Z540-1-1994, “Calibration Laboratories and Measuring and Test Equipment - General Requirements,” provide guidance for the calibration and control of measuring and test equipment used in the maintenance of instrument setpoints. Generic Letter (GL) 91-04, “Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle,” provides guidance on issues that should be addressed by the setpoint analysis when calibration intervals are extended from 12 or 18 to 24 months. SRP Appendix 7.1-B provides guidance for evaluating conformance to the requirements of IEEE Std 279-1971. SRP Appendix 7.1-C provides guidance for evaluating conformance to IEEE Std 603-1991. SRP Appendix 7.1-D provides guidance for evaluating conformance to the acceptance criteria contained in RG 1.152, “Criteria for Use of Computers in Safety Systems of Nuclear Power Plants,” which endorses IEEE Std 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating