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
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CFR Title: 

Content:
and control of measuring and test equipment used in the maintenance of instrument setpoints. Generic Letter 91-04, "Guidance on Preparation of a Licensee Amendment Request for Changes in 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. Appendix 7.1-C provides Standard Review Plan (SRP) acceptance criteria for safety system compliance with 10 CFR 50.55a(h). Appendix 7.1-B provides SRP acceptance criteria for protection system compliance with 10 CFR 50.55a(h). Appendix 7.1-D provides SRP acceptance criteria for digital I&C compliance with IEEE Std. 7-4.3.2-2003, "IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations," as endorsed by Regulatory Guide 1.152, Revision 2, "Criteria for Digital Computers in Safety Systems of Nuclear Power Plants." 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," provides guidance on the use of probabilistic risk assessment (PRA) findings and risk insights in support of licensee requests for changes to a plant's licensing basis, as in requests for licensing amendments and technical specification changes. Regulatory Guide 1.177, "An Approach for Plant-Specific, Risk-Informed Decision Making: Technical Specifications," provides guidance on assessing the nature and impact of proposed technical specification changes by considering engineering issues and applying risk insights. Regulatory Guide 1.200 (For Trial Use), "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," provides guidance on determining that the quality of the PRA, in total or the parts that are used to support an application, is sufficient to provide confidence in the results such that the