Document: NUREG-0800
Document ID: 2dffe24e-cd37-4ffc-9c37-16faf25676b1
Document Type: srp
Title: Appendix 7-A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500579.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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CFR Title: 

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digital computer timing requirements, architecture, and design commitments. For this level of detail, the reviewer verifies that system timing requirements calculated from the design basis events and other criteria have been allocated to the digital computer portion of the system as appropriate, and have been satisfied in the digital system architectural design. When inspections, tests, analyses and acceptance criteria (ITAAC) or detailed design documents that describe designs, tests, analyses, or other methods of demonstrating satisfaction of design commitments are available, the reviewer verifies that the installed plant systems perform as predicted, and that appropriate measurement and analysis techniques have been used to compensate for the uncertainties introduced by certain design and implementation practices, such as the use of interrupts. This level of review verifies satisfaction of the latter two acceptance criteria groups, performance verification and use of part-scale prototypes. C. References ANSI/IEEE Std 279-1971. "Criteria for Protection Systems for Nuclear Power Generating Stations." Draft Regulatory Guide DG-1045. Proposed Revision 3 to Regulatory Guide 1.105, "Instrument Setpoints for Safety Systems." Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997. IEEE Std 603-1991. "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." Appendix 7-A Rev. 4 — June 1997 BTP HICB-21-7 IEEE Std 7-4.3.2-1993. "IEEE Standard for Digital Computers in Safety Systems of Nuclear Power Generating Stations." ISA-S67.04-1994. "Setpoints for Nuclear Safety-Related Instrumentation Used in Nuclear Power Plants." NUREG/CR-6082. "Data Communications." August 1993. NUREG/CR-6083. "Reviewing Real-Time Performance of Nuclear Reactor Safety Systems." August 1993. Regulatory Guide 1.152. "Criteria for Digital Computers in Safety Systems of Nuclear Power Plants." Office of Nuclear Regulatory Research, U.S. Nuclear