Document: NUREG-0800
Document ID: 6209b3e7-917d-48d2-a299-4d1230aa5b51
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550070.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
Based on review of the available information and applicant/licensee commitments, the reviewer should reach a conclusion appropriate to the level of detail and type of submittal. For certified designs under 10 CFR 52, preliminary SARs, or topical reports, the level of detail typically includes only information to verify limiting response times, 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 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 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 two acceptance criteria groups - performance verification and use of part-scale prototypes. C. REFERENCES 1. IEEE Std. 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations." 2. IEEE Std. 603-1991, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." 3. IEEE Std. 7-4.3.2-2003, "IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations." 4. IEEE/EIA Std. 12207.0-1996, "Industry Implementation of International Standard ISO/IEC 12207: 1995 (ISO/IEC 12207) Standard for Information TechnologySoftware Life Cycle Processes," March 1998. 5. IEEE Std. 1012-1998, "IEEE Standard for Software Verification and Validation," March 1998. 6. ISA-S67.04-1994, "Setpoints for Nuclear Safety-Related Instrumentation." 7.