Document: NUREG-0800
Document ID: 6acfc377-3e1c-4cb9-b2d1-500f564d2f4b
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B011.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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, controllers, computer nodes, or actuation devices required to scale the test system to full scale. BTP 7-21-9 Draft Revision 6 – August 2015 Test data should confirm scaling as well as performance projections. Exceptions are considered anomalies or abnormal events. Prototypes designed to demonstrate scaling should include all significant architectural elements plus enough additional elements to show the scaling effects to be measured. 4. Review Procedures 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 Part 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. BTP 7-21-10 Draft Revision 6 – August 2015 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