Document: NUREG-0800
Document ID: debf22b1-f3aa-4c75-a43c-f162d22de1c8
Document Type: srp
Title: of the plant safety analysis report (SAR).  Although the NRC did not endorse the annexes of
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A491.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.6
CFR Part: 
CFR Title: 

Content:
Nuclear Power Plants.” This guidance is in addition to the equipment qualification criteria provided by IEEE Std 603-1991 and Subsection 5.4 of SRP Appendix 7.1-C and the following criteria that are necessary to qualify digital computers for use in safety systems. 5.4.1 Computer System Testing (IEEE Std 7-4.3.2, Sub-Clause 5.4.1) Computer system equipment qualification testing should be performed with the computer functioning with software and diagnostics that are representative of those used in actual operation. All portions of the computer necessary to accomplish safety functions, or those portions where operation or failure could impair safety functions, should be exercised during testing. This includes, as appropriate, exercising and monitoring the memory, central processing unit, inputs, outputs, display functions, diagnostics, associated components, communications paths, and interfaces. Testing should demonstrate that the performance criteria related to safety functions have been met. 5.4.2 Qualification of Existing Commercial Computers (IEEE Std 7-4.3.2, Sub-Clause 5.4.2) EPRI TR-106439, as accepted by the NRC safety evaluation dated July 17, 1997, provides guidance for the evaluation of existing commercial computers and software to comply with the criteria of Sub-Clause 5.4.2 of IEEE Std 7-4.3.2. The guidance of SRP BTP 7-14 may be applied to the evaluation of vendor processes described in EPRI TR-106439. EPRI TR-107330, “Generic Requirements Specification for Qualifying a Commercially Available PLC for Safety-Related Applications in Nuclear Power Plants,” as accepted by the NRC safety evaluation dated July 30, 1998, provides more specific guidance for the evaluation of existing programmable logic controllers (PLC). The fundamental criteria for demonstrating reasonable assurance that the computer will perform its intended safety functions is presented in this portion of IEEE Std 7-4.3.2 and additional guidance is provided in EPRI TR-106439 and EPRI