Document: NUREG-0800
Document ID: 896f0b4b-b27c-462b-aed0-872a58b455c8
Document Type: srp
Title: Revision 6 – August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A327.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
ance on Digital Computer Real-Time Performance,” and SRP BTP 7-17, “Guidance on Self-Test and Surveillance Test Provisions.” Administrative or hardware lockout controls that prevent unauthorized modification of the PLC software should be in place. This is particularly important because many PLCs are designed so BTP 7-18-5 Revision 6 – August 2016 that their software is easy to modify. All software changes should be under configuration management control. In particular, administrative procedures for maintaining control of the software implemented in the PLC should be detailed in the configuration management plan. Review Procedures PLC applications should be reviewed in the same manner as other digital computer I&C applications. SRP Appendix 7.0-A, SRP Section 7.1, “Instrumentation and Controls – Introduction,” SRP BTP 7-14, SRP BTP 7-17, and SRP BTP 7-21 describe these review procedures. C. REFERENCES 1. Electric Power Research Institute, EPRI Topical Report TR-106439, “Guideline on Evaluation and Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Applications,” EPRI, October 1996. 2. Electric Power Research Institute, EPRI TR-107330, “Generic Requirements Specification for Qualifying a Commercially Available PLC for Safety-Related Applications in Nuclear Power Plants,” EPRI, December 1996. 3. Electric Power Research Institute, IEEE Std 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” Piscataway, NJ. 4. U.S. Nuclear Regulatory Commission, NUREG/CR-6090, “The PLC and Its Application in Nuclear Reactor Protection Systems,” September 1993. 5. U.S. Nuclear Regulatory Commission, NUREG/CR-6421, “A Proposed Acceptance Process for Commercial Off-the-Shelf (COTS) Software in Reactor Applications,” June 1996. 6. U.S. Nuclear Regulatory Commission, NUREG/CR-6463, Revision 1, “Review Guidelines on Software Languages for Use in Nuclear Power Plant Safety