Document: NUREG-0800
Document ID: 409035a3-eae4-4524-8ae0-ca7775f4072a
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550073.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
t the acceptance criteria contained in SRP BTP 7-14, appropriately graded for the application in which the PLC will be used. The application software (ladder logic or other) should meet the acceptance criteria contained in SRP BTP 7-14 commensurate with the system it is designed to support. Application software should conform with the recommended practices of NUREG/CR-6463. Tools for developing application software or loading it into the PLC should be qualified to a level commensurate with the system they are designed to support. PLC-based functions should conform with the guidance regarding real-time performance and testing outlined in SRP BTP 7-21 and SRP BTP 7-17. 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 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. 4. 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, SRP BTP 7-14, SRP BTP 7-17, and SRP BTP 7-21 describe these review procedures. BTP 7-18-5 Revision 5 - March 2007 C. REFERENCES 1. EPRI Topical Report TR-106439, “Guideline on Evaluation and Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Applications,” EPRI, October 1996. 2. EPRI TR-107330, “Generic Requirements Specification for Qualifying a Commercially Available PLC for Safety-Related Applications in Nuclear Power Plants,” EPRI, December 1996. 3. IEEE Std 7-4.3.2-2003, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.” 4. NUREG/CR-6090, “The PLC and Its Application in Nuclear Reactor Protection Systems,”