Document: NUREG-0800
Document ID: ec9b19e0-e107-4857-a035-4384fcd84e58
Document Type: srp
Title: B-11
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550087.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
Revision 5 - March 2007 4.19. Identification of Protective Actions and Information Read-Out (IEEE Std. 279-1971 Clauses 4.19 and 4.20) The review of information displays should be coordinated with the organization that is responsible for the review of reactor systems to confirm that the information displayed and characteristics of the displays (e.g., location, range, type, and resolution) support operator awareness of system and plant status and will allow plant operators to make appropriate decisions. The review of information displays for manually controlled actions should include confirmation that displays will be functional (e.g., power will be available and sensors are appropriately qualified) during plant conditions under which manual actions may be necessary. Protection system bypass and inoperable status indication should conform with the guidance of Regulatory Guide 1.47. 4.20. Information Read-Out (IEEE Std. 279-1971 Clause 4.20) See subsection 4.19 above. 4.21. System Repair (IEEE Std. 279-1971 Clause 4.21) Protection systems may include self-diagnostic capabilities to aid in troubleshooting. 4.22. Identification (IEEE Std. 279-1971 Clause 4.22) Guidance on identification is provided in Regulatory Guide 1.75, which endorses IEEE Std. 384-1992. The preferred identification method is color coding of components, cables, and cabinets. 5. REFERENCES 1. IEEE Std. 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations." 2. IEEE Std. 323-2000, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations." 3. IEEE Std. 338-1987, "Standard Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems." 4. IEEE Std. 379-1988, "Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems." 5. IEEE Std. 384-1992, "IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits." 6. IEEE Std. 603-1991, "IEEE Standard Criteria for