Document: NUREG-0800
Document ID: 0dbbf3f4-58b3-47a9-9786-896a381f2c92
Document Type: srp
Title: B-12
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A091.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
Revision 6 – August 2016 4.18. Access to Setpoint Adjustments, Calibrations, and Test Points (IEEE Std 279-1971, Clause 4.18) The review of access control should confirm that design features provide the means to control physical access to protection system equipment, including access to test points and means for changing setpoints. Typically such access control includes provisions such as alarms and locks on protection system panel doors, or control of access to rooms in which protection system equipment is located. 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 RG 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 RG 1.75, which endorses IEEE Std 384. The preferred identification method is color coding of components, cables, and cabinets. 5. REFERENCES 1. Institute of Electrical and Electronics Engineers, IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,”