Document: NUREG-0800
Document ID: d52a97d0-a519-4817-9ad6-64d94c9518af
Document Type: srp
Title: DATA COMMUNICATION SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B177.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.9
CFR Part: 
CFR Title: 

Content:
plicable to each DCS may be different. Acceptance criteria for the review of DCSs are based on meeting the relevant requirements of the regulations listed below. Requirements applicable to any DCS are as follows: 1. Title 10 of the Code of Federal Regulations (10 CFR) 50.54(jj) and 10 CFR 50.55(i). 2. 10 CFR 50.55a(h), “Protection and Safety Systems,” requires compliance with the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std) 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” and the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, the applicant or licensee may elect to comply instead with the plant-specific licensing basis. For nuclear power plants with construction permits issued between January 1, 1971, and May 13, 1999, the applicant or licensee may elect to comply instead with the requirements stated in IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” The minimum requirements that are applicable to all DCS are IEEE Std 603-1991, Clause 5.6.3, “Independence Between Safety Systems and Other Systems,” or IEEE Std 279-1971, Clause 4.7.2, “Isolation Devices,” or the plant-specific licensing basis, as defined by 10 CFR 50.55a(h), as noted above. 3. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion (GDC) 1, “Quality Standards and Records.” 4. GDC 24, “Separation of Protection and Control Systems.” Additional requirements applicable to all DCSs that support protection system functions reactor trip system (RTS) (SRP Section 7.2) or engineered safety features actuation system (ESFAS) (SRP Section 7.3): 1. 10 CFR 50.34(f)(2)(v), regarding automatic indication of bypassed and inoperable status of safety system equipment. 7.9-4 Draft Revision