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
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Content:
or NRC review and approval as noted (list applicable system or topics and identify references). 3. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. 4. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” 2. IEEE Std 379, “IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems.” 7.9-13 Draft Revision 6 - August 2015 3. IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.” 4. IEEE Std -7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.” 5. NUREG/CR-6082, “Data Communications,” August 1993. 6. RG 1.22, “Periodic Testing of Protection System Actuation Functions.” 7. RG 1.47, “Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems.” 8. RG 1.53, “Application of the Single-Failure Criterion to Nuclear Power Plant Protection