Document: NUREG-0800
Document ID: b6428ab0-2037-4bac-9b93-b46af9f2fdfb
Document Type: srp
Title: DATA COMMUNICATION SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070650036.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.9
CFR Part: 
CFR Title: 

Content:
ces Other SRP sections interface with this section as follows: 1. SRP Section 7.0 describes the coordination of reviews, including the information to be reviewed and the scope required for each of the different types of applications that the staff may review. Refer to that section for information regarding how the areas of review are affected by the type of application under consideration and for a description of coordination between the organization responsible for review of I&C systems and other review organizations. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 7.9-3 Revision 5 - March 2007 The requirements applicable to DCSs derive from the requirements for the system(s) supported by the DCS. The requirements for a specific DCS are the union of those requirements applicable to the systems supported by that DCS. A given plant design may contain more than one DCS. In this case, the requirements applicable 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. 10 CFR 50.55a(a)(1), “Quality Standards for Systems Important to Safety.” 2. 10 CFR 50.55a(h), “Protection and Safety Systems,” requires compliance with IEEE 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/ 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/licensee may elect to comply instead with the requirements stated