Document: NUREG-0800
Document ID: fa9a9d5c-42ee-4507-b736-571f01da69cc
Document Type: srp
Title: CONTROL SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070670042.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.7
CFR Part: 
CFR Title: 

Content:
n certain DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. Review Interfaces 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 necessary 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 the review of I&C and other organizations. 2. In addition to the coordinated reviews discussed in SRP Section 7.0, the review of SRP Section 7.7 should be coordinated with the organizations responsible for the review of reactor systems and plant systems to confirm the adequacy of control systems with 7.7-3 Revision 5 - March 2007 respect to maintaining variables within operational limits during plant operation and to confirm that the impact of control system failures is appropriately included in the design basis accident analyses. 3. For those areas being reviewed as part of the primary review responsibility of other organizations, the acceptance criteria necessary for the review, and their methods of application, are contained in the SRP sections identified in SRP Appendix 7.1-A, subsection 2(e). The specific acceptance criteria and review procedures are contained in the reference SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 50.55a(a)(1). 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