Document: NUREG-0800
Document ID: b3d7a8f7-62f4-4ace-b8c7-32606edaa8f5
Document Type: srp
Title: CONTROL SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B161.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.7
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view of a COL application, the scope of the review is dependent on whether the COL applicant references a DC, an early site permit or other NRC approvals (e.g., manufacturing license, site suitability report or topical report). 3. For review of both DC and COL applications, SRP Section 14.3 should be followed for the review of ITAAC. The review of ITAAC cannot be completed until after the completion of this section. IV. EVALUATION FINDINGS The reviewer verifies that the applicant has provided sufficient information and that the review and calculations (if applicable) support conclusions of the following type to be included in the staff’s safety evaluation report. The reviewer also states the bases for those conclusions. 1. The NRC staff concludes that the design of the control systems is acceptable and meets the relevant requirements of General Design Criteria 1, 10, 13, 15, 19, 24, 28, 29, and 44, and of 10 CFR 50.34(f), 10 CFR 50.54(jj) and 50.55(i), and 10 CFR 50.55a(h). The staff conducted a review of these systems for conformance to the guidelines in the RGs and industry codes and standards applicable to these systems. The staff concluded that the applicant or licensee adequately classified and identified the guidelines applicable to these systems. The staff finds that the control systems are appropriately designed and are of sufficient quality to minimize the potential for challenges to safety systems. Based upon the review of the system design, the staff finds that there is reasonable assurance that the systems fully conform to the applicable guidelines. Therefore, the staff finds that the requirements of GDC 1 and 10 CFR 50.54(jj) and 50.55(i) have been met. The staff conducted a review of the plant transient response to normal load changes and anticipated operational occurrences such as reactor trip, turbine trip, upsets in the feedwater, and steam bypass systems. The staff concludes that the control systems are capable of maintaining system variables