Document: NUREG-0800
Document ID: 3bfd6067-581b-482f-bfda-c7f2ef7fad32
Document Type: srp
Title: INSTRUMENTATION AND CONTROLS - OVERVIEW OF REVIEW PROCESS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A049.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.0
CFR Part: 
CFR Title: 

Content:
generic safety evaluations of specific topics. Guidance is also provided to the reviewer in applying Chapter 7 of the SRP to these reviews. Figure 7.0-1 provides an overview of the I&C review process. Each of the reviewer activities shown in the figure is discussed below. Ideally, applicants will request that the staff's review begin during the early stages of the development life cycle. Early interaction with the applicant is important so that differences between the staff and the applicant are identified as early as possible. The staff should work with the applicant to resolve issues expeditiously to minimize the impact on design and implementation activities. Early resolution of fundamental issues minimizes the rework necessary in areas where changes to the design bases are needed to resolve staff concerns. This helps assure that changes are correctly propagated through the design effort, thus improving the staff's confidence in design quality. Structure of SRP Chapter 7 Figure 7.0-2 illustrates the structure of SRP Chapter 7. SRP Section 7.0 should be the entry point for any I&C review activity. It discusses the different types of applications I&C reviewers may encounter, the information expected to accompany each application, the general scope of the I&C review, and the expected interfaces with other elements of a plant review. SRP Section 7.0 also encourages the reviewer to develop a review plan to guide review activities and to communicate expectations to management and the applicant. SRP Appendix 7.0-A, “Review Process for Digital Instrumentation and Control Systems,” is provided to explain the general philosophy and approach to the review of digital computer-based systems. The NRC standard format and content guides, RG 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition),” and RG 1.206, “Combined License Applications for Nuclear Power Plants (LWR Edition),” advise the applicant that SRP Section