Document: NUREG-0800
Document ID: 1df526d9-2ae0-4da2-b936-2e24b038ca8c
Document Type: srp
Title: DIVERSE INSTRUMENTATION AND CONTROL SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070650035.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.8
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Content:
.g., interface requirements and site parameters). For a COL application referencing a DC, a COL applicant must address COL action items (referred to as COL license information in 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 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 the review of I&C and organizations responsible for other review topics. 7.8-3 Revision 5 - March 2007 2. In addition to the coordination described in SRP Section 7.0, the organization responsible for the review of reactor systems evaluates the following aspects of the diverse I&C systems: • Consistency of the ATWS mitigation protective functions with the requirements of 10 CFR 50.62 and the ATWS analysis referenced in the safety analysis report (SAR), Chapter 15, for anticipated operational occurrences and to verify the adequacy of the design of mechanical systems used to mitigate ATWS. • The adequacy of the set of manual control and display functions is reviewed to confirm it is sufficient to monitor the plant states and to actuate systems required by the control room operators to place the nuclear plant in a hot-shutdown condition and to control the following critical safety functions: reactivity control, core heat removal, reactor coolant inventory, containment isolation, and containment integrity. • For plants with a digital RTS or ESFAS, DAS functions and other D3-related functions are reviewed to confirm