Document: NUREG-0800
Document ID: 1b73c7c7-6991-449e-9bea-daaea39fefa5
Document Type: srp
Title: INSTRUMENTATION AND CONTROLS - INTRODUCTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550076.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
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Content:
REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of instrumentation and controls Secondary - None I. AREAS OF REVIEW The objectives of the review of safety analysis report (SAR) Section 7.1 are to confirm (1) that the instrumentation and control (I&C) system design includes the functions necessary to operate the nuclear power plant safely under normal conditions and to maintain it in a safe condition under accident conditions, (2) that these functions, the implementing systems and equipment have been properly classified to identify their importance to safety, and (3) that commitments have been made to use appropriate quality standards for I&C systems for the design, fabrication, construction, and testing of I&C systems and equipment commensurate with the importance of the safety functions performed. 1. The necessary functions are those needed to monitor variables and systems over their anticipated operating ranges, to maintain these variables and systems within their prescribed operating ranges, to automatically initiate the operation of systems and components to assure that fuel design limits are not exceeded as a result of anticipated operational occurrences, and to sense accident conditions and initiate the operation of systems and components important to safety. 7.1-2 Revision 5 - March 2007 The I&C systems that perform these functions are within the scope of Standard Review Plan (SRP) Chapter 7. In typical reactor designs, these systems fall into the nine categories listed below. Protection and safety systems are I&C systems that initiate safety actions to mitigate the consequences of design basis events. Protection systems include reactor trip systems (RTSs) and engineered safety features actuation systems (ESFASs). A. The RTS initiates rapid control rod insertion to mitigate the consequences of anticipated operating occurrences or design basis events. RTS is discussed in Section 7.2 of the SAR. B. The ESFAS initiates and controls