Document: NUREG-0800
Document ID: a8853b5a-7119-4e4d-8880-496c64ff5b6c
Document Type: srp
Title: INSTRUMENTATION AND CONTROLS - INTRODUCTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A050.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
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CFR Title: 

Content:
, 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. The I&C systems that perform these functions are within the scope of 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 safety equipment that remove heat or otherwise assist with maintaining the integrity of the physical barriers to radioactive release - cladding, reactor coolant pressure boundary, and containment. ESFAS is discussed in Section 7.3 of the SAR. C. Safe shutdown systems function to achieve and maintain a safe shutdown condition of the plant. The safe shutdown systems include I&C systems used to maintain the reactor core in a subcritical condition and provide adequate core cooling to achieve and maintain both hot and cold shutdown conditions. Safe shutdown systems are discussed in Section 7.4 of the SAR. D. Information systems important to safety provide information for the safe operation of the plant during normal operation, anticipated operational occurrences, and accidents, and include systems that provide information for manual initiation and control of safety systems. These systems indicate that plant safety functions are being accomplished and provide information from which appropriate