Document: NUREG-0800
Document ID: 6f2ffbec-a876-42d7-a247-d27c02ea9b4a
Document Type: srp
Title: DIVERSE INSTRUMENTATION AND CONTROL SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A096.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.8
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CFR Title: 

Content:
for a description of coordination between the organization responsible for the review of I&C and organizations responsible for other review topics. 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 that they are consistent with the portions of the accident analysis that support the D3 analysis. The specific acceptance criteria and review procedures are contained in the reference SRP sections. 7.8-4 Revision 6 – August 2016 II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 50.54(jj) and 10 CFR 50.55(i). 2. 10 CFR 50.55a(h), “Protection and Safety Systems,” requires compliance with the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std) 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” and the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, the