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
CFR Part: 
CFR Title: 

Content:
puter software development process and design outputs, the staff concludes that the computer systems meet the guidance of RG 1.152, “Criteria for Digital Computers in Safety Systems of Nuclear Power Plants.” Therefore, the special characteristics of computer systems have been adequately addressed, and the staff finds that the diverse I&C systems satisfy the requirements of GDC 1. 3. Additional evaluation findings applicable to ATWS mitigation systems: The ATWS mitigation system instrumentation includes [summarize the basic functions and elements of the I&C system design submitted for review]. Based on the review of these functions and the design bases submitted by the applicant, the staff concludes that the ATWS mitigation design includes an appropriate set of functions. Based on review of the interfaces of the ATWS mitigation system and equipment with the RTS, the staff concludes that the separation and independence design features of the RTS are not compromised by the ATWS mitigation system design. Where isolation devices are provided in the RTS to support ATWS mitigation interfaces, the isolation devices are applied and qualified to the guidelines of SRP BTP 7-11, “Guidance on Application and Qualification of Isolation Devices.” 7.8-11 Revision 6 – August 2016 Based on the above items, the staff concludes that the design of the ATWS mitigation system is acceptable and satisfies the specific design requirements identified in 10 CFR 50.62 for [identify reactor type]. 4. Additional evaluation findings applicable to diverse I&C system manual controls and displays: Based on a review of diverse manual displays and controls, the staff concludes that these controls and displays are independent and diverse from the safety computer system, and sufficient for manual, system-level actuation of critical safety functions and monitoring of parameters that support the safety functions. Therefore, the staff concludes that the manual controls and displays fulfill the