Document: NUREG-0800
Document ID: f2ddec6c-0cce-4223-b813-233678ee07d0
Document Type: srp
Title: DIVERSE INSTRUMENTATION AND CONTROL SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B171.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.8
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Content:
REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of instrumentation and controls Secondary - None Review Note: The revision numbers of Regulatory Guides (RG) and the years of endorsed industry standards referenced in this Standard Review Plan (SRP) section are centrally maintained in SRP Section 7.1-T (Table 7-1). Therefore, the individual revision numbers of RGs (except RG 1.97) and years of endorsed industry standards are not shown in this section. References to industry standards incorporated by reference into regulation (IEEE Std 279-1971 and IEEE Std 603-1991) and industry standards that are not endorsed by the agency do include the associated year in this section. See Table 7-1 to ensure that the appropriate RGs and endorsed industry standards are used for the review. I. AREAS OF REVIEW This SRP section describes the review process and acceptance criteria for the diverse instrumentation and control (I&C) systems and equipment provided for the express purpose of protecting against potential common-cause failures of protection systems. 7.8-2 Draft Revision 6 – August 2015 The objectives of this review are to assure that the anticipated transient without scram (ATWS) mitigation systems and equipment are designed and installed in accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.62, “Requirements for Reduction of Risk from Anticipated Transients Without Scram (ATWS) Events for Light Water Cooled Nuclear Power Plants,” and that other diverse I&C systems within the scope of this section comply with the U.S. Nuclear Regulatory Commission (NRC) position on diversity and defense-in-depth (D3). 1. The following systems are covered by this section: • ATWS mitigation systems that are required for compliance with 10 CFR 50.62. As defined in 10 CFR 50.62, an ATWS event is an anticipated operational occurrence followed by failure of the reactor trip portion of the protection system. Regulations in 10