Document: NUREG-0800
Document ID: fe8ec6c2-e960-404c-854f-55c77bde1672
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML2400/ML24005A077.pdf
Revision Date: 2024-05
Chapter: 7
Section ID: 7
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Content:
w light-water reactor are based on RG 1.206, “Combined License Applications for Nuclear Power Plants (LWR Edition).” These documents are made available to the public as part of the NRC's policy to inform the nuclear industry and the general public of regulatory procedures and policies. Individual sections of NUREG-0800 will be revised periodically, as appropriate, to accommodate comments and to reflect new information and experience. Comments may be submitted by email to NRR_SRP@nrc.gov. Requests for single copies of SRP sections (which may be reproduced) should be made to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section; by fax to (301) 415-2289; or by email to DISTRIBUTION@nrc.gov. Electronic copies of this section are available through the NRC's public website at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800, or in the NRC's Agencywide Documents Access and Management System, at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML24005A077. BTP 7-19-2 Revision 9 — May 2024 The overall objective of this branch technical position (BTP) is to provide criteria for the NRC staff’s evaluation of the acceptability of the applicant’s assessment of the effects of digital I&C (DI&C) system common-cause failures (CCFs). The acceptance criteria provided in this BTP are not limited to performance characteristics of I&C systems but instead address plant performance in response to CCFs of DI&C systems. Therefore, the evaluation activities described in this BTP are not intended to be assigned exclusively to I&C technical review staff. For any given project, the activities should be coordinated and distributed among the various technical review disciplines so that the correct area of review and level of expertise are applied to the evaluation effort. For example, a reactor safety system engineer should perform the evaluation of a best-estimate analysis for each