Document: NUREG-0800
Document ID: 6cac2015-4823-4421-9a34-1ee7f23d1ec2
Document Type: srp
Title: or ESFAS — Section 7.3):
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500512.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
so supported by the DCS design to achieve (1) prompt, hot shutdown of the reactor, and Rev. 4 — June 1997 SRP 7.9-10 (2) subsequent cold shutdown of the reactor. Therefore, we conclude that the DCSs employed by the diverse I&C system satisfy the requirements of GDC 19. Note: the following conclusion is applicable to all applications. The conclusions noted above for the DCS are applicable to all portions of the systems except for the following, for which acceptance is based upon prior NRC review and approval as noted [List applicable system or topics and identify references]. V. Implementation Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the NRC's regulations, as they regard the DCS, the method described herein will be used by the Staff in its evaluation of conformance with NRC regulations. For implementation of a DCS via the design acceptance criteria (DAC) and ITAAC approach to design certification, see Chapter 14 of the SRP. VI. References ANSI/IEEE Std 279-1971. "Criteria for Protection Systems for Nuclear Power Generating Stations." Draft Regulatory Guide DG-1045. Proposed Revision 3 to Regulatory Guide 1.105, "Instrument Setpoints for Safety Systems." Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997. IEEE Std 603-1991. "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." IEEE Std 7-4.3.2-1993. "IEEE Standard for Digital Computers in Safety Systems of Nuclear Power Generating Stations." NUREG/CR-6082. "Data Communications." August 1993. Regulatory Guide 1.22. "Periodic Testing of Protection System Actuation Functions." Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1972. Regulatory Guide 1.47. "Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems." Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1973. Regulatory Guide 1.53. "Application