Document: NUREG-0800
Document ID: 14c7085e-8b87-4b50-97fb-a095ea003ae8
Document Type: srp
Title: describes the general procedures to be followed in reviewing any I&C system. Procedures for
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500511.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
itional evaluation findings applicable to DAS: Based on review of the design bases submitted by the applicant, the Staff concludes that the DAS is acceptable. The functional requirements, independence requirements, and diversity requirements for this system are consistent with the applicant's defense-in-depth and diversity analysis, and fulfill the applicable requirements of the SRM on SECY-93-087, item II.Q. Note: the following conclusion is applicable to all applications. The conclusions noted above for the diverse I&C systems 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/licensee proposes an acceptable alternative method for complying with specified portions of the NRC's regulations, the method described herein will be used by the NRC staff in its evaluation of conformance with NRC regulations. Implementation schedules for conformance to the method discussed herein are contained in 10 CFR 50.62, the 10 CFR 50.62 considerations identified in the Federal Register Notice (FR Vol. 49, No. 124), and Generic Letter 85-06. VI. References ANSI/IEEE Std 279-1971. "Criteria for Protection Systems for Nuclear Power Generating Stations." Federal Register 49 FR 26042. "Statement of Considerations for the ATWS Rule," 10 CFR 50.62. Generic Letter 85-06. "Quality Assurance Guidance for ATWS Equipment that is not Safety-Related," April 16, 1986. IEEE Std 603-1991. "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." Regulatory Guide 1.152. "Criteria for Digital Computers in Safety Systems of Nuclear Power Plants," Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1996. Regulatory Guide 1.153. "Criteria for Power, Instrumentation, and Control Portions of Safety Systems," Office of Nuclear Regulatory