Document: NUREG-0800
Document ID: 1df526d9-2ae0-4da2-b936-2e24b038ca8c
Document Type: srp
Title: DIVERSE INSTRUMENTATION AND CONTROL SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070650035.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.8
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Content:
e consistent with the applicant’s diversity and defense-in-depth analysis, and fulfill the applicable guidance of the SRM on SECY-93-087, Item II.Q. 6. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. 7. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. 8. 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 on prior NRC review and approval as noted [list applicable system or topics and identify references]. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. IEEE Std 279-1971. “Criteria for Protection Systems for Nuclear Power Generating Stations.” 7.8-11 Revision 5 - March 2007 2. IEEE Std 603-1991. “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.” 3. IEEE Std 7-4.3.2-2003. “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.” 4. Regulatory Guide 1.152. “Criteria for Digital Computers in Safety Systems of Nuclear Power Plants,” Office of Nuclear Regulatory Research, U.S.