Document: NUREG-0800
Document ID: dc958d35-16ef-4066-a1b5-bcfb8b0b4f0c
Document Type: srp
Title: INSTRUMENTATION AND CONTROLS - OVERVIEW OF REVIEW PROCESS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1007/ML100740146.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.0
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Content:
ia, and guidance in more detail and provides review guidance for each. Three IEEE standards play extensive roles in the review of I&C systems important to safety: (1) IEEE Std. 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations," (2) IEEE Std. 603-1991, "Criteria for Safety Systems for Nuclear Power Generating Stations," and (3) IEEE Std. 7-4.3.2-2003, "IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations." Because of their importance and breadth, the acceptance criteria, guidance, and associated review methods in these three standards are discussed separately in SRP Appendices 7.1-B, 7.1-C, and 7-1.D. SRP Sections 7.2 through 7.9 address the I&C systems important to safety that are typically included in a plant design. These sections summarize the review scope and acceptance criteria applicable to each system but reference the appendices of SRP Section 7.1 for the details of requirements, guidance, and review methods. The discussion of review procedures in SRP Sections 7.2 through 7.9 also highlights review topics that have in the past required the most attention by reviewers. 7.0-3 Revision 6 - May 2010 For some review topics, branch technical positions (BTPs) have been prepared to resolve technical problems or questions of interpretation that arose during plant reviews. The BTPs are separated from the discussion in the Appendices of SRP Section 7.1 to avoid drowning the overall discussion of acceptance criteria and review methods with details about specific topics. The appendices of SRP Section 7.1 and the Review Procedures discussion of SRP Sections 7.2 through 7.9 reference these BTPs. II. APPLICATION TYPES The type of application under review largely determines the review activities to be conducted and impacts the complexity and scope of the review. NRC regulations provide for the following types of license applications relevant to nuclear power reactors. 1. Construction permits (CPs)