Document: NUREG-0800
Document ID: 0a15bfe3-b20f-42c5-a9ae-f05462e14c42
Document Type: srp
Title: REACTOR TRIP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A059.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

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ning, that the licensee shall perform, and the acceptance criteria that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, the facility has been constructed and will operate in conformity with the COL, the provisions of the Atomic Energy Act, and the NRC’s regulations. SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC‘s regulations identified above are contained in SRP Section 7.1, “Instrumentation and Controls – Introduction," SRP Table 7-1, and SRP Appendix 7.1-A, “Acceptance Criteria and Guidelines for Instrumentation and Controls Systems Important to Safety,” which list standards, RGs, and branch technical positions (BTPs). The SRP is not a substitute for the NRC‘s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. 1. SRP Appendix 7.1-B, “Guidance for Evaluation of Conformance to IEEE Std 279,” provides guidance for evaluating conformance to the requirements of IEEE Std 279-1971. 7.2-5 Revision 6 – August 2016 2. SRP Appendix 7.1-C, “Guidance for Evaluation of Conformance to IEEE Std 603,” provides guidance for evaluating conformance to IEEE Std 603 1991. 3. SRP Appendix 7.1-D, “Guidance for Evaluation of the Application of IEEE Std 7-4.3.2,” provides guidance for evaluating conformance to the acceptance criteria contained in RG 1.152, “Criteria for Digital Computers in Safety Systems of Nuclear Power Plants,” which endorses IEEE Std 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating