Document: NUREG-0800
Document ID: fea61ff0-f344-4101-adfb-590e3d9dfafe
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A946.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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Content:
s produced acceptable design outputs. This branch technical position (BTP) provides guidelines for evaluating software life cycle processes for digital computer-based instrumentation and control (I&C) systems. These guidelines are based on reviews of applicant or licensee submittals, Electric Power Research Institute (EPRI) requirements for advanced reactor designs, and the analysis of standards and practices documented in NUREG/CR-6101, “Software Reliability and Safety in Nuclear Reactor Protection Systems.” The structure of the BTP is derived from the review process described in SRP, Appendix 7.0-A. It is assumed that the software development plans, described in this BTP, are implemented within a Quality Assurance (QA) program that conforms to regulatory requirements. The plans are assumed to augment and supplement the processes and procedures in the QA program. A.1 Regulatory Basis The regulatory bases are found in SRP Appendix 7.1-A, and are summarized below. 1. Title 10 of the Code of Federal Regulations (10 CFR) 50.54(jj) and 10 CFR 50.55(i) require that Structures, systems, and components subject to the codes and standards in 10 CFR 50.55a must be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. 2. 10 CFR 50.55a(h), “Protection and Safety Systems,” requires compliance with the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std) 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” and the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, the applicant or licensee may elect to comply instead with their plant specific licensing basis. For nuclear power plants with construction permits issued between January 1, 1971 and May 13, 1999 the applicant or licensee may elect to comply instead with the requirements