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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sidered this risk. The use of commercial software and hardware may be attractive due to cost, schedule and availability, but there is some risk that a commercial grade dedication process will show the items to lack the quality necessary for use in safety-related systems in nuclear power plants. The SDP should clearly state which tasks are a part of each life cycle, and state the life cycle inputs and outputs. The review, V&V of those outputs should be defined. Under the Resource Characteristics, the methods and tools to be used should be evaluated. Of particular interest is the method by which the output of software tools, such as compilers or assemblers, will be verified to be correct. The criteria from IEEE Std 7-4.3.2 is that software tools should be used in a manner such that defects not detected by the software tool will be detected by V&V activities. If this is not possible, the tool itself should be safety-related. The SDP should list the international, national, industry, and company standards and guidelines, including RGs, which will be followed. The reviewer needs to determine if these standards and guidelines have previously been approved by the staff, and if not, the standard needs to be reviewed to ensure that following that standard will result in meeting NRC requirements. Coding standards should be checked against the suggestions contained in NUREG/CR-6463, “Review Guidelines for Software Languages for Use in Nuclear Power Plant Safety Systems,” and the applicant or licensee should be asked to justify any deviations. B.3.1.3 Software Quality Assurance Plan (SQAP) Typically a SQAP will be implemented under an NRC approved QA program, such as one deemed acceptable by RG 1.28, “Quality Assurance Program Criteria (Design and Construction),” which endorses ASME NQA-1, “Quality Assurance Requirements for Nuclear Facility Applications,” and the ASME NQA-1a Addenda, “Addenda to ASME NQA-1-2008 Quality Assurance Requirements for Nuclear Facility