Document: NUREG-0800
Document ID: 4f141c71-35ca-4353-9047-a13efe6d56b7
Document Type: srp
Title: Revision 6 - August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A308.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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Content:
merical techniques described in or BTP 7.14-61 Revision 6 - August 2016 derived from the SDS. All parameters passed between software units should be consistent with respect to number, type, structure, physical units, and direction. Minimum and maximum execution times should be consistent with expected overall performance. Correctness means that the code implements all of the requirements in the SDS, and contains no features or functions that are not required. Style means that the programming style constraints specified in the design documents are followed. NUREG/CR-6463, “Review Guidelines on Software Languages for Use in Nuclear Power Plant Safety Systems,” provides guidance on coding practices to be avoided. In particular, data structures should be protected so that they cannot be changed simultaneously. Arrays should have a fixed, predefined length. Global variables and dynamic memory allocation should not be used. Traceability means that a two-way trace exists between the elements of the detailed design and the elements in code. A two-way trace should exist between the code elements and the specific software subsystem or system which contains that element during factory build and test. There should be a forward trace from each detailed design element to the specific inspections, analyses, or tests that will be used to confirm that the element has been correctly implemented. Verifiability means that it is possible to construct specific analyses, reviews, and tests to verify that the code correctly implements the detailed design. B.3.3.4.3 Review Guidance for CL In addition to the above, the CL should have sufficient comments and annotations that the intent of the code developer is clear. This is not only so the reviewer can understand and follow the code, but also so future modifications of the code are facilitated. Undocumented code should not be accepted as suitable for use in safety-related systems in nuclear power plants. The documentation should be