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
CFR Part: 
CFR Title: 

Content:
ncern to the safety of the system, and therefore of minimal concern to the reviewer. The management indicators used and the process by which the project will be managed are primarily of concern to the software development organization, and should be reviewed only to the extent that safety of the final product is maintained. The same is true of the budget and personnel from the resource characteristics. The budget and number of personnel for the project is a trade-off with the length of time required, and therefore is of minimal concern. The adequacy of the budget and personnel for the quality assurance organization, the software safety organization and the software V&V organization is of interest, and should be reviewed to ensure that those groups have adequate resources to support a high quality design effort. This will require some judgment, and it may require a justification by the applicant or licensee or vendor. In addition, safety and V&V personnel should be competent in software engineering in order to ensure that software safety and software V&V are effectively implemented. A general rule of thumb is that the V&V personnel should be as least a qualified as the design personnel. B.3.1.2 Software Development Plan RG 1.173, “Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants,” endorses IEEE Std 1074, “IEEE Standard for Developing Software Life Cycle Processes,” subject to exceptions listed, as providing an approach acceptable to the staff, for meeting the regulatory requirements and guidance as they apply to development processes for safety system software. RG 1.152, “Criteria for Use of 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 Stations,” subject to the provisions and exceptions, provides BTP 7.14-18 Draft Revision 6 - August 2015 guidance for