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:
tallation Plan (SInstP). • Software Maintenance Plan (SMaintP). • Software Training Plan (STrngP). • Software Operations Plan (SOP). • Software Safety Plan (SSP). • Software Verification and Validation Plan (SVVP). • Software Configuration Management Plan (SCMP). • Software Test Plan (STP). B.2.2 Software Life Cycle Process Implementation The information to be reviewed may be contained in the following: • Safety analyses. • Verification and validation analysis and test reports. • Configuration management reports. • Testing Activities. One or more sets of these reports should be available for each of the following activity groups: • Requirements. • Design. • Implementation. • Integration. • Validation. • Installation. BTP 7.14-10 Draft Revision 6 - August 2015 • Operations and maintenance. B.2.3 Software Life Cycle Process Design Outputs The information to be reviewed may be contained in the following: • Software requirements specifications (SRS). • Hardware and software architecture descriptions (SAD). • Software design specifications (SDS). • Code listings. • Build documents. • Installation configuration tables. • Operations manuals. • Maintenance manuals. • Training manuals. System requirements documents should also be examined to provide context for this review. B.3 Acceptance Criteria An appropriate set of life cycle activities is provided in RG 1.173, “Developing Software Life Cycle Processes for Digital Computer Software used in Safety Systems of Nuclear Power Plants,” which endorses IEEE Std 1074, “Standard for Developing Life Cycle Processes.” Commercial-off-the-shelf software and software embedded in commercial-off-the-shelf components, such as meters, circuit breakers, or alarm modules should be appropriately evaluated to confirm that required characteristics are met. EPRI Topical Report TR-106439, “Guideline on Evaluation and Acceptance of Commercial Grade Digital Equipment for Nuclear Safety