Document: NRC Regulatory Guide
Document ID: 12dd3f35-6baa-4f6a-8372-84c90ef96a91
Document Type: regulatory_guide
Title: Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants + HISTORY - HISTORY 08/2012 – DG-1207 , Proposed Revision 1 08/1996 – DG-1056 , Proposed Revision 0 (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0833/ML083370243.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.170
CFR Part: 
CFR Title: 

Content:
ure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures that incorporate the requirements and acceptance limits contained in applicable design documents. Test procedures must include provisions for ensuring that all prerequisites for the given test have been met, that adequate test instrumentation is available and used, and that the test is performed under suitable environmental conditions. Criterion XI also requires that test results be documented and evaluated to ensure that test requirements have been satisfied. DG-1207, Page 4 • Criterion XVII, “Quality Assurance Records,” requires, in part, that the sufficient quality records be maintained so that specific itemized records for test documentation and controlled by the SCM as the software evolves with development and maintenance are identifiable and retrievable. Test records must identify the inspector or data recorder, the type of observation made, the results, the acceptability of the results, and the action taken in connection with any noted deficiencies. Accepted practice for the development of software for safety-related applications includes the use of a software life-cycle process that incorporates software testing activities (e.g., IEEE Std. 1074-2006, “IEEE Standard for Developing a Software Life Cycle Process” (Ref. 8)). Software testing is a key element in software verification and validation (V&V) activities, as indicated by IEEE Std. 1012-2004, “IEEE Standard for Software Verification and Validation” (Ref. 9), as endorsed by Regulatory Guide 1.168, “Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants” (Ref. 10), and as indicated by IEEE Std. 7-4.3.2-2003, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations” (Ref. 11), as