Document: NUREG-0800
Document ID: 65bf963b-2ae7-4caf-aee2-1ceabe52e775
Document Type: srp
Title: INITIAL PLANT TEST PROGRAM - FINAL SAFETY ANALYSIS REPORT1
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070650.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.2
CFR Part: 
CFR Title: 

Content:
initial testing activities will be conducted in a sequence and manner which minimizes operational reliance on untested SSCs/safety functions. 3. Appendix B to 10 CFR 50 requires, in Section XI, that a test program be established to assure that all testing required to demonstrate that SSCs will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents. The test program is required to include, as appropriate, proof tests prior to installation, preoperational tests, and operational tests of SSCs. Test procedures are required to include provisions for assuring 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. Test results are required to be documented and evaluated to assure that test requirements have been satisfied. Regulatory Guide 1.68 describes the general scope and depth acceptable to the NRC staff of the initial test program required by Section XI of Appendix B for light-water-cooled nuclear power plants. The SSCs which are subject to initial testing perform safety functions including fission product containment and/or control; reactivity monitoring and control; reactor safe shutdown (including maintaining safe shutdown); core cooling; accident prevention; and consequence mitigation as specified in the design and assumed/credited in safety analyses. Application of 10 CFR 50 Appendix B, Section XI to the initial test program ensures that SSC capabilities to perform these specified/analyzed functions are initially verified with adequate precision and accuracy, that necessary SSC and plant baseline performance data is obtained, that deficiencies are identified and corrected, and that activities are conducted in a sequence and manner which minimizes operational reliance on untested