Document: NUREG-0800
Document ID: cb6b6dfb-a102-4dfd-9dd3-2eba63985e8b
Document Type: srp
Title: INITIAL PLANT TEST PROGRAM - DESIGN CERTIFICATION AND NEW LICENSE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550027.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.2
CFR Part: 
CFR Title: 

Content:
r ensuring that all prerequisites for the given test have been met, adequate test instrumentation is available and used, and the test is performed under suitable environmental conditions. Test results should be documented and evaluated to ensure that test requirements have been satisfied. The SSCs that are subject to initial testing perform safety functions, including fission product containment and/or control, reactivity monitoring and control, reactor safe shutdown (including maintaining the safe shutdown), core cooling, accident prevention, and consequence mitigation, as specified in the design and as assumed/credited in safety analyses. The application of Section XI of Appendix B to 10 CFR Part 50 to the ITP ensures that DC, COL, and OL applicants provide all testing required to demonstrate that (1) SSC capabilities to perform specified/analyzed functions are initially verified with adequate precision and accuracy, (2) necessary SSC and plant baseline performance data are obtained, (3) deficiencies are identified and corrected, and (4) activities are conducted in a sequence and manner that minimizes operational 14.2-12 Revision 3 - March 2007 reliance on untested SSCs/safety functions. This provides a high degree of assurance of SSC and overall plant readiness for safe operation within the bounds of the design and safety analyses, protection against unexpected or unanalyzed SSC/plant behavior, and prevention of early SSC/safety function failures in service. 4. Appendix J to 10 CFR Part 50 requires, in part, that upon completion of construction of the primary reactor containment, including installation of all portions of mechanical, fluid, electrical, and instrumentation systems penetrating the primary reactor containment pressure boundary, and prior to any reactor operating period, preoperational leakage rate tests are conducted as specified (e.g., in Section III.A). The primary reactor containment provides a barrier against the release of fission products after