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:
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 SSCs/safety functions. This provides high degrees of assurance of SSC and overall plant readiness for safe operation within the bounds of the design and safety analyses, assurance against unexpected or unanalyzed SSC/plant behavior, and assurance against early SSC/safety function failures in service. 4. Appendix J to 10 CFR 50 requires that upon completion of construction of the primary reactor containment, preoperational leakage rate tests be conducted as specified therein (e.g., in Section III.A). The primary reactor containment provides a barrier against the 14.2-11 DRAFT Rev. 3 - April 1996 release of fission products following accidents. The extent of overall containment leakage at pressures attendant with accident conditions affects the public dose and environmental damage consequences of accidents. Application of 10 CFR 50, Appendix J to the initial test program ensures that the performance of the containment as a leakage barrier is as specified in the design and assumed/credited in safety analyses which evaluate public dose and environmental consequences of design basis accidents. III. REVIEW PROCEDURES Preparation for the review of Chapter 14 of the applicant's FSAR should include the following: 51 1. Review of the Commission's any related Safety Evaluation Report(s) that was issued upon review of a referenced standard design and/or the Construction Permit application . 52 This review is conducted for the purpose of familiarization with the principal design criteria for the facility and to identify any specific staff or ACRS concerns or unique design features that may warrant special test consideration. 2. Review of Chapters 1 through 12 of the FSAR for the purpose of familiarization with 53 the facility design and the nomenclature that is applied to