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:
perating 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 accidents. The extent of overall containment leakage at pressures associated with accident conditions affects the public dose and environmental damage consequences of accidents. Application of Appendix J to the ITP ensures that the containment performs as a leakage barrier as specified in the design and as assumed/credited in safety analyses that evaluate the public dose and environmental consequences of design- basis accidents. 5. 10 CFR 52.47(b)(1) requires DC applicants to include in the application the proposed ITAAC that are sufficient to ensure that the SSCs in this area of review are built and will operate in accordance with the certification and the Commission’s regulations. The ITP is described as Tier 1 information because of the essential role of a test program in verifying that SSCs have been constructed and will perform satisfactorily in service. The Tier 1 description directs that the ITP is performed under suitably controlled conditions and processes. The development of test procedures, conduct of the tests, and safe execution of the test program are important considerations in ensuring that the as-built facility is in accordance with the DC and applicable regulations. Thus, the staff will have reasonable assurance that the ITP will be implemented effectively by the COL or OL applicant who references the certified design. 6. 10 CFR 52.79 requires that each COL application contain a final SAR (FSAR) that describes the facility, presents the design bases and the limits on its operation, and presents a safety analysis of the SSCs and of the facility as a whole, including plans for preoperational testing and initial operations. A major ITP objective (including preoperational testing and testing during initial operation) is to verify that SSCs are capable