1. Configuration Management in New Reactor Construction Tom Kozak, NRO/DCIP/CAEB Thomas.kozak@nrc.gov 630-829-9866

2. CONSTRUCTION REACTOR SAFETY License and regulate the use of byproduct, source, and special nuclear materials to ensure adequate protection of the public health and safety DESIGN/ ENGINEERING CONSTRUCTION/ INSTALLATION PROCUREMENT/ FABRICATION INSPECTION/ TESTING SAFEGUARDS PROGRAMS OPERATIONAL READINESS SECURITY PROGRAMS for CONSTRUCTION INSPECTION AND OPERATIONS OPERATIONAL PROGRAMS Cross-Cutting Areas Baseline Inspection Program Safety Conscious Work Environment cROP Regulatory Framework

3. AP 1000 Construction Significance Determination Matrix Quality of Construction Row 4 Row 3 Row 2 Row 1 Very LowLow Intermediate High System/Structure Risk Importance Construction Technical Finding SDP

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5. Standard Design Certifications Allows NSSS vendor/applicant to obtain pre-approval of design Certified design becomes an Appendix to Part 52 Reduces licensing uncertainty by resolving design issues early Facilitates standardization Facilitates regulatory finality through rulemaking Certification good for 15 yrs + renewal 5

6. Design Certification via Rulemaking Part 52 Appendix A – GE ABWR Appendix B – C-E System 80+ Appendix C – Westinghouse AP-600 Appendix D – Westinghouse AP-1000 Appendix E - Next Design Appendix F - Future Design So on 6

7. Combined License Combined construction permit and operating license with conditions Contain ITAAC which must be met in order to operate the plant (condition) Fundamental licensing process in Part 52 for reducing financial risk of applicants/licensees Can reference ESP, Certified Design, Design Approval, Manufacturing License, or none Lasts 40 yrs + renewal 7

8. Combined Licenses Issued by NRC Vogtle Units 3 and 4 COLs issued on February 10, 2012 Summer Units 2 and 3 COLs issued on March 30, 2012 NRC construction inspection program consists of region-based and resident inspectors 3 construction resident inspectors assigned to Summer Units 2 and 3 3 construction resident inspectors assigned to Vogtle Units 3 and 4 8

10. Vogtle Unit 3 and 4 March 2012 (courtesy of Southern Company) 10

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12. ITAAC ITAAC – the inspections, tests, and analyses that the licensee shall perform, and the acceptance criteria that, if met, are necessary and sufficient to provide reasonable assurance that the facility has been constructed and will be operated in conformity with the license, the provisions of the Act, and the Commission’s regulations. ITAAC are essentially the design requirements for the facility being constructed There are approximately 850 ITAAC in the combined licenses for Vogtle Units 3 and 4 and Summer Units 2 and 3. 12

13. Example ITAAC Finding 13

14. Example ITAAC Finding Continued Design Requirement: The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category I and are designed and constructed to withstand design basis loads as specified in the Design Description, without loss of structural integrity and the safety-related functions. Facility Configuration Information: The design control document provides the reinforcement configuration (rebar) of the connection of the nuclear island basemat with the south exterior wall of the auxiliary building on Column Line 1. In this figure, the top and bottom reinforcement layers are shown as being anchored in the wall with hooks. Physical Configuration: NRC inspectors observed that the lower basemat reinforcement was not anchored into the exterior walls of the auxiliary building around the perimeter of the nuclear island. 14

15. Example ITAAC Finding Continued Construction drawing was revised by the licensee to modify the connection detail between the basemat and the exterior walls of the auxiliary building around the perimeter of the nuclear island by deleting the hooks at the ends of the layers 1, 2, 4 and 5 reinforcement bars. This change required a license amendment prior to implementation. Failure to translate design basis into instructions (10 CFR 50, Appendix B, Criteria III violation). Failure to obtain required NRC approval of design change (similar to a 10 CFR 50.59 violation). 15

16. Basemat Rebar