Configuration Management in
New Reactor Construction
Tom Kozak, NRO/DCIP/CAEB
Thomas.kozak@nrc.gov
630-829-9866
cROP Regulatory Framework
License and regulate the use of
byproduct, source, and special
nuclear materials to ensure
adequate protection of the
public health and safety
CONSTRUCTION
REACTOR SAFETY
DESIGN/
ENGINEERING
PROCUREMENT/
FABRICATION
SAFEGUARDS
PROGRAMS
CONSTRUCTION/
INSTALLATION
INSPECTION/
TESTING
Baseline Inspection
Program
OPERATIONAL
READINESS
SECURITY
PROGRAMS for
CONSTRUCTION
INSPECTION
AND
OPERATIONS
Safety Conscious
Work Environment
Cross-Cutting Areas
OPERATIONAL
PROGRAMS
Construction Technical Finding SDP
Quality of Construction
AP 1000 Construction Significance Determination Matrix
Row 4
Row 3
Row 2
Row 1
Very Low
Low
Intermediate
System/Structure Risk Importance
High
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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
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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
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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
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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
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Vogtle Unit 3 and 4 March 2012
(courtesy of Southern Company)
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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.
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Example ITAAC Finding
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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.
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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).
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Basemat Rebar