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Combined License Application Review North Anna 3 (NA3) Safety - PowerPoint PPT Presentation

NRC-011 Combined License Application Review North Anna 3 (NA3) Safety Panel March 23, 2017 1 Panelists James Shea Senior Project Manager Vladimir Graizer PhD Geophysicist Manas Chakravorty Senior Structural Engineer


  1. NRC-011 Combined License Application Review North Anna 3 (NA3) Safety Panel March 23, 2017 1

  2. Panelists • James Shea – Senior Project Manager • Vladimir Graizer – PhD Geophysicist • Manas Chakravorty – Senior Structural Engineer • Matt Thomas – Reactor Systems Engineer 2

  3. Safety Panel Topics • Mineral, Virginia Earthquake • Certified Seismic Design Response Spectra (CSDRS) exceedances effect on Structure, Systems, and Components (SSCs) including reactor fuel 3

  4. NA3 Seismic Closure Plan 2014 • March 11, 2011, Fukushima event • August 23, 2011, Mineral, Virginia earthquake • Central Eastern United States- Seismic Source Characterization Model (CEUS-SSC) (2012) • The EPRI Ground Motion Model (GMM) updated (2013) 4

  5. Seismic Parameters UHRS: Uniform Hazard Response Spectra GMRS: Ground Motion Response Spectra FIRS: Foundation Input Response Spectra ISRS ISRS: In-Structure Response Spectra Structure CSDRS: Certified Seismic Design Response Spectra CSDRS Structure FIRS GMRS FIRS Soil UHRS (Rock ) Rock Earthquake (Sources) 5

  6. Safety Panel Topic 1 • Mineral Virginia Earthquake • ESBWR CSDRS Exceedance Vladimir Graizer – PhD Geophysicist Office of New Reactors 6

  7. Mineral, Virginia Earthquake August 23, 2011 • M5.8 11 miles from NA3 Site • Central Virginia Seismic Zone • Exceeded Design Basis Earthquake for NA1&2 • Staff requested reassessment of the NA3 Probabilistic Seismic Hazard Analysis (PSHA) 7

  8. North Anna Site and Mineral, Virginia Earthquake Mechanism of the earthquake was blind reverse fault with hypocenter located at the depth of 5 miles . From NA3 FSAR Figure 2.5.2-228 8

  9. Variance from ESP Variance NA3 (2013) ESP VAR 2.0-4: The applicant took a variance from values in the ESP because of: • Different building elevations than assumed in ESP • New CEUS-SSC model (NUREG- 2115 2012) and new Ground Motion Model (EPRI, 2013) • Mineral, Virginia earthquake 9

  10. Vibratory Ground Motion • Staff performed independent PSHA based on updated models • Staff confirmed that the site- specific COLA ground motion response spectra (GMRS) envelope the North Anna 3 site variations (FSER Chapter 2 Section 2.5.2) 10

  11. NA3 GMRS and ESBWR CSDRS 1.6 1.4 1.2 Spectral Acceleration, g 1.0 0.8 0.6 0.4 COLA GMRS, El. 224 ft ESP GMRS, El. 250 ft 0.2 ESBWR CSDRS 0.0 0.1 1 10 100 Frequency, Hz 11

  12. Mineral Earthquake Compared to ESBWR CSDRS 1.6 Earthquake North-South Motion 1.4 Earthquake Vertical Motion Spectral Acceleration, g 1.2 Earthquake East_West Motion 1 ESBWR_CSDRS 0.8 0.6 0.4 0.2 0 0.1 1 10 100 Frequency, Hz 12

  13. Conclusion • The site-specific GMRS adequately represents the seismic hazard at the NA3 site and meets the relevant regulatory requirements provided in 10 CFR Part 52 and 10 CFR Part 100 13

  14. Safety Panel Topic 2 CSDRS exceedances and its effect on NA3 site specific SSCs Manas Chakravorty – Senior Structural Engineer Office of New Reactors 14

  15. CSDRS exceedances affect NA3 site specific SSCs • Staff evaluation of the NA3 site specific SSCs analysis evaluated in FSER Chapter 3 Section 3.7 and Section 3.8 • NA3 Departure 3.7-1 • NA3 Exemption 3 15

  16. NA3 Site Foundation Input Response Spectra (FIRS) Comparison of the ESBWR CSDRS and CB FIRS 10 5% Damped Spectral Acceleration, g 1 0.1 ESBWR_CSDRS 0.01 FIRS_CB 0.001 0.1 1 10 100 Frequency, Hz 16

  17. Site-Specific Analyses Because of this exceedance, the applicant performed: • Site-specific analysis to establish seismic demand using FIRS • Site-specific evaluations of Category 1 structures, systems, and components 17

  18. Site-Specific Evaluation • Soil-structure interaction (SSI) analysis was performed to establish the site-specific seismic demand • Site-specific seismic demand including the In-Structure Response Spectra (ISRS) exceed DCD seismic demand 18

  19. Site-Specific Evaluation • Staff reviewed the standard design using the site specific seismic and standard design non- seismic loads which identified some site-specific design changes • Site-specific required changes include arrangement of rebar, the size of shear ties, welds, anchor bolts and a steel girder 19

  20. Site-Specific Evaluation • Staff verified by audit and confirmatory analysis that site- specific seismic demands using the standard methodology required some minor changes to the standard ESBWR • With these structural design changes, the design met ESBWR acceptance limits 20

  21. Site-Specific Evaluation • Site-specific ISRS that exceed standard design ISRS are used for qualification of equipment and components • ITAAC ensure that the Seismic Category I SSCs are qualified to the seismic design basis loads 21

  22. Conclusion • Staff confirmed that site-specific seismic loads and non-seismic standard loads with the identified design changes do not exceed structural acceptance limit of the ESBWR standard design • Therefore, with the identified changes, the ESBWR design is acceptable at the NA3 site 22

  23. Safety Panel Topic 3 Fuel Assembly and Control Rod Structural Response Matt Thomas – Reactor Systems Engineer Office of New Reactors 23

  24. Increased Seismic Loads • NA3 site-specific seismic exceedances (NA3 DEP 3.7-1) cause increased accelerations at the fuel assembly and control rods • Staff requested the applicant to perform an analysis to demonstrate that fuel assembly and control rod capacity limits are not exceeded under site-specific conditions 24

  25. Fuel and Control Rod Review • The staff reviewed the applicant’s site-specific analysis of the fuel assembly and control rod structural response using SRP 4.2 Appendix A • The staff conducted an audit of the site-specific calculations to confirm that the applicant followed the DCD methodology 25

  26. Conclusion • The staff found that the increase in the combined loading of the fuel assembly and control rod remains bounded by the approved capacity limits; therefore, the fuel assemblies and control rods meet GDC-2 2 26 6

  27. Acronyms • CB – Control Building • CEUS-SSC – Central and Eastern U.S. Seismic Source Characterization • COL – Combined Operating License • COLA – Combined Operating License Application • CSDRS – Certified Seismic Design Response Spectra 27

  28. Acronyms • DCD – Design Control Document • DEP – Departure from Standard Design • EPRI – Electric Power Research Institute • EPRI-SOG – Electric Power Research Institute – Seismic Owners Group • ESBWR – Economic Simplified Boiling Water Reactor 28

  29. Acronyms • ESP – Early Site Permit • FIRS – Foundation Input Response Spectra • GDC – General Design Criteria • GDC-2 – Appendix A to 10 CFR Part 50 - Criterion 2—Design bases for protection against natural phenomena • GMRS – Ground Motion Response Spectra 2 29 9

  30. Acronyms • ISRS – In-Structure Response Spectra • ITAAC – Inspections, Tests, Analyses, and Acceptance Criteria • NA3 – North Anna 3 • NA1&2 – North Anna Units 1&2 PSHA – Probabilistic Seismic Hazard Analysis • SRP – Standard Review Plan 3 30 0

  31. Acronyms • SSCs – Structures, Systems, and Components • SSE – Safe Shutdown Earthquake • SSI – Soil-structure interaction • UHRS – Uniform Hazard Response Spectra • VAR – Variance to NA3 ESP 3 31 1

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