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

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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


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SLIDE 1

Combined License Application Review North Anna 3 (NA3)

Safety Panel March 23, 2017

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NRC-011

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SLIDE 2

Panelists

  • James Shea – Senior Project

Manager

  • Vladimir Graizer – PhD

Geophysicist

  • Manas Chakravorty – Senior

Structural Engineer

  • Matt Thomas – Reactor Systems

Engineer

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SLIDE 3

Safety Panel Topics

  • Mineral, Virginia Earthquake
  • Certified Seismic Design Response

Spectra (CSDRS) exceedances effect on Structure, Systems, and Components (SSCs) including reactor fuel

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SLIDE 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)

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SLIDE 5

Seismic Parameters

UHRS (Rock ) GMRS FIRS ISRS

Rock Soil Earthquake (Sources)

UHRS: Uniform Hazard Response Spectra GMRS: Ground Motion Response Spectra FIRS: Foundation Input Response Spectra ISRS: In-Structure Response Spectra CSDRS: Certified Seismic Design Response Spectra

Structure

FIRS

Structure

5 CSDRS

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SLIDE 6
  • Mineral Virginia Earthquake
  • ESBWR CSDRS Exceedance

Vladimir Graizer – PhD Geophysicist Office of New Reactors

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Safety Panel Topic 1

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SLIDE 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)

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SLIDE 8

North Anna Site and Mineral, Virginia Earthquake

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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

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SLIDE 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

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SLIDE 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)

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SLIDE 11

NA3 GMRS and ESBWR CSDRS

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0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 0.1 1 10 100

Spectral Acceleration, g

Frequency, Hz

COLA GMRS, El. 224 ft ESP GMRS, El. 250 ft ESBWR CSDRS

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SLIDE 12

Mineral Earthquake Compared to ESBWR CSDRS

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0.2 0.4 0.6 0.8 1 1.2 1.4 1.6 0.1 1 10 100

Spectral Acceleration, g

Frequency, Hz

Earthquake North-South Motion Earthquake Vertical Motion Earthquake East_West Motion ESBWR_CSDRS

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SLIDE 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

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SLIDE 14

Safety Panel Topic 2

CSDRS exceedances and its effect

  • n NA3 site specific SSCs

Manas Chakravorty – Senior Structural Engineer Office of New Reactors

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SLIDE 15

CSDRS exceedances affect NA3 site specific SSCs

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  • 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
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SLIDE 16

NA3 Site Foundation Input Response Spectra (FIRS)

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0.001 0.01 0.1 1 10 0.1 1 10 100 5% Damped Spectral Acceleration, g Frequency, Hz

Comparison of the ESBWR CSDRS and CB FIRS

ESBWR_CSDRS FIRS_CB

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SLIDE 17

Site-Specific Analyses

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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

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SLIDE 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

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SLIDE 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

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SLIDE 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

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SLIDE 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

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SLIDE 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

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SLIDE 23

Safety Panel Topic 3 Fuel Assembly and Control Rod Structural Response

Matt Thomas – Reactor Systems Engineer Office of New Reactors

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SLIDE 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

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SLIDE 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

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SLIDE 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

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SLIDE 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

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SLIDE 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

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SLIDE 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

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SLIDE 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

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SLIDE 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

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