ML18129A424

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Advanced Framatome Methods LAR - NRC Pre-Application Meeting
ML18129A424
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 05/10/2018
From:
Susquehanna
To:
Office of Nuclear Reactor Regulation
Hood T
References
Download: ML18129A424 (12)
v • d • e


Text

Susquehanna - Advanced Framatome Methods LAR NRC Pre-Application Meeting

=

Background===

[This version redacts information considered to be confidential]

  • During a site visit on 04/13/18, Talen Energy and the NRC discussed Susquehannas intent to submit an LAR to adopt advanced Framatome methods
  • Advanced Framatome methods are needed to support ATRIUM 11* deployment
  • Advanced Framatome methods approval is needed by

[REDACTED] to support the first reload of ATRIUM 11

  • This application will not be a first of a kind deployment

2

Background (cont)

  • Information will be provided on, Motivation for LAR Proposed Milestones / Schedule LAR Content o Staged submittal for some cycle specific items for first reload of ATRIUM 11 LAR Methodologies o Generic advanced Framatome methods o Other technical considerations 3

Motivation for LAR

  • Susquehanna has operated ATRIUM 10 fuel design since 1997
  • Talen Energy desires to deploy ATRIUM 11 fuel in reload quantities 11x11 array reduces LHGR improving safety margin Improved debris protection features (fuel failure risk reduction)

Improved channel performance and fuel economics

  • First ATRIUM 11 Reloads Unit 2 Cycle 21 - Startup [REDACTED]

Unit 1 Cycle 23 - Startup [REDACTED]

4

Proposed Milestones

  • Transition cores will only contain Framatome fuel types Currently operating with full cores of ATRIUM 10 No multi-vendor core issues to review
  • Date for LAR Submittal

[REDACTED]

  • SER need date to support first ATRIUM 11 Reload

[REDACTED]

[REDACTED] months available for review of Advanced Framatome Methods LAR 5

LAR Content

  • Reports submitted with LAR based upon SSES equilibrium ATRIUM 11 Design:

Assembly Mechanical Design reports Methods Applicability Supplement Document Thermal Hydraulic Design Report LOCA / MAPLHGR Report BWR Licensing Methodology Compendium o Updated for new methods (AURORA-B [LOCA / Transients and Accidents / CRDA],

ACE / ATRIUM 11, SAFLIM3D, RODEX4, and Cr-Doped fuel) 6

LAR Content (cont)

  • Reports submitted with LAR based upon SSES equilibrium ATRIUM 11 Design (continued):

Fuel Cycle Design Report Nuclear Fuel Bundle Design Report Fuel Rod Design Report AURORA-B Limiting Transient Analysis Uncertainty Demonstration 7

LAR Content (cont)

  • Implementation cycle reports will be submitted after the LAR for information on a slightly accelerated licensing analysis schedule Fuel Cycle Design Report Nuclear Fuel Bundle Design Report Safety Limit MCPR Report Fuel Rod Design Report Reload Safety Analysis Report 8

LAR Content: TS 5.6.5 Additions

  • Framatome Thermal-mechanical methodologies BAW-10247P-A, Revision 0 Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors BAW-10247P-A, Supplement 1P-A, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 1: Qualification of RODEX4 for Recrystallized Zircaloy-2 Cladding BAW-10247P-A, Supplement 2P, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 2: Mechanical Methods ANP-10340P Revision 0, Incorporation of Chromium-Doped Fuel in AREVA Approved Methods 9

LAR Content: TS 5.6.5 Additions (cont)

  • Framatome Licensing methodologies ANP-10335P Revision 0, ACE/ATRIUM 11 Critical Power Correlation ANP-10300P-A Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios ANP-10332P Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios ANP-10333P Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident Scenarios ANP-10307P-A Revision 0 AREVA MCPR Safety Limit Methodology for Boiling Water Reactors 10

LAR Methodologies: Framatome Generic

  • It is anticipated that all required Framatome generic methodologies will be approved by the time of submittal
  • TN-B1 License for ATRIUM 11 Shipments Updated SAR submitted - NRC Approval Expected by Spring 2019 11

Summary

  • Proposed date for LAR submittal - [REDACTED]
  • SER need date - [REDACTED]
  • [REDACTED] month LAR review
  • LAR will request the addition of advanced Framatome methodologies 12

Susquehanna - Advanced Framatome Methods LAR NRC Pre-Application Meeting

=

Background===

[This version redacts information considered to be confidential]

  • During a site visit on 04/13/18, Talen Energy and the NRC discussed Susquehannas intent to submit an LAR to adopt advanced Framatome methods
  • Advanced Framatome methods are needed to support ATRIUM 11* deployment
  • Advanced Framatome methods approval is needed by

[REDACTED] to support the first reload of ATRIUM 11

  • This application will not be a first of a kind deployment

2

Background (cont)

  • Information will be provided on, Motivation for LAR Proposed Milestones / Schedule LAR Content o Staged submittal for some cycle specific items for first reload of ATRIUM 11 LAR Methodologies o Generic advanced Framatome methods o Other technical considerations 3

Motivation for LAR

  • Susquehanna has operated ATRIUM 10 fuel design since 1997
  • Talen Energy desires to deploy ATRIUM 11 fuel in reload quantities 11x11 array reduces LHGR improving safety margin Improved debris protection features (fuel failure risk reduction)

Improved channel performance and fuel economics

  • First ATRIUM 11 Reloads Unit 2 Cycle 21 - Startup [REDACTED]

Unit 1 Cycle 23 - Startup [REDACTED]

4

Proposed Milestones

  • Transition cores will only contain Framatome fuel types Currently operating with full cores of ATRIUM 10 No multi-vendor core issues to review
  • Date for LAR Submittal

[REDACTED]

  • SER need date to support first ATRIUM 11 Reload

[REDACTED]

[REDACTED] months available for review of Advanced Framatome Methods LAR 5

LAR Content

  • Reports submitted with LAR based upon SSES equilibrium ATRIUM 11 Design:

Assembly Mechanical Design reports Methods Applicability Supplement Document Thermal Hydraulic Design Report LOCA / MAPLHGR Report BWR Licensing Methodology Compendium o Updated for new methods (AURORA-B [LOCA / Transients and Accidents / CRDA],

ACE / ATRIUM 11, SAFLIM3D, RODEX4, and Cr-Doped fuel) 6

LAR Content (cont)

  • Reports submitted with LAR based upon SSES equilibrium ATRIUM 11 Design (continued):

Fuel Cycle Design Report Nuclear Fuel Bundle Design Report Fuel Rod Design Report AURORA-B Limiting Transient Analysis Uncertainty Demonstration 7

LAR Content (cont)

  • Implementation cycle reports will be submitted after the LAR for information on a slightly accelerated licensing analysis schedule Fuel Cycle Design Report Nuclear Fuel Bundle Design Report Safety Limit MCPR Report Fuel Rod Design Report Reload Safety Analysis Report 8

LAR Content: TS 5.6.5 Additions

  • Framatome Thermal-mechanical methodologies BAW-10247P-A, Revision 0 Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors BAW-10247P-A, Supplement 1P-A, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 1: Qualification of RODEX4 for Recrystallized Zircaloy-2 Cladding BAW-10247P-A, Supplement 2P, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 2: Mechanical Methods ANP-10340P Revision 0, Incorporation of Chromium-Doped Fuel in AREVA Approved Methods 9

LAR Content: TS 5.6.5 Additions (cont)

  • Framatome Licensing methodologies ANP-10335P Revision 0, ACE/ATRIUM 11 Critical Power Correlation ANP-10300P-A Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios ANP-10332P Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios ANP-10333P Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident Scenarios ANP-10307P-A Revision 0 AREVA MCPR Safety Limit Methodology for Boiling Water Reactors 10

LAR Methodologies: Framatome Generic

  • It is anticipated that all required Framatome generic methodologies will be approved by the time of submittal
  • TN-B1 License for ATRIUM 11 Shipments Updated SAR submitted - NRC Approval Expected by Spring 2019 11

Summary

  • Proposed date for LAR submittal - [REDACTED]
  • SER need date - [REDACTED]
  • [REDACTED] month LAR review
  • LAR will request the addition of advanced Framatome methodologies 12
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