ML12170A014

6/18/12 Meeting Slides - Slides for Meeting with Tennessee Valley Authority Regarding Areva Xm Fuel Transition Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Use of Areva Xm Fuel

ML12170A014
Person / Time
Site:	Browns Ferry
Issue date:	06/18/2012
From:	Tennessee Valley Authority
To:	Ellen Brown Plant Licensing Branch II
Brown, Eva A.
References
Download: ML12170A014 (13)

Text

Use of AREVA XM Fuel at Browns Ferry June 18, 2012 Nuclear Browns Ferry Nuclear Plant

Agenda 2

Nuclear

• Overview

• Licensing considerations

• Licensing Amendment Request (LAR) content

• ACE CPR correlation issue

• Schedule

• Additional considerations

Overview 3

Nuclear

• TVA desires to transition to ATRIUM-10 XM fuel

- All three Browns Ferry units

• Fuel cycle cost benefits

• XM better suited for potential future EPU operation

• Smaller batch sizes will reduce dry storage requirements

• XM is an industry proven design

- Significant European experience

- One domestic customer utilizing XM

• First targeted XM reloads by unit

- Unit 2 spring 2015

- Unit 3 spring 2016

- Unit 1 fall 2016

• Transition cores will only contain AREVA fuel types

- Remaining GNF fuel discharged from Unit 1 in 2016

- No multi vendor core issues to review

Licensing Considerations 4

Nuclear

• XM fuel design meets all criteria in ANF-89-98(P)(A) Generic Mechanical Design Criteria for BWR Fuel Designs

• NRC completed XM compliance review in November 2010

• XM use approved for Brunswick

- Identical XM fuel design will be used for Browns Ferry

- Brunswick is comparable to Browns Ferry

• Same core lattice geometry

• TVA requesting XM approval for current power level only

Licensing Considerations 5

Nuclear

• Application of AREVA methodologies to Browns Ferry

- Fully reviewed with the three exceptions noted

- Previous reviews

• NRC methods audit August 2008

- Focused largely on application to Browns Ferry

• Review of unit 1 ATRIUM-10 LAR

- In depth review of LOCA methods

- Resulted in modified methodology for Browns Ferry

• Same methodologies as used for ATRIUM-10

- Three exceptions

• Addition of RODEX4 for thermal mechanical analyses

• Addition of ACE correlation for XM fuel CPR monitoring

• Replacement of SAFLIM2 safety limit methodology with SAFLIM-3D

LAR Content 6

Nuclear

• Provide similar reports as the approved Unit 1 ATRIUM-10 LAR

- Mechanical design report

- Thermal hydraulic design report

- Fuel cycle design report

- Reload safety analysis report

- LOCA break spectrum report

• Same modified methodology as outlined in ANP-3015 report

- BWR licensing methodology compendium

• Updated for new methods (RODEX4, SAFLIM-3D)

- RAI compendium

• Fuel type dependent RAIs from the ATRIUM-10 RAI compendium will be answered in the context of XM

• Will include RAIs from the Brunswick XM LAR as appropriate

LAR Content 7

Nuclear

• Additional LAR information

- Specific to application of the three new methodologies

• Equilibrium fuel cycle report (part of RODEX4 application)

• Rod thermal mechanical report (part of RODEX4 application)

• SAFLIM-3D application (SLMCPR calculation for lead reload)

• Plant specific ACE supplement

- Thermal conductivity issue

• RODEX2 still used for transient and LOCA analyses

• LAR will address the resolution agreed upon between AREVA and NRC

• Will use lead Browns Ferry XM reload as the basis for the transition analyses

- Unit 2 cycle 19

LAR Content 8

Nuclear

• LAR will include Technical Specifications changes

• Technical Specification 5.6.5.b will be modified

- Add new methodology references:

• BAW-10247PA Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Revision 0, April 2008

• ANP-10298PA ACE/ATRIUM 10XM Critical Power Correlation Revision 0, March 2010

• ANP-10307PA AREVA MCPR Safety Limit Methodology for Boiling Water Reactors Revision 0, June 2011

• Technical Specification 2.1.1.2 (SLMCPR)

- SLMCPR will be reduced relative to current values

- LAR will include a new value for unit 2 only

• Changes for the other two units in separate LARs

LAR Content 9

Nuclear

• Technical Specification Bases changes

- Some TS Bases will require modification

- References in select Bases will be updated to reflect new methods

• Bases for SLMCPR and other thermal limits

• No other Technical Specifications changes required

ACE Correlation Issue 10 Nuclear

• Current ACE method has an identified deficiency

- Axial averaging process for K factor

• AREVA has a corrected K factor methodology

- AREVA has submitted a generic ACE supplement to the NRC

• Issues may arise with review timing

- Uncertainty over when generic supplement will be approved relative to Browns Ferry XM LAR approval

• Proposed solution

- Develop Browns Ferry specific ACE supplement and include in XM LAR

- If generic supplement is approved prior to XM LAR

• Supplement XM LAR requesting generic ACE supplement be added to Browns Ferry Technical Specifications

- If XM LAR is approved before the generic ACE supplement

• Technical Specification reference for ACE will be annotated to reference the SE for the XM LAR

Schedule 11 Nuclear

• Transition work underway

- Will complete in late 2012

• Target date for LAR submittal

- January 2013

• SER need date

- February 2014

- Need date is tied to reload design and fuel fabrication milestones

Additional Considerations 12 Nuclear

• TVA developing EPU Licensing path forward

- Subject of future meeting

• Downstream EPU timing

- First XM application (unit 2 cycle 19) not targeted for EPU

- 2016 reloads are potential EPU cycles

• Unit 3 cycle 18

• Unit 1 cycle 12

- Potential for concurrent EPU and XM intro in these two cycles

- TVA views this as acceptable under the ELTR process

• Lead XM reload would not be EPU concurrent

• Additional EPU LAR information

- Information docketed for EPU does not consider XM

• Only GE14 and ATRIUM-10 considered

- Will need a future meeting to discuss how to supplement EPU LAR to account for XM fuel

13 Nuclear Discussion