ML020790567

Summary Meeting - Tennessee Valley Authority Brown Ferry Nuclear Plant Independent Spent Fuel Storage

ML020790567
Person / Time
Site:	Browns Ferry
Issue date:	03/19/2002
From:	Abney T Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
References
Download: ML020790567 (15)

Text

-m- - -- - - - - - - - -m- - m - -m-Tennessee Valley Authority Browns Ferry Nuclear Plant Independent Spent Fuel Storage TVAINRC Meeting Region II- Atlanta, GA March 14, 2002 Enclosure 2

Agenda

• Meeting Objectives Tim Abney

• Background Tim Abney

• Schedule Alan Chapman

• Proposed Location Alan Chapman

• Security Alan Chapman

• Site Specific Issues Alan Chapman

• Licensing Tim Abney

• Summary and Closing Remarks Tim Abney Tim Abney 1

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Introduction/Meeting Objectives LLLU Meeting Objectives

- Provide Status of Browns Ferry Nuclear Plant Spent Fuel Storage Situation

- Discuss BFN Activities to Date

- Provide a Schedule for Major Project Milestones

- Discuss Site Specific Issues

- Obtain Staff Input/Lessons Learned Tim Abney 2

- - -M- M - - - -M- M -- - - - - rn Background LLWJ

• BFN Spent Fuel Pool

- Spent Fuel Pools are Currently Licensed for 3471 Fuel Assemblies (FA) Per Unit

- Full Core Reserve is 764 FAs

- Unit 1 Spent Fuel Pool Currently Contains 1978 FAs

- Unit 2 Spent Fuel Pool Currently Contains 2558 FAs

- Unit 3 Spent Fuel Pool Currently Contains 2160 FAs Including 284 Fresh Assemblies

- Unit 3 Will Lose Full Core Offload Capacity in November 2005 Tim Abney 3

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Background (Cont) LU Options Considered

- Rerack Unit 3

> Provide Storage for Unit 3 Until 2012

> Provide Storage for Unit 2 Until 2013 Using the Unit I Pool

- Dry Storage

> Construct On Site ISFSI and Implement Dry Cask by July 2005 Tim Abney 4

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Background (Cont) L

• Other Considerations

- Extended Power Uprate

- Plant License Renewal

• Decision to Proceed With Dry Storage

• Contract Awarded to Holtec International, November 2001 Tim Abney 5

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Schedule 2/2002 5/2002 3/20103 Hardware Fabrication / Delivery 10/2004 Negotiate final colt at 0 'M MPG's 1W Assemble Team MPC's Detailed schedule development V HI-STORM's Identify Dwgs/procedureW HI-TRAC Environmental Assessment Handling Equipment Ancillary Equipment 1/2002 5/2003 Design 10/2003 12/2004 Construction RFF and Truck Bay Evaluations *TV M 1W Soil Sampling and Analysis Work plan development Heavy Load Transport Path Design Start-up/Testing/

Construction activities ISFSI Design Closure activities NRC Demonstrations Security System Design 6/2005 SFP RB Crane Design Ops and Maint Procedure Dev. 10/2004 Pre-operations Teeing Training Dry Runs On site overpack Fabrication Load 3 Casks 1/2002 Engineering, Licensing and Other Evaluations 2/2005 7/2005 9/2005 Lo wl oDi opFAnalysis Dose rate Assessments Load, weld 72.212 Report (close) and 72.48 Procedure transport Alan Chapman Licensing Submittals 6

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BFN Proposed Location ULl

• Phase I

- Located Just Outside Current Protected Area Boundary Adjacent to the Switch Yard

• Transport pathway Approximately 1500 ft

• Surrounded By

- 100 Year Flood Control Ditch (Moat)

- Switch Yard Alan Chapman 7

Security

• Extend the Current Protected Area to Encompass Phase I Storage Location

- Isolation Zone

- Lighting

- Camera Locations

• Revise Security Plan

• Eliminate the East Access Point

• Minimal Impact on Current Security Forces Alan Chapman  %.7

Site Specific Issues

• Evaluations and Analyses

- Heavy Load Handling Path Evaluation

> NUREG-0612, Control Of Heavy Loads

- 10 CFR 72.212 Evaluations

- NRC Bulletin 96-04 and ISG-15 Compliance Evaluation

- Various Off-Normal Condition Analyses and Calculations

- Radiation Assessment

• Plant Modifications Required to Support Spent Fuel Off-Loading

- Cask Support Stands and Work Platform

- Reactor Building Crane Upgrade NUREG-0554, Single-Failure-Proof Cranes for Nuclear Power Plants

- Truck Bay and Egress Modifications (Potential)

Alan Chapman 9

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Site Specific Issues (Cont.)

• Design and Construction of Storage Facility

- Phase I ISFSI

> 88-Cask Capacity

> Sufficient Storage For Current End-of-License For All 3 Units Through 2016

- Phase 11 and Phase Ill Contingency If DOE Does Not Accept Spent Fuel After 2016 Alan Chapman 10

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Site Specific Issues (Cont.)

• Design and Construction of Storage Facility (Cont)

- Transport Roadway and Staging Pad

- Security Boundary Revision (Fence, Cameras, Lighting, E-Field, etc.)

• Facility Startup / Testing

- Procedures Development

- Training Program Development

- Personnel Training

- NRC Demonstrations

- Startup Testing of Ancillary Equipment

- Cask Loading and Closure Operations for Initial Campaign Alan Chapman 11

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Site Specific Issues (Cont.) LLLLl

• Major Procurement Items

- Multi Purpose Canister

- Storage Overpack

- Transfer Cask

- Handling and Ancillary Equipment Alan Chapman 12

Licensing UXL

• 10 CFR 72.210, General License

• Selection Considerations

- Flexibility

- Well Defined

- Regulatory Precedence

- Minimize TVA and Staff Resources

- Efficiency Associated With a Standard Design

- SQN Site Will Use a General License

- Lessons Learned

• Potential Submittals

- Radiological Emergency Plan

- Security Plan

- Quality Assurance Plan Tim Abney 13

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Summary and Closing Remarks Tim Abney 14