ML033240636

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Meeting Between Duke Energy, Framatome Anp and NRC Staff on Use of MOX Lead Test Fuel Assemblies at Catawba Nuclear Station
ML033240636
Person / Time
Site: Catawba  
Issue date: 11/17/2003
From:
Duke Energy Corp, Framatome ANP, NRC/NRR/DLPM
To:
Martin R, NRR/DLPM, 415-1493
References
Download: ML033240636 (14)
v • d • e


Text

ATTENDEES LIST NOVEMBER 13. 2003 MEETING WITH DUKE ENERGY NAME Bob Martin Undine Shoop Anne Cottingham Mike Schoppman Jeff Tucker George Meyer Steve Nesbit Mike Cash Skip Copp Matt Langsehwager John A. Nakoski Tony Attard Katie Kannler Frank Akstulewicz Brad Grimmel David Alberstein Patrick Rhoads Samuel Hernandez Lambros Lois Ralph Landry Marcus King Andrew Persinko Henry Wagage Harold Scott Ed Hackett ORGANIZATION NRC NRC Winston & Strawn Framatome ANP Framatome ANP Framatome ANP Duke Energy Duke Energy Duke Energy NRC NRC NRC NRC NRC NRC DOE/NNSA DOE/NNSA NRC NRC NRC Numark Associates NRC NRC NRC NRC Attachment

Meeting Agenda for the November 13 meeting with Duke Energy and Framatome, ANP 8:00 - 8:15 8:15-8:45 8:45 - 10:00 10:00 - 10:15 10:15 - 11:00 11:00- 12:00 12:00- 1:00 1:00 - 1:15 1:15 - 1:45 1:45 - 2:15 2:15 - 2:45 2:45

Introductions

MOX Fuel Project - Overall Status (Duke)

Duke LTA submittal (NRC)

Status of Program and Schedule Discussion of RAI responses Discussion of additional information needed to support approval of the submittal Break Continuation of LTA Submittal LTA confirmatory program (NRC)

Lunch CABRI Data Access (NRC)

Program Element Review Schedule (Duke)

Summary Public Comments Adjourn

MOX Fuel Project Status NRC - Duke Power - Framatome ANP Meeting NRC Offices - White Flint, MD Steve Nesbit Duke Power November 13,2003 Duke lPower

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911 rist taRt FROI1Z1 Russian Plutonium Disposition
  • Late 2002 - U.S.-Russian agreement on basis for Russian plutonium disposition program Russian MOX Fuel Fabrication Facility (R-MFFF) based on design of United States facility Primary use of MOX fuel in VVER-1000 pressurized water reactors
  • Goal of starting construction on U.S. and Russian fabrication facilities in 2004
  • Issue of liability for western contractors is still unresolved D Duke OEPower.

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United States MUFF

  • Construction authorization scheduled for end of 2003 Recent change In U.S. MFFF Controlled Area Boundary may impact schedule
  • Atomic Safety and Licensing Board hearings in 2004
  • Begin construction in summer 2004, contingent on Regulatory approval Russian progress
  • Produce MOX fuel for McGuire and Catawba -2009 Duke PPower-
  • A"DC~,-

3 mlaallMOX bitts timi~ sal t wlit U.S. Reactor Use of MOX Fuel

  • Lead assembly program Feb 27,2003 - Duke submitted license amendment request (LAR) for approval to use MOX fuel lead assemblies at McGuire or Catawba September 23, 2003-Duke amended LAR to apply to Catawba only NRC approval requested by August 2004 Load lead assemblies in Catawba Unit I spring 2005
  • Batch use of MOX fuel

- Submit license amendment request for McGuire and Catawba In 2004 Begin batch use of MOX fuel In 2009 Dispose of 34,000 kg of surplus plutonium through use as MOX fuel PNDuke OrPower 4

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Lead Assembly Program - Activities and Schedule

  • Spring 2004 - Complete polishing plutonium oxide powder at Los Alamos National Laboratory
  • Summer-fall 2004 - Transport plutonium oxide powder to Europe
  • Winter 2004-2005 - Fabricate MOX fuel pellets and rods at Cadarache and bundle assemblies at Melox
  • Spring 2005 - Transport lead assemblies to Catawba PbDuke Ypower.

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o80e MOX Fuel Lead Assembly Irradiation Plan

  • Spring 2005 - spring 2008 Two eighteen month cycles Irradiate all four MOX fuel assemblies In relatively high power locations Certify MOX fuel for batch use following 2 d cycle, based on poolside post-Irradiation examination (PIE) results
  • Spring 2008 - fall 2009 Irradiate one or more MOX fuel assemblies for a third cycle In relatively low power locations Conduct hot cell (PIE) of MOX fuel rods Duke Power.

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Required Regulatory Approvals

  • Duke topical reports (thermal-hydraulic, nuclear analysis)
  • Framatome topical reports (fuel performance, fuel assembly design, MOX fuel design)
  • DOE export license application
  • Packaging Technology transportation package certifications (powder and fuel assemblies)

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'Power.

7 88MOX Lead Assembly License Amendment Request RAls

  • NRC Request for Additional Information (RAI) on Boraflex Issued July 14, 2003 Response October 1, 2003
  • NRC RAI - Reactor Systems, Radiological, Env.

Issued July 25, 2003 Partial response October3, 2003 Complete response November3, 2003

  • NRC RAI on quality assurance Issued August 13, 2003 Response October 1, 2003 13k Duke roPower.

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Summary

  • The United States MOX fuel lead assembly program is a key element of the international initiative to reduce the stockpiles of weapons grade plutonium in the United States and Russia
  • NRC review and approval schedule is important
  • Duke and Framatome ANP are committed to working with NRC to facilitate regulatory approvals Duke COO ITVPower.

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MOX Fuel Qualification NRC - Duke Power - Framatome ANP Meeting NRC Offices - White Flint, MD George Meyer Framatome ANP November 13, 2003 A

FRAMATOME ANP

> NRC - Duke Power-Framatome ANP Meeting, 13 Nov 2003

MOX Fuel Qualification Plan

> Maximize use of European experience base

  • Research programs
  • Established manufacturing process
  • Reactor irradiation experience

> Proven fuel assembly design

> Confirmatory lead assembly program A

> NRC - Duko Power-Framatome ANP Meeting, 13 Nov 2003 FRAMATOME ANP

MOX Fuel Qualification

> Lead Assembly Program

  • Required to confirm acceptability for batch operation
  • Plan has evolved since the FQP (April 2001):
  • Expect to fabricate and irradiate four lead assemblies
  • Fabrication will be in existing MOX facilities Pellets and rods fabricated at Cadarache Assemblies will be fabricated at MELOX
  • Irradiation at Catawba commencing in Spring, 2005
  • Two cycles of irradiation, with poolside PIE after each
  • Certification for batch deployment after 2nd cycle poolside PIE
  • Hot cell PIE of selected rods after second cycle
  • Third cycle irradiation of one or two LAs to go beyond 50,000 MWd/t burn up

> NRC-Duke Power-Framatome ANP Meeting, 13 Nov 2003 FRAMATOME ANP

Poolside PIE -After Each cycle (Basic PIE)

Fuel Assembly Visual Examination

  • Overall appearance - Assess need for additional examinations Fuel Rod Visual Examination
  • Examine peripheral rods to verify appearance consistent with expectations Fuel Assembly Growth
  • Confirm growth consistent with prediction Fuel Rod Growth (Shoulder Gap Closure)
  • Confirm predictions and acceptability for continued operation Fuel Assembly Bow and Distortion
  • Confirm expected behavior A

> NRC-Duke Power-Framatome ANP Meeting, 13 Nov 2003 FRAMATOME ANP

Poolside PIE -After Discharge (Extended PIE - preliminary

> Extended PIE scope will depend on results of basic PIE and is expected to include examinations such as:

  • Grid Width
  • Fuel rod oxide thickness
  • Fuel assembly RCCA drag
  • Rod-to-rod spacing
  • Guide thimble profile A

> NRC - Duke Power-Framatome ANP Meeting, 13 Nov 2003 FRAMATOME ANP

Hot Cell PIE

> Hot Cell PIE is expected to include:

  • Fission gas release
  • Clad metallography
  • Clad ductility
  • Fuel pellet ceramography
  • Burnup analysis
  • Burnup distribution A

> NRC - Duke Power-Framatome ANP Meeting, 13 Nov 2003.

FRAMATOME ANP

NRC Regulatory Actions MOX Fuel Lead Assembly Licensing X

COPERNIC Fuel Rod Design Framatome December 1999 Approved.

Computer Code (U0 2 )

COPERNIC Fuel Rod Design Framatome July 2000 Under NRC review.

Computer Code (MOX)

Nuclear Design Methodology using CASMO-4/

Duke August 2001 Under NRC review.

SIMULATE 3 MOX Thermal Hydraulic Statistical Duke September 2001 Approved.

Core Design Methodology Advanced Mk-BW Fuel Framatome April 2002 Under NRC review.

Assembly Mechanical Design License amendment request to Duke February 2003 Under review. Includes request for exemptions to use MOX fuel lead assemblies 10 CFR 50.

Responses to RAls dated:

Responses sent:

(a) 07/14/03 - Boraflex Duke (a) 10/01/03 UnderNRC review (b) 07/25/03 - Rx systems, etc (b) 10/03/03 & 11/03/03 (c) 08/13/03-QA (c) 10/01/03 MOX Fuel Design Report Framatome May 2003 (Rev 1)

Under NRC review (Draft RAs have been issued and Security plan Duke September 2003 NRC reviewing classification of security plan submittal.

Security plan Duke September 2003 Submittal includes request for exemptions to 10 CFR 73.

Export Licens DOE October 2003

~~License to ship 140 kg Of Pu0 2 powder to France for lead Export License DOE October 2003 assembly fabrication (NRC/OIP review).

Request for certification of Packaging Submitted to DOT August 2003. DOT sent to NRC in FS-47 package (PuO2 powder Technology October 2003 October.

shipment).

I Request for certification of Packaging FS-65 package (for lead Technology 2004 Pending review and approval by French authority.

assembly shipment)

I Duke V Power.

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MIXED OXIDE FUEL PROJECT

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