ML060790305

03/10/2006, Meeting Handouts for Summary of Meeting W/Carolina Power & Light Regarding the Fuel Transition Process and Licensing Submittals for Brunswick, Units 1 & 2

ML060790305
Person / Time
Site:	Brunswick
Issue date:	03/10/2006
From:	Nuclear Generation Group, Progress Energy Co
To:	Carolina Power & Light Co, Office of Nuclear Reactor Regulation
Mozafari B, NRR/ADRO/DORL, 415-2020
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ML061290361	List: ML060790305
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Download: ML060790305 (18)

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.5ni Transition to Framatome ANP Fuel Carolina Power & Light-Company Brunswick Steam Electric Plant, Units 1 and 27 ___ -___March 10, 2006 Nuclear I Generation I Group I2 Progress Energy Meeting Agenda* Purpose* Background

• Transition approach P Licensing o Analysis o Methodology

• Licensing submittals and schedule* Summary b2 .Progress Energy Purpose* Describe the transition process from GNF to Framatome ANP fuel supply* Communicate transition plan* Discuss licensing activities and schedule i A*b U3 Progress Energy 3

Background

Fuel supplier change.Progress Energy fuel bid.Proposals requested Summer 2004.) Bids received Winter 2004.Framatome ANP awarded Brunswick fuel supply Fall 2005.Transition to FANP fuel supply March 2008 A%&5 Progress Energy 4

Background

GE14 11 Ills In. I I RI Iffimm= pS 11 Key Features* 1Ox10 lattice* Large central water rods (2)is14 nprt lanrgth rodz (~2/3 lonrgth* 8 spacers* Debris filter lower tie plate 179 kgU i Extensive operating experience 5 @ Progress Energy

Background

ATRIUM-1 0 Key Features* 1 Ox1 0 lattice* Square internal water channel 8nr pa nr lengt rods(rI3I le/ "ngth)%J J LA I i I ,II LIII J %.,: K O*8 8spacers*Debris filter lower tie plate*178 kgU* Extensive operating experience 6 ~ Progress Energy

Background

Brunswick Plant* 24 month fuel cycles* Extended power uprate to 120% of original license o Unit 1 Cycle 15; Spring 2004 i Unit 2 Cycle 17; Spring 2005* Current licensing basis fuel designs o GE13 9x9* GE14 10x1O (full core in each unit)* ATRIUMŽ-10 lead use assemblies Unit 2 Cycle 14* Transition to Framatome ANP ATRIUMTM-10 o Unit 1 Cycle 17; March 2008 o Unit 2 Cycle 19; March 2009 (j 7 -gB Progress Energy

Background

Core monitoring

• PPX-ll in use since 1994* PPX-lll upgrade prior to fuel transition i CASMO-4*uO" R 0U BR__ N -B* iviiIROUK3UN-B2

• Benchmark past cycles o EPUR operation o Methodology uncertainty validation

• Implementation under 50.59 8 A ProgsEnergy Transition to ATRIUM T m-10 Fuel , .- ._ -* Licensing approach* Analysis approach*eApproved methodologies A%&O .Progress Energy 9 Licensing Approach* Minimize changes to the current plant licensing basis* ATRIUMTM-1 0 fuel evaluated in accordance with 1 0 CFR 50.59* Technical Specification changes o Update references to NRC-approved methods i LHGR operating limit addition o SLMCPR, scram speed option changes o Remove vendor-specific criticality analysis methods (k-infinity)

P Design features update* Cycle specific submittals

• COLR* SLMCPR o 50.46 annual report o Periodic FSAR updates k 10 § Progress Energy Licensing Approach MELLLA+* MELLLA+ separate from fuel transition

• Reload analyses will bound MELLLA+* Operation contingent upon additional

• " LO% Wf LO AV N -I 'f* MELLLA+ (NEDO-33006-P, Rev. 1)i Stability (ANP-1 0262)license* Schedule determined by methodology and approval review A%Progress Energy 11 Analysis approach __* Review all event analyses identified in FSAR* Disposition analyses as: o Not impacted by the change in fuel design^ Bounded by the UouiSquences of another event-Potentially limiting* Analyze potentially limiting events with NRC approved Framatome ANP methodology

• Current licensing basis retained for events not impacted by the change in fuel design (Gb 12 Progress Energy Approved Methodologies COLR TS References

-Mechanical Analysis* XN-NF-81-58(P)(A), RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model.* XN-NF-85-67(P)(A), Ge Exxon Nurc1laqr 1 kt Pum neric Mechanical Design p BWR Reload Fut!L for* EMF-85-74(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model* ANF-89-98(P)(A), Generic Mechanical Design for BWR Fuel Designs Criteria Aib w Progress Energy 13 Approved Methodologies COLR TS References

-Neutronic Analysis XN-NF-80-19(P)CA)

Volume 1, Exxon Nuclear Methodology for oiling Water Reactors -Neutronic Methods for Design and Analysis.* XN-NF-80-1 9(P)(A) Volume 4, Exxon Nuclear.Methodoinn\/

for Boiling W\Aater Reactors:

Applcation of the ENU O/Aethodology to BWR Reloads.* EMF-2158(P)(A),,-Siemens Power Corporation Methodology for Boilinq Water Reactors:

Evaluation and Validation of CAS 0-4/MICROBURN-B2.

o XN-NF-80-19(P)(A)

Volume 3, Exxon Nuclear Methodology for boiling Water Reactors THERMEX: Thermal Limits Methocology Summary Description G 14 .Progress Energy Approved Methodologies COLR TS References

-Transient Analysis o XN-NF-84-105(P)(A)

Volume 1, XCOBRA-T:

A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis.o ANF-524(P)(A), ANF Critical Power Methodology for Boiling Water Reactors.P ANF-913(P)(A)

Volume 1, COTRANSA2:

A Computer Program for Boiling Water Reactor Transient Analyses.o ANF-1 358(P)(A), The Los's of Feedwater Heating Transient in Boiling Water Reactors.15 .Progress Energy d,&b Approved Methodologies COLR TS References

-CPR and LOCA P EMF-2209(P)(A), SPCB Critical Power Correlation o EMF-2245(P)(A), Application of Siemens Power Corporation's Critical Power Correlations to Co-I ROIdetI ILFue,.o EMF-2361 (P)(A), EXEM BWR-2000 ECCS Evaluation Model.o EMF-2292(P)(A), ATRIUMTM-10:

Heat Transfer Coefficients.

Appendix K Spray d,4 K3 Progress Energy 16 Licensing Submittals Schedule* TS amendment request o Submit January 2007 o Request approval by January 2008..ACPRP amendmeint reus I kilyy L-"I 5 .IVbI July I I, I IAE I II L I ,;L II2007U i Submit July 2007 o Request approval by January 2008 Ab Q Progress Energy 17 Summary.* Established ATRIUM-1 0 transition process O Browns Ferry (2004)0 Columbia Generating Station (2003)I River Bend and Grand Gulf (2001)* NRC-approved methodology will be used for the transition

• 'Progress Energy and Framatome ANP are committed to support the NRC's review 18 .Progress Energy