ML060790305

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
Shared Package
ML061290361	List: ML060790305
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Download: ML060790305 (18)

Text

. 5ni Transition to Framatome ANP Fuel Carolina Power & Light-Company Brunswick Steam Electric Plant, Units 1 and 2 77, ,' 7 W E ___ - ___

March 10, 2006 Nuclear IGeneration IGroup 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

U3 Progress Energy A*b 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% 4

&5 Progress Energy

=

Background===

GE14 11Ills In.

II RI Iffimm= pS jm 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

• 1Ox1 0 lattice

• Square internal water channel 8nr pa lengt rods(rI3I nr le/"ngth)

• 8 8spacers

%J J LA I I filter

• Debris ,II LIII i J tie plate lower

%.,: K O

• 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)

• ATRIUM'-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

• iviiIROUK3UN-B2

• uO" R 0U BR__ -

N B

• Benchmark past cycles o EPUR operation o Methodology uncertainty validation

• Implementation under 50.59 8 A ProgsEnergy

Transition to ATRIUMT m-10 Fuel

• Licensing approach

• Analysis approach

• eApproved methodologies A%& 9 O .Progress Energy

Licensing Approach

• Minimize changes to the current plant licensing basis

• ATRIUMTM-1 0 fuel evaluated in accordance with 10 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 license

• " LO%

Wf LO AV N - I 'f

• MELLLA+ (NEDO-33006-P, Rev. 1) i Stability (ANP-1 0262)

• Schedule determined by methodology review and approval Progress Energy A% 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 neric Mechanical Design for Exxon Nurc1laqr 1kt Pum p BWR Reload Fut!L

• EMF-85-74(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model

• ANF-89-98(P)(A), Generic Mechanical Design Criteria for BWR Fuel Designs Aib 13 w Progress Energy

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.

d,&b 15 . Progress Energy

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: Appendix K Spray Heat Transfer Coefficients.

K3 Progress Energy d,4 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 JulyI I, IAEI I II L I ,;L II2007U i Submit July 2007 o Request approval by January 2008 Ab 17 Q Progress Energy

Summary.

• Established ATRIUM-1 0 transition process OBrowns 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