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{{#Wiki_filter:.5ni Transition to Framatome ANP Fuel Carolina Power & Light-Company Brunswick Steam Electric Plant, Units 1 and | {{#Wiki_filter:. 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 | * 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 | * 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=== | ===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 | 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 | 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* | 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=== | ===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 | 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=== | === | ||
Background=== | |||
Core monitoring | Core monitoring | ||
* PPX-ll in use since 1994* PPX-lll upgrade prior to fuel transition i CASMO-4*uO" R 0U BR__ N | * 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 | * Benchmark past cycles o EPUR operation o Methodology uncertainty validation | ||
* Implementation under 50.59 8 A ProgsEnergy Transition to | * Implementation under 50.59 8 A ProgsEnergy | ||
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 | Transition to ATRIUMT m-10 Fuel | ||
* 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) | * Licensing approach | ||
* Current licensing basis retained for events not impacted by the change in fuel design (Gb 12 Progress Energy Approved Methodologies COLR TS References | * Analysis approach | ||
-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 | *eApproved methodologies A%& 9 O .Progress Energy | ||
-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\/ | Licensing Approach | ||
for Boiling W\Aater Reactors: | * Minimize changes to the current plant licensing basis | ||
Applcation of the ENU O/Aethodology to BWR Reloads.* EMF-2158(P)(A),,-Siemens Power Corporation Methodology for Boilinq Water Reactors: | * ATRIUMTM-1 0 fuel evaluated in accordance with 10 CFR 50.59 | ||
Evaluation and Validation of CAS 0-4/MICROBURN-B2. | * 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) | ||
o XN-NF-80-19(P)(A) | P Design features update | ||
Volume 3, Exxon Nuclear Methodology for boiling Water Reactors THERMEX: Thermal Limits Methocology Summary Description G 14 .Progress Energy Approved Methodologies COLR TS References | * Cycle specific submittals | ||
-Transient Analysis o XN-NF-84-105(P)(A) | * COLR | ||
Volume 1, XCOBRA-T: | * SLMCPR o 50.46 annual report o Periodic FSAR updates k 10 § Progress Energy | ||
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: | Licensing Approach MELLLA+ | ||
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 | * MELLLA+ separate from fuel transition | ||
-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: | * Reload analyses will bound MELLLA+ | ||
Heat Transfer Coefficients. | * Operation contingent upon additional license | ||
*" LO% | |||
*'Progress Energy and Framatome ANP are committed to support the NRC's review 18 .Progress Energy}} | 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}} |
Revision as of 21:56, 23 November 2019
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: |
References | |
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
- 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
Licensing Approach MELLLA+
- MELLLA+ separate from fuel transition
- Reload analyses will bound MELLLA+
- Operation contingent upon additional license
- " LO%
- 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