ML13277A038
| ML13277A038 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/24/2013 |
| From: | Global Nuclear Fuel, Hitachi America, Ltd |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13277A038 (48) | |
Text
Enclosure 4 BSEP 13-0104 GEH Presentation on Methods Applicability to AREVA ATRIUM 1OXM Fuel (Non-Proprietary Version)
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Brunswick MELLLA+ Project GEH/GNF Nuclear Analysis Methods Applicability to AREVA ATRI UM TM 1OXM Fuel HITACHI GN'**
Page 1 Global Nuclear Fuel A Jo.t V...o, of GL Toshlb. & Kioche
Non-Proprietary Information - Class I (Public)
AGENDA Introduction
" Meeting Purpose
- ATRIUM TM 10 Fuel Background Experience
- ATRIUM TM 1OXM Fuel for ATWS Methods
- Technical Uncertainty Identification/Management Process
- ATRIUM TM 1OXM Modeling Approach Methods Application Core Modeling ATWS Analysis Applicable Interim Methods LTR and MELLLA+ LTR Limitations and Conditions Summary S
HITACHI rPge2 MAW, Nuclear Fuel A J-.. V.o1. W GE. T..,b. & ffiwh
Introduction
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Product Requirements Review I
The purpose of this meeting is to describe the process used to apply GEH/GNF nuclear methods to perform ATWS analyses for ATRIUM TM 1OXM fuel.
I Conceptual Design Review I
Yes 4-I Detailed Design Review I
E I
Design Validation Review HITACHI GN'-
WOk" Nucebw Fuel A Jo,*.
WG
."...o6ob.. A &ui~
Page 4
Non-Proprietary Information - Class I (Public)
GEH/GNF Experience with ATRIUM TM 10
" Significant experience with modeling ATRIUM TM 10.
- LaSalle, Columbia, River Bend, and Grand Gulf
- Fuel geometry and materials explicitly modeled through input based AREVA supplied information
- Fuel specific models based on AREVA supplied performance data
" TGBLA lattice model - MCNP benchmarking
- GSTRM or PRIME thermal mechanical model
- Thermal hydraulic model - Frictional losses in active channel, water box and leakage paths
- GEXL Critical power correlation S
HITACHI GN'r Pge5 Ghba Nuclmr Fuel A Jý eo.t
.. of GE.
Toshiba & H-hi
Non-Proprietary Information - Class I (Public)
ATRIUM TM 1OXM Fuel for ATWS Methods Geometry of ATRIUM TM 1OXM explicitly modeled in core representation and ATWS transient calculations.
" Conservative uncertainties are applied to cover variability in fuel parameters and uncertainties in performance for ATRIUM TM 1OXM fuel.
- Brunswick ATWS with ATRIUM TM 1OXM is first GEH/GNF use of this fuel type.
0 Process remains the same as for previous ATWS analyses with GNF fuel.
S HITACHI Gage ObdNuleaw Fuml A J*U.
0o 6G T*.*,
& WWah,
Non-Proprietary Information - Class I (Public)
Technical Uncertainty Identification / Management Process
- Identification of uncertainties for new projects.
" GEH has previously performed ATWS analyses in support of MELLLA+
" Uncertainty associated with simulation of ATRIUM TM 1OXM fuel for ATWS events
- Mitigating actions to manage uncertainties
- Identify and bound uncertainties associated with simulation of ATRIUUM TM 1OXM fuel
- Perform design reviews Product Requirements Review Specifications and Requirements Completed Identify uncertainties Conceptual Design Review Assess feasibility Completed Evaluate impact of Uncertainties Detailed Design Review Evaluate process versus requirements Planned Validation Design Review Validate final analysis Planned j
HITACHI G31 Page 7 NkWNu*ew Fuel A Jým YuWý 0 GL. Tahib. & HiM.rhi
Non-Proprietary Information - Class I (Public)
ATRIUM TM 1OXM Modeling Approach Modeling
" Fuel geometry and materials explicitly modeled through data from AREVA
- TGBLA lattice model - MCNP benchmarking PRIME thermal mechanical ATRIUM TM 10 model with uncertainties applied to bound ATRIUMTM 1OXM.
" Differences in other fuel parameters for ATRIUM TM 1OXM bounded by uncertainties
- Thermal hydraulic model - frictional losses in active channel tie plates and spacers, water box and leakage paths consistent with GEH/GNF methods supplied by Duke GEXL critical power correlation fitted to bound ATRIUM TM 1OXM data by AREVA HITACHI Gage 8
- MAW Nucl*m Fuml A JO.. %ý W GEý Th.Mo. & Macbi
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ATRIUM TM 1OXM Modeling Approach Uncertainties Uncertainties with simulating ATRIUM TM 1OXM fuel for ATWS identified at Product Requirements Review (PRR) 1))
- Impact of uncertainties evaluated and analysis process reviewed at Conceptual Design Review (CDR).
Sensitivity to uncertainties small relative to margin to licensing limits HITACHI G*r 01"W Nuclear Fuel A Jo. V.. of GE. To.ib. & U.Oh, Page 9
Core Modeling
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ATRIUMTM 1OXM Data Migration from AREVA
- Convert design inputs to GNF/GEH methods Use explicit ATRIUM TM 1OXM design inputs
" Lattice Design
" TGBLA lattice library generation MCNP benchmarking to support TGBLA application qualification for Brunswick ATRIUM TM 1OXM fuel designs Core Design PANAC core equilibrium evaluation ISCOR thermal hydraulics modeled explicitly Consistent evaluation basis between AREVA and GNF/GEH methods.
SHITACHI GN'r Page 11 Glb Nucllea Fuel A JM V. W*
GE. T*hb. & #iwh
Non-Proprietary Information - Class I (Public)
Core Modeling Inputs PANAC simulation uses AREVA design input for:
- Core power
- Core flow
" Rod patterns Cycle exposure statepoints
- Total cycle energy Equilibrium core loading Bundle designs
" PANAC simulation uses ISCOR outputs for:
Dome Pressure Inlet Enthalpy Channel Inlet Losses and Bypass Flow Consistent evaluation basis between AREVA and GNF/GEH methods.
SHITACHI w*mr Page 12 G1bd Nuclear Fuel A Jo..# V.e*...1 GE To-k.b. & INOd,.
Non-Proprietary Information - Class I (Public)
Comparisons - Hot Eigenvalue Consistency I]
HITACHI GNF GObal Nuoloa Fuel A JOWV. V.,,
Non-Proprietary Information - Class I (Public)
Comparisons - Thermal Hydraulic Consistency
- Duke has confirmed thermal hydraulic consistency between vendor methods.
I]
I Consistent evaluation basis between AREVA and GNF/GEH methods. I HITACHI GNr Gl*udlear Fuel A Jla V..l.e.1 GL ToMiba & MA-hi Page 14
Non-Proprietary Information - Class I (Public)
Comparisons - Thermal Hydraulic Consistency I]
HITACHI GNF GlsbW Nucr Fuel A J-GE, T-.b.,& Hf.h Page 15
Non-Proprietary Information - Class I (Public)
Comparisons - Thermal Hydraulic Consistency
))
HITACHI GNF OhbeI Nude., Fuel A Am %1 of GEý Io. b& & kmcMd Page 16
Non-Proprietary Information - Class I (Public)
Comparisons - BOC Axial Power Consistency
))
I Good BOC axial power consistency between vendor methods.
I HITACHI GNF Global Nulew Fuel A ko 1.
W o GE, T.h. & Nkk Poge 17
Non-Proprietary Information - Class I (Public)
Comparisons - BOC Axial Power Consistency I]
I Good BOC axial power consistency between vendor methods.
HITACHI Gu Gimba Nuagew Fuel A JoV.fY Wf GE Tbh.h & IHood.
Page 18
Non-Proprietary Information - Class I (Public)
Comparisons - MOC Axial Power Consistency
))
I Good MOC axial power consistency between vendor methods. I HITACHI GNr IW Nudear Fuel A Jo". Vý.*
of GE TSoFk
& NMi-h Page 19
Non-Proprietary Information - Class I (Public)
Comparisons - MOC Axial Power Consistency
))
I Good MOC axial power consistency between vendor methods. I 0
HITACHI GIN Suh" Nuclear Fuel Page 20
Non-Proprietary Information - Class I (Public)
Comparisons - EOC Axial Power Consistency
))
I Good EOC axial power consistency between vendor methods.
0 HITACHI GNP W"Wa Nucare Fuel A JWM t..
- WoGL, T..b. & W.hi Page 21
Non-Proprietary Information - Class I (Public)
Comparisons - EOC Axial Power Consistency
((
I]
I Good EOC axial power consistency between vendor methods. I HITACHI GNr-Nubll Nude.' Fuel A jo*- W GE. ToM.b. & Hi04hi Page 22
Non-Proprietary Information - Class I (Public)
Comparisons - BOC Radial Power Consistency Radial power difference between vendor methods.
I]
I Good BOC radial power consistency between vendor methods. I HITACHI GNr Ok" Nucear Fuel A JOi.l ikýr
.1 OL F. TW~b. & Hibal:hi Page 23
Non-Proprietary Information - Class I (Public)
Comparisons - EOC Radial Power Consistency Radial power difference between vendor methods.
I]
))
Good EOC radial power consistency between vendor methods. I
- HITACHI GNr GO5.b Nuebw Fuel A JO*W,-9 o GL e. hb & "chi Page 24
Non-Proprietary Information - Class I (Public)
Core Modeling Conclusions Results are representative of equilibrium ATRIUMTM 1OXM cycle performance.
Good axial and radial power agreement between core simulators.
Good thermal hydraulic agreement between core simulators.
Differences are addressed by applied uncertainties in ATWS analysis.
Differences observed in core simulator vendor methods are similar or less than cycle to cycle variation within the same methods.
" Core modeling results are reasonable and acceptable.
GEH ATWS analysis is cycle independent.
Good agreement means that the core is well represented in PANAC and is appropriate for use in GEH ATWS methods.
I Consistent core modeling between AREVA and GNF/GEH methods.
HITACHI GN'r Page 25 QIsAb Nuwlo Ful A Jo.. Výew W GE* T*Jb. & Ha.,hJ
ATWS Analyses
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ATWS Approach Overview GEH ATWS methods for ODYN and TRACG are already well-defined, and they are unchanged for ATRIUM TM 1OXM fuel.
" GEH experience base for ATWS already includes AREVA fuel.
GEH has modeled ATRIUM TM 10 fuel in ATWS previously.
ATRIUM TM 1OXM fuel is very similar to ATRIUM TM 10 fuel.
Water box with 10x10 array and full/part-length rods.
Differences are captured and explicitly addressed.
Inputs to ATWS are explicit and fuel-specific.
TGBLA is qualified using MCNP for ATRIUM TM 1OXM features.
PANAC core of ATRIUM TM 1OXM is used as direct input.
ATRIUM TM 1OXM ISCOR/TASC/TRACG channels have been developed.
ATRIUM TM 1OXM GEXL coefficients have been provided by AREVA.
ATRIUM TM 1OXM PRIME data has been established.
HITACHI Page 27 G1ehd Nuelow FuMe A J.eW Veh.
GLE T"hfb. & N*A.
Non-Proprietary Information - Class I (Public)
GEH ATWS Methods and Models for Brunswick 0 ATWS with Instability (ATWSI)
TRACG Analysis ATWS with recirculation pump trip or turbine trip PCT calculations for regional mode and core wide oscillations Long-Term ATWS ODYN / STEMP Analysis MSIV Closure and Pressure Regulator Failure Open (PRFO) ATWS Pool heatup and containment pressure response ATWS with Depressurization (ATWSD)
TRACG Analysis MSIV closure ATWS if pool reaches heat capacity temperature limit (HCTL)
Not needed if HCTL is not reached in ODYN/STEMP PCT effects of reactor blowdown ODYN is conservative but is not qualified for blowdown analysis HITACHI GN'r Page 28 0
WNuclur Fuel A J400 V..
d4 GEA T..bc
& IfIfadh
Non-Proprietary Information - Class I (Public)
ATWS Parameter Overview
° Plant parameters ((
]i
-Plant-specific data is used for the plant parameters.
All pertinent fuel parameters are addressed via either explicit models or sensitivity analysis.
A select few fuel parameters are addressed via nominal fuel data and sensitivity analysis.
Each fuel parameter from the sensitivity analysis ranges is addressed explicitly.
HITACHI GN'r Wolml Nucloe Fuel A
.JM Vý. W GE T.O.Ab. & Hiahi Page 29
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ATWS Design Process ATWS PIRT I
Product Requirements Review I
I Conceptual Design Review I
I 4Yes Detailed Design Review LNoI M
I Design Validation Review HITACHI GNu' Gl" Nueiw Fuel Page 30
Non-Proprietary Information - Class I (Public)
Fuel Parameters Down Selection I]
0 Items in green shading are parameters "down-selected."
Down selection means to standard GEH ATWS that the parameters require special treatment relative methods.
a HITACHI GNr ON"bd Nucles Fueh A AM
ý fo.e~
GE. TO".E &~
I Ehi Page 31
Non-Proprietary Information - Class I (Public)
Fuel Parameters Down Selection Purpose of Conceptual Design Review (CDR) was to approve sensitivity determination.
- The ranges selected for CDR were intended to be large enough to provide meaningful sensitivity results.
- Ranges for ATRIUMTM 1OXM fuel have been selected with further input from Duke and AREVA.
" GEXL coefficients are provided by Areva.
" Gap conductance multipliers for ATRIUMTM 1OXM relative to ATRIUMTM 10 is provided by Areva.
" Remaining ranges developed by GEH and confirmed by Duke.
CDR sensitivity calculations revealed the application-specific results impact.
S HITACHI G*
og3 HITACHIPage 32 QIsbd Nudlew Ful A Jo-V.
o OL Th.W, & 1*Ih,
Non-Proprietary Information - Class I (Public)
ATWS Acceptance Criteria Limit Values related to ATWS Generic Limits Peak Vessel Pressure = 1500 psig PCT = 2200 'F
[NUREG-0800]
Brunswick-Specific Limits Pool Temperature = 207.7 'F Containment Pressure = 62 psig HITACHI GN'-
SObld Nucler FuMl A J*1. w W GLE T-hb& & AH*i, Page 33
Non-Proprietary Information - Class I (Public)
ATWSI Fuel Parameter Sensitivity Results TRACG04 Calculation of ATWS with Instability Turbine Trip w/Bypass (TTWBP)
Cases run at limiting conditions [H
]
" Recirculation Pump Trip (RPT)
Feedwater temperature reduction is based on Brunswick-specific data Cases run at limiting conditions ((
))
([
11 Limiting Channel PCTs are calculated
" Sensitivities Selected (Areas Important to ATWSI)
[C 1]
HITACHI GN'rPae3 Page 34 bA l i
Nu* cer G
Fuel A
GA.AV*Mýo GE oTbMb.
& Hib
Non-Proprietary Information - Class I (Public)
ATWSI Fuel Parameter Sensitivity Results
))
HITACHI G*.'
Wh" Nuclear Fuel A Me V..1of GL. TMb& & i.thi Page 35
Non-Proprietary Information - Class I (Public)
ATWSI Fuel Parameter Sensitivity Results
- The rewet model in TRACG has been updated.
Results presented above do not reflect the updated rewet model.
Results presented above are for a plant which is not Brunswick and for a fuel that is of GNF type.
- The fuel parameter effects on PCT are ((
))
All fuel parameter sensitivity areas investigated are addressed explicitly for Brunswick.
All Brunswick-specific ATWS calculations incorporate the revised rewet model.
HITAHI G Page 36 S"WNuclea Fu A Jo. V-WA GE. T*MAb. & H&h,
Non-Proprietary Information - Class I (Public)
ATWSI Fuel Parameter Sensitivity Results All pertinent fuel parameters have been captured.
- ((
J]
Plant parameters, consistent with Duke input for the Brunswick plant and Emergency Operating Procedures, H[
HITACHI GNr' GiebW Nuclear Fuel A Jo V.oo.1 GE To*.bG & Hiohi
))
Page 37
Non-Proprietary Information - Class I (Public)
ATWSD Fuel Parameter Sensitivity Results
" TRACG Calculation of MSIV Closure ATWS with Depressurization Model is Brunswick plant-specific used for prior MELLLA+ analysis Fuel in CDR sensitivities is GE14 used for prior MELLLA+ analysis Pool temperature, containment pressure, PCT and vessel bottom pressures are calculated.
" Sensitivities Selected (Areas Important to ATWSD)
- ((
))
HITACHI GNr' 06"Wb Nudua Fuel A JO.. V.ý.t. W GE, T.*o b. & Hidhi Page 38
Non-Proprietary Information - Class I (Public)
ATWSD Fuel Parameter Sensitivity Results
))
0 HITACHI GNF Gkdo Nuaclr Fuel A JOWo b e
- d GE.
TA hib & Nitachi Page 39
Non-Proprietary Information - Class I (Public)
ATWSD Fuel Parameter Sensitivity Results i]
0 HITACHI GNP:
GON"l Nuclear Fuel A J.M. V...
b &O A,..
& Gh, Page 40
Non-Proprietary Information - Class I (Public)
ODYN ATWS Implications
" ODYN is used for calculation of PCT, peak suppression pool temperature, and containment pressure.
" ODYN analysis is used to determine if further TRACG analysis is required.
Increased boron enrichment of SLCS should offset EPU/MELLLA+ effects.
If the pool temperature reaches HCTL in ODYN analysis, then TRACG calculation of ATWS with depressurization is required.
° ODYN has been used in this capacity for ATRIUMTM 10.
AREVA is performing short-term ATWS overpressure via their normal reload process.
HITACHI G.-
Poge 4 GId N~uciew Fuel A J OIN V
of GS Tohib. & Hifah
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ATWS Resulting Conceptual Design Base calculations are performed without uncertainties for ATWSI (TRACG), ATWSD (TRACG), and long-term ATWS (ODYN).
Plant-specific fuel parameter ranges have been selected.
Fuel parameter sensitivities are repeated on a plant-specific basis for
((
))
The final ATWSI (TRACG), ATWSD (TRACG) [if needed], and long-term ATWS (ODYN) calculations will incorporate the sensitivity of the down selected fuel parameters.
Margins calculated in the CDR sensitivities indicate that there is adequate margin to accommodate this approach.
S HITACHI GN'r Page 42 0l*d Nucler Fuel A Jaim V.
- W.
Of. Toshib, & Himchi
I Limitations and Conditions
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Applicable Interim Methods, MELLLA+ and TRACG Supplement 3 LTR Limitations and Conditions Interim Methods LTR NEDC-33173P-A 9.12 LHGR and Exposure Qualification Requires GEH to use PRIME.
PRIME is used and bounding uncertainty applied to cover ATRIUM TM 10XM fuel.
9.15 Void reactivity 1 Void reactivity representative of lattice design.
Benchmarked to MCNP and AREVA methods.
9.16 Void reactivity 2 Incorporation of void history.
Void history effect covered by application of bounding uncertainty 9.19/20 Void Quality correlation Applicability of void-quality correlation for ATRIUM TM 1OXM fuel.
9.22 Mixed core method 2 Applicability to ATRIUM TM 10XM fuel.
Benchmarked to MCNP and AREVA methods.
HIA H Page 144 S HITACHI G D
Okl Nulw FuM A J.U Y.
oW GE T. ib. & HIlft.h
Non-Proprietary Information - Class I (Public)
Applicable Interim Methods, MELLLA+ and TRACG Supplement 3 LTR Limitations and Conditions MELLLA+ LTR NEDC-33006P-A 12.1 GEXL-PLUS GEXL+ critical power and frictional pressure drop justified by experimental data.
GEXL+ correlation fitted to bound ATRIUM TM 10XM by AREVA.
Spacer, tie plate and leakage path frictional losses fitted by Duke using GEH/GNF methods to AREVA data. Additional bounding uncertainty applied.
12.2 Applicable IMLTR limitations - See IMVlLTR limitations.
12.23.6 Limitations from Appendix A RAI 14.9 Bounding ATWSI analysis for applications beyond GE14.
Bounding uncertainties applied.
HITACHI G* r Page 45 QlelNuW eFue A Jor-V...
GL To.*5*. & IH-h.
Non-Proprietary Information - Class I (Public)
Applicable Interim Methods, MELLLA+ and TRACG Supplement 3 LTR Limitations and Conditions TRACG04 LTR NEDE-32906P Supplement 3-A 4.2 Applicable IMLTR limitations - See IMLTR limitations.
4.6 Fuel thermal conductivity and gap conductance conditions.
Covered by IMLTR limitation 9.12.
4.20 Interfacial shear model qualification conditions.
Applicability of interfacial shear model (void fraction) for ATRIUM TM 1OXM fuel.
Covered by IMLTR limitation 9.19/20.
4.21/22 Void reactivity coefficient.
Covered by IMLTR Limitations 9.15/16.
4.28 Fuel Lattice Limitation.
Covered by IMLTR Limitations 9.15/16.
4.31 Direct moderator heating Applications beyond GE14. Bounding uncertainties applied.
4.34 Applicable MELLLA+ Limitations - See MELLLA+ limitations S
HITACHI GNPage46 Glabil Nuclear Fuel A MO V o of GE. Tfthib., & Hitachi
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Summary
- GEH has used an extensive uncertainty identification and management process.
- Explicit ATRIUM TM 1OXM PANACEA core has been constructed based upon Duke/AREVA input with good agreement to Duke/AREVA analyses.
- Fuel-specific uncertainties are being explicitly captured and bounded.
- All applicable Interim Methods LTR and MELLLA+ LTR limitations and conditions are addressed appropriately.
HITACHI GNr Page 47 Glo I Nucler Fuel A MW V
. of GE.
Toshb.. & N0h0r