Text

Enclosure 2: Presentation
	ML20357A392
Person / Time
Site:	07109319
Issue date:	12/07/2020
From:	; Framatome
To:	; Office of Nuclear Material Safety and Safeguards
	PSaverot - NMSS/DFM/STL - 301.415.7505
Shared Package
ML20357A388	List: ML20357A390; ML20357A392;
References
	EPID L-2020-LLA-0247
	Download: ML20357A392 (28)
	v • d • e

1 MAP License Amendment - December 7, 2020

2 MAP License Amendment - December 7, 2020

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 17x17 Type 3 Fuel Assembly Details

5. Criticality Evaluation a) Methods of Analysis b) Benchmarking

6. Structural Evaluation a) Type 3 Discussion

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

3 MAP License Amendment - December 7, 2020

Tim Tate, Manager, Environmental, Health, Safety, and Licensing

Calvin Manning, Manager, Licensing and Compliance

Bryan Flanagan, Packaging Engineer, Licensing and Compliance

Dan Talmadge, PWR Product Engineer

Dan Mensink, PWR Product Engineer

Brian Friend, PWR Design Advisory Engineer

Michelle Guzzardo, Nuclear Criticality Safety Engineer

Ben Nelson, Nuclear Criticality Safety Engineer

ORANO Federal Services

Rob Machen, Project Manager

Phil Noss, Licensing Manager

Slade Klein, Engineering Manager

Erik Gonsiorowski, Nuclear Criticality Safety Engineer

John Scaglione, Nuclear Criticality Safety Engineer

Donald Mueller, Nuclear Criticality Safety Engineer Framatome Team

4 MAP License Amendment - December 7, 2020

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 17x17 Type 3 Fuel Assembly Details

5. Criticality Evaluation a) Methods of Analysis b) Benchmarking

6. Structural Evaluation a) Type 3 Discussion

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

5 MAP License Amendment - December 7, 2020

Advanced Fuel Management (AFM) Project

Significantly reduce the utility customers operating costs in the near term by bringing to market technologies which increase cycle lengths and capacity factors

Reducing the number of refueling outages

Improving fuel cycle economics

Framatome is working in conjunction with a US reactor site to realize these benefits

NRC License Amendment Request

Increase allowable enrichment above 5 wt.% 235U for 17x17 fuel assemblies

Introduce the 17x17 Type 3 (GAIA) fuel design parameters

Applicable for both the MAP-12 and MAP-13 packages

6 MAP License Amendment - December 7, 2020

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 17x17 Type 3 Fuel Assembly Details

5. Criticality Evaluation a) Methods of Analysis b) Benchmarking

6. Structural Evaluation a) Type 3 Discussion

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

7 MAP License Amendment - December 7, 2020

Type A and Type B Contents

Both Type A and Type B contents shall remain the same material, fuel pellets loaded in rods are uranium oxides primarily as ceramic UO2 and U3O8. The maximum enrichment is being increased above 5.0 wt.% 235U and within high assay low enriched limits.

New Contents Tables for >5 wt.% 235U material

Table for < 5.0 wt.% 235U will remain unchanged

Basis for Primary Radionuclides

Source for new material will conform to ASTM standard being developed for Uranium Hexafluoride (ASTM number not yet assigned)

Enriched Commercial Grade UF6 with 235U <6%

with 235U <7%

with 235U <8%

232U 0.0001 g/gU 0.0001 g/gU, 0.0001 g/gU, 234U 11.910x103 g/g235U 12.020x103 g/g235U 13.0x103 g/g235U 236U 250 g/gU 250 g/gU 250 g/gU 99Tc 0.012 g/gU 0.014 g/gU 0.017 g/gU Enriched Slightly Contaminated Uranium with Trace Quantities Limits UF6 with 235U <6%

with 235U <7%

with 235U <8%

232U 0.080 g/gU 0.095 g/gU 0.110 g/gU 234U 5650 g/gU 6650 g/gU 7650 g/gU 236U Not specified Not specified Not specified 99Tc 6 g/gU 7 g/gU 8.5 g/gU

8 MAP License Amendment - December 7, 2020

Comparison of Quantity of Radioactive Material for Shipment in MAP

SAR Table 1-1 Current Table 1-1 New Table 1-1a for >5 wt.% 235U Allowable Assembly Arrays 14x14, 15x15, 16x16 and 17x17 Main Nuclides Low enriched uranium 5 wt% 235U State of Uranium Uranium oxide ceramic

pellet, Solid Normal Form Fuel Assembly Maximum Enrichment 5.0 wt% Maximum Number of Fuel Rods Containing Absorbers Unlimited Maximum mass of Uranium Dioxide Pellets 574 kg per Fuel Assembly 1,148 kg per Package Maximum 235U mass 25.5 kg per Fuel Assembly 51.0 kg per Package Allowable Assembly Arrays 17x17 Main Nuclides High assay low enriched uranium TBD wt% 235U State of Uranium Uranium oxide ceramic

pellet, Solid Normal Form Fuel Assembly Maximum Enrichment TBD wt% Maximum Number of Fuel Rods Containing Absorbers Unlimited Maximum mass of Uranium Dioxide Pellets 574 kg per Fuel Assembly 1,148 kg per Package Maximum 235U mass TBD kg per Fuel Assembly TBD kg per Package

9 MAP License Amendment - December 7, 2020

Comparison of Maximum Allowable Quantity of Radioactive Material

SAR Table 1-2 Current Table 1-2 Add New Table 1-2a for >5 wt.% 235U Isotope Maximum Content U-232 2.00E-09g/gu U-234 2.00E-03g/gu U-235 5.00E-02g/gu U-236 2.50E-02g/gu U-238 9.23E-02g/gu Np-237 1.66E-06g/gu Pu-238 6.20E-11g/gu Pu-239 3.04E-09g/gu Pu-240 3.04E-09g/gu Gamma Emitters 6.46E+05MeV-Bq/kgU Isotope Maximum Content U-232 Values willberevisedaccordingly withtheincreasein235U U-234 U-235 U-236 Tc-99 Np-237 Pu-238 Pu-239 Pu-240 Gamma Emitters

10 MAP License Amendment - December 7, 2020

Introducing Gadolinia Requirements for >5 wt.% 235U

Similar to approach previously approved for the TN-B1 package (Docket No. 9372).

Contents >5 wt.% 235U Enrichment Parameter Units Type Type Type Type Fuel Assembly Type Rods 14x14 15x15 16x16 17x17 Min Gadolinia Requirements Lattice Average Enrichment Max TBD wt% 235U TBD wt% 235U TBD wt% 235U 5.0 wt% 235U

@ wt%

Gd2O3 Not evaluated Not evaluated Not evaluated No Gadolinia requirements Not evaluated Not evaluated Not evaluated No Gadolinia requirements Not evaluated Not evaluated Not evaluated No Gadolinia requirements

@ TBD wt%

@ TBD wt%

@ TBD wt%

No Gadolinia requirements

11 MAP License Amendment - December 7, 2020

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 17x17 Type 3 Fuel Assembly Details

5. Criticality Evaluation a) Methods of Analysis b) Benchmarking

6. Structural Evaluation a) Type 3 Discussion

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

12 MAP License Amendment - December 7, 2020

17x17 Type 3 (GAIA) Parameters Versus Previously Approved FAs 17x17 Type 3 Fuel Assembly Details Fuel Rod Array W17x171 GAIA 17x17 Assy Type 1

2 3

Fuel Rods 264

Non-Fuel Cells 25 Nominal Fuel Rod Pitch (inches) 0.502 0.496 0.496 Maximum Pellet OD (inches) 0.3252 0.3232 TBD2 Minimum Pellet OD (inches) 0.3238 0.3188 TBD2 Minimum Fuel Rod OD (inches) 0.377 0.372 TBD2 Minimum Clad Wall Thickness (inches) 0.0220 0.0205 TBD2 Minimum Guide Tube Wall Thickness (inches)

N/A Minimum Guide Tube OD (inches)

N/A Number of Guide Tubes per Assembly N/A Minimum Instrument Tube Wall Thickness (inches)

N/A Minimum Instrument Tube OD (inches)

N/A Number of Instrument Tubes per Assembly N/A Max 235U Loading (kg) 27.77 27.43 TBD3 Clad/Tube Material Type Zr Alloy Bare or Cr Coated Maximum Active Length (inches) 160

1. Same as existing CoC.

2. These attributes will be defined in the application.

These items remain close or bounded by previously approved designs.

3. The 235U loading will increase to accommodate higher enrichment.

13 MAP License Amendment - December 7, 2020

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 17x17 Type 3 Fuel Assembly Details

5. Criticality Evaluation a) Methods of Analysis b) Benchmarking

6. Structural Evaluation a) Type 3 Discussion

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

14 MAP License Amendment - December 7, 2020

Methods of Analysis

Criticality evaluations performed using SCALE 6.4.2

CSAS6 (Keno-VI) with ENDF/B-VII 238 group library

Initial focus on 17x17 assembly type with enrichments > 5.0 wt% U-235

Gd2O3 fuel rods used for criticality control (multiple configurations evaluated for different enrichments)

Licensing basis consistent with current SAR methodology to identify the most reactive credible configuration consistent with the chemical and physical form of the material

Configuration based on fuel at T.D. and fully flooded fuel cavity, void in outer cavity for HAC array

2 inch reduction in nominal height and width, plus complete removal of lid stiffener spacing for HAC array

Benchmarking

Benchmarks will be selected from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE) that contains ~5,000 laboratory critical experiments performed at various critical facilities around the world

Sensitivity/Uncertainty Analysis are being used to mathematically identify applicable critical experiments to the application model

TSUNAMI-3D (Scale module) used to generate sensitivity data file (SDF) for licensing basis application model

TSUNAMI-IP (Scale module) used to used to evaluate the similarity of critical experiments to application model (SDFs for critical experiments are taken from IHECSBE)

Bias and bias uncertainty for application model generated using keff results for applicable sets of critical experiment models and single-sided tolerance interval for 95% probability and 95% confidence level

15 MAP License Amendment - December 7, 2020

Selection of critical experiments

The critical experiments and the safety basis model need to use the nuclear data in a similar energy-dependent manner; otherwise, an incorrect bias could be generated

Historically, similarity has been left largely to professional judgment using qualitative and integral quantitative comparisons to select critical experiments

Sensitivity/uncertainty (S/U) tools can be used to assess application and critical experiment model similarity with a quantifiable metric

Uncertainty analysis is performed for the safety analysis (application) model and for each candidate critical experiment model

Sensitivity is the fractional change in keff due to a fractional change in a nuclear data value or S (k/k)/(/)

Energy-dependent keff uncertainties for each application model and each critical experiment are compared, producing a correlation coefficient (ck) for each application/experiment model pair

A high ck value of near 1 for an application/critical experiment pair indicates that both models have similar sensitivities to the same nuclear data and consequently should have similar biases

Low ck values indicate that the two systems differ significantly and may have significantly different biases

16 MAP License Amendment - December 7, 2020

-0.6

-0.4

-0.2 0

0.2 0.4 0.6 0.8 1

Ck Plot of Ck by LCE group ICF ICI ICM ICT IMF IMI IMM IST LCF LCM LCT L-Met_T L-Misc-T LST Ck 0.9 = 732 Ck 0.8 = 999

17 MAP License Amendment - December 7, 2020

Keff Draft Results Configuration Calculated keff Uncertainty ()

keff + 2 MAP with Fuel Assembly (DRAFT RESULTS)

NCT (Infinite Array) 0.2434 0.0004 0.2442 HAC (Maximum k for 2N Array) 0.9332 0.0007 0.9346

18 MAP License Amendment - December 7, 2020

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 17x17 Type 3 Fuel Assembly Details

5. Criticality Evaluation a) Methods of Analysis b) Benchmarking

6. Structural Evaluation a) Type 3 Discussion

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

19 MAP License Amendment - December 7, 2020

Fuel Assembly Details

The GAIA 17x17 AFM fuel design structural response to normal and accident condition does not change from the existing drop testing qualification that was based on Mark-BW 17x17 fuel with essentially unchanged structural response characteristics.

Attributes such as fuel rod wall thickness and payload weight are still bounded by test conditions.

The static and dynamic evaluations for reactor conditions confirm the AFM GAIA 17x17 grid strengths when compared to the Mark-BW 17x17 design and that they would perform similarly at accident conditions for the container.

GAIA 17x17 grids, being of comparable grid strip area and cross-section properties have similar load bearing performance.

The GAIA 17x17 grid design utilizes shorter spaced supports on the diagonal compared to the Mark-BW providing further resistance to buckling.

All of the other key load bearing components (i.e., Nozzles, guide tubes, grid counts, connections) are all of the same design characteristics as the currently qualified fuel design bases.

The GAIA 17x17 fuel design allows for either Zirconium Alloy or chromium coated Zirconium alloy fuel rod cladding.

Either condition falls within previously approved evaluations associated with Rev. 12 of the CoC.

Weights are still bounded by existing licensing basis.

Structural Evaluation

20 MAP License Amendment - December 7, 2020

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 17x17 Type 3 Fuel Assembly Details

5. Criticality Evaluation a) Methods of Analysis b) Benchmarking

6. Structural Evaluation a) Type 3 Discussion

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

21 MAP License Amendment - December 7, 2020

Thermal

An update of this section shall be provided based on >5.0 wt% 235U specific criteria to be performed for the likely small increases in decay heat for the new contents. No change to the results are anticipated.

Containment

There is no change to the containment criterion as the fuel rod cladding remains the containment boundary.

Each fuel rod is demonstrated to have a leakage rate less than 1E-07 ref-cc/sec during fabrication.

Clarification will be added distinguishing the difference between <5.0 wt% 235U, >5.0 wt% 235U, and Type B contents.

Shielding

An update of this section shall be provided based on >5.0 wt% 235U specific criteria to be performed of the likely small increases in radiation for the new contents. No change to the results are anticipated.

Thermal, Containment, and Shielding Discussion

22 MAP License Amendment - December 7, 2020

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 17x17 Type 3 Fuel Assembly Details

5. Criticality Evaluation a) Methods of Analysis b) Benchmarking

6. Structural Evaluation a) Type 3 Discussion

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

23 MAP License Amendment - December 7, 2020

Schedule:

NRC Submittal - December 31, 2020

Amendment Request - December 31, 2021 Proposed Schedule

24 MAP License Amendment - December 7, 2020

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 17x17 Type 3 Fuel Assembly Details

5. Criticality Evaluation a) Methods of Analysis b) Benchmarking

6. Structural Evaluation a) Type 3 Discussion

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

25 MAP License Amendment - December 7, 2020

26 MAP License Amendment - December 7, 2020

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 17x17 Type 3 Fuel Assembly Details

5. Criticality Evaluation a) Methods of Analysis b) Benchmarking

6. Structural Evaluation a) Type 3 Discussion

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

27 MAP License Amendment - December 7, 2020

28 MAP License Amendment - December 7, 2020

v t e Letter Sequence Other
EPID:L-2020-LLA-0247, Framatome MAP-12 and MAP-13 Shipping Container, Amendment (Approved, Closed)
Initiation Request Acceptance Administration Meeting, Meeting Questions Answers Results Approval Other: ML20357A392, ML21343A229
MONTHYEAR2021-12-16 [Table View]

ML20357A392

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