Text

NRC Pre-Application Meeting 12-13-2022
	ML22353A088
Person / Time
Site:	07109372
Issue date:	12/13/2022
From:	; Framatome
To:	; Division of Fuel Management
Shared Package
ML22353A086	List: ML22353A087; ML22353A088; ML22353A090;
References
	EPID L-2022-LLA-0093
	Download: ML22353A088 (1)
	v • d • e

1 TN-B1 License Amendment - December 13, 2022

2 TN-B1 License Amendment - December 13, 2022

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. Fuel Assembly Details

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

6. Structural Evaluation

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

3 TN-B1 License Amendment - December 13, 2022

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

Calvin Manning, Manager, Licensing and Compliance

Bryan Flanagan, Packaging Engineer, Licensing and Compliance

Kevin Elliott, BWR Product Engineer

Michelle Guzzardo, Nuclear Criticality Safety Engineer

Ben Nelson, Nuclear Criticality Safety Engineer

Colin Weber, Health Physicist

ORANO Federal Services

Rob Machen, Project Manager

Phil Noss, Licensing Manager

Slade Klein, Engineering Manager

John Scaglione, Nuclear Criticality Safety Engineer

Donald Mueller, Nuclear Criticality Safety Engineer Framatome Team

4 TN-B1 License Amendment - December 13, 2022

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. Fuel Assembly Details

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

6. Structural Evaluation

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

5 TN-B1 License Amendment - December 13, 2022

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 (PWR)

Reducing the number of fresh fuel assemblies (BWR)

Improving fuel cycle economics

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

Following the same evaluation process used for the MAP package amendment (Docket 71-9319)

NRC License Amendment Request

Increase allowable enrichment above 5 wt.% 235U for 11x11 fuel assemblies

Includes BWR 11x11 and PWR 17x17 Type 3 loose fuel rod configuration above 5 wt.% 235U

6 TN-B1 License Amendment - December 13, 2022

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. Fuel Assembly Details

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

6. Structural Evaluation

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

7 TN-B1 License Amendment - December 13, 2022

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 up to 8.0 wt.% 235U, 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). Same as used for MAP package.

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 TN-B1 License Amendment - December 13, 2022

Comparison of Quantity of Radioactive Material for Shipment in TN-B1

SAR Table 1-2 Current Table 1-2 New Column for >5 wt.% 235U Allowable Assembly Arrays 8x8, 9x9, 10x10 and 11x11 Main Nuclides Low enriched uranium 5 wt% 235U State of Uranium Uranium oxide ceramic

pellet, (Solid)

Fuel Assembly Average Enrichment 5.0 wt% Maximum Fuel Rod Maximum Enrichment 5.0 wt% Maximum Number of Fuel Rods Containing gadolinia See Table 6-1 Maximum mass of Uranium Dioxide Pellets 574 kg per Fuel Assembly 1,148 kg per Package Weight of uranium dioxide pellets (per fuel assembly 235 kg (8x8), 240 kg (9x9), 275 kg (10x10),

281 kg (11x11)

Allowable Assembly Arrays 11x11 Main Nuclides Low enriched uranium 8 wt% 235U State of Uranium Uranium oxide ceramic

pellet, (Solid)

Fuel Assembly Average Enrichment 8.0 wt% Maximum Fuel Rod Maximum Enrichment 8.0 wt% Maximum Number of Fuel Rods Containing gadolinia See Table 6-1 Maximum mass of Uranium Dioxide Pellets 574 kg per Fuel Assembly 1,148 kg per Package Weight of uranium dioxide pellets (per fuel assembly 281 kg

9 TN-B1 License Amendment - December 13, 2022

Comparison of Maximum Allowable Quantity of Radioactive Material

SAR Table 1-3 Current Table 1-3 Add New Table 1-3a 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-01g/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 5.18E+05MeV-Bq/kgU Isotope Maximum Content U-232 1.10E-07g/gU U-234 7.65E-03g/gU U-235 8.00E-02g/gU U-236 2.50E-02g/gU U-238 8.87E-01g/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 5.18E+05MeV-Bq/kgU

10 TN-B1 License Amendment - December 13, 2022

Gadolinia Requirements for >5 wt.% 235U

No gadolinia requirements for loose rods

ATRIUM 11 Contents >5 wt.% 235U Enrichment Fuel Assembly Type Type 11x11 Parameter

Gd Rods Wt.% Gd2O3 Min Gadolinia Requirements Lattice Average Enrichment Max 8.0 wt.% 235U 7.5 wt.% 235U 7.0 wt.% 235U 6.5 wt.% 235U 6.1 wt.% 235U 5.8 wt.% 235U 21 19 17 15 13 13 4.0 4.0 4.0 4.0 4.0 2.0

11 TN-B1 License Amendment - December 13, 2022

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. Fuel Assembly Details

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

6. Structural Evaluation

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

12 TN-B1 License Amendment - December 13, 2022

ATRIUM 11 (11x11) Parameters Versus Previously Approved Fuel Assemblies

No changes from existing CoC Loose Rods

Now includes PWR 17x17 Type 3 for >5 wt.% 235U

For the generic PWR fuel rod parameters in the current CoC, the Fuel Rod OD is less than the current minimum. All other criteria, including Cladding Wall Thickness, is bounding.

The 17x17 Type 3 parameters will be distinguished within the SAR for the 8.0 wt.% 235U Fuel Assembly Details 17x17 Type 3 Fuel Rod Maximum Pellet OD, in 0.3254 Minimum Pellet OD, in 0.3188 Minimum Fuel Rod OD, in 0.372 Minimum Clad Wall Thickness, in 0.0205

13 TN-B1 License Amendment - December 13, 2022

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. Fuel Assembly Details

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

6. Structural Evaluation

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

14 TN-B1 License Amendment - December 13, 2022

Methods of Analysis

Criticality evaluations performed using SCALE 6.2.4

CSAS5 (Keno-Va) Monte Carlo neutron transport code

Focus on same 11x11 assembly models with increasing 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 preferential flooding (fully flooded fuel cavity), void in cavity between inner and outer containers for HAC array

10.2 kg of polyethylene, not including cushioning foam pads

Benchmarking

Benchmarks 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 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 TN-B1 License Amendment - December 13, 2022

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 engineering 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

The similarity of a benchmark to the application is characterized by the correlation coefficient, ck, which is calculated by TSUNAMI-IP

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 TN-B1 License Amendment - December 13, 2022

CSI DRAFT Results Atrium 11 fuel assemblies with the specified maximum lattice average enrichments with each assembly containing a minimum number of UO2+Gd2O3 fuel rods with minimum Gd2O3 loading maximum CSI is less than or equal to 3.3.

Wt% 235U

Gd rods wt% Gd2O3 CSI 8.0 21 4.0 3.2 7.5 19 4.0 3.2 7.0 17 4.0 3.2 6.5 15 4.0 3.2 6.1 13 4.0 3.2 5.8 13 2.0 3.2

Atrium 11 fuel rods with enrichments no greater than 8.0 wt% 235U

Up to 25 loose or bundled fuel rods, CSI = 1.0

Up to 30 fuel rods in a 5-inch stainless steel pipe or a protective carrier (described in Section 1.2.3.4.7 of the currently approved TN-B1 SAR revision [23]), CSI = 2.3

PWR 17x17, type 3 fuel rods with enrichments no greater than 8.0 wt% 235U

Up to 25 loose or bundled fuel rods, CSI = 1.0

Up to 30 fuel rods in a 5-inch stainless steel pipe or a protective carrier (described in Section 1.2.3.4.7),

CSI = 2.5

17 TN-B1 License Amendment - December 13, 2022

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. Fuel Assembly Details

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

6. Structural Evaluation

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

18 TN-B1 License Amendment - December 13, 2022

Fuel Assembly Details

No changes from existing CoC for ATRIUM 11 (11x11)

Loose Rod Details

The GAIA 17x17 Type 3 AFM fuel rod design remains essentially the same as previously authorized PWR rods

Although the Fuel Rod OD is less than the current minimum value in the CoC (0.945 cm vs.

1.118 cm) the minimum Cladding Wall Thickness is bounded (0.052 cm vs. 0.033 cm)

The 17x17 Type 3 parameters will be distinguished within the SAR for the 8.0 wt.% 235U

Weights remain bounded by existing licensing basis.

Structural Evaluation

19 TN-B1 License Amendment - December 13, 2022

FS1-0042700,Outer Container Fixture Assembly Installation

Add new Flag Note 4 to BOM Item 9, Vibroisolating Rubber

Size and quantity of Item 9 may vary depending on vibration performance factors of the rubber material

No impact on NCT or HAC package performance as the vibroisolators function is to reduce normal transportation road vibrations that affect fuel rod fretting Structural Evaluation

20 TN-B1 License Amendment - December 13, 2022

FS1-0042699, Outer Container Fixture Assembly

Replaces 105E3739 to comply with Framatome procedures

Natural Rubber material call-out changed to Rubber for Items 7, 8, and 11 to allow use of various rubber materials for replacement.

Legacy change from previous amendment (CoC Rev. 3)

Structural Evaluation

21 TN-B1 License Amendment - December 13, 2022

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. Fuel Assembly Details

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

6. Structural Evaluation

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

22 TN-B1 License Amendment - December 13, 2022

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

23 TN-B1 License Amendment - December 13, 2022

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. 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

24 TN-B1 License Amendment - December 13, 2022

Schedule:

NRC Submittal - January 31, 2023

Amendment Request - January 31, 2024 Proposed Schedule

25 TN-B1 License Amendment - December 13, 2022

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. Fuel Assembly Details

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

6. Structural Evaluation

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

26 TN-B1 License Amendment - December 13, 2022

27 TN-B1 License Amendment - December 13, 2022

1. Framatome Team

2. Project Description

3. Contents >5 wt.% 235U Enrichment

4. Fuel Assembly Details

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

6. Structural Evaluation

7. Thermal, Containment, and Shielding Discussion

8. Proposed Schedule

9. Opportunity for Public Comment 10.Conclusion Agenda

28 TN-B1 License Amendment - December 13, 2022

29 TN-B1 License Amendment - December 13, 2022

v t e Letter Sequence Meeting
EPID:L-2022-LLA-0093, Summary of December 13, 2022 Meeting with Framatome (Open)
Initiation Request, Request, Request, Request Acceptance... Administration Meeting, Meeting, Meeting, Meeting Questions Answers Results Approval... Other: ML23031A217, ML24156A105
MONTHYEAR2023-01-31 [Table View]

ML22353A088

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