ML19093A957

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Orano Federal Services Calculation CALC-3021788, TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal, Revision 1
ML19093A957
Person / Time
Site: Crane, 07200020  
Issue date: 03/19/2019
From: Gonsiorowski E
Orano Federal Services, US Dept of Energy, Idaho Operations Office
To:
Office of Nuclear Material Safety and Safeguards
References
CLN190779 CALC-3021788
Download: ML19093A957 (39)
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Page 1 of 39 Orano Federal Services orano CALCULATION Document No.:

CALC-3021788 Rev. No.

001 Page 1 of 39 Pro*ect No.:

02029. 00. 0000. 02 Pro*ect Name:

License Renewal Su ort

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Summary:

The Nuclear Regulatory Commission (NRC) has requested additional information to support the technical review of the Three Mile Island Unit 2 (TMl-2) Independent Spent Fuel Storage Installation (ISFSI) license renewal.

Request for additional information {RAI) 3-7 asks for additional evidence that the TMl-2 Canister will be subcritical following Licon material losses RAI 3-8 requests additional justification that changes to the Licon material properties, due to aging, are not important to maintaining TMl-2 Canister subcriticality This calculation further evaluates the TMl-2 Fuel Canister reactivity following changes to the Licon material to support the responses to the above RAls.

A comparison of TMl-2 criticality evaluations is presented in Appendix A.

Revision 1 of this calculation revises the benchmark analysis to address concerns from the NRC.

Contains Unverified Input/ Assumptions:

Yes: D No: [gl Software Utilized (Name and Revision):

SCALE 6.2.1, Excel 2010 Location of Computer Files:

COLDStor Printed Name Signature Date Preparer:

E. Gonsiorowski Checker:

S. Gibboney Approver:

C. Backus FS-EN-FRM-002 Rev. 11 (Effective January 7, 2019)

Refer to FS-EN-PRC-002 Orano Federal Services MAR 19 2019 Records Management

Page 2 of 39 Orano Federal Services orano

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Revision History Rev.

Changes 0

Initial Release 1

Benchmark analysis revised to address NRC concerns Page 2 of 39

Page 3 of 39 Orano Federal Services orano

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Page 3 of 39 Table of Contents Page REVISION HISTORY................................................................................................................................................................... 2 LIST OF TABLES......................................................................................................................................................................... 4 LIST OF FIGURES....................................................................................................................................................................... 4 1.0 PURPOSE...................................................................................................................................................................... 5 2.0 METHODOLOGY........................................................................................................................................................... 5 2.1 Criticality Design Criteria and Features............................................................................................................ 5 3.0 ASSUMPTIONS............................................................................................................................................................. 7 3.1 Unverified Assumptions.................................................................................................................................... 7 3.2 Justified Assumptions....................................................................................................................................... 7 4.0 DESIGN INPUTS........................................................................................................................................................... 8 4.1 Fuel Specification............................................................................................................................................. 8 4.1.1 Non-Fuel Hardware.......................................................................................................................... 8 4.1.2 Fuel Condition.................................................................................................................................. 8 4.2 Model Specification.......................................................................................................................................... 9 4.2.1 Configuration.................................................................................................................................... 9 4.2.2 Material Properties........................................................................................................................... 9 5.0 CALCULATIONS.......................................................................................................................................................... 14 5.1 Criticality Analysis........................................................................................................................................... 14 5.1.1 Computer Codes............................................................................................................................ 14 5.1.2 Multiplication Factor........................................................................................................................ 15 5.1.3 Benchmark Comparisons............................................................................................................... 19 6.0 RES UL TS AND CONCLUSIONS................................................................................................................................. 24 7.0 COMPUTER SOFTWARE USAGE.............................................................................................................................. 25 7.1 In-Use Testing of SCALE 6.2.1...................................................................................................................... 25 7.2 File Listing...................................................................................................................................................... 25

8.0 REFERENCES

............................................................................................................................................................. 33 9.0 SAMPLE INPUT FILE.................................................................................................................................................. 35 9.1 Collapsed_ 4x3.inp.......................................................................................................................................... 35 APPENDIX A :

COMPARISON OF SELECT TMl-2 ISFSI CRITICALITY CASES.............................................................. 36

Page 4 of 39 orano Orano Federal Services

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support List of Tables Page 4 of 39 Page Table 5-1 : Non-Structural Loss of Licon Results.................................................................................. 16 Table 5-2: Water Absorption in Licon Results...................................................................................... 17 Table 5-3: Compression of Packing due to Structural Loss of Licon Results........................................ 18 Table 5-4: Benchmark Experiments Used............................................................................................ 19 Table 5-5: USL Results........................................................................................................................ 21 Table 5-6: Benchmark Experiment Data.............................................................................................. 24 Table A-1 : Comparison of Select TMl-2 ISFSI Criticality Cases........................................................... 37 List of Figures Page Figure 2-1: NUHOMS-12T Dry Shielded Canister................................................................................ 6 Figure 2-2: NUHOMS-12T Horizontal Storage Module......................................................................... 6 Figure 4-1 : Criticality Model with Credit for Licon Structural Properties (Radial View).......................... 10 Figure 4-2: Criticality Model with Credit for Licon Structural Properties (Axial View)............................ 11 Figure 4-3: Criticality Model with No Credit for Licon Structural Properties (Triangular Array).............. 12 Figure 4-4: Criticality Model with No Credit for Licon Structural Properties (Square Array).................. 13 Figure 5-1: Non-Structural Loss of Licon Results................................................................................. 16 Figure 5-2: Water Absorption in Licon Results..................................................................................... 17 Figure 5-3: Compression of Packing due to Structural Loss of Licon Results....................................... 18

Page 5 of 39 orano Orano Federal Services

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support 1.0 PURPOSE Page 5 of 39 The Nuclear Regulatory Commission (NRC) has requested additional information [1] to support the technical review of the Three Mile Island Unit 2 (TMl-2) Independent Spent Fuel Storage Installation (ISFSI) license renewal application (LRA) [2]. Request for additional information (RAI) 3-7 asks for additional analysis that the TMI-2 Canister will be subcritical following Licon material losses. RAI 3-8 requests additional justification that changes to the Licon material properties, due to aging, are not important to maintaining TMI-2 Canister subcriticality.

This calculation further evaluates the TMI-2 Fuel Canister reactivity, using credible limits for water and poison content, following changes to the Licon material. Total loss of Licon is evaluated, including changes due to loss of the structural integrity of the TMI-2 Fuel Canister shell. Water absorption in Licon is also evaluated. After a subsequent reconfiguration of the TMI-2 Fuel Canister into the most reactive configuration, a conservative keff value is computed by packing the 12 TMl-2 Fuel Canisters together via surface-to-surface contact of their Bora!

shrouds. The results of this calculation will serve as the technical basis for the responses to RAI 3-7 and RAI 3-8.

This calculation is formatted using the guidance for spent fuel dry storage system criticality evaluations in NUREG-1536 [4].

A comparison ofTMI-2 criticality evaluations is presented in Appendix A.

Revision 1 of this calculation revises the benchmark analysis to address concerns from the NRC [22]. The NRC requests that the benchmark analysis be revised to include more trending parameters and exclude experiments containing materials that are not relevant. Additionally, the NRC requests that all experimental benchmarks utilize the same techniques (i.e. the CELLMI X option) used in the TMI-2 Fuel Canister models.

2.0 METHODOLOGY 2.1 Criticality Design Criteria and Features Criticality analysis of the TMI-2 ISFSI is discussed in Section 3.3.4 of the TMI-2 ISFSI Safety Analysis Report (FSAR) [3]. The "original" criticality evaluation discussed in Sections 3.3.4.1 and 3.3.4.2 of the TMI-2 ISFSI FSAR is contained in TN West Calculation 0219.02.0300, "Criticality Evaluation for the 1 OCFR72 INEL/TMI-2 Fuel ISS (NUHOMS-l 2T)" [5], while the "second" criticality evaluation discussed in Sections 3.3.4.3 and 3.3.4.4 of the TMI-2 ISFSI FSAR is contained in Idaho Cleanup Project Report INEEL/INT-99-00126, "Criticality Safety Evaluation of TMl-2 Canister Transportation and Storage" [6]. The second criticality evaluation was performed to model beyond-credible quantities of water content in stored fuel. Due to the significantly higher maximum ketT value calculated in the second criticality evaluation compared to the original criticality evaluation, the analysis contained in this calculation is based on analysis performed in [6]. This is consistent with the logic outlined in RAI 3-7.

The TMI-2 ISFSI storage design is described in Section 2 of [6]. The TMI-2 ISFSI is comprised of concrete horizontal storage modules (HSMs) containing steel dry shielded canisters (DSCs). Within each DSC, a steel basket holds twelve TMI-2 core debris Canisters. There are three types ofTMI-2 Canisters: Fuel, Knockout, and Filter. RAI 3-7 and RAI 3-8 are only relevant to the TMI-2 Fuel Canister as that is the only TMI-2 Canister that contains Licon. The TMI-2 Fuel Canister consists of a central cavity containing core debris surrounded by layers of steel, Bora!, and Licon. The TMI-2 Fuel Canister may also contain water leftover from wet loading or absorbed during storage. The steel basket and DSC assemblies are detailed in [7], [8], [9], and [10]. The TMI-2 Canisters are detailed in [11], [12], and [13]. The TMI-2 ISFSI DSC and HSM assemblies are shown in Figure 2-1 and Figure 2-2.

Page 6 of 39 orano Orano Federal Services

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Page 6 of 39 To evaluate the importance of Licon with respect to criticality, the design-basis TMI-2 Fuel Canister criticality model in Section 6.4 of [6] (specifically, case LDC-05) is modified and further evaluated following the degradation of Licon due to aging, up to and including complete loss of Licon. Degradation includes non-structural loss of Licon material, structural loss of Licon material, and absorption of water in Licon.

Modifications to the criticality model are minimized to ensure outputs are comparable to those originally generated. Cases are not run using the non-credible original assumptions in [6] (10 L of water mixed with the fuel and Bora! replaced with water). Instead, cases are run using limits outlined in the FSAR and applicable regulations that are also consistent with the original criticality evaluation in [5] (8 L of water mixed with the fuel per Section 3.3.4.4.1 of [3] and 75% credit for Baral per Section 7.4 of [ 4]).

Figure 2-1: NUHOMS-12T Dry Shielded Canister Figure 2-2: NUHOMS-12T Horizontal Storage Module

Page 7 of 39 Orano Federal Services orano

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support 3.0 ASSUMPTIONS 3.1 Unverified Assumptions There are no unverified assumptions.

3.2 Justified Assumptions Page 7 of 39 The assumptions listed in the FSAR Section 3.3.4.4.A [3] are restated below with applicability addressed as necessary:

1. "Batch 3 fresh fuel only (2.98 wt.% U-235)."
2. "Enrichment: batch 3 average+ 2cr."

The batch 3 average+ 2cr is equal to 2.98 wt.% U-235.

3. "No cladding or core structural material."
4. "No soluble poison or control materials from the core."
5. "Fuel lump is a whole fuel pellet."

Fuel pellets are modeled with a 0.939 cm diameter, consistent with [6], rather than the 0.9525 cm (0.375-in.) diameter discussed in FSAR Section 3.3.4.2.B.

6. "Filter canisters are enveloped by knockout canisters."

Though unstated, it was also assumed that the TMI-2 Fuel Canister is enveloped by the TMI-2 Knockout Canister. Only the TMI-2 Fuel Canister is analyzed in this calculation.

7. "Fuel is U02 and no credit is taken for degradation to less dense oxides."
8. "Canister fuel regions are filled with 1908 lb ofU02, which is the maximum reported canister payload."

Since only the TMI-2 Fuel Canister is analyzed in this calculation, the maximum TMI-2 Fuel Canister payload used in all fuel regions is 1740 lb U02. This is consistent with TMI-2 Fuel Canister modeling performed in [6].

9. "Fuel is smeared to fill all volume available in the fuel regions."
10. "Water and fuel are modeled at the top of the canisters, rather than at the bottom or sides (the nominal canister configuration), since this produces more conservative results."

Water and fuel are modeled at the bottom of the TMI-2 Fuel Canister, consistent with the TMI-2 Fuel Canister analysis in [6]. This is more conservative than modeling the fuel region on the side and very similar to modeling the fuel region at top (only steel shell thickness varies between the top and bottom).

Additionally, the second criticality evaluation assumed all poison structures are replaced with water. This is not consistent with the design basis identified in the original criticality evaluation (see FSAR Section 3.3.4.2.A),

certain runs in the second criticality evaluation (see FSAR Section 3.3.4.4.B), and applicable regulations where poison structures are modeled with 75% boron credit. All poison structures are modeled in this calculation with 75% boron credit.

Further assumptions, beyond those presented in the FSAR and pertaining specifically to this calculation, are as follows:

Page 8 of 39

_}

Orano Federal Services orano

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Page 8 of 39

1.

The TMI-2 Fuel Canister shell could deform following the loss of Licon material. This conservatively bounds the possible structural effects of Licon degradation.

2. The fuel will remain in the TMI-2 Fuel Canister cavity following any Licon degradation. While conservative shell deformation is modeled, the formation of shell holes or openings is not considered credible.
3. No more than 8 L of water will be present in the fuel region of the TMI-2 Fuel Canister.
4. The optimal fuel pitch found in [6] for a TMI-2 Fuel Canister containing 10 L of water will not change for a TMI-2 Fuel Canister containing 8 L of water.

4.0 DESIGN INPUTS 4.1 Fuel Specification No changes are made to the fuel characteristics specified in [6].

4.1.1 Non-Fuel Hardware No non-fuel hardware is modeled. Fuel is modeled as either pure U02 or U02 mixed with water. This is consistent with TMI-2 ISFSI FSAR Sections 3.3.4.2 and 3.3.4.4, which assume "No cladding or core structural material" and "No soluble poison or control material from the core".

4.1.2 Fuel Condition Fuel is modeled as 1740 lb of U02 (maximum TMI-2 Fuel Canister core debris weight per Section 6.5 of [6])

enriched to 2.98 wt.% U-235 (assumed maximum enrichment per Section 3.3.4.4 of [3]). All fuel is unirradiated.

Fuel is modeled as 0.939 cm diameter rods in a 1.45 cm triangular pitch when mixed with water. The 0.939 cm diameter is based on an undamaged, unclad fuel pellet (Section 6.0 of [ 6]) while the 1.45 cm triangular pitch is the worst-case pitch based on parameter optimization (Section 6.4 of [6]). When not mixed with water, the fuel is modeled 0.939 cm diameter rods in a 0.939 cm triangular pitch.

Page 9 of 39 Orano Federal Services orano

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support 4.2 Model Specification 4.2.1 Configuration Page 9 of 39 The geometry used in [6] is maintained. Dimensions are based on those contained in the Listing-12 input file (case LDC-05) in Appendix B of [6]. The TMI-2 Fuel Canister is modeled enclosed in a 14-in. (35.56 cm) outer diameter, 0.19-in. (0.49 cm) thick stainless steel shell. The TMI-2 Fuel Canister internal fuel region is modeled with a 9.13-in. (23.18 cm) square cavity, surrounded by a shroud composed of 0.04-in. (0.1 cm) thick stainless steel, 0.13-in. (0.33 cm) thick Bora!, and 0.08-in. (0.2 cm) thick stainless steel. The Licon fills the annulus of the inner shell wall and the outer Bora! shroud steel. Compared to [12], the TMI-2 Fuel Canister model geometry has a larger cavity (9-in. square on drawing), thinner Bora! (0.135-in. thick on drawing), and a thinner outer wall (0.25-in. thick on drawing). No credit is taken for the DSC basket, resulting in a tight packing of the twelve TMI-2 Fuel Canisters. No water is modeled between TMI-2 Fuel Canisters to maximize reactivity, as proven by the results in Table 17 in [6]. The 0.625-in. (1.5875 cm) thick carbon steel DSC is modeled as "collapsed",

immediately surrounding the twelve TMI-2 Fuel Canisters resulting in a reduced outer diameter of 63.77-in.

(161.975 cm) when compared to [8]. Similarly, HSM concrete immediately surrounds the DSC. The HSM concrete is, at minimum, 24-in. (61 cm) thick. All cases analyzed use the "collapsed" geometry.

The TMI-2 Fuel Canister cavity has three regions: fuel-water mixture, unmoderated fuel, and void. The height of each region is based on fuel and water volumes. Region heights are adjusted from the values used in [6] due to the changed water content and confirmed using CSAS5 output fi le values. The total fuel height for 1740 lb U02 is 174.54 cm. The fue l-water mixture height is 24.08 cm for 8 L water (originally 30.04 cm for 10 L water offull-density water). The simplified TMI-2 Fuel Canister model axial dimensions used in [6] are maintained. The cavity is 71.1-in. (180.52 cm) tall, with a 0.375-in. (0.9525 cm) wall on the bottom and a 2-in. (5.08 cm) wall on the top. To assess the effects of non-structural degradation of Licon, the model is configured as shown in Figure 4-1 and Figure 4-2.

To perform a bounding assessment of the effects of structural degradation of Licon, a set of configurations are evaluated without credit for the structural properties of Licon. The TMI-2 Fuel Canisters' shells are collapsed until in contact with the Bora! shroud steel and the TMI-2 Fuel Canister packing configuration is evaluated to find the most reactive orientation. No changes are made to the DSC or HSM dimensions (e.g. the DSC is not further collapsed beyond the non-structural degradation model configuration). The model configuration with no credit taken for the structural properties of Licon resulting in the maximum compression of triangular pitch TMI-2 Fuel Canister packing configuration is shown in Figure 4-3. The model configuration for the maximum possible compression of TMI-2 Fuel Canister packing configuration, a 4 by 3 square array, is shown in Figure 4-4.

4.2.2 Material Properties No changes are made to the material compositions syecified in criticality run LDC-05 in [6]. Bora! is defined per Table A-1 in [6] and corresponds to 0.03 g B-10/cm (75% of 0.04 g B-10/cm2 given in [12]) in natural boron combined with aluminum. Materials defined using CSAS preprogrammed definitions (such as water, carbon steel, and stainless steel 304) change slightly due to changes in the underlying definitions between versions.

Densities and volume fractions of water and/or Licon are varied depending on the case. All materials are modeled at room temperature (293 K).

The efficacy of the Bora! neutron absorber will not degrade beyond the modeled 75% boron credit. Per page 4 of

[ 14], "the neutron flux produced by the spent nuclear fuel would deplete only a small percentage of neutron absorbing material during several thousand years of exposures." Similarly, Section 3.4.2 of [15] concludes that any possible degradation of Bora! used in dry storage system for spent nuclear fuel is either not credible or will not "reduce the neutron absorbing capability".

Page 10 of 39 orano Orano Federal Services

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Page 10 of 39 Figure 4-1: Criticality Model with Credit for Licon Structural Properties (Radial View)

Page 11 of 39 orano Orano Federal Services

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Page 11 of 39 Figure 4-2: Criticality Model with Credit for Licon Structural Properties (Axial View)

Page 12 of 39 J;

orano Orano Federal Services

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Page 12 of 39 Figure 4-3: Criticality Model with No Credit for Licon Structural Properties (Triangular Array)

Page 13 of 39 orano Orano Federal Services

Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Page 13 of 39 Figure 4-4: Criticality Model with No Credit for Licon Structural Properties (Square Array)

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Title:

TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support 5.0 CALCULATIONS 5.1 Criticality Analysis 5.1.1 Computer Codes Page 14 of 39 The maximum keff TMI-2 Fuel Canister case from Section 6.4 of [6] is case LDC-05 (collapsed DSC, 10 L water in fuel region, 0.05 water volume fraction in Licon) and is contained in the file LDC-05 _ CSASIX. inp. All models in [6] were analyzed in SCALE 4, using CSASIX (which is built around the KENO V.a module) and an ENDF/B-IV 27-group library [16]. All new cases are analyzed in SCALE 6.2.1 [17], using CSAS5 (which is also built around the KENO V.a module) and an ENDF/B-VII.O 238-group library. Per Section 10.1.2.1 of [17], the 238-group library is "available mainly for general-purpose criticality analyses".

To assess the effect of format and library changes between CSASIX and CSAS5, the case LDC-05 input is remade in file LDC-05_CSAS5.inp for CSAS5. The CSAS5 input results in a kerr of0.93028 +/-.00058 (ks of 0.93144, see Section 5.1.3), while the original CSASIX input resulted in a kerr of 0.9260 +/- 0.0014 (ks of 0.9288).

Other important parameters, such as fuel mass (1740 lb) and water volume mixed with fuel (10 L), are also confirmed. It is concluded that the conversion to CSAS5 is acceptable as it maintains the original material and geometry definitions and generates similar results (less than 1 % difference). All case input files are based on file LDC-05_CSAS5.inp.

All cases are run using 250 generations, with I 0,000 neutrons per generation and 50 generations skipped. All run errors are less than 0.0008.

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TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support 5.1.2 Multiplication Factor Page 15 of 39 Three parameter studies are performed to evaluate the effect of Licon degradation. First, the non-structural loss of Licon is evaluated by reducing the atom density of Licon. Second, the absorption of water in Licon is evaluated by increasing the density of water in Licon. Third, the structural loss of Licon is evaluated by collapsing TMI-2 Fuel Canister outer walls and shifting TMI-2 Fuel Canisters closer together. The third parameter study bounds the structural effects of the loss of Licon. All cases are run using 8 L of water mixed with the fuel and 75% credit taken for the Bora! shroud. Unless otherwise stated, all cases use a Licon water volume fraction of 0.00 as this is determined to be the most reactive condition from the results of Table 5-2 (whereas Table 18 of [6] found 0.05 is most reactive). The value ks, described in Section 5.1.3, is reported alongside keff and o for each case.

The results for the non-structural loss of Licon study are shown in Table 5-1 and Figure 5-1. Licon fractional density (the Licon density expressed as a fraction of nominal) is reduced from 1 (full density) to O (Licon removed), bounding the non-structural effects of loss of Licon. It can be seen that the decrease in density results in a slight decrease in keff, showing that the loss of Licon due to aging does not result in an increase in reactivity when structural effects of loss of Licon are not taken into account.

The results for the absorption of water in Licon study are shown in Table 5-2 and Figure 5-2. The water volume fraction in Licon is increased from O (no water absorbed) to 1 (full density water absorbed in entire Licon volume), bounding the effects of water absorption in Licon. It can be seen that increase in water volume fraction in Licon results in a decrease in keff, showing that water absorption in Licon due to aging does not result in an increase in reactivity. This is similar to the results in Table 18 of [ 6], which showed a small increase in keff at low water volume fractions before decreasing steadily. Note, the case with a water volume fraction of 0.05 can be directly compared to case LDC-05 in [6] to show the significant effect of reducing the water volume mixed with the fuel and taking credit for Bora!.

For the third parameter study, the results for the compression ofTMI-2 Fuel Canister packing following the loss of Licon structural properties are shown in Table 5-3 and Figure 5-3. The arbitrary compression factor, describing the compression ofTMI-2 Fuel Canister packing through fractional shrinking of x-axis and y-axis separation gaps, is increased from O (maximum packing of TMI-2 Fuel Canisters when structural integrity of Licon is credited, same configuration as other parameter studies) to 1 (maximum packing of TMI-2 Fuel Canisters with no credit for Licon structural properties in a semi-triangular array). Additionally, a similar case is analyzed where the twelve TMI-2 Fuel Canisters are arranged in a maximum packing 4 by 3 square array. It can be seen that increasing the compression of TMI-2 Fuel Canister packing results in a significant increase in keff* The 4 by 3 square array increases keff further, to a maximum ks value for all cases of 0.85926.

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TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Table 5-1: Non-Structural Loss of Licon Results Licon Fractional kett ks Density C1 1.0 0.78846 0.00054 0.78954 0.9 0.78520 0.00051 0.78622 0.8 0.78593 0.00048 0.78689 0.7 0.78446 0.00054 0.78554 0.6 0.78573 0.00067 0.78707 0.5 0.78282 0.00061 0.78404 0.4 0.78250 0.00057 0.78364 0.3 0.78157 0.00056 0.78269 0.2 0.78053 0.00051 0.78155 0.1 0.77977 0.00059 0.78095 0.0 0.77832 0.00055 0.77942 0.95 0.9 0.85 b

N

+

It: 0.8 a,

~

A II

~

A A

~

0.75 0.7 0.65 1.0 0.8 0.6 0.4 0.2 Licon Fractional Density Figure 5-1: Non-Structural Loss of Licon Results Page 16 of 39 A

0.0

Page 17 of 39 orano Orano Federal Services

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TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Table 5-2: Water Absorption in Licon Results Water Volume kett Fraction in Licon a

ks 0

0.78846 0.00054 0.78954 0.05 0.77857 0.00061 0.77979 0.1 0.76814 0.00067 0.76948 0.15 0.75867 0.00053 0.75973 0.2 0.75045 0.00069 0.75183 0.25 0.74141 0.00068 0.74277 0.3 0.73299 0.00057 0.73413 0.4 0.71998 0.00067 0.72132 0.5 0.70885 0.00050 0.70985 0.6 0.69949 0.00064 0.70077 0.7 0.69302 0.00063 0.69428 0.8 0.68959 0.00074 0.69107 0.9 0.68171 0.00050 0.68271 1.0 0.67793 0.00062 0.67917 Page 17 of 39 0.85 +---------------------------

t:>

N

+

.:t:.f.0.80 +---------------------------

11 0.65 +------,-------..--------,,------....------,

0.0 0.2 0.4 0.6 0.8 1.0 Water Volume Fraction in Licon Figure 5-2: Water Absorption in Licon Results

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TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

02029.00.0000.02 -

License Renewal Support Page 18 of 39 Table 5-3: Compression of Packing due to Structural Loss of Licon Results Compression kett a

ks Factor 0.0 0.77581 0.00059 0.77699 0.1 0.78279 0.00050 0.78379 0.2 0.78860 0.00060 0.78980 0.3 0.79472 0.00058 0.79588 0.4 0.80219 0.00065 0.80349 0.5 0.80886 0.00059 0.81004 0.6 0.81691 0.00059 0.81809 0.7 0.82495 0.00050 0.82595 0.8 0.83392 0.00043 0.83478 0.9 0.84266 0.00062 0.84390 1.0 0.85026 0.00064 0.85154 4x3 Square 0.85770 0.00078 0.85926 Array 0.95 0.90 0.85 t:>

N

+

J0.80 II

~,....

.ll::

0.75 0.70 0.65 0.0 0.2 0.4 0.6 0.8 1.0 TMl-2 Fuel Canister Compression Factor Figure 5-3: Compression of Packing due to Structural Loss of Licon Results

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License Renewal Support 5.1.3 Benchmark Comparisons Page 19 of 39 The Monte Carlo computer program CSAS5 is utilized for this benchmark analysis [ 17]. CSAS5, which is built upon the KENO V.a module of the SCALE program, has been used extensively in criticality evaluations and is considered a standard in the industry. ENDF/B-VII 238-group cross section data is utilized for all benchmarks, consistent with the criticality calculations performed in this calculation.

The ORNL USLSTATS code [18] is used to establish an Upper Subcritical Limit (USL) for the analysis.

USLSTATS provides a simple means of evaluating and combining the statistical error of the calculation, code biases, and benchmark uncertainties. The USLST A TS calculation uses the combined uncertainties and data to provide a linear trend and overall uncertainty. Computed multiplication factors, keff, for the package are deemed to be adequately subcritical if the computed value of ks is less than or equal to the USL as follows:

k 5 = keff + 2cr ~ USL The USL includes the combined effects of code bias, uncertainty in the benchmark experiments, uncertainty in the computational evaluation of the benchmark experiments, and an administrative margin. This methodology has accepted precedence in establishing criticality safety limits.

5.1.3.1 Applicability of Benchmark Experiments The critical experiment benchmarks are selected from the International Handbook of Evaluated Criticality Safety Benchmark Experiments [19] based upon their similarity to the TMI-2 Fuel Canister contents and storage configuration. The important selection parameters are low enriched uranium (wt.% U-235 s; 10) compounds (U02) with a thermal spectrum. Fifty (50) benchmarks are used that meet these criteria. The titles for all utilized experiments are listed in Table 5-4.

For revision 1 of this calculation, the set of selected benchmarks is further reduced by removing all experiments containing reflector or absorber materials not relevant to the TMI-2 Fuel Canister criticality cases. Such materials include lead, Boroflex, copper, and cadmium. The "reduced" set contains thirty-eight (38) benchmarks.

Additionally, all benchmark models are revised to incorporate usage of the CELLMI X option. Use of the CELLMI X option results in an increase in all benchmark keff values (0.8% max, 0.2% average)

Table 5-4: Benchmark Experiments Used Series Title LEU-COMP-THERM-001 Water-Moderated U(2.35)02 Fuel Rods in 2.032-cm Square-Pitched Arrays LEU-COMP-THERM-002 Water-Moderated U(4.31)02 Fuel Rods in 2.54-cm Square-Pitched Arrays LEU-COMP-THERM-010 Water-Moderated U(4.31)02 Fuel Rods Reflected by Two Lead, Uranium, or Steel Walls Water-Moderated Rectangular Clusters of U(2.35)02 LEU-COMP-THERM-042 Fuel Rods (1.684-Cm Pitch) Separated by Steel, Baral, Boroflex, Cadmium, or Copper Plates with Steel Reflecting Walls

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License Renewal Support 5.1.3.2 Bias Determination Page 20 of 39 The USL is calculated by application of the USLSTATS computer program [18]. USLSTATS receives as input the k.,ffas calculated by CSAS5, the total uncertainty (combined benchmark and CSAS5 uncertainties), and a trending parameter. Four trending parameters have been selected: (1) Energy of Average Lethargy of Fission (EALF), (2) U-235 number density in the fuel, (3) atom ratio of hydrogen to U-235, and (4) enrichment.

The uncertainty value, 0 101a1, assigned to each case is a combination of the benchmark uncertainty for each experiment, obench, and the Monte Carlo uncertainty associated with the particular computational evaluation of the case, OcsAss, or:

2

+ 2 Ototal =

Obench 0 csAS5 These values are input into the USLSTA TS program in addition to the following parameters, the values for which are selected in accordance with the USLST A TS User's Manual [ 18]:

P, proportion of the population falling above lower tolerance level= 0.995 (note that this parameter is a required input but is not utilized in the calculation ofUSL Method 1) 1-y, confidence on fit= 0.95 a, confidence of proportion P = 0.95 (note that this parameter is a required input but is not utilized in the calculation of USL Method 1) ilkm, administrative margin used to ensure subcriticality = 0.05 These values are followed by triplets of trending parameter value, computer keff, and uncertainty for each case. A confidence band analysis is performed on the data for each trending parameter using USL Method 1. The USL generated for each of the trending parameters utilized is provided in Table 5-5. All benchmark data used as input to USLST A TS is reported in Table 5-6. Benchmarks excluded from the reduced benchmark set are denoted by case numbers with grey backgrounds.

Energy of Average Lethargy of Fission EALF is used as the first trending parameter for the benchmark cases. Over the range of applicability, the minimum USL is 0.9435 for the full benchmark set and 0.9438 for the reduced benchmark set. The USL is constant for increasing EALF. While TMI-2 Fuel Canister cases' EALF values are slightly outside the range of applicability, "the range of applicability may be extended beyond the range of conditions represented by the benchmark experiments by extrapolating the trends established for the bias" as long the extrapolation is not "large" per Section 4.1 of [20]. The EALF value is 1.19487 eV for the most reactive TMI-2 Fuel Canister case.

U-235 Number Density in Fuel The U-235 number density in the fuel is used as the second trending parameter for the benchmark cases. Over the range of applicability, the minimum USL is 0.9441 for the full benchmark set and 0.9440 for the reduced benchmark set. The U-235 number density in the fuel is constant for all TMI-2 Fuel Canister cases and falls within the range of applicability. The USL is trending upwards for increasing U-235 number density in the fuel.

The U-235 number density in the fuel is 6.81347E-04 U-235 atoms/b-cm for the most reactive TMI-2 Fuel Canister case.

Atom Ratio of Hydrogen to U-235 The atom ratio of hydrogen to U-235 in the fuel unit cell is used as the third trending parameter for the benchmark cases. Over the range of applicability, the minimum USL is 0.9440 for the full benchmark set and 0.9442 for the reduced benchmark set. The atom ratio of hydrogen to U-235 is constant for all TMI-2 Fuel Canister cases and

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License Renewal Support Page 21 of 39 falls within the range of applicability. The USL is trending downwards for increasing atom ratio of hydrogen to U-235. The atom ratio of hydrogen to U-235 is 2.58E+02 atoms hydrogen per atom U-235 for the most reactive TMI-2 Fuel Canister case.

Enrichment The enrichment of the fuel is used as the fourth trending parameter for the benchmark cases. Over the range of applicability, the minimum USL is 0.9441 for the full benchmark set and 0.9440 for the reduced benchmark set.

The enrichment is constant for all TMI-2 Fuel Canister cases and falls within the range of applicability. The USL is trending upwards for increasing enrichment. The enrichment is 2.98 wt.% U-235 for the most reactive TMI-2 Fuel Canister case.

Recommended USL For all trending parameters, the minimum calculated USL is 0.9435 using EALF as a trending parameter with the full benchmark set. Therefore, a USL of 0.9435 is justified. This USL is significantly higher than the most reactive TMI-2 Fuel Canister case ks of 0.85926.

Table 5-5: USL Results Trending Set Minimum USL over Range of Applicability Parameter Range of Applicability EALF (eV)

Full 0.9435 8.95E-2 < X < 5.64E-1 Reduced 0.9438 NDEN (U-235 atoms/b-cm)

Full 0.9441 4.88E-4 < X < 1.01 E-3 Reduced 0.9440 H/U-235 (atom ratio)

Full 0.9440 1.05E+2 < X < 3.99E+2 Reduced 0.9442 Enrichment (wt.%)

Full 0.9441 2.35 < X < 4.31 Reduced 0.9440

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License Renewal Support Page 22 of 39 Table 5-6: Benchmark Experiment Data Experiment Case Kett CJ CJ CJ EALF NDEN (U-235 H/U-235 Enrichment (CSAS5)

(CSAS5)

(Benchmark)

(Total)

(eV) atoms/b-cm)

(atom ratio)

(wt. %)

1 0.99975 0.00056 0.00310 0.00315 9.27826E-02 4.87850E-04 3.98955E+02 2.35 2

0.99912 0.00050 0.00310 0.00314 9.21462E-02 4.87850E-04 3.98955E+02 2.35 3

0.99893 0.00058 0.00310 0.00315 9.11762E-02 4.87850E-04 3.98955E+02 2.35 LEU-COMP-4 0.99979 0.00043 0.00310 0.00313 9.17512E-02 4.87850E-04 3.98955E+02 2.35 THERM-001 5

0.99823 0.00048 0.00310 0.00314 9.03091 E-02 4.87850E-04 3.98955E+02 2.35 6

0.99973 0.00057 0.00310 0.00315 9.14864E-02 4.87850E-04 3.98955E+02 2.35 7

0.99944 0.00050 0.00310 0.00314 8.95407E-02 4.87850E-04 3.98955E+02 2.35 8

0.99779 0.00066 0.00310 0.00317 9.07058E-02 4.87850E-04 3.98955E+02 2.35 1

1.00253 0.00071 0.00200 0.00212 1.04163E-01 1.01020E-03 2.56344E+02 4.31 2

1.00179 0.00071 0.00200 0.00212 1.04057E-01 1.01020E-03 2.56344E+02 4.31 LEU-COMP-3 1.00096 0.00060 0.00200 0.00209 1.03877E-01 1.01020E-03 2.56344E+02 4.31 THERM-002 4

1.00101 0.00055 0.00200 0.00207 1.03075E-01 1.01020E-03 2.56344E+02 4.31 5

1.00153 0.00071 0.00200 0.00212 1.01212E-01 1.01020E-03 2.56344E+02 4.31 1

1.00724 0.00058 0.00210 0.00218 1.08970E-01 1.01020E-03 2.56344E+02 4.31 2

1.00819 0.00053 0.00210 0.00217 1.06269E-01 1.01020E-03 2.56344E+02 4.31 3

1.00615 0.00068 0.00210 0.00221 1.04385E-01 1.01020E-03 2.56344E+02 4.31 4

1.00045 0.00067 0.00210 0.00220 1.01208E-01 1.01020E-03 2.56344E+02 4.31 5

1.00284 0.00060 0.00210 0.00218 3.28884E-01 1.01020E-03 2.56344E+02 4.31 LEU-COMP-6 1.00332 0.00056 0.00210 0.00217 2.41996E-01 1.01020E-03 2.56344E+02 4.31 THERM-010 7

1.00338 0.00054 0.00210 0.00217 1.93932E-01 1.01020E-03 2.56344E+02 4.31 8

1.00046 0.00063 0.00210 0.00219 1.70844E-01 1.01020E-03 2.56344E+02 4.31 9

1.00409 0.00055 0.00210 0.00217 1.13091 E-01 1.01020E-03 2.56344E+02 4.31 10 1.00423 0.00052 0.00210 0.00216 1.09191 E-01 1.01020E-03

2. 56344E +02 4.31 11 1.00584 0.00058 0.00210 0.00218 1.06346E-01 1.01020E-03 2.56344E+02 4.31 12 1.00456 0.00056 0.00210 0.00217 1.03257E-01 1.01020E-03 2.56344E+02 4.31

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License Renewal Support Page 23 of 39 Table 5-6: Benchmark Experiment Data (continued)

Experiment Case Kett cr cr cr EALF NDEN (U-235 H/U-235 Enrichment (CSAS5)

(CSAS5)

(Benchmark)

(Total)

(eV) atoms/b-cm)

(atom ratio)

(wt. %)

13 1.00339 0.00062 0.00210 0.00219 1.01190E-01 1.01020E-03 2.56344E+02 4.31 14 1.00593 0.00056 0.00280 0.00286 2.89008E-01 1.01020E-03 1.05453E+02 4.31 15 1.00501 0.00062 0.00280 0.00287

2. 77260E-01 1.01020E-03 1.05453E+02 4.31 16 1.00498 0.00061 0.00280 0.00287 2.67566E-01 1.01020E-03 1.05453E+02 4.31 17 1.00463 0.00065 0.00280 0.00287 2.61075E-01 1.01020E-03 1.05453E+02 4.31 18 1.00381 0.00076 0.00280 0.00290 2.57358E-01 1.01020E-03 1.05453E+02 4.31 19 1.00409 0.00073 0.00280 0.00289 2.50737E-01 1.01020E-03 1.05453E+02 4.31 20 1.00470 0.00049 0.00280 0.00284
2. 75655E-01 1.01020E-03 1.05453E+02 4.31 LEU-COMP-21 1.00467 0.00063 0.00280 0.00287 2.67803E-01 1.01020E-03 1.05453E+02 4.31 THERM-010 22 1.00420 0.00061 0.00280 0.00287 2.56813E-01 1.01020E-03 1.05453E+02 4.31 23 1.00343 0.00068 0.00280 0.00288 2.50455E-01 1.01020E-03 1.05453E+02 4.31 24 1.00221 0.00061 0.00280 0.00287 5.63523E-01 1.01020E-03 1.05453E+02 4.31 25 1.00349 0.00061 0.00280 0.00287 5.21862E-01 1.01020E-03 1.05453E+02 4.31 26 1.00425 0.00058 0.00280 0.00286 4.83393E-01 1.01020E-03 1.05453E+02 4.31 27 1.00345 0.00073 0.00280 0.00289 4.53415E-01 1.01020E-03 1.05453E+02 4.31 28 1.00421 0.00053 0.00280 0.00285 4.23277E-01 1.01020E-03 1.05453E+02 4.31 29 1.00378 0.00055 0.00280 0.00285 3.98123E-01 1.01020E-03 1. 05453E +02 4.31 30 1.00137 0.00064 0.00280 0.00287 3.46986E-01 1.01020E-03 1.05453E+02 4.31 1

0.99850 0.00050 0.00160 0.00168 1.62388E-01 4.87850E-04 2.18707E+02 2.35 2

0.99886 0.00054 0.00160 0.00169 1.68400E-01 4.87850E-04 2.18707E+02 2.35 3

1.00131 0.00076 0.00160 0.00177 1.75125E-01 4.87850E-04 2.18707E+02 2.35 LEU-COMP-4 1.00174 0.00054 0.00170 0.00178 1.73453E-01 4.87850E-04 2.18707E+02 2.35 THERM-042 5

0.99933 0.00048 0.00330 0.00333 1.70349E-01 4.87850E-04 2.18707E+02 2.35 6

1.00025 0.00048 0.00160 0.00167 1.62115E-01 4.87850E-04 2.18707E+02 2.35 7

0.99817 0.00060 0.00180 0.00190 1.67005E-01 4.87850E-04 2.18707E+02 2.35

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License Renewal Support 6.0 RESULTS AND CONCLUSIONS Page 24 of 39 As demonstrated in Section 5.1.1, the use of CSAS5 rather than CSASIX produces similar criticality results. As demonstrated in Section 5.1.2, reducing the water volume mixed with the fuel (in accordance with the TMI-2 ISFSI FSAR) and taking credit for Bora! (per applicable regulations) results in a significant decrease in ks from 0.93144, calculated from the CSAS5 results in Section 5.1.1, to 0.77979, calculated from the 0.05 water volume fraction in Table 5-2. Thus, the margin to criticality for the TMI-2 Fuel Canister under credible conditions is significantly higher than as described in [6]. Furthermore, the three parameter studies in Section 5.1.2 demonstrate that the TMI-2 Fuel Canisters maintain subcriticality following the degradation of Licon due to aging. Non-structural loss of Licon and water absorption in Licon both result in a decrease in reactivity, while structural loss of Licon does not result in a large enough increase in reactivity to exceed the subcriticality limits.

It is concluded that the TMI-2 Fuel Canister criticality analysis in [6], which is referred to as the "second" criticality evaluation in the TMI-2 ISFSI FSAR, is sufficiently conservative that it bounds the possible effects of Licon degradation due to aging.

In relation to RAJ 3-7 specifically, the effect of material loss of Licon due to aging will not adversely affect the results of the second criticality analysis in Section 3.3.4.3 of the TMI-2 ISFSI FSAR such that the subcritical limit is exceeded. Evaluation of the complete loss of Licon, including collapse of the TMI-2 Fuel Canister outer wall and compressed packing of the TMI-2 Fuel Canisters within the DSC, bounds any credible material losses for Licon as well as the dimensional effects of these material losses. The second criticality analysis in the TMI-2 ISFSI FSAR bounds the criticality results of this evaluation and thus continues to show the TMI-2 ISFSI storage system will be subcritical when these material losses are taken into account.

In relation to RAJ 3-8 specifically, the changes to the Licon material properties, as a result of aging, are not significant to maintaining the subcriticality function of the TMI-2 Fuel Canisters. Analysis of both the water content of Licon as well as material loss of Licon shows that the TMI-2 Fuel Canisters stored at the TMI-2 ISFSI will remain subcritical as a result of any possible changes due to Licon aging. Analysis of material loss of Licon includes analysis of complete loss of Licon and the resulting possible structural effects. No other degradation of Licon is considered credible. It is concluded that the Licon is not relied on for maintaining nuclear criticality safety of the TMI-2 ISFSI.

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License Renewal Support 7.0 COMPUTER SOFTWARE USAGE Revision 0 Computer Name:

Hardware Profile of Computer:

Operating System:

Revision 1 Computer Name:

Hardware Profile of Computer:

Operating System:

Software Used:

EGONSIOROWSKil Intel Xeon CPU ES-1650 @ 3.50 GHz, 16.0 GB RAM 64-bit Windows 7 Enterprise, Service Pack 1 EGONSI0ROWSKI2 Intel Xeon W-2155 CPU @3.30 GHz, 32.0 GB 64-bit Windows 7 Enterprise, Service Pack 1 SCALE 6.2. l (SD-SCALE-6.2.1-SRA-3018486-000)

Excel 2010 (Exempt from EASI requirements) 7.1 In-Use Testing of SCALE 6.2.1 Revision 0 Page 25 of 39 Input filesp2438al_egl.inp and epru65b_egl.inp are taken from the SCALE 6.2.1 software dedication report [21) for in-use testing. Both files are run on 7/16/2018. The resulting output files are identical to those in [2 l] except for run-unique parameters (such as date and time of run), indicating that SCALE 6.2.1 performs as expected and is acceptable for use.

The input files in this calculation are not affected by SCALE 6.2.1 Error Notice 2018-01.

Revision 1 Input files CHP _egl.out and Pu6_egl.out are taken from the SCALE 6.2.1 software dedication report [21) for in-use testing. Both files are run on 2/12/2019. The resulting output files are identical to those in [21) except for run-unique parameters (such as date and time of run), indicating that SCALE 6.2.1 performs as expected and is acceptable for use.

7.2 File Listing Revision 0 Directory : Runs\\Benchmarking\\Cases\\LEU-COMP-THERM- 001 Mode LastWri teTi me Length Name

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License Renewal Support Page 26 of 39

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License Renewal Support Page 27 of 39

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License Renewal Support Revision 1 Directory : Runs\\Benchmarking\\Cases\\LEU-COMP-THERM- 001 LastWriteTime Length Name 2/5/2019 2 : 39 PM 3161 CASE 1 cm. inp 2/5/2019 3 : 28 PM 921176 CASE 1 cm. out 2/5/2019 2 : 4 0 PM 3505 CASE_2_cm. inp 2/5/2019 3 : 28 PM 923529 CASE 2 cm.out 2/5/2019 2 : 40 PM 3503 CASE_3_cm. inp 2/5/2019 3 : 28 PM 923078 CASE 3 cm. out 2/5/2019 2 : 40 PM 3639 CASE_4_cm. inp 2/5/2019 3 : 28 PM 925322 CASE 4 cm. out 2/5/2019 2 : 40 PM 3500 CASE_5_cm. inp 2/5/2019 3 : 28 PM 923439 CASE 5 cm. out 2/5/2019 2 : 40 PM 3629 CASE _6_cm.inp 2/5/2019 3 : 28 PM 925486 CASE 6 cm. out 2/5/2019 2 : 40 PM 350 1 CASE_7_cm.inp 2/5/2019 3 : 28 PM 923000 CASE 7 cm. out 2/5/2019 2 : 40 PM 350 1 CASE_8_cm. inp 2/5/2019 3 : 28 PM 923374 CASE 8 cm. out Directory : Runs\\Benchmarking\\Cases\\LEU-COMP-THERM- 002 LastWriteTime 2/5/2019 2:44 PM 2/5/2019 3 : 29 PM 2/5/2019 2 : 44 PM 2/5/2019 3 : 29 PM 2/5/2019 2 : 44 PM 2/5/2019 3 : 29 PM 2/5/2019 2 : 44 PM 2/5/2019 3 : 29 PM 2/5/2019 2 : 44 PM 2/5/2019 3 : 29 PM Length Name 2690 CASE_l_cm. inp 944965 CASE 1 cm. out 2683 CASE 2 cm. inp 945488 CASE 2 cm. out 2683 CASE_3_cm. inp 945414 CASE 3 cm.out 2655 CASE 4 cm. inp 944039 CASE 4 cm. out 2652 CASE_5_cm. inp 943965 CASE 5 cm. out Directory : Runs\\Benchmarking\\Cases\\LEU-COMP-THERM- 010 LastWriteTime Length Name 2/5/2019 2 : 48 PM 3171 case 10 _cm. inp 2/5/2019 3 : 39 l?M 957105 case 10 cm. out 2/5/2019 2 : 48 PM 3171 case 11 _cm. inp 2/ 5 /2019 3 : 39 PM 957108 case 11 cm. out 2/5/2019 2 : 48 PM 317 1 case 12 _cm. i np 2/5/2019 3 : 39 PM 956880 case 12 cm. out 2/5/2019 2 : 48 PM 3171 case 13_cm. inp 2/5/2019 3 : 39 PM 956887 case 13 cm. out 2/5/2019 2 : 54 PM 3174 case 14 _cm. inp 2/5/2019 3 : 46 PM 956913 case 14 cm. out 2/5/2019 3 : 09 PM 3174 case_15_cm. inp 2/5/2019 3 : 46 PM 957148 case 15 cm. out 2/5/2019 3 : 09 PM 3174 case_16_cm. inp 2/5/2019 3 : 46 PM 957128 case 16 cm. out 2/5/2019 3 : 09 PM 3174 case_17_cm. inp Page 30 of 39

Page 31 of 39 Orano Federal Services orano

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License Renewal Support 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/20 19 2/5/20 19 2/5/20 19 2/5/20 19 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/20 19 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/2019 3 : 4 6 PM 3 : 09 PM 3 : 46 PM 3 : 09 PM 3 : 4 6 PM 2 : 4 7 PM 3 : 40 PM 3 : 09 PM 3 : 46 PM 3 : 09 PM 3 : 46 PM 3 : 09 PM 3 : 46 PM 3 : 09 PM 3 : 4 6 PM 3 : 09 PM 3 : 4 6 PM 3 : 09 PM 3 : 4 6 PM 3 : 09 PM 3 : 4 6 PM 3 : 09 PM 3 : 4 6 PM 3 : 09 PM 3 : 4 6 PM 3 : 09 PM 3 : 4 6 PM 2 : 48 PM 3 : 40 PM 3 : 09 PM 3 : 4 6 PM 2 : 48 PM 3 : 40 PM 2 : 48 PM 3 : 39 PM 2 : 48 PM 3 : 39 PM 2 : 48 PM 3 : 39 PM 2 : 48 PM 3 : 39 PM 2 : 48 PM 3 : 39 PM 2 : 48 PM 3 : 39 PM 956701 case 17 cm.out 3175 case_ 18_ cm.inp 956806 case 18 cm.out 3175 case_19_cm.inp 956894 case 19 cm.out 2879 case_l_cm. inp 945729 case 1 cm. out 2877 case_20_cm. inp 945550 case 20 cm. out 2921 case_21_cm. inp 946156 case 21 cm. out 2923 case_ 22_cm. inp 945977 case 22 cm. out 2923 case_23_cm. inp 946487 case 23 cm. out 2966 case_24_cm. inp 945554 case 24 cm. out 2966 case_25_cm. inp 945572 case 25 cm. out 2966 case_26_cm. inp 945304 case 26 cm. out 2966 case_27_cm.inp 945238 case 27 cm. out 2966 case 28_ cm. inp 945452 case 28 cm. out 2966 case_29_cm. inp 945265 case 29 cm. out 2920 case_2_cm. inp 946483 case 2 cm. out 2966 case_30_cm. inp 945120 case 30 cm. out 2921 case_3_cm. inp 946047 case 3 cm. out 2921 case_ 4_ cm. inp 946585 case 4 cm. out 2963 case_5_cm. inp 945407 case 5 cm. out 2963 case_6_cm. i np 945580 case 6 cm. out 2963 case_7_cm. inp 945601 case 7 cm. out 2963 case_ 8_ cm. inp 945708 case 8 cm.out 3172 case_ 9_ cm. inp 957120 case 9 cm. out Directory : Runs\\Benchmarking\\Cases\\LEU-COMP-THERM- 042 LastWr iteTime 2/5/2019 3 : 17 PM 2/5/2019 3 : 50 PM 2/5/2019 3 : 23 PM 2/5/2019 3 : 50 PM 2/5/2019 3 : 23 PM Length Name 4265 CASE 1 cm. inp 1027688 CASE 1 cm. out 4227 case_2_cm. inp 1028293 case 2 cm. out 4245 CASE_3_cm. inp Page 31 of 39

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License Renewal Support 2/5/2019 2/5/2019 2/5/20 19 2/5/2019 2/5/2019 2/5/2019 2/5/2019 2/5/20 19 2/5/2019 3 : 50 PM 3 : 23 PM 3 : 50 PM 3 : 23 PM 3 : 50 PM 3 : 23 PM 3 : 50 PM 3 : 23 PM 3 : 50 PM 1022326 CASE 3 cm.out 4451 CASE_ 4_cm.inp 1070323 CASE 4 cm.out 4495 CASE_5_cm.inp 1069093 CASE 5 cm. out 4220 CASE_6_ cm. inp 1027455 CASE 6 cm. out 4639 CASE 7 cm. inp 1036460 CASE 7 cm. out Directory : Runs\\Benchmarking\\USLSTATS LastWriteTi me 2/11/2019 2/11/2019 2/12/2019 2/12/2019 2/11/2019 2/11/2019 2/12/2019 2/12/2019 2/11/2019 2/ 11 /2019 2/12/2019 2/12/2019 2/11/2019 2/11/2019 2/12/2019 2/12/2019 1 : 36 PM 1 : 40 PM 8 : 30 AM 8 : 39 AM 1 : 37 PM 1 : 40 PM 8 : 29 AM 8 : 39 AM 1 : 37 PM 1 : 40 PM 8 : 30 AM 8 : 39 AM 1 : 36 PM 1 : 40 PM 8 : 30 AM 8 : 39 AM Length Name 1533 EALF Full Set. in 8880 EALF Ful l Set. out 1188 EALF ReducedSet. i n 7929 EALF ReducedSet. out 1189 Enri chment FullSet.in 8783 Enrichment FullSet. out 930 Enrichment ReducedSet. in 7917 Enrichment ReducedSet. out 1536 HU-235 Ful lSet. in 9122 HU-235 FullSet. out 1193 HU-235 ReducedSet.in 8172 HU-235 ReducedSet. out 1533 NDEN FullSet. in 9115 NDEN FullSet. out 1188 NDEN ReducedSet.in 8164 NDEN ReducedSet. out Directory : Runs\\In-Use Testing LastWriteTime 4/24/2012 7 : 17 AM 2/12/2019 10 : 51 AM 2/8/2012 10 : 48 AM 2/12/2019 10 : 51 AM Directory : Spreadsheets LastWriteTime 2/12/2019 10 : 26 AM Length Name 1764 CHP_egl. in 9518 CHP_ egl. out 1992 Pu6_egl.in 10986 Pu6 egl. out Length Name 36137 Benchmarking revl. xlsx Page 32 of 39

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License Renewal Support

8.0 REFERENCES

Page 33 of 39

1. NRC Correspondence, Request for Additional Information for the Technical Review of the Application for Renewal of the Three Mile Island Unit 2 Independent Spent Fuel Storage Installation License No. SNM-2508, January 29, 2018, NRC Accession Number ML18030Al 72
2. License Renewal Application, TMI-2 Independent Spent Fuel Storage Installation Application for 10 CFR 72 Specific License Renewal, Special Nuclear Materials License Number SNM-2508 (Docket No.

72-20), Revision 1, September 26, 2018, NRC Accession Number ML18296A527

3. Safety Analysis Report, TMI-2 Safety Analysis Report, Materials License No. SNM-2508
4. NUREG-1536, Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility, United States Nuclear Regulatory Commission, July 2010
5. Transnuclear West Calculation, Cale. No. 0219-02.0300, Criticality Evaluation for the JOCFR72 INELITMI-2 Fuel ISS (NUHOMs9-J2T), Revision 1, August 1999
6. Idaho Cleanup Project Internal Report, INEEL/INT-99-00126, Criticality Safety Evaluation ofTMI-2 Canister Transportation and Storage, Revision 4, May 2005
7. Transnuclear West Drawing, Dry Shielded Canister Basket Assembly Safety Analysis Report, Drawing Number 219-02-2000, Revision 2
8. Transnuclear West Drawing, Dry Shielded Canister Shell Assembly Safety Analysis Report, Drawing Number 219-02-2001, Revision 2
9. Transnuclear West Drawing, Dry Shielded Canister Basket-Shell Assembly Safety Analysis Report, Drawing Number 219-02-2002, Revision 2
10. Transnuclear West Drawing, Dry Shielded Canister Main Assembly Safety Analysis Report, Drawing Number 219-02-2003, Revision 2
11. Babcock & Wilcox Drawing, Filter Canister SAR Information, Drawing Number 1161299, Revision 1
12. Babcock & Wilcox Drawing, Fuel Canister SAR Information, Drawing Number 1161300, Revision 3
13. Babcock & Wilcox Drawing, Knockout Canister SAR Information, Drawing Number 1161301, Revision 1
14. NRC Correspondence, Federal Register Notices Publishing Environmental Assessments and Findings of No Significant Impacts for Requests for Exemptions from Requirements of 10 CFR Parts 20 and 72, Docket No. 72-20, March 1999, NRC Accession Number 9903230211
15. NUREG-2214, Managing Aging Processes in Storage (MAPS) Report, United States Nuclear Regulatory Commission, October 2017, NRC Accession Number MLl 7289A237
16. NUREG/CR-0200, Volume 3, Section M4, SCALE Cross-Section Libraries, Oak Ridge National Laboratory, Revision 6, September 1998
17. ORNL/TM-2005/39, SCALE Code System, Oak Ridge National Laboratory, Version 6.2.1, August 2016, RSICC Package ID C00834MNYCP02
18. USLSTATS, USLSTATS: A Utility to Calculate Upper Subcritical Limits for Criticality Safety Applications, Build Date June 22, 2016. Note: USLSTATS is described in Appendix C, User's Manual for USLSTATS Vl.O, in NUREG/CR-6361, Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages, March 1997. No new user's manual has been developed for later updates to the program.

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License Renewal Support Page 34 of 39

19. International Handbook of Evaluated Criticality Safety Benchmark Experiments, Nuclear Energy Agency, NEA/NSC/DOC(95)03, September 2015
20. NUREG/CR-6361, Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages, Oak Ridge National Laboratory, March 1997
21. AREY A Federal Services Calculation, CALC-3018409, Software Dedication Report for SCALE 6. 2.1, Revision 0
22. NRC Correspondence, Request for Clarification of Response to Additional Information for the Technical Review of the Application for Renewal of the Three Mile Island Unit 2 Independent Spent Fuel Storage Installation License No. SNM-2508, February 5, 2019, ADAMS Accession No. ML19037A066

Page 35 of 39 Orano Federal Services orano

Title:

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02029.00.0000.02 -

License Renewal Support 9.0 SAMPLE INPUT FILE 9.1 Collapsed_ 4x3.inp The sample input file has been removed due to concerns about proprietary information.

Page 35 of 39

Page 36 of 39 Orano Federal Services orano

Title:

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License Renewal Support Page 36 of 39 APPENDIX A:

COMPARISON OF SELECT TMl-2 ISFSI CRITICALITY CASES To aid comparisons of the first criticality evaluation in [5], the second criticality evaluation in [6], and this calculation, Table A-1 summarizes the key criticality parameters for select cases in the two evaluations and this calculation. Common parameters across selected cases include:

Enrichment for all cases is 2.98 wt.% U-235.

Fuel pellet diameter for all cases is 0.93904 cm except for the analysis of the TMI-2 Filter Canister in [5],

which uses a fuel pellet diameter of 850 microns.

TMI-2 Canisters are modeled in a triangular pitch, close packed configuration within a collapsed DSC for all cases except:

o Case FUEL002 from [6], which uses a normal DSC configuration o

Cases from this calculation modeling compression ofTMI-2 Canisters following structural loss of Licon.

For cases from [5] and [6], ks is calculated differently than as described in Section 5.1.3:

k 5 = keff + 2cr + Bias + Additional Margin ~ USL Calculation of bias is discussed within each individual calculation and varies depending on the code version and cross-section library used. For cases from this calculation, bias is included in the USL.

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License Renewal Support Page 37 of 39 Table A-1: Comparison of Select TMl-2 ISFSI Criticality Cases First Criticality Evaluation Individual Individual Individual 12 Knockout Fuel Canister Knockout Canister Filter Canister Canisters in DSC Case Identifier Single Fuel Canister Single Knockout Single Filter Canister HSM with 12 Knockout Model Canister Model Canisters Fuel Loading per Can

>19081b

>19081b

>19081b

>19081b Fuel Region Geometry Homogenous Smear Homogenous Smear Homogenous Smear Homogenous Smear Water Content in 8.8E-5 glee 8.8E-5 glee 8.8E-5 glee 8.8E-5 glee Fuel Region Fuel Pellet 0.93904 cm 0.93904 cm 850 microns 0.93904 cm Triangular Pitch Poison Credit 75% Boral 75% Boron Carbide 75% Boron Carbide 75% Boron Carbide Kett 0.26047 0.26174 0.24641 0.54051 0

0.00053 0.00055 0.00051 0.00082 USL 0.95 0.95 0.95 0.95 Bias 0.00762 0.00762 0.00762 0.00762 Additional Margin 0.05 0.05 0.05 0.05 Ks 0.31915 0.32046 0.30505 0.59977

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License Renewal Support Page 38 of 39 Table A-1: Comparison of Select TMl-2 ISFSI Criticality Cases (Continued)

Second Criticality Evaluation 12 Knockout Canisters 12 Fuel Canisters 12 Fuel Canisters in DSC in DSC in DSC Case Identifier DSC420 LDC-05 FUEL002 Fuel Loading per Can 19081b 17401b 17401b Fuel Region Geometry Wet/Dry/Air (Inverted)

Wet/Dry/Air Wet/Dry/Air Water Content in 8L 10 L 30 L Fuel Region Fuel Pellet 1.35 cm (Wet),

1.45 cm (Wet),

1.45 cm (Wet),

Triangular Pitch 0.93904 cm (Dry) 0.93904 cm (Dry) 0.93904 cm (Dry)

Poison Credit Water Water 75% Baral Kett 0.9111 0.9260 0.9051 a

0.0012 0.0014 0.0014 USL 0.95 0.95 0.95 Bias 0.01 0.01 0.01 Additional Margin Ks 0.9235 0.9388 0.9179

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TMl-2 Canister Licon Criticality Analysis for TMl-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-001 Project:

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License Renewal Support Page 39 of 39 Table A-1: Comparison of Select TMl-2 ISFSI Criticality Cases (Continued)

CALC-3021788 12 Fuel Canisters 12 Fuel Canisters 12 Fuel Canisters 12 Fuel Canisters 12 Fuel Canisters in DSC in DSC in DSC in DSC in DSC Case Identifier Normal Condition Licon replaced Water Volume Compression 4 x 3 Array with Void Fraction in Licon = 1 Factor= 1 Fuel Loading per Can 17401b 17401b 17401b 17401b 17401b Fuel Region Geometry Wet/Dry/Air Wet/Dry/Air Wet/Dry/Air Wet/Dry/Air Wet/Dry/Air Water Content in 8L 8L 8L 8L 8L Fuel Region Fuel Pellet 1.45 cm (Wet),

1.45 cm (Wet),

1.45 cm (Wet),

1.45 cm (Wet),

1.45 cm (Wet),

Triangular Pitch 0.93904 cm (Dry) 0.93904 cm (Dry) 0.93904 cm (Dry) 0.93904 cm (Dry) 0.93904 cm (Dry)

Poison Credit 75% Boral 75% Boral 75% Boral 75% Boral 75% Boral Kett 0.78846 0.77832 0.67793 0.85026 0.85770 a

0.00054 0.00055 0.00062 0.00064 0.00078 USL 0.9435 0.9435 0.9435 0.9435 0.9435 Bias Additional Margin Ks 0.78954 0.77942 0.67917 0.85154 0.85926

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