ML18331A321

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Calculation CALC-3021788, TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal
ML18331A321
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Issue date: 08/31/2018
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NA NA NA Orano Federal Services August 31, 2018 Records Management CALC-3021788-000 Page 1 of 37

(]

orano Orano Federal Services CALCULATION Document No.:

CALC-3021788 Rev. No.

000 Page 1 of 37 Project No.:

02029.00.0000.02 Project Name:

License Renewal Support

Title:

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.

Safety 12]

Non-Safety D

Contains Unverified Input/ Assumptions:

Yes: D No: [8]

Software Utilized: Yes Software Active in FS EASI: Yes: 12] NA*: 0

  • Not Applicable per Section 5. 7 of FS-EN-PRC-002 Error Notices & Associated Corrective Actions Reviewed: Yes: 12]

No: D Printed Name Preparer:

E. Gonsiorowski Checker:

S. Gibboney Approver:

D. Hillstrom Other:

FS-EN-FRM-002 Rev. 10 (Effective March 1, 2018)

Refer to FS-EN-PRC-002 Version:

SCALE 6.2.1 Excel2010*

Storage Media: Yes: 12]

No:D Location:

COLDStor Signature Date lJ_~

8 / 30 /\\R

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support Revision History Rev.

Changes 0

Initial Release CALC-3021788-000 Page 2 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support 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 RESULTS AND CONCLUSIONS................................................................................................................ 23 7.0 COMPUTER SOFTWARE USAGE............................................................................................................. 24 7.1 In-Use Testing of SCALE 6.2.1...................................................................................................................... 24 7.2 File Listing...................................................................................................................................................... 24

8.0 REFERENCES

............................................................................................................................................ 29 9.0 SAMPLE INPUT FILE.................................................................................................................................. 31 9.1 Collapsed_4x3.inp.......................................................................................................................................... 31 APPENDIX A : COMPARISON OF SELECT TMI-2 ISFSI CRITICALITY CASES.................................................. 34 CALC-3021788-000 Page 3 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support List of Tables 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.............................................................................................. 21 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 CALC-3021788-000 Page 4 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support 1.0 PURPOSE The Nuclear Regulatory Commission (NRC) has requested additional information [1] to support the technical review of the Three Mile Island Unit 2 (TMI-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 TMI-2 Fuel Canisters together via surface-to-surface contact of their Boral 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 of TMI-2 criticality evaluations is presented in Appendix A.

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 10CFR72 INEL/TMI-2 Fuel ISS (NUHOMS-12T) [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 TMI-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 keff 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 of TMI-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, Boral, 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.

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 CALC-3021788-000 Page 5 of 37

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02029.00.0000.02 - License Renewal Support and Boral 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 Boral per Section 7.4 of [4]).

Figure 2-1: NUHOMS-12T Dry Shielded Canister Figure 2-2: NUHOMS-12T Horizontal Storage Module CALC-3021788-000 Page 6 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support 3.0 ASSUMPTIONS 3.1 Unverified Assumptions There are no unverified assumptions.

3.2 Justified Assumptions 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 + 2.

The batch 3 average + 2 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 UO2 and no credit is taken for degradation to less dense oxides.
8. Canister fuel regions are filled with 1908 lb of UO2, 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 UO2. 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:

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02029.00.0000.02 - License Renewal Support

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 UO2 or UO2 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 UO2 (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.

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support 4.2 Model Specification 4.2.1 Configuration 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 Boral, and 0.08-in. (0.2 cm) thick stainless steel. The Licon fills the annulus of the inner shell wall and the outer Boral shroud steel. Compared to [12], the TMI-2 Fuel Canister model geometry has a larger cavity (9-in. square on drawing), thinner Boral (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 file values. The total fuel height for 1740 lb UO2 is 174.54 cm. The fuel-water mixture height is 24.08 cm for 8 L water (originally 30.04 cm for 10 L water of full-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 Boral 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 specified in criticality run LDC-05 in [6]. Boral is defined per Table A-1 in [6] and corresponds to 0.03 g B-10/cm2 (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 Boral 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 Boral used in dry storage system for spent nuclear fuel is either not credible or will not reduce the neutron absorbing capability.

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support Figure 4-1: Criticality Model with Credit for Licon Structural Properties (Radial View)

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support Figure 4-2: Criticality Model with Credit for Licon Structural Properties (Axial View)

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02029.00.0000.02 - License Renewal Support Figure 4-3: Criticality Model with No Credit for Licon Structural Properties (Triangular Array)

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02029.00.0000.02 - License Renewal Support Figure 4-4: Criticality Model with No Credit for Licon Structural Properties (Square Array)

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support 5.0 CALCULATIONS 5.1 Criticality Analysis 5.1.1 Computer Codes 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.0 238-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 keff of 0.93028 +/-.00058 (ks of 0.93144, see Section 5.1.3), while the original CSASIX input resulted in a keff 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 10,000 neutrons per generation and 50 generations skipped. All run errors are less than 0.0008.

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02029.00.0000.02 - License Renewal Support 5.1.2 Multiplication Factor 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 Boral 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 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 0 (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 0 (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 Boral.

For the third parameter study, the results for the compression of TMI-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 of TMI-2 Fuel Canister packing through fractional shrinking of x-axis and y-axis separation gaps, is increased from 0 (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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02029.00.0000.02 - License Renewal Support Table 5-1: Non-Structural Loss of Licon Results Licon Fractional Density keff ks 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 Figure 5-1: Non-Structural Loss of Licon Results 0.65 0.7 0.75 0.8 0.85 0.9 0.95 0.0 0.2 0.4 0.6 0.8 1.0 ks = keff + 2 Licon Fractional Density CALC-3021788-000 Page 16 of 37

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02029.00.0000.02 - License Renewal Support Table 5-2: Water Absorption in Licon Results Water Volume Fraction in Licon keff 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 Figure 5-2: Water Absorption in Licon Results 0.65 0.70 0.75 0.80 0.85 0.90 0.95 0.0 0.2 0.4 0.6 0.8 1.0 ks = keff + 2 Water Volume Fraction in Licon CALC-3021788-000 Page 17 of 37

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02029.00.0000.02 - License Renewal Support Table 5-3: Compression of Packing due to Structural Loss of Licon Results Compression Factor keff ks 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 Array 0.85770 0.00078 0.85926 Figure 5-3: Compression of Packing due to Structural Loss of Licon Results 0.65 0.70 0.75 0.80 0.85 0.90 0.95 0.0 0.2 0.4 0.6 0.8 1.0 ks = keff + 2 TMI-2 Fuel Canister Compression Factor CALC-3021788-000 Page 18 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support 5.1.3 Benchmark Comparisons 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 USLSTATS 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:

ks = keff + 2 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 10) compounds (UO2) 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.

Table 5-4: Benchmark Experiments Used Series Title LEU-COMP-THERM-001 Water-Moderated U(2.35)O2 Fuel Rods in 2.032-cm Square-Pitched Arrays LEU-COMP-THERM-002 Water-Moderated U(4.31)O2 Fuel Rods in 2.54-cm Square-Pitched Arrays LEU-COMP-THERM-010 Water-Moderated U(4.31)O2 Fuel Rods Reflected by Two Lead, Uranium, or Steel Walls LEU-COMP-THERM-042 Water-Moderated Rectangular Clusters of U(2.35)O2 Fuel Rods (1.684-Cm Pitch) Separated by Steel, Boral, Boroflex, Cadmium, or Copper Plates with Steel Reflecting Walls CALC-3021788-000 Page 19 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support 5.1.3.2 Bias Determination The USL is calculated by application of the USLSTATS computer program [18]. USLSTATS receives as input the keff as calculated by CSAS5, the total uncertainty (combined benchmark and CSAS5 uncertainties), and a trending parameter. Two trending parameters have been selected: (1) Energy of Average Lethargy of Fission (EALF) and (2) U-235 number density in the fuel.

The uncertainty value, total, assigned to each case is a combination of the benchmark uncertainty for each experiment, bench, and the Monte Carlo uncertainty associated with the particular computational evaluation of the case, CSAS5, or:

total = bench 2

+ CSAS5 2

These values are input into the USLSTATS program in addition to the following parameters, the values for which are selected in accordance with the USLSTATS Users 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 of USL Method 1) 1-, confidence on fit = 0.95

, 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) km, 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 USLSTATS are reported in Table 5-6.

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 0.9428. The USL is trending upwards for increasing EALF. While case 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]. No credit is taken for the upwards trend of USL for increasing EALF. The EALF value is 1.19487 eV for the most reactive 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 0.9422. The U-235 number density in the fuel is constant for all 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 case.

Recommended USL For the EALF trending parameter, the minimum USL is 0.9428, while for the EALF trending parameter, the minimum USL is 0.9422. Therefore, a USL of 0.9422 is justified.

CALC-3021788-000 Page 20 of 37

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Title:

TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support Table 5-5: USL Results Trending Parameter Filename Minimum USL over Range of Applicability Range of Applicability EALF (eV)

EALF 0.9428 9.36E-2 < X < 6.00E-1 NDEN (U-235 atoms/b-cm)

NDEN 0.9422 4.88E-4 < X < 1.01E-3 Table 5-6: Benchmark Experiment Data Experiment Case Keff (CSAS5)

(CSAS5)

(Benchmark)

(Total)

EALF (eV)

NDEN (U-235 atoms/b-cm)

LEU-COMP-THERM-001 1

0.99805 0.00054 0.00310 0.00315 9.64307E-02 4.87850E-04 2

0.99864 0.00056 0.00310 0.00315 9.55183E-02 4.87850E-04 3

0.99766 0.00055 0.00310 0.00315 9.49998E-02 4.87850E-04 4

0.99772 0.00061 0.00310 0.00316 9.57092E-02 4.87850E-04 5

0.99642 0.00048 0.00310 0.00314 9.41998E-02 4.87850E-04 6

0.99738 0.00049 0.00310 0.00314 9.53579E-02 4.87850E-04 7

0.99710 0.00046 0.00310 0.00313 9.36295E-02 4.87850E-04 8

0.99668 0.00052 0.00310 0.00314 9.43703E-02 4.87850E-04 LEU-COMP-THERM-002 1

0.99843 0.00061 0.00200 0.00209 1.13063E-01 1.01020E-03 2

0.99849 0.00072 0.00200 0.00213 1.13313E-01 1.01020E-03 3

0.99982 0.00057 0.00200 0.00208 1.12867E-01 1.01020E-03 4

0.99735 0.00050 0.00200 0.00206 1.11899E-01 1.01020E-03 5

0.99796 0.00066 0.00200 0.00211 1.10367E-01 1.01020E-03 LEU-COMP-THERM-010 1

1.00313 0.00070 0.00210 0.00221 1.18119E-01 1.01020E-03 2

1.00483 0.00051 0.00210 0.00216 1.14888E-01 1.01020E-03 3

1.00298 0.00063 0.00210 0.00219 1.13047E-01 1.01020E-03 4

0.99625 0.00053 0.00210 0.00217 1.10340E-01 1.01020E-03 5

1.00031 0.00056 0.00210 0.00217 3.55933E-01 1.01020E-03 6

0.99924 0.00057 0.00210 0.00218 2.65331E-01 1.01020E-03 7

1.00095 0.00063 0.00210 0.00219 2.11832E-01 1.01020E-03 8

0.99823 0.00050 0.00210 0.00216 1.86992E-01 1.01020E-03 9

1.00072 0.00056 0.00210 0.00217 1.22224E-01 1.01020E-03 10 1.00145 0.00055 0.00210 0.00217 1.18188E-01 1.01020E-03 11 1.00123 0.00053 0.00210 0.00217 1.15400E-01 1.01020E-03 12 0.99964 0.00059 0.00210 0.00218 1.12407E-01 1.01020E-03 13 0.99578 0.00054 0.00210 0.00217 1.10385E-01 1.01020E-03 14 1.00319 0.00076 0.00280 0.00290 3.06227E-01 1.01020E-03 15 1.00221 0.00065 0.00280 0.00287 2.93564E-01 1.01020E-03 CALC-3021788-000 Page 21 of 37

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02029.00.0000.02 - License Renewal Support Table 5-6: Benchmark Experiment Data (continued)

Experiment Case Keff (CSAS5)

(CSAS5)

(Benchmark)

(Total)

EALF (eV)

NDEN (U-235 atoms/b-cm)

LEU-COMP-THERM-010 16 1.00275 0.00064 0.00280 0.00287 2.85031E-01 1.01020E-03 17 1.00194 0.00061 0.00280 0.00287 2.79068E-01 1.01020E-03 18 1.00232 0.00054 0.00280 0.00285 2.73688E-01 1.01020E-03 19 1.00134 0.00068 0.00280 0.00288 2.67083E-01 1.01020E-03 20 1.00287 0.00053 0.00280 0.00285 2.93297E-01 1.01020E-03 21 1.00400 0.00075 0.00280 0.00290 2.84075E-01 1.01020E-03 22 1.00295 0.00064 0.00280 0.00287 2.73343E-01 1.01020E-03 23 1.00140 0.00060 0.00280 0.00286 2.66985E-01 1.01020E-03 24 0.99951 0.00054 0.00280 0.00285 6.00491E-01 1.01020E-03 25 1.00316 0.00080 0.00280 0.00291 5.55338E-01 1.01020E-03 26 1.00237 0.00054 0.00280 0.00285 5.14005E-01 1.01020E-03 27 1.00274 0.00066 0.00280 0.00288 4.79524E-01 1.01020E-03 28 1.00194 0.00056 0.00280 0.00286 4.52575E-01 1.01020E-03 29 1.00263 0.00053 0.00280 0.00285 4.27241E-01 1.01020E-03 30 1.00029 0.00079 0.00280 0.00291 3.72891E-01 1.01020E-03 LEU-COMP-THERM-042 1

0.99889 0.00057 0.00160 0.00170 1.68544E-01 4.87850E-04 2

0.99762 0.00053 0.00160 0.00169 1.74907E-01 4.87850E-04 3

0.99914 0.00056 0.00160 0.00170 1.81329E-01 4.87850E-04 4

0.99885 0.00052 0.00170 0.00178 1.80811E-01 4.87850E-04 5

0.99799 0.00054 0.00330 0.00334 1.76997E-01 4.87850E-04 6

0.99897 0.00050 0.00160 0.00168 1.68774E-01 4.87850E-04 7

0.99572 0.00069 0.00180 0.00193 1.73449E-01 4.87850E-04 CALC-3021788-000 Page 22 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support 6.0 RESULTS AND CONCLUSIONS 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 Boral (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 RAI 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 RAI 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.

CALC-3021788-000 Page 23 of 37

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02029.00.0000.02 - License Renewal Support 7.0 COMPUTER SOFTWARE USAGE Computer Name:

EGONSIOROWSKI1 Hardware Profile of Computer:

Intel Xeon CPU E5-1650 @ 3.50 GHz, 16.0 GB RAM Operating System:

64-bit Windows 7 Enterprise, Service Pack 1 7.1 In-Use Testing of SCALE 6.2.1 Input files p2438al_eg1.inp and epru65b_eg1.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 [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.

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

7.2 File Listing Directory: Runs\\Benchmarking\\Cases\\LEU-COMP-THERM-001 Mode LastWriteTime Length Name

-a--- 7/11/2018 1:05 PM 2224 CASE_1.inp

-a--- 7/11/2018 1:04 PM 505220 CASE_1.out

-a--- 7/11/2018 1:06 PM 2565 CASE_2.inp

-a--- 7/11/2018 1:12 PM 507235 CASE_2.out

-a--- 7/11/2018 1:07 PM 2563 CASE_3.inp

-a--- 7/11/2018 1:12 PM 507147 CASE_3.out

-a--- 7/11/2018 1:08 PM 2702 CASE_4.inp

-a--- 7/11/2018 1:13 PM 509197 CASE_4.out

-a--- 7/11/2018 1:07 PM 2560 CASE_5.inp

-a--- 7/11/2018 1:12 PM 507115 CASE_5.out

-a--- 7/11/2018 1:07 PM 2689 CASE_6.inp

-a--- 7/11/2018 1:12 PM 509190 CASE_6.out

-a--- 7/11/2018 1:07 PM 2561 CASE_7.inp

-a--- 7/11/2018 1:12 PM 507091 CASE_7.out

-a--- 7/11/2018 1:06 PM 2561 CASE_8.inp

-a--- 7/11/2018 1:12 PM 507136 CASE_8.out Directory: Runs\\Benchmarking\\Cases\\LEU-COMP-THERM-002 Mode LastWriteTime Length Name

-a--- 7/11/2018 1:42 PM 1892 CASE_1.inp

-a--- 7/11/2018 1:46 PM 461644 CASE_1.out

-a--- 7/11/2018 1:42 PM 1888 CASE_2.inp

-a--- 7/11/2018 1:46 PM 461736 CASE_2.out

-a--- 7/11/2018 1:42 PM 1888 CASE_3.inp

-a--- 7/11/2018 1:46 PM 461863 CASE_3.out

-a--- 7/11/2018 1:42 PM 1860 CASE_4.inp

-a--- 7/11/2018 1:46 PM 460459 CASE_4.out

-a--- 7/11/2018 1:42 PM 1857 CASE_5.inp

-a--- 7/11/2018 1:46 PM 460355 CASE_5.out CALC-3021788-000 Page 24 of 37

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02029.00.0000.02 - License Renewal Support Directory: Runs\\Benchmarking\\Cases\\LEU-COMP-THERM-010 Mode LastWriteTime Length Name

-a--- 7/10/2018 1:31 PM 2085 case_1.inp

-a--- 7/10/2018 1:34 PM 462179 case_1.out

-a--- 7/10/2018 1:44 PM 2377 case_10.inp

-a--- 7/10/2018 2:02 PM 473402 case_10.out

-a--- 7/10/2018 1:44 PM 2377 case_11.inp

-a--- 7/10/2018 2:08 PM 473583 case_11.out

-a--- 7/10/2018 1:44 PM 2377 case_12.inp

-a--- 7/10/2018 2:08 PM 473707 case_12.out

-a--- 7/10/2018 1:44 PM 2377 case_13.inp

-a--- 7/10/2018 2:09 PM 473468 case_13.out

-a--- 7/10/2018 1:46 PM 2380 case_14.inp

-a--- 7/10/2018 2:09 PM 473633 case_14.out

-a--- 7/10/2018 1:47 PM 2380 case_15.inp

-a--- 7/10/2018 2:09 PM 473720 case_15.out

-a--- 7/10/2018 1:47 PM 2380 case_16.inp

-a--- 7/10/2018 2:14 PM 473683 case_16.out

-a--- 7/10/2018 1:47 PM 2380 case_17.inp

-a--- 7/10/2018 2:14 PM 473730 case_17.out

-a--- 7/10/2018 1:47 PM 2381 case_18.inp

-a--- 7/10/2018 2:14 PM 473437 case_18.out

-a--- 7/10/2018 1:47 PM 2381 case_19.inp

-a--- 7/10/2018 2:14 PM 473831 case_19.out

-a--- 7/10/2018 1:42 PM 2126 case_2.inp

-a--- 7/10/2018 1:53 PM 462614 case_2.out

-a--- 7/10/2018 1:47 PM 2083 case_20.inp

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-a--- 7/10/2018 1:47 PM 2127 case_21.inp

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-a--- 7/10/2018 1:47 PM 2129 case_22.inp

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-a--- 7/10/2018 1:47 PM 2129 case_23.inp

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-a--- 7/10/2018 1:47 PM 2172 case_24.inp

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-a--- 7/10/2018 1:47 PM 2172 case_25.inp

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-a--- 7/10/2018 1:47 PM 2172 case_26.inp

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-a--- 7/10/2018 1:47 PM 2172 case_27.inp

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-a--- 7/10/2018 1:47 PM 2172 case_28.inp

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-a--- 7/10/2018 1:47 PM 2172 case_29.inp

-a--- 7/10/2018 2:18 PM 462158 case_29.out

-a--- 7/10/2018 1:42 PM 2127 case_3.inp

-a--- 7/10/2018 1:57 PM 462879 case_3.out

-a--- 7/10/2018 1:47 PM 2172 case_30.inp

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-a--- 7/10/2018 1:42 PM 2127 case_4.inp

-a--- 7/10/2018 2:01 PM 462874 case_4.out CALC-3021788-000 Page 25 of 37

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02029.00.0000.02 - License Renewal Support

-a--- 7/10/2018 1:43 PM 2169 case_5.inp

-a--- 7/10/2018 2:04 PM 462012 case_5.out

-a--- 7/10/2018 1:43 PM 2169 case_6.inp

-a--- 7/10/2018 2:02 PM 462116 case_6.out

-a--- 7/10/2018 1:43 PM 2169 case_7.inp

-a--- 7/10/2018 2:02 PM 462149 case_7.out

-a--- 7/10/2018 1:43 PM 2169 case_8.inp

-a--- 7/10/2018 2:02 PM 461929 case_8.out

-a--- 7/10/2018 1:44 PM 2378 case_9.inp

-a--- 7/10/2018 2:02 PM 473506 case_9.out Directory: Runs\\Benchmarking\\Cases\\LEU-COMP-THERM-042 Mode LastWriteTime Length Name

-a--- 7/11/2018 2:24 PM 3328 CASE_1.inp

-a--- 7/11/2018 2:28 PM 611715 CASE_1.out

-a--- 7/11/2018 2:24 PM 3290 case_2.inp

-a--- 7/11/2018 2:28 PM 612414 case_2.out

-a--- 7/11/2018 2:24 PM 3308 CASE_3.inp

-a--- 7/11/2018 2:28 PM 606490 CASE_3.out

-a--- 7/11/2018 2:24 PM 3514 CASE_4.inp

-a--- 7/11/2018 2:28 PM 655004 CASE_4.out

-a--- 7/11/2018 2:24 PM 3558 CASE_5.inp

-a--- 7/11/2018 2:28 PM 652987 CASE_5.out

-a--- 7/11/2018 2:24 PM 3283 CASE_6.inp

-a--- 7/11/2018 2:28 PM 611521 CASE_6.out

-a--- 7/11/2018 2:24 PM 3702 CASE_7.inp

-a--- 7/11/2018 2:28 PM 620879 CASE_7.out Directory: Runs\\Benchmarking\\USLSTATS Mode LastWriteTime Length Name

-a--- 7/12/2018 2:45 PM 1525 EALF.in

-a--- 7/12/2018 2:46 PM 9048 EALF.out

-a--- 7/12/2018 2:45 PM 1527 NDEN.in

-a--- 7/12/2018 2:45 PM 9049 NDEN.out Directory: Runs\\Criticality\\Collapsed Can Mode LastWriteTime Length Name

-a--- 7/18/2018 1:29 PM 3698 Collapsed_4x3.inp

-a--- 7/18/2018 1:31 PM 1052052 Collapsed_4x3.out

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_0.0.inp

-a--- 7/18/2018 1:24 PM 1052224 Collapsed_CF_0.0.out

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_0.1.inp

-a--- 7/18/2018 1:23 PM 1052292 Collapsed_CF_0.1.out

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_0.2.inp

-a--- 7/18/2018 1:24 PM 1052289 Collapsed_CF_0.2.out

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_0.3.inp

-a--- 7/18/2018 1:23 PM 1052219 Collapsed_CF_0.3.out

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_0.4.inp

-a--- 7/18/2018 1:23 PM 1052059 Collapsed_CF_0.4.out

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_0.5.inp

-a--- 7/18/2018 1:23 PM 1052102 Collapsed_CF_0.5.out CALC-3021788-000 Page 26 of 37

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02029.00.0000.02 - License Renewal Support

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_0.6.inp

-a--- 7/18/2018 1:23 PM 1052228 Collapsed_CF_0.6.out

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_0.7.inp

-a--- 7/18/2018 1:23 PM 1052046 Collapsed_CF_0.7.out

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_0.8.inp

-a--- 7/18/2018 1:23 PM 1051802 Collapsed_CF_0.8.out

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_0.9.inp

-a--- 7/18/2018 1:23 PM 1052171 Collapsed_CF_0.9.out

-a--- 7/18/2018 1:18 PM 3711 Collapsed_CF_1.0.inp

-a--- 7/18/2018 1:23 PM 1052080 Collapsed_CF_1.0.out Directory: Runs\\Criticality\\LDC-05 Mode LastWriteTime Length Name

-a--- 7/17/2018 3:14 PM 3596 LDC-05_CSAS5.inp

-a--- 7/17/2018 3:17 PM 1087988 LDC-05_CSAS5.out

-a--- 6/26/2018 9:14 AM 3869 LDC-05_CSASIX.inp Directory: Runs\\Criticality\\Licon Density Mode LastWriteTime Length Name

-a--- 7/18/2018 9:36 AM 3668 Licon_0.0.inp

-a--- 7/18/2018 9:44 AM 1087324 Licon_0.0.out

-a--- 7/18/2018 9:39 AM 3682 Licon_0.1.inp

-a--- 7/18/2018 9:44 AM 1087156 Licon_0.1.out

-a--- 7/18/2018 9:39 AM 3682 Licon_0.2.inp

-a--- 7/18/2018 9:44 AM 1086954 Licon_0.2.out

-a--- 7/18/2018 9:39 AM 3682 Licon_0.3.inp

-a--- 7/18/2018 9:44 AM 1087390 Licon_0.3.out

-a--- 7/18/2018 9:38 AM 3682 Licon_0.4.inp

-a--- 7/18/2018 9:44 AM 1086944 Licon_0.4.out

-a--- 7/18/2018 9:38 AM 3682 Licon_0.5.inp

-a--- 7/18/2018 9:45 AM 1087035 Licon_0.5.out

-a--- 7/18/2018 9:38 AM 3682 Licon_0.6.inp

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-a--- 7/18/2018 9:22 AM 3668 Licon_1.0.inp

-a--- 7/18/2018 9:45 AM 1087221 Licon_1.0.out Directory: Runs\\Criticality\\Water Content Mode LastWriteTime Length Name

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02029.00.0000.02 - License Renewal Support

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-a--- 11/10/2016 3:56 PM 3697 epru65b_eg1.inp

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-a--- 7/16/2018 12:59 PM 19200 Benchmarking.xlsx

-a--- 8/30/2018 9:36 PM 12014 Evaluation Comparison.xlsx

-a--- 7/18/2018 4:37 PM 24201 Tables.xlsx CALC-3021788-000 Page 28 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support

8.0 REFERENCES

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
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 0

3. Safety Analysis Report, TMI-2 Safety Analysis Report, Materials License No. SNM-2508, Amendment 4
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, Calc. No. 0219-02.0300, Criticality Evaluation for the 10CFR72 INEL/TMI-2 Fuel ISS (NUHOMS-12T), Revision 1, August 1999
6. Idaho Cleanup Project Internal Report, INEEL/INT-99-00126, Criticality Safety Evaluation of TMI-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 1
8. Transnuclear West Drawing, Dry Shielded Canister Shell Assembly Safety Analysis Report, Drawing Number 219-02-2001, Revision 1
9. Transnuclear West Drawing, Dry Shielded Canister Basket-Shell Assembly Safety Analysis Report, Drawing Number 219-02-2002, Revision 1
10. Transnuclear West Drawing, Dry Shielded Canister Main Assembly Safety Analysis Report, Drawing Number 219-02-2003, Revision 1
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
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, Users Manual for USLSTATS V1.0, in NUREG/CR-6361, Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages, March 1997. No new users manual has been developed for later updates to the program.

CALC-3021788-000 Page 29 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support

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. AREVA Federal Services Calculation, CALC-3018409, Software Dedication Report for SCALE 6.2.1, Revision 0 CALC-3021788-000 Page 30 of 37

Page 31 of 37 Orano Federal Services

Title:

TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support 9.0 SAMPLE INPUT FILE 9.1 Collapsed_4x3.inp

=csas5 parm=( )

LDC-05, Remade from Listing-12 of INEEL/INT-99/00126 Rev. 4 (w/ 8L, Boral, and 4x3 Array) v7-238 read comp

' Wet Fuel, mixed in material 501 U-238 100 0 2.18749-2 293 END U-235 100 0 6.81347-4 293 END O 100 0 4.51125-2 293 END H2O 200 1.0 293 END

' Dry Fuel, mixed into material 502 U-238 1 0 2.18749-2 293 END U-235 1 0 6.81347-4 293 END O 1 0 4.51125-2 293 END

' Stainless Steel 304 SS304 4 1.0 293 END

' NOT USED?

H2O 5 8.8-5 293 END

' DSC Carbon Steel CARBONSTEEL 6 1.0 293 END

' NOT USED?

H2O 7 0.2 293 END

' Boral B-10 8 0 5.26187-3 293 END B-11 8 0 2.12228-2 293 END AL 8 0 5.76341-2 293 END

' HSM Concrete C 9 0 1.6000-3 293 END O 9 0 3.9700-2 293 END NA 9 0 5.5000-4 293 END AL 9 0 1.6000-3 293 END SI 9 0 1.5200-2 293 END S 9 0 5.0000-5 293 END CA 9 0 3.1000-3 293 END FE 9 0 3.8000-4 293 END H2O 9 0.114 293 END

' Licon

'H2O 3 0.00 293 END

'O 3 0 1.1855-2 293 END

'NA 3 0 1.4380-4 293 END

'MG 3 0 3.5859-5 293 END

'AL 3 0 2.8385-3 293 END

'SI 3 0 8.7196-4 293 END

'CA 3 0 1.3101-3 293 END

'FE 3 0 1.3576-5 293 END end comp read celldata LATTICECELL TRIANGPITCH PITCH=1.45 200 FUELD=0.93904 100 cellmix=501 END LATTICECELL TRIANGPITCH PITCH=0.93904 0 FUELD=0.93904 1 cellmix=502 END end celldata CALC-3021788-000 Page 31 of 37

Page 32 of 37 Orano Federal Services

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support READ PARA TME=800.0 GEN=250 NPG=10000 RUN=YES FLX=YES FDN=NO FAR=NO PLT=YES NSK=50 LIB=4 HTM=NO END PARA READ GEOM UNIT 1 COM=* Wet Fuel in Fuel Canister (1289) 1st layer

  • CUBOID 501 1 4P11.59 24.07602 -0.0 CUBOID 4 1 4P11.69 24.07602 -0.0 CUBOID 8 1 4P12.02 24.07602 -0.0 CUBOID 4 1 4P12.22 24.07602 -0.0 CUBOID 4 1 4P12.71 24.07602 -0.9525 UNIT 2 COM=* Dry Fuel in Fuel Canister (1289) 2nd layer
  • CUBOID 502 1 4P11.59 150.46862 -0.0 CUBOID 4 1 4P11.69 150.46862 -0.0 CUBOID 8 1 4P12.02 150.46862 -0.0 CUBOID 4 1 4P12.22 150.46862 -0.0 CUBOID 4 1 4P12.71 150.46862 -0.000 UNIT 3 COM=* Empty Section of Canister (1289) 3rd layer
  • CUBOID 0 1 4P11.59 180.52078 -0.0 CUBOID 4 1 4P11.69 180.52078 -0.0 CUBOID 8 1 4P12.02 180.52078 -0.0 CUBOID 4 1 4P12.22 180.52078 -0.0 CUBOID 4 1 4P12.71 185.60078 -0.000 GLOBAL UNIT 7 COM=* SILO*

CYLINDER 0 1 79.400001 474.0275 -0.9525 HOLE 1 -38.13 0.00 0.0 HOLE 1 12.71 0.00 0.0 HOLE 1 -12.71 0.00 0.0 HOLE 1 38.13 25.42 0.0 HOLE 1 -38.13 25.42 0.0 HOLE 1 38.13 -25.42 0.0 HOLE 1 -38.13 -25.42 0.0 HOLE 1 12.71 25.42 0.0 HOLE 1 -12.71 25.42 0.0 HOLE 1 12.71 -25.42 0.0 HOLE 1 -12.71 -25.42 0.0 HOLE 1 38.13 0.00 0.0 HOLE 2 -38.13 0.00 24.07602 HOLE 2 12.71 0.00 24.07602 HOLE 2 -12.71 0.00 24.07602 HOLE 2 38.13 25.42 24.07602 HOLE 2 -38.13 25.42 24.07602 HOLE 2 38.13 -25.42 24.07602 HOLE 2 -38.13 -25.42 24.07602 HOLE 2 12.71 25.42 24.07602 HOLE 2 -12.71 25.42 24.07602 HOLE 2 12.71 -25.42 24.07602 HOLE 2 -12.71 -25.42 24.07602 HOLE 2 38.13 0.00 24.07602 CALC-3021788-000 Page 32 of 37

Page 33 of 37 Orano Federal Services

Title:

TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support HOLE 3 -38.13 0.00 174.54464 HOLE 3 12.71 0.00 174.54464 HOLE 3 -12.71 0.00 174.54464 HOLE 3 38.13 25.42 174.54464 HOLE 3 -38.13 25.42 174.54464 HOLE 3 38.13 -25.42 174.54464 HOLE 3 -38.13 -25.42 174.54464 HOLE 3 12.71 25.42 174.54464 HOLE 3 -12.71 25.42 174.54464 HOLE 3 12.71 -25.42 174.54464 HOLE 3 -12.71 -25.42 174.54464 HOLE 3 38.13 0.00 174.54464 CYLINDER 6 1 80.9875 474.0275 -0.9525 CUBOID 9 1 4P142.0 534.98 -61.0 END GEOM end data end CALC-3021788-000 Page 33 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support APPENDIX A: COMPARISON OF SELECT TMI-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 of TMI-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:

ks = keff + 2 + 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.

CALC-3021788-000 Page 34 of 37

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TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support Table A-1: Comparison of Select TMI-2 ISFSI Criticality Cases First Criticality Evaluation Individual Fuel Canister Individual Knockout Canister Individual Filter Canister 12 Knockout Canisters in DSC Case Identifier Single Fuel Canister Model Single Knockout Canister Model Single Filter Canister HSM with 12 Knockout Canisters Fuel Loading per Can

>1908 lb

>1908 lb

>1908 lb

>1908 lb Fuel Region Geometry Homogenous Smear Homogenous Smear Homogenous Smear Homogenous Smear Water Content in Fuel Region 8.8E-5 g/cc 8.8E-5 g/cc 8.8E-5 g/cc 8.8E-5 g/cc Fuel Pellet Triangular Pitch 0.93904 cm 0.93904 cm 850 microns 0.93904 cm Poison Credit 75% Boral 75% Boron Carbide 75% Boron Carbide 75% Boron Carbide Keff 0.26047 0.26174 0.24641 0.54051 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 CALC-3021788-000 Page 35 of 37

Page 36 of 37 Orano Federal Services

Title:

TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support Table A-1: Comparison of Select TMI-2 ISFSI Criticality Cases (Continued)

Second Criticality Evaluation 12 Knockout Canisters in DSC 12 Fuel Canisters in DSC 12 Fuel Canisters in DSC Case Identifier DSC420 LDC-05 FUEL002 Fuel Loading per Can 1908 lb 1740 lb 1740 lb Fuel Region Geometry Wet/Dry/Air (Inverted)

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

0.93904 cm (Dry) 1.45 cm (Wet),

0.93904 cm (Dry) 1.45 cm (Wet),

0.93904 cm (Dry)

Poison Credit Water Water 75% Boral Keff 0.9111 0.9260 0.9051 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 CALC-3021788-000 Page 36 of 37

Page 37 of 37 Orano Federal Services

Title:

TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal Doc./Rev.: CALC-3021788-000 Project:

02029.00.0000.02 - License Renewal Support Table A-1: Comparison of Select TMI-2 ISFSI Criticality Cases (Continued)

CALC-3021788 12 Fuel Canisters in DSC 12 Fuel Canisters in DSC 12 Fuel Canisters in DSC 12 Fuel Canisters in DSC 12 Fuel Canisters in DSC Case Identifier Normal Condition Licon replaced with Void Water Volume Fraction in Licon = 1 Compression Factor = 1 4 x 3 Array Fuel Loading per Can 1740 lb 1740 lb 1740 lb 1740 lb 1740 lb Fuel Region Geometry Wet/Dry/Air Wet/Dry/Air Wet/Dry/Air Wet/Dry/Air Wet/Dry/Air Water Content in Fuel Region 8 L 8 L 8 L 8 L 8 L Fuel Pellet Triangular Pitch 1.45 cm (Wet),

0.93904 cm (Dry) 1.45 cm (Wet),

0.93904 cm (Dry) 1.45 cm (Wet),

0.93904 cm (Dry) 1.45 cm (Wet),

0.93904 cm (Dry) 1.45 cm (Wet),

0.93904 cm (Dry)

Poison Credit 75% Boral 75% Boral 75% Boral 75% Boral 75% Boral Keff 0.78846 0.77832 0.67793 0.85026 0.85770 0.00054 0.00055 0.00062 0.00064 0.00078 USL 0.9422 0.9422 0.9422 0.9422 0.9422 Bias Additional Margin Ks 0.78954 0.77942 0.67917 0.85154 0.85926 CALC-3021788-000 Page 37 of 37

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