ML21067A043

Enclosure 1 - NAC International Responses to the Us Nuclear Regulatory Commission Request for Additional Information 1 for Magnastor FSAR RAI Responses for Amendment 10, Revision 21A

ML21067A043
Person / Time
Site:	07201031
Issue date:	02/28/2021
From:	NAC International
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML21067A041	List: ML21067A042 ML21067A043
References
ED20210025
Download: ML21067A043 (98)

Text

MAGNASTOR

(,Modular Advanced Q.eneration Nuclear All-purpose STORage)

FINAL SAFETY ANALYSIS REPORT

• MSO Amendment RAI Responses NON-PROPRIETARY VERSION ANAC V/fl INTE RNATIO NAL Atla-te Corporate HeacJqu.ten 3930 East ~ Bridge Road, No.-cros*, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1787, www nac,nt1 com

Enclosure I to ED20210025 Page I of I Enclosure 1 NAC INTERNATIONAL RESPONSES TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION REQUEST FOR ADDffiONAL INFORMATION #1

• for MAGNASTOR FSAR RAI Responses for Amendment 10 Revision 21A (Docket No 72-1031)

NAC International February 2021

MAGNASTOR~

Docket No.: 72-1031 CoCNo.: 1031 NAC INTERNATIONAL NON-PROPRIETARY RESPONSE TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION REQUEST FOR ADDITIONAL INFORMATION #1 October 2020

• FOR REVIEW OF THE MAGNASTOR (CoC NO. 1031, DOCKET NO. 72-1031)

February 2021

• Page 1 of 14

MAGNASTOR Docket No.: 72-1031 CoC No.: 1031

• TABLE OF CONTENTS Structural Evaluation ..................................................................................................................................... 3 Thermal Evaluation ....................................................................................................................................... 6 Shielding Evaluation ...................................................................................................................................... 9 Materials Evaluation ................................................................................................................................... 10 Material Observations: ............................................................................................................................... 14

• Page 2 of 14

MAGNASTOR<I)

Docket No.: 72-1031 CoC No.: 1031

• Structural Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION 3-1. Clarify how the effects of material nonlinearities (e.g., strain rate and triaxiality) are accounted for in the structural integrity evaluation of the MSO pedestal assembly and transportable storage container (TSC) when subjected to a 24-inch drop accident.

Based on the LS-DYNA finite element models provided with the SAR and the evaluation of the 24-inch drop presented in Calculation Package No. 30082-2604, "Evaluation of the MAGNASTOR Metal Storage Overpack for a 24-inch Drop," it is not clear to the staff if these material nonlinearities have been accounted for in the plastic analysis of the MSO pedestal assembly or the finite element models supporting the plastic analysis. In the finite element models of the 24-inch drop provided to the staff, it appears that strain rate effects and triaxiality of failing components have not been incorporated into the analysis.

For the piecewise linear plasticity material model used for the pedestal components, the option to account for strain rate effects by scaling the yield stress was chosen. However, the curve for the scaling factor does not appear to have been defined. The staff is concerned that higher g-loads could be experienced by the TSC and the structural integrity of the pedestal could be diminished when incorporating these material properties. Since the structural evaluation of the TSC in the drop is based on a comparison of the g-loads to the design TSC g-loads, the staff's concern is related to confinement And since the deformations in the pedestal affect the geometry of the MSO air inlets, the staff's concern also relates to the thermal performance of the cask. The staff requests clarification of how these material nonlinearities are addressed and that the simulations, calculations, and the SAR be updated as necessary.

This information is needed to determine compliance with the regulatory requirements in 10 CFR 72.236(1).

NAC International Response to Structural Evaluation RAI 3-1:

The effects of strain rate are accounted for by defining stress versus plastic strain curve for different strain rates. The solutions for the different cases were regenerated using the strain rate sensitive properties. From the revised solutions, a Triaxiality factor was determined using ASME Section VIII Division 2 Part 5 for protection against local failure. The factors of safety were recomputed using the Triaxiality factor .

• Page 3 of 14

MAGNASTOR~

Docket No.: 72-1031 CoC No.: 1031

• Structural Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION 3-2. Clarify the geometry of the MSO pedestal and the g-loads experienced by the TSC as a result of the 24-inch drop scenario.

LS-DYNA simulations of the 24-inch drop scenario show the TSC striking the MSO pedestal. The simulations show the part labeled "SHORT support rail," which is green in Figure 3-1 below and apparently unlabeled in the drawings but shown in detail AA-AA on sheet 4 of Drawing No. 71160-565, "MSO Body, Li~ and Details," rotating and engaging the inner liner (shown in red). The clearance between the inner "SHORT support rail" and the inner liner according to the drawings is (proprietary information removed)

The staff is concerned that this extra clearance allows the pedestal to absorb more of the impact energy in the model than it would in the real drop. The "SHORT support rail" should "lock up" with the inner liner earlier in the simulation, this would increase the stiffness and allow for an "anvil and hammer" effect, which would increase the g-loads

• on the TSC. The staff also notes that several parts of the top portion of the MSO (e.g., the trunnions) are "ghosting through" (i.e., unrealistically passing through with no resistance) outer portions of the MSO. Though as this behavior occurs at the top of the model, the staff accepts that it may not impact the area of concern at the bottom of the model. The staff requests clarification of the MSO pedestal geometry, clarification of the g-loads experienced by the TSC in the drop scenario, and that the LS-DYNA models that simulate drop events, the calculations, and the FSAR be updated as necessary.

(Proprietary figure removed)

Figure 3-1, "SHORT Support Rail in LS-DYNA Heavy Drop Model" This information is needed to determine compliance with the regulatory requirements in 10 CFR 72.236(1).

NAC International Response to Structural Evaluation RAI 3-2:

NAC International Response to Structural Evaluation RAI 3-2 can be found in the proprietary section of this enclosure .

• Page 4 of 14

MAGNASTOR<ll Docket No.: 72-1031 CoC No.: 1031

• Structural Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION 3-3. Justify the assumption that the MSO will behave as a cantilever beam when determining the natural frequency of the MSO in Appendix A to Calculation Package No. 30082-2605, "TiJrOver Analysis for the MAGNASTOR Metal Storage Overpack (MSO)."

The stress analysis for the non-mechanistic tip-over provided on page 30 of the calculation package considers the MSO to be a simply supported beam with a triangular loading applied when striking the pad. However, this calculation applies a dynamic load factor that is derived from the natural frequency of the MSO calculated in Appendix A, which assumes a cantilever beam behavior. The staff notes that the LS-DYNA model that simulates tip-over produces the largest accelerations when the bottom lip of the MSO and tip of the MSO are in contact with the pad, resembling more closely a simply supported beam. Looking at Figure 6.1.5-1 of Calculation Package 30082-2605, the staff believes that the dynamic load factor determined from assuming a cantilever beam behavior may be non-conservative when a simply supported beam assumption appears to be more appropriate for the boundary conditions of the MSO when striking the pad. The staff requests justification of the assumption of cantilever beam behavior in the tip-over stress analysis and that the calculations and FSAR be updated with the appropriate dynamics load factor as necessary.

This information is needed to determine compliance with the regulatory requirements in 10 CFR 72.236(1).

NAC International Response to Structural Evaluation RAI 3-3:

The calculation of the fundamental mode of the MSO has been updated using a pinned-free boundary condition, which is considered to be more appropriate than a cantilevered assumption. Also, the resulting fundamental frequency of pinned-free beam is higher than both a cantilevered and simply supported beam, and this results in a higher filtering frequency to be applied to the accelerations time histories, which is conservative. In addition, the methodology for calculating the MSO frequency has been modified by treating the MSO as a single composite beam comprised of the inner and outer liners.

Both bending and shear effects are considered, and the calculated fundamental frequency of the MSO is 189 Hz. A filter frequency of 200 Hz is applied to the nodal accelerations from the solution results. Using the revised acceleration and pulse duration, the DLF has been updated .

• Page 5 of 14

MAGNASTOR~

Docket No.: 72-1031 CoC No.: 1031

• Thermal Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION 4-1. If the casks will be situated outside on a concrete pad, demonstrate that low-speed wind does not adversely impact the fuel peak clad temperature or other components important to safety such that the components exceed their allowable temperature limits described in the SAR In the response to request for supplemental information "Submission of a Responses to the NRCs Request for Supplemental Information for the NAC International MAGNASTOR Cask System Amendment No. 10" (ADAMS Accession No. ML20143A102), the applicant states that it does not expect any negative thermal performance effects due to low wind speed even though this new cask design has traditional inlets and nontraditional outlet vents. These non-traditional outlet vents are circular and encompass the entire perimeter of the upper cask. However, the staff notes that because of a larger number of outlet vents that encompass the entire circumference, air exiting the outlet vents could encounter a larger resistance to the air flow compared to the traditional discrete design. Any justification that this outlet design does not impact the cask thermal performance needs to be supported by adequate analysis. The staff needs this information to have assurance predicted temperatures remain below the allowable limits described in the SAR, during long term storage. 10 CFR Part 72 regulations require that the spent fuel cladding must be protected during storage against degradation that leads to gross ruptures or the fuel must be otherwise confined such that degradation of the fuel during storage will not pose operational safety problems with respect to its removal from storage. The above is accomplished by keeping the cladding temperature below 400°C for the entire duration of the licensed storage period.

Currently the SAR shows that for normal conditions of storage, predicted peak cladding temperature (PCT) is about l 5°C below the allowable limit Based on the information provided in the SAR regarding the unique design of the MSO outlet vent, the staff can't determine whether the increase in PCT (due to a potential reduction in air flow because of low speed wind) can be accommodated by the margin shown in the SAR Therefore, the staff does not have reasonable assurance the spent fuel cladding would be protected from degradation during the entire licensed period for normal storage.

This information is needed to determine compliance with the regulatory requirements in 10 CFR 72.236(b) and 72.236(+/-).

NAC International Response to Thermal Evaluation RAJ 4-1:

As previously submitted to the RSI response cycle the MSO is expected to be used within a building protecting the cask from low speed impact. Technical Specification requirement for the use of a building is added to the MSO definition and Section 4.3 .1 as

• item G). The thermal basis building requirements are discussed in the response to RAJ 4-2.

Page 6 of 14

MAGNASTOR~

Docket No.: 72-1031 CoC No.: 1031

• Thermal Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION 4-2. If the casks will be situated outside on a concrete pad, demonstrate that low-speed wind does not adversely impact the fuel peak clad temperature or other components important to safety such that the components exceed their allowable temperature limits described in the SAR In the response to request for supplemental information "Submission of a Responses to the NRCs Request for Supplemental Information for the NAC International MAGNASTOR~ Cask System Amendment No. 10" (ADAMS Accession No. ML20143Al02), the applicant states that it does not expect any negative thermal performance effects due to low wind speed even though this new cask design has traditional inlets and nontraditional outlet vents. These non-traditional outlet vents are circular and encompass the entire perimeter of the upper cask. However, the staff notes that because of a larger number of outlet vents that encompass the entire circumference, air exiting the outlet vents could encounter a larger resistance to the air flow compared to the traditional discrete design. Any justification that this outlet design does not impact the cask thermal performance needs to be supported by adequate analysis. The staff needs this information to have assurance predicted temperatures remain below the allowable limits described in the SAR, during long term storage. 10 CFR Part 72 regulations require that the spent fuel cladding must be protected during storage against degradation that leads to gross ruptures or the fuel must be otherwise confined such that degradation of the fuel during storage will not pose operational safety problems with respect to its removal from storage. The above is accomplished by keeping the cladding temperature below 400°C for the entire duration of the licensed storage period. Currently the SAR shows that for normal conditions of storage, predicted peak cladding temperature (PCT) is about 15°C below the allowable limit Based on the information provided in the SAR regarding the unique design of the MSO outlet vent, the staff can't determine whether the increase in PCT ( due to a potential reduction in air flow because of low speed wind) can be accommodated by the margin shown in the SAR Therefore, the staff does not have reasonable assurance the spent fuel cladding would be protected from degradation during the entire licensed period for normal storage.

This information is needed to determine compliance with the regulatory requirements in 10 CFR 72.236(b) and 72.236(f) .

• Page 7 of 14

MAGNASTOR~

Docket No.: 72-1031 CoC No.: 1031

• NAC International Response to Thermal Evaluation RAI 4-2:

As discussed in RAI 4-1 the use of the MSO is limited to building assuring protection from low speed wind. This building design will depend on site specific conditions, including but no limited to type of building material used, number of casks to be stored, heat load of casks to be stored, and environment conditions outside' the building. 10 CFR 72.212 (6) requires an evaluation of site parameters to see if they are bounded. In this case the buildings influence on cask performance must be evaluated. Per 10 CFR 72.212 (7) a 72.48(c) based evaluation for any changes must be performed which limits the evaluation to FSAR MOE or equivalent methods.

NAC is also proposing Technical Specification condition 5.4(d) explicitly requiring this evaluation to be performed in the context of thermal limits .

• Page 8 of 14

MAGNASTOR~

Docket No.: 72-1031 CoC No.: 1031

• Shielding Evaluation REQUEST NAC INTERNATIONAL RESPONSE FOR TO ADDffiONAL INFORMATION 5-1. See proprietary section of this enclosure. The entire question contains proprietary information.

5-2 See proprietary section of this enclosure. The entire question contains proprietary information.

NAC International Response to Shielding Evaluation RAl 5-1 and 5-2 can be found in the proprietary section of this enclosure .

• Page 9 of 14

MAGNASTORill Docket No.: 72-1031 CoCNo.: 1031

• Materials Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDIDONAL INFORMATION 8-1. Clarify the fracture toughness testing requirements and acceptance criteria for the procured structural steels for the MSO and provide a technical basis for any criteria that deviates from the design code.

SAR Tables 1.3-5 and 2.1-1 state that all steel materials shall meet applicable requirements in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, and that the design code of the MSO is ASME B&PV Code, Section ill, Division 1, Subsection NF. ASME B&PV NF-2300 includes testing requirements and acceptance criteria for procured steels to verify that the steels were produced with adequate toughness. However, the staff notes that some of the fracture toughness testing requirements and acceptance criteria for the MSO structural steels do not appear to be defined in the S ~ while other test requirements appear to be inconsistent with the ASME B&PV code.

SAR Section 8.1.1, "Fracture Toughness," does not include a description of the toughness testing and acceptance criteria for many of the MSO components, such as the bottom

• weldment and inner and outer liners. In addition, the basis provided for not requiring fracture toughness testing of the MSO trunnion steels (the MSO handling is limited to temperatures of 0°F and above) does not appear to be consistent with ASME Code. The staff notes that ASME B&PV Code,Section III, Division 1, Subsection NF-2300 includes materials that do not require testing; however, it is not clear how the trunnion steels meet the ASME B&PV Code exception criteria In order to complete its review, the staff requires information on the fracture toughness testing and acceptance criteria for the procured MSO steels and a technical basis for any criteria that deviates from the design code.

This information is needed to determine compliance with the regulatory requirements in 72.146(a), 72.234(a), and 72.236(b).

NAC International Response to Materials Evaluation RAI 8-1:

The Metal Storage Overpack (MSO) is evaluated for the same design events as the Concrete Cask (CC) and qualified to meet the stress design factors of ASME Section III, Division 1, Subsection NF, in accordance with Article NF-3000 "Design". The MSO is not considered an ASME NF component and need not be fabricated in accordance with ASME Section ill, Division 1, Subsection NF requirements. As noted in the revised 71160-565 license drawing, the MSO structural materials shall meet ASTM requirements and all welding procedures and qualifications are to be in accordance with A WS D 1.1 or Page 10 of 14

MAGNASTOR~

Docket No.: 72-1031 CoC No.: 1031

• NAC International Response to Materials Evaluation RAI 8-1 Continued:

ASME Section IX. The interfacing lift points (i.e., trunnions) are qualified to meet ANSI N14.6 stress requirements for non-critical lift conditions and the cask is evaluated for drop conditions in accordance with NUREG-0612. The identified MSO design basis for storage conditions does not require impact testing of the materials used unless dictated by the ASTM material standard. As noted, consistent with the Concrete Cask, for lift conditions the interfacing lift points of the MSO have been qualified to ANSI N14.6 requirements for lifting devices. Similarly, the impact testing requirements of ANSI Nl4.6 are applied to the lift anchors of the Concrete Cask and lift trunnions of the MSO.

Descriptions in Chapter 8 provide justification for why the Concrete Cask lift anchors are exempt from impact testing by stating the material type, thickness and service temperature that is consistent with the ASME Section III, Division 1, Subsection NF exemptions in Article NF-2300. The exemptions provided in Article NF-2300 do not address the ASTM A696 material used for the MSO trunnions. Therefore, consistent with the imposed requirements of the Concrete Cask, impact testing is to be required for the MSO trunnion material to support a lift service temperature of 0°F. The impact testing requirements detailed in Article NF-2300 are used as the basis for qualifying the MSO trunnion material using Charpy V-Notch testing. SAR pages are revised to clarify the fabrication requirements including applicable impact testing as follows:

Table 1.3-5 is revised to clarify the fabrication specification summary for the MSO.

Section 1.8 is revised to reflect the updated revision number for the 71160-565 license drawing.

• Chapter 8 is revised for the clarification of the steel components for the MSO o Sections 8.1, 8.2, & 8.10.2.2 are updated to reflect ASTM materials for the MSO consistent with the revised 71160-565 license drawing.

o Section 8.1.1 is revised to clarify the impact testing requirements for the MSO trunnion material consistent with the above discussion.

o Section 8.4 is revised to clarify the requirement for weld design and specification.

• Section 10.1.1 is revised to provide visual inspection and nondestructive examination requirement description of MSO steel components consistent with the changes made to Table 1.3-5, the 71160-565 license drawing, and Section 8.4 .

• Page 11 of 14

MAGNASTOR<li Docket No.: 72-1031 CoC No.: 1031

• Materials Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION 8-2. Provide a copy of the NS-3 shielding material fabrication specification per SAR licensing Drawing No. 71160-565, Revision OP and describe the qualification activities for the installation (mixing/pouring) process that demonstrates that it will prevent or sufficiently minimire gaps and voids to ensure shielding performance, with no requirement for testing of the MSO for shielding effectiveness.

SAR Section 8.7.2 stated that the NS-3 shielding material is installed by pouring the material into the annulus formed by the MSO inner and outer shells and the cavity of the MSO lid and that the installation of the material utilizes a process that minimires gaps and voids in the installed material. Consequently, no shop or field testing of the MSO for gamma or neutron shielding effectiveness is required or performed.

The staff requests additional information on the details of the fabrication specification and the qualification activities that were performed to demonstrate that the specification will minimize or ensme the absence of voids and gaps, without the need for subsequent shielding performance tests. Such qualification details may include, but are not necessarily limited to, shielding effectiveness tests that were performed on NS-3 material fabricated over the ranges of processing variables allowed under the specification.

This information is required to ensure compliance with 10 CFR 72.146(a) and 72.236(d).

NAC International Response to Materials Evaluation RAI 8-2:

The NS-3 material is cementitious, mixed in a typical mortar mixer, and will be placed in the MSO shielding cavity in a similar manner to the way concrete is placed in NAC concrete overpacks. No specific void/gap testing is required for concrete placement and no such testing is expected for the NS-3 placement. 10 CFR 72.104/106 requirements are placed on controlled boundary performance and significant voiding, not expected of the cementitious product placed into the open cask cavity, would be required to impact controlled area boundary dose. Technical Specification 3.3.1 will ensure that the bulk shield of the MSO meets controlled area boundary requirements.

NS-3 has been used in NAC concrete cask shield plugs and a NUHOMS transfer cask design. Installation procedures that assure a uniform mix were prepared for each of the installations and are included with the RAI response (Attachments 1 and 2 in the proprietary section of this enclosure). The procedures are consistent with NS3 samples that were tested and are designed to eliminate significant gaps or voids. Gaps and shrinkage are minimired by covering the material during curing avoiding excess moisture loss. NAC records related to the shield plugs do not indicate any significant shrinkage or voids.

Page 12 of 14

MAGNASTOR~

Docket No.: 72-1031 CoCNo.: 1031

• NAC International Response to Materials Evaluation RAI 8-2 Continued:

Material properties resulting from the testing/qualification are included in the updated FSAR (as a response to Chapter 5 RAis). The testing included radiation and thermal impacts of the material. Material mixed and placed in accordance with installation procedures will serve its intended function similar to the requirements of a concrete radiation shield.

Fabrication Specification A placeholder fabrication specification number was placed on the NAC license drawing.

Fabrication specifications are not written and approved until a CoC is granted and the licensed component has been purchased by an NAC customer. As the specification has not been required at this time the number has since been removed in Revision 1 of the drawing.

Pregualification of each NS-3 Lot for Hydrogen Content A test kit for each lot ofNS-3 material will be mixed and sent to a laboratory for hydrogen content testing. The minimum hydrogen requirement will be limited by what is analyzed in the NAC shielding calculation (4.85wt°/o). As demonstrated in Chapter 5 total dose rates are relatively sensitive to the hydrogen levels in the material. The minimum hydrogen requirement was therefore added to the licensing drawing.

Placement of NS-3 in an MSO The NS-3 material will be mixed in a typical mortar mixer and pumped into the shielding cavity. In its liquid state, NS-3 flows readily. It contains no aggregate and there is no rebar in the cavity impeding its flow as is the case with concrete. The wet density of the NS-3 will be measured prior to placement into the metal overpack as is similarly done for concrete installations into NAC concrete overpacks. Similar to the concrete requirement, the MSO licensing drawing has been updated to include the minimum required material density (i.e., that evaluated in Chapter 5) of 1. 70 g/cm3

• Minimum hydrogen content and density, in conjunction with an appropriate installation procedure, will assure that the cask will perform its intended safety function .

• Page 13 of 14

MAGNASTOR~

Docket No.: 72-1031 CoCNo.: 1031

- Material Observations:

8-1 The description for item 6, shielding material, in the bill of materials on licensing Drawing No. 71160-565 sheet 1 of 9 refers to note 13, however note 13 does not describe the shielding material. Note 12 describes shielding material.

The staff observed that all descriptions that refer to drawing notes are incorrect for the following items: 22, 26, 28, 33 and 49.

NAC International Response to Materials Observation Evaluation RAI 8-1:

Corrections have been made to Licensing Drawing No. 71160-565, Revision IP of the drawing to address the noted inconsistencies.

8-2 SAR Licensing Drawing No. 71160-565, sheet 2 of 9, Detail D-D. The weld symbol for welding item 5 gussets to item 7 bottom weldment shows a 0.5-inch weld. However, the staff does not recognize whether this weld symbol is a groove (square) or fillet weld.

NAC International Response to Materials Observation Evaluation RAI 8-2:

Specification of the welds for the assembly weldment are revised in Licensing Drawing No.

71160-565, Revision IP of the drawing for clarity and consistency with the structural evaluation.

As detailed in the revised drawing, 1/2 inch fillet welds on both sides are used to attach each of the eight Gussets (Item 5) to the Bottom Weldment (Item 7) and the Inner Liner (Item 1).

8-3 SAR licensing Drawing No. 71160-565, sheet 4 of 9, View U-U. The weld symbol for welding item 12 stand to item 14 base plate shows a 1/4-inch weld, every 4 inches.

However, the staff does not recognize whether this weld symbol is a groove (square) or fillet weld.

NAC International Response to Materials Observation Evaluation RAI 8-3:

The weld symbol is revised in Licensing Drawing No. 71160-565, Revision IP of the drawing to clarify a fillet weld geometry. The Short Support Rails (Item 10), Long Support Rails (Item 11) and Support Rail Gussets (Item 13) are welded to form a cross-beam structure for the bottom weldment which supports the Base Plate (Item 14) and is supported by the Inlet Tops (Item 9).

The weld in question attaches the Base Plate (Item 14) to the welded cross-beam structure of Items 10, 11 and 13. Delta Note 27 specifies that the weld starts at the radius of the Stand (Item

12) and extends outwards for the specified length of 4 inches .

• Page 14 of 14

MAGNASTOR~

Docket No.: 72-1031 CoC No.: 1031 NAC INTERNATIONAL PROPRIETARY RESPONSE TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION REQUEST FOR ADDillONAL INFORMATION #1 October 2020

• FOR REVIEW OF THE MAGNASTOR (CoC NO. 1031, DOCKET NO. 72-1031)

February 2021

• Page 1 of 12

MAGNASTOR~

Docket No.: 72-1031 CoC No.: 1031

• TABLE OF CONTENTS Structural Evaluation ..................................................................................................................................... 3 Thermal Evaluation ....................................................................................................................................... 7 Shielding Evaluation ...................................................................................................................................... 8 Materials Evaluation ................................................................................................................................... 10

• Page 2 of 12

MAGNASTOR~

Docket No.: 72-1031 CoCNo.: 1031

• Structural Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION 3-1. See the non-proprietary section of this enclosure. The entire question contains non-proprietary information.

NAC International Response to Structural Evaluation RAJ 3-1 can be found in the non-proprietary section of this enclosure.

• Page 3 of 12

NAC PROPRIETARY INFORMATION REMOVED MAGNASTORll Docket No.: 72-1031 Coe No.: 1031

• NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Structural Evaluation 3-2 .

• Page 4 of 12

NAC PROPRIETARY INFORMATION REMOVED MAGNAS1DR<I)

Docket No.: 72-1031 CoCNo.: 1031

• Page 5 of 12

MAGNASTOR~

Docket No.: 72-1031 CoC No.: 1031

• Structural Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDmONAL INFORMATION 3-3. See the non-proprietary section of this enclosure. The entire question contains non-proprietary information.

NAC International Response to Structural Evaluation RAJ 3-3 can be found in the non-proprietary section of this enclosure.

• Page 6 of 12

MAGNASTOR~

Docket No.: 72-1031 CoCNo.: 1031

• Thermal Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION 4-1. See the non-proprietary section of this enclosure. The entire question contains non-proprietary information.

4-2 See the non-proprietary section of this enclosure. The entire question contains non-proprietary information.

NAC International Response to Thermal Evaluation RAI 4-1 and 4-2 can be found in the non-proprietary section of this enclosure .

• Page 7 of 12

NAC PROPRIETARY INFORMATION REMOVED MAGNAS1DR~

Docket No.: 72-1031 CoC No.: 1031

• Shielding Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION 5-1.

• Page 8 of 12

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR~

Docket No.: 72-1031 CoC No.: 1031

• NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION Shielding Evaluation 5-2 .

• Page 9 of 12

MAGNAS1DR~

Docket No.: 72-1031 CoCNo.: 1031

• Materials Evaluation NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDffiONAL INFORMATION 8-1. See the non-proprietary section of this enclosure. The entire question contains non-proprietary information.

8-2 See the non-proprietary section of this enclosure. The entire question contains non-proprietary information.

NAC International Response to Materials Evaluation RAI 8-1 and 8-2 can be found in the non-proprietary section of this enclosure.

Materials Observation 8-1. See the non-proprietary section of this enclosure. The entire question contains non-proprietary information .

• 8-2 8-3 See the non-proprietary section of this enclosure. The entire question contains non-proprietary information.

See the non-proprietary section of this enclosure. The entire question contains non-proprietary information.

NAC International Response to Materials Observation RAI 8-1, 8-2 and 8-3 can be found in the non-proprietary section of this enclosure .

• Page 10 of 12

MAGNASTOR,z Docket No.: 72-1031 CoC No.: 1031 Attachment 1 NAC Proprietary NS-3 Installation Procedure

• BISCO Procedure No. NS-3-02 Rev. 5 PROCEDURE IS PROPRIETARY AND WITHHELD IN ITS ENTIRETY PER 10 CFR 2.390

• Page 11 of 12

MAGNASTOR~

Docket No.: 72-1031 CoCNo.: 1031 Attachment 2 NAC Proprietary NS-3 Installation Procedure IONICS, Inc. Procedure No. MI-1142 Rev. 1

• PROCEDURE IS PROPRIETARY AND WITHHELD IN ITS ENTIRETY PER 10 CFR 2.390

• Page 12 of 12

Enclosure 2 to ED202 l 0025 Page I of 3 Enclosure 2 List of Changes for MAGNASTOR FSAR

• RAI Responses for Amendment 10 Revision 21A (Docket No 72-1031)

NAC International February 2021

Enclosure 2 to ED20210025 Page2 of 3

• List of Changes for the MAGNASTOR FSAR, Revision 21A Note: The List of Effective Pages and the Chapter Table of Contents, List of Figures, and List of Tables have been revised accordingly to reflect the list of changes detailed below.

Chapter 1

• Page 1.3-23, modified Table 1.3-5 where indicated.

• Page 1.7-2, inserted new Reference 25, and renumbered and modified Reference 26 where indicated.

• Page 1.8-1, modified the list of License Drawings where indicated. (Proprietary version only.)

• Page 1.8-2, text flow changes (editorial). (Proprietary version only.)

Chapter2

• No changes Chapter3

• Pages 3.11.4-15 thru 3.11.4-16, modified text throughout Section 3.11.4.5 where indicated.

• Page 3 .11.4-17, modified text in the last paragraph of Section 3 .11.4.6, including the embedded table, where indicated.

• Page 3 .11 .4-18, text flow changes.

• Pages 3.11.4-19 thru 3.11.4-20, replaced Figures 3.11.4-2 and 3.11.4-3 where indicated.

• Page 3.11.4-21, text flow changes.

• Page 3.11.4-22, replaced Figure 3.11.4-5 where indicated.

• Page 3.11.4-23, text flow changes.

Chapter4

• No changes Chapter5

• Pages 5.12.4-2 thru 5.12.4-4, modified text throughout Sections 5.12.4.2 and 5.12.4.3 where indicated.

• Pages 5.12.4-5 thru 5.12.4-6, text flow changes.

• Pages 5.12.4-7 thru 5.12.4-12, added new Figures 5.12.4-3 thru 5.12.4-8 where indicated.

• Page 5.12.4-13, modified column heading in Table 5.12.4-2 where indicated.

• Chapter6

• No changes

Enclosure 2 to ED202 l 0025 Page 3 of 3

• Chapter 7

• No changes Chapter 8

• Page 8 .1-2, modified text near the middle of the page, where indicated.

• Pages 8.1-3 thru 8.1-4, modified text in the fourth paragraph in Section 8.1.1 where indicated.

• Page 8.2-1, modified text in the fourth and fifth paragraphs of Section 8.2, where indicated.

• Page 8.4-1, modified text in the third paragraph in Section 8.4 where indicated.

• Page 8.10-4, modified text at the top of the page in the last paragraph of Section 8.10.2.2 where indicated.

Chapter 9

• No changes Chapter 10 Page 10.1-1, modified text in Section 10.1.1, step "e"; deleted first sentence of the second paragraph where indicated.

Pages 10.1-2, modified text in Section 10.1.1, step 'j; deleted last two sentences of the step where indicated.

Page 10.1-3, text flow changes.

Chapter 11

• No changes Chapter 12

• ~o changes Chapter 13

• No changes Chapter 14

• No changes Chapter 15

• No changes

Enclosure 3 to ED202 l 0025 Page 1 of 2 Enclosure 3 List of Drawing Changes for MAGNASTOR FSAR

• RAI Responses for Amendment 10 Revision 21A (Docket No 72-1031)

NAC International February 2021

Enclosure 3 to ED202 l 0025 NAC PROPRIETARY INFORMATION Page2 of 2

• Drawing 71160-565, Body, Lid and Details, Metal Storage Overpack (MSO),

DRAWINGS UPDATED lN TIIIS SUBMITTAL ARE PROPRIETARY AND WITHHELD lN THEIR ENTIRETY PER 10 CFR 2.390

Enclosure 4 to ED202 l 0025 Page 1 of 1 Enclosure 4 Proposed Changes for MAGNASTOR Technical Specifications RAI Responses to Amendment 10 Revision 21A (Docket No 72-1031)

NAC International February 2021

Definitions 1.1

• MSO (Metal Storage Overpack)

The MSO is the vertical storage module that receives, holds and protects the sealed TSC for storage at the ISFSI. The MSO passively provides the radiation shielding, structural protection, and heat dissipation capabilities for the safe storage of spent fuel in a TSC. The ISFSI pad (storage pad) for the MSO must be located within a building structure.

NONFUEL HARDWARE NONFUEL HARDWARE is defined as reactor control components (RCCs), burnable poison absorber assemblies (BPMs), guide tube plug devices (GTPDs), neutron sources/

neutron source assemblies (NSAs), hafnium absorber assemblies (HFRAs), instrument tube tie components, guide tube anchors or other similar devices, in-core instrument thimbles, steel rod inserts (used to displace water from lower section of guide tube), and components of these devices such as individual rods.

All nonfuel hardware, with the exception of instrument tube tie components, guide tube anchors or other similar devices, and steel rod inserts, may be activated during in-core operations.

RCCs are commonly referred to as rod cluster control assemblies (RCCAs), control rod assemblies (CRAs), or control element assemblies (CEAs). RCCs are primarily designed to provide reactor shutdown reactivity control, are inserted into the guide tubes of the assembly, and are typically employed for a significant number of operating cycles. Burnup poison absorber assemblies (BPMs) are commonly referred to as burnup poison rod assemblies (BPRAs), but may have vendor specific nomenclature such as BPRA, Pyrex BPRA or WABA (wet annular burnable absorber). BPMs are used to control reactivity of fresh fuel or high reactivity fuels and are commonly used for a single cycle, but may be used for multiple cycles.

GTPDs are designed to block guide tube openings when no BPAA is employed and are commonly referred to as thimble plugs (TPs), thimble plug devices (TPDs), flow mixers (FMs),

water displacement guide tube plugs, or vibration suppressor inserts. GTPDs may be employed for multiple cycles. NSAs are primary and secondary neutron sources used during reactor startup and may be used for multiple cycles.

Integral fuel burnable absorbers, either integral to a fuel rod or as a substitution for a fuel rod, and fuel replacement rods (fueled, stainless steel, or zirconium alloy) are considered components of spent nuclear fuel (SNF) assemblies and are not considered to be nonfuel hardware .

• Certificate of Compliance No. 1031 A1-4 (continued)

Amendment No. 10

Definitions 1.1 OPERABLE A system, component, or device is OPERABLE when it is capable of performing its specified safety functions.

SPENT NUCLEAR FUEL Irradiated fuel assemblies consisting of end-fittings, grids, fuel (SNF) rods and integral hardware. Integral hardware for PWR assemblies primarily consists of guide/instrument tubes, but may contain integral fuel burnable absorbers, either integral to a fuel rod or as a fuel rod substitution, and fuel replacement rods (another fuel rod, stainless steel rod, or zirconium alloy rod).

For BWR fuel, integral hardware may consist of water rods in various shapes, inert rods, fuel rod cluster dividers, and/or fuel assembly channels (optional). PWR SNF may contain NONFUEL HARDWARE.

STORAGE CASK A STORAGE CASK is either a CONCRETE CASK or an MSO.

STORAGE OPERATIONS STORAGE OPERATIONS include all licensed activities that are performed at the ISFSI following placement of a CONCRETE CASK or MSO containing a loaded TSC at its designated storage location on the storage pad.

TRANSFER CASK TRANSFER CASK is a shielded lifting device designed to hold

• TRANSFER OPERATIONS the TSC during LOADING OPERATIONS, TRANSFER OPERATIONS, and UNLOADING OPERATIONS. Either a MAGNASTOR TRANSFER CASK (MTC)

MAGNASTOR TRANSFER CASK (PMTC) may be used.

or Passive TRANSFER OPERATIONS include all licensed activities involved in using a MAGNASTOR TRANSFER CASK (MTC) or Passive MAGNASTOR TRANSFER CASK (PMTC) to move a loaded and sealed TSC from a; CONCRETE CASK to another CONCRETE CASK or from an MSO to another MSO.

TRANSPORT OPERATIONS TRANSPORT OPERATIONS include all licensed activities performed on a loaded MAGNASTOR CONCRETE CASK or MSO when it is being moved to and from its designated location on the ISFSI. TRANSPORT OPERATIONS begin when the loaded CONCRETE CASK or MSO is placed on or lifted by a transporter and end when the CONCRETE CASK or MSO is set down in its storage position on the ISFSI pad.

(continued)

• Certificate of Compliance No. 1031 A1-5 Amendment No. 10

Definitions 1.1

• TRANSPORTABLE STORAGE CANISTER (TSC)

The TRANSPORTABLE STORAGE CANISTER (TSC) is the welded container consisting of a basket in aweldment composed of a cylindrical shell welded to a baseplate. The TSC includes a closure lid, a shield plate (optional), a closure ring, and redundant port covers at the vent and the drain ports. The closure lid is welded to the TSC shell and the closure ring is welded to the closure lid and the TSC shell. The port covers are welded to the closure lid. The TSC provides the confinement boundary for the radioactive material contained in the TSC cavity.

TSC TRANSFER FACILITY The TSC TRANSFER FACILITY includes: 1) a transfer location for the lifting and transfer of a TRANSFER CASK and placement of a TSC into or out of a CONCRETE CASK or MSO; and 2) either a stationary lift device or a mobile lifting device used to lift the TRANSFER CASK and TSC, but not licensed as part of the 10 CFR 50 facility.

UNDAMAGED FUEL SNF that can meet all fuel specific and system-related functions.

UNDAMAGED FUEL is SNF that is not DAMAGED FUEL, as defined herein, and does not contain assembly structural

• defects that adversely affect radiological and/or criticality safety .

As such, UNDAMAGED FUEL may contain:

a) BREACHED SPENT FUEL RODS (i.e, rods with minor defects up to hairline cracks or pinholes) but cannot contain grossly breached fuel rods; b) Grid, grid strap, and/or grid spring damage provided that the unsupported length of the fuel rod does not exceed 60 inches.

UNLOADING OPERATIONS UNLOADING OPERATIONS include the activities required to remove the fuel assemblies from a sealed TSC. UNLOADING OPERATIONS begin with the movement of the TSC from a CONCRETE CASK or MSO into a TRANSFER CASK in an unloading facility and end when the last fuel assembly has been removed from the TSC .

• Certificate of Compliance No. 1031 A1-6 Amendment No. 10

DESIGN FEATURES 4.0

• minimum radiation shield equivalent to 2 inches of carbon steel or stainless steel and 3.2 inches of lead gamma shielding and 2.25 inches of NS-4-FR (with 0.6 wt

% B4C and 6.0 wt % H) neutron shielding. Material and dimensions of the individual shield layers may vary provided maximum calculated radial dose rates of 1100 mrem/hr (PWR system) and 1600 mrem/hr (BWR system) are maintained on the vertical surface (not including doors or vent shielding).

4.1.4 TSC Confinement Integrity The TSC shell, bottom plate, all confinement welds, and the COMPOSITE CLOSURE LID shall be fabrication helium leak-tested in accordance with ANSI N14.5 to leaktight criterion.

The closure lid shall be helium leak-tested during fabrication (in accordance with ANSI N14.5 to leaktight criterion) if it is constructed with a lid thickness less than 9 inches (nominal).

42 Codes and Standards The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2001 Edition with Addenda through 2003, Section Ill, Subsection NB, is the governing Code for the design, material procurement, fabrication, and testing of the TSC.

The ASME Code, 2001 Edition with Addenda through 2003, Section 111, Subsection NG, is the governing Code for the design, material procurement, fabrication and testing of the spent fuel baskets.

The American Concrete Institute Specifications ACl-349 and ACl-318 govern the design and construction of the vertically reinforced concrete structure of the CONCRETE CASK, respectively and not the CONCRETE CASK lid or upper segment, if equipped.

The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2001 Edition with Addenda through 2003, Section 111, Subsection NF, is the governing Code for the design of the MSO. The applicable standards of the American Society for Testing and Materials (ASTM) govern material procurement and the American Welding Society (A'NS) D1 .1 or ASME Code Section VIII govern fabrication of the MSO.

The American National Standards Institute ANSI N14.6 (1993) and NUREG-0612 govern the TRANSFER CASK design, operation, fabrication, testing, inspection, and maintenance.

4.2.1 Alternatives to Codes, Standards, and Criteria Table 2.1-2 of the FSAR lists approved alternatives to the ASME Code for the design, procurement, fabrication, inspection and testing of MAGNASTOR SYSTEM TSCs and spent fuel baskets.

(continued)

Certificate of Compliance No. 1031 A4-2 Amendment No. 10

DESIGN FEATURES 4.0

• e. In cases where engineered features (i.e., berms, shield walls) are used to ensure that requirements of 10 CFR 72.104(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category on a site-specific basis.

f. The TRANSFER CASK shall not be operated and used when surrounding air temperature is < 0°F. This limit is NOT applicable to the stainless steel MTC or PMTC.

g. The CONCRETE CASK or MSO shall not be lifted by the lifting lugs with surrounding air temperatures< OOF.

h. Loaded CONCRETE CASK or MSO lifting height limit S24 inches.

i. The maximum design basis earthquake acceleration of 0.37g in the horizontal direction (without cask sliding) and 0.25g in the vertical direction at the ISFSI pad top surface do not result in cask tip-over.

For design basis earthquake accelerations up to and greater than 0.37g in the horizontal direction and 0.25g in the vertical direction at the ISFSI pad top surface, site-specific cask sliding is permitted with validation by the cask user that the cask does not slide off the pad and that the g-load resulting from the collision of two sliding casks remains bounded by the cask tip-over accident condition analysis presented in Chapter 3 of the FSAR.

An alternative to crediting site-specific cask sliding for design basis earthquake accelerations up to and greater than 0.37g in the horizontal direction and 0.25g in the vertical direction at the ISFSI pad top surface, the use of the MAGNASTOR system is permitted provided the ISFSI pad has bollards and the cask user validates that the cask does not overturn, g-loads resulting from the cask contacting the bollard is bounded by the cask tip-over accident condition presented in Chapter 3 of the FSAR, and the ISFSI pad and bollards are designed, fabricated and installed such that they are capable of handling the combined loading of the design basis earthquake and any contact between the bollard and cask during the design basis earthquake.

j. The storage pad for the MSO must be located within a building structure.

The building shall provide cooling to the storage pad array via natural convection and no credit shall be taken for any mechanical cooling of the building.

4.4 TSC Handling and Transfer Facility The TSC provides a leaktight confinement boundary and is evaluated for normal and off-normal handling loads. A handling and transfer facility is not required for TSC and TRANSFER CASK handling and transfer operations within a 10 CFR 50 licensed facility or for utilizing an external crane structure integral to a 10 CFR 50 licensed facility.

Certificate of Compliance No. 1031 A4-4 Amendment No. 10

DESIGN FEATURES 4.0

• f. Verify that the time to complete the transfer of the TSC from the TRANSFER CASK to the CONCRETE CASK or MSO and from a CONCRETE CASK to another CONCRETE CASK, and from an MSO to another MSO assures that the fuel cladding temperature limit of 400°C is not exceeded.

g. The surface dose rates of the CONCRETE CASK or MSO are adequate to allow proper storage and to assure consistency with the offsite dose analysis.

h. The equipment used to move the loaded CONCRETE CASK or MSO onto or from the ISFSI site contains no more than 50 gallons of fuel.

This program will control limits, surveillances, compensatory measures and appropriate completion times to assure the integrity of the fuel cladding at all times in preparation for and during LOADING OPERATIONS, UNLOADING OPERATIONS, TRANSPORT OPERATIONS, TRANSFER OPERATIONS and STORAGE OPERATIONS, as applicable.

5.3 Transport Evaluation Program A program that provides a means for evaluating transport route conditions shall be developed to ensure that the design basis impact g-load drop limits are met.

For lifting of the loaded TRANSFER CASK, CONCRETE CASK, or MSO using devices that are integral to a structure governed by 10 CFR 50 regulations, 10 CFR 50 requirements apply. This program evaluates the site-specific transport route conditions and controls, including the transport route road surface conditions; road and route hazards; security during transport; ambient temperature; and equipment operability and lift heights. The program shall also consider drop event impact g-loading and route subsurface conditions, as necessary.

5.4 ISFSI Operations Program A program shall be established to implement FSAR requirements for ISFSI operations.

At a minimum, the program shall include the following criteria to be verified and controlled:

a. Minimum CONCRETE CASK or MSO center-to-center spacing.

b. ISFSI pad parameters (i.e., thickness, concrete strength, soil modulus, reinforcement, etc.) are consistent with the FSAR analyses.

c. Maximum CONCRETE CASK or MSO lift heights ensure that the g-load limits analyzed in the FSAR are not exceeded .

• Certificate of Compliance No. 1031 AS-2 Amendment No. 10

DESIGN FEATURES 4.0

• d. For storage operations using the MSO, thermal evaluations must be performed on the cask array within the building to assure that system maximum component temperatures, in particular fuel clad temperature, remain within allowable limits. In addition, the building shall be evaluated under 10 CFR 72.212 requirements to ensure storage within the building structure does not create a new credible accident not presented in the FSAR.

5.5 Radiation Protection Program 5.5.1 Each cask user shall ensure that the 10 CFR 50 radiation protection program appropriately addresses dry storage cask loading and unloading, and ISFSI operations, including transport of the loaded CONCRETE CASK or MSO outside of facilities governed by 10 CFR 50 as applicable.

The radiation protection program shall include appropriate controls and monitoring for direct radiation and surface contamination, ensuring compliance with applicable regulations, and implementing actions to maintain personnel occupational exposures ALARA. The actions and criteria to be included in the program are provided as follows.

5.5.2 Each user shall perform a written evaluation of the TRANSFER CASK and associated operations, 30 days prior to first use, to verify that it meets public, occupational, and ALARA requirements (including shielding design

• and dose characteristics) in 10 CFR Part 20, and that it is consistent with the program elements of each user's radiation protection program. The evaluation should consider both normal operations and unanticipated occurrences, such as handling equipment malfunctions, during use of the transfer cask.

5.5.3 As part of the evaluation pursuant to 10 CFR 72.212(b)(5)(iii), the licensee shall perform an analysis to confirm that the dose limits of 10 CFR 72.104(a) will be satisfied under actual site conditions and ISFSI configuration, considering the number of casks to be deployed and the cask contents.

5.5.4 Each user shall establish limits on the surface contamination of the CONCRETE CASK, MSO, TSC and TRANSFER CASK, and procedures for the verification of meeting the established limits prior to removal of the components from the 10 CFR 50 structure. Surface contamination limits for the TSC prior to placement in STORAGE OPERATIONS shall meet the limits established in LCO 3.3.2.

5.6 Deleted (continued)

• Certificate of Compliance No. 1031 A5-3 Amendment No. 10

Enclosure 5 to ED202 l 0025 Page 1 of 2 Enclosure 5 Supporting Calculations for

• MAGNASTOR FSAR RAJ Responses to Amendment 10 Revision 2 lA (Docket No 72-1031)

NAC International February 2021

Enclosure 5 to ED202 l 0025 Page2 of 2

• List of Calculations:

30082-2604 Revision 2 30082-2605 Revision 1 CALCULATIONS ARE PROPRIETARY AND WITHHELD IN TIIEIR ENTIRETY PER 10 CFR 2.390

Enclosure 6 to ED202 l 0025 Page 1 of 1 Enclosure 6 FSAR Changed Pages and LOEP for

• MAGNASTOR FSAR RAI Responses to Amendment 10 Revision 21A (Docket No 72-1031)

NAC International February 2021

MAGNASTOR (Modular ~dvanced .§eneration Nuclear ~II-purpose STORage)

FINAL SAFETY

• ANALYSIS REPORT NON-PROPRIETARY VERSION

• A NAC INTERNATIONAL A1lsnla Caporale i-i-lqua-1era 3930 East Jones Bndge Road, Norcrosa, Georgm 30092 USA Phone 770-447-1144, Fax 770-447-1797, www nacrnJ com

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21A

• Chapter 1 List of Effective Pages Page 1-i ................................. Revision 19C Page 1-1 ................................ Revision 19C Page 2.6-1 ................................. Revision 0 Page 2.6-2 ............................. Revision l 9C Page 1.1-1 ............................. Revision 19C Chapter 3 Page 1.1-2 thru 1.1-3 ................. Revision 5 Page 3-i ..................................... Revision 6 Page 1.1-4 thru 1.1-6 ............. Revision 19C Page 3-ii ................................ Revision 19C Page 1.2-1 ............................. Revision 19C Page 3-iii ................................... Revision 9 Page 1.2-2 ................................. Revision 5 Page 3-iv ................................... Revision 5 Page 1.3-1 ............................. Revision 19C Page 3-v thru 3-vi ...................... Revision 9 Page 1.3-2 thru 1.3-3 ................. Revision 5 Page 3-vii ............................. Revision 21A Page 1.3-4 thru 1.3-22 ........... Revision 19C Page 3-viii thru 3-ix .............. Revision 19C Page 1.3-23 .......................... Revision 21A Page 3-x ............................... Revision 21A Page 1.4-1 ................................. Revision 7 Page 3-1 .................................... Revision 0 Page 1.5-1 ............................. Revision 19C Page 3.1-1 thru 3.1-6 ............. Revision 19C Page 1.6-1 ............................. Revision 19C Page 3.2-1 thru 3.2-5 ............. Revision 19C Page 1.6-2 ................................. Revision 0 Page 3.3-1 ................................. Revision 0 Page 1. 7-1 ................................. Revision 0 Page 3.4-1 thru 3.4-2 ............. Revision 19C Page 1.7-2 ............................ Revision 21A Page 3.4-3 ................................. Revision 6 Page 1.8-1 thru 1.8-2 ............ Revision 21A Page 3.4-4 ................................. Revision 1 Page 3.4-5 ................................. Revision 5

• 26 drawings (see Section 1.8)

Chapter 2 Page 2-i ..................................... Revision 9 Page 2-ii ................................ Revision 19C Page 2-1 .................................... Revision 5 Page 3.4-6 thru 3.4-14 ............... Revision 3 Page 3.4-15 ............................... Revision 9 Page 3.4-16 thru 3.4-42 ............. Revision 3 Page 3.4-43 thru 3.4-63 ............. Revision 9 Page 3.5-1 ............................. Revision 19C Page 3.5-2 thru 3.5-4 ................. Revision 9 Page 2.1-1 ................................. Revision 5 Page 3.5-5 ................................. Revision 6 Page 2.1-2 ............................. Revision 19C Page 3.5-6 ............................. Revision 19C Page 2.1-3 ................................. Revision 5 Page 3.5-7 thru 3.5-9 ................. Revision 6 Page 2.1-4 ................................. Revision 8 Page 3.5-10 ........................... Revision 19C Page 2.1-5 ................................. Revision 5 Page 3.5-11 thru 3.5-13 ............. Revision 6 Page 2.2-1 ................................. Revision 5 Page 3.5-14 ........................... Revision 19C Page 2.2-2 thru 2.2-3 ................. Revision 9 Page 3.5-15 ............................... Revision 6 Page 2.2-4 thru 2.2-5 ................. Revision 0 Page 3.5-16 thru 3.5-17 ............. Revision 6 Page 2.2-6 ................................. Revision 5 Page 3.5-18 ........................... Revision 19C Page 2.2-7 ................................. Revision 9 Page 3.5-19 ............................... Revision 6 Page 2.2-8 ................................. Revision 6 Page 3.5-20 ........................... Revision 19C Page 2.3-1 thru 2.3-10 ........... Revision 19C Page 3.5-21 thru 3.5-26 ............. Revision 6 Page 2.4-1 ................................. Revision 0 Page 3.5-27 thru 3.5-30 ............. Revision 8 Page 2.4-2 ................................. Revision 2 Page 3.6-1 thru 3.6-2 ............. Revision 19C Page 2.4-3 ............................. Revision 19C Page 3.6-3 thru 3.6-4 ................. Revision 9 Page 2.4-4 ................................. Revision 5 Page 3.6-5 thru 3.6-19 ............... Revision 6 Page 2.4-5 thru 2.4-7 ............. Revision 19C Page 3.7-1 ............................. Revision 19C

• Page 2.5-1 ............................. Revision 19C Page 3.7-2 ................................. Revision 9 Page 1 of 7

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21A List of Effective Pages (cont'd)

Page 3.7-3 thru 3.7-5 ............. Revision 19C Page 3.7-6 ................................. Revision 6 Page 3.7-7 ............................. Revision 19C Page Page Page 3.10.2-1 thru 3.10.2-26 ..... Revision 4 3.10.3-1 thru 3.10.3-2 ....... Revision 8 3.10.3-3 ............................ Revision 0 Page 3.7-8 thru 3.7-9 ................. Revision 6 Page 3.10.3-4 thru 3.10.3-23 ..... Revision 1 Page 3.7-10 ........................... Revision 19C Page 3.10.3-24 .......................... Revision 8 Page 3.7-11 thru 3.7-13 ............. Revision 6 Page 3.10.3-25 thru 3.10.3-38 ... Revision 1 Page 3.7-14 ........................... Revision 19C Page 3.10.4-1 thru 3.10.4-2 ....... Revision 1 Page 3.7-15 ............................... Revision 6 Page 3.10.4-3 thru 3.10.4-9 ....... Revision 0 Page 3.7-16 ........................... Revision 19C Page 3.10.4-10 .......................... Revision 1 Page 3.7-17 thru 3.7-21 ............. Revision 6 Page 3.10.4-11 thru 3.10.4-14 ... Revision 0 Page 3.7-22 ........................... Revision 19C Page 3.10.5-1 ............................ Revision 1 Page 3.7-23 thru 3.7-25 ............. Revision 6 Page 3.10.5-2 ............................ Revision 2 Page 3.7-26 ........................... Revision 19C Page 3.10.5-3 thru 3.10.5-9 ....... Revision 9 Page 3.7-27 ............................... Revision 6 Page 3.10.6-1 thru 3.10.6-2 ....... Revision 5 Page 3.7-28 thru 3.7-30 ......... Revision 19C Page 3.10.6-3 ............................ Revision 4 Page 3.7-31 ............................... Revision 6 Page 3.10.6-4 thru 3.10.6-6 ....... Revision 5 Page 3.7-32 ........................... Revision 19C Page 3.10.6-7 thru 3.10.6-10 ..... Revision 4 Page 3.7-33 ............................... Revision 6 Page 3.10.6-11 thru 3.10.6-13 ... Revision 2 Page 3.7-34 ........................... Revision 19C Page 3.10.6.14 thru 3.10.6-16 ... Revision 4 Page 3.7-35 thru 3.7-37 ............. Revision 6 Page 3.10.6-17 thru 3.10.6-18 ... Revision 2 Page 3.7-38 ........................... Revision 19C Page 3.7-39 thru 3.7-46 ............. Revision 6 Page 3.7-47 thru 3.7-56 ......... Revision 19C Page 3.7-57 thru 3.7-58 ............. Revision 6 Page 3.7-59 thru 3.7-61 ............. Revision 8 Page 3. 7-62 thru 3. 7-64 ............. Revision 6 Page Page Page Page Page Page 3.10.6-19 .......................... Revision 4 3.10.6-20 thru 3.10.6-21... Revision 2 3.10.6-22 thru 3.10.6-34 ... Revision 4 3.10.7-1 thru 3.10.7-2 ....... Revision 0 3.10.8-1 ............................ Revision 4 3.10.8-2 ............................ Revision 2 Page 3.7-65 ............................... Revision 8 Page 3.10.8-3 thru 3.10.8-8 ....... Revision 0 Page 3.7-66 ............................... Revision 6 Page 3.10.9-1 ............................ Revision 6 Page 3.7-67 thru 3.7-68 ............. Revision 8 Page 3.10.9-2 ............................ Revision 4 Page 3.7-69 ............................... Revision 6 Page 3.10.9-3 thru 3.10.9-11.. ... Revision 0 Page 3.7-70 thru 3.7-72 ............. Revision 8 Page 3.10.10-1 thru 3.10.10-8 ... Revision 5 Page 3.7-72 thru 3.7-81.. ........... Revision 6 Page 3.11-1 ........................... Revision 19C Page 3.7-73 thru 3.7-79 ............. Revision 6 Page 3.11.1-1 thru Page 3.7-80 ............................... Revision 8 3.11.1-7 ..................... Revision 19C Page 3.7-81 ............................... Revision 6 Page 3 .11.2-1 thru Page 3.8-1 thru 3.8-10 ............... Revision 0 3 .11.2-4 ..................... Revision 19C Page 3.9-1 ................................. Revision 0 Page 3.11.3-1 thru Page 3.9-2 ................................. Revision 1 3 .11.3-3 ..................... Revision l 9C Page 3.9-3 ................................. Revision 9 Page 3.11.4-1 thru Page 3.10-1 ............................... Revision 0 3.11 .4-14 ................... Revision 19C Page 3.10.1-1 ............................ Revision 5 Page 3 .11.4-15 thru Page 3.10.1-2 thru 3.10.1-4 ....... Revision 2 3.11.4-23 .................. Revision 21A Page 3.10.1-5 ............................ Revision 1 Page 3.10.1-6 thru 3.10.1-32 ..... Revision 5 Page 2 of7

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21A

• Chapter 4 List of Effective Pages (cont'd)

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• Page 4.9-1 ................................. Revision 9 Page 5 .5-6 ................................. Revision 0 Page 3 of7

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21A List of Effective Pages (cont'd)

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MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21A

• List of Effective Pages {cont'd)

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• 5.12.4-13 .................. Revision 21A Page 5.12.5-1 thru 5.12.5-2 ..................... Revision 19C Page 5.12.6-1 ........................ Revision 19C Page 5.12.7-1 ........................ Revision 19C Page 5.12.8-1 thru Page 6.7.5-2 thru 6.7.5-7 ........... Revision 0 Page 6.7.6-1 .............................. Revision 7 Page 6.7.6-2 thru 6.7.6-3 ........... Revision 2 Page 6.7.6-4 .............................. Revision 7 Page 6.7.6-5 thru 6.7.6-6 ........... Revision 2 Page 6.7.6-7 .............................. Revision 7 5.12.8-7 ..................... Revision 19C Page 6.7.6-8 thru 6.7.6-22 ......... Revision 2 Page 6.7.6-23 thru 6.7.6-24 ....... Revision 7 Chapter 6 Page 6. 7 .6-25 thru 6. 7 .6-27 ....... Revision 2 Page 6-i thru 6-vi ...................... Revision 5 Page 6.7.6-28 ............................ Revision 7 Page 6-1 .................................... Revision 0 Page 6.7.7-1 thru 6.7.7-27 ......... Revision 0 Page 6.1-1 thru 6.1-3 ................. Revision 9 Page 6.7.8-1 thru 6.7.8-3 ........... Revision 5 Page 6.1-4 thru 6.1-6 ................. Revision 7 Page 6.7.8-4 .............................. Revision 7 Page 6.1-7 thru 6.1-10 ............... Revision 5 Page 6.7.8-5 thru 6.7.8-80 ......... Revision 5 Page 6.1-11 ............................... Revision 7 Page 6.7.8-81 thru 6.7.8-83 ....... Revision 7 Page 6.1-12 ............................... Revision 5 Page 6.7.8-84 ............................ Revision 5 Page 6.1-13 ............................... Revision 7 Page 6.7.8-85 thru 6.7.8-87 ....... Revision 7 Page 6.2-1 ................................. Revision 5 Page 6.7.8-88 thru 6.7.8-89 ....... Revision 5 Page 6.2-2 thru 6.2-5 ................. Revision 0 Page 6.7.8-90 ............................ Revision 7 Page 6.3-1 ................................. Revision 5 Page 6.3-2 ................................. Revision 6 Chapter 7 Page 6.3-3 ................................. Revision 5 Page 7-i .................................... Revision 5 Page 6.3-4 thru 6.3-8 ................. Revision 0 Page 7-1 .................................... Revision 0

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MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21A List of Effective Pages (cont'd)

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5 2

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MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21A

• Chapter 12 List of Effective Pages (cont'd)

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• Page 7 of7

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Table 1.3-5 MSO Fabrication Specification Summary Materials

• All steel materials shafl be of the material as specified in the referenced drawings .

• NS-3 non-structural biological shielding material shall be governed by the referenced drawings.

Welding

• Welds shall be in accordance with the referenced drawings.

• Filler metals shall be appropriate ASME Code materials.

• Welders and welding operators shall be qualified in accordance with ASME Code Section IX [12] or ANSI/A WS D1.1 [25].

• Welding procedures shall be written and qualified in accordance with ASME Code Section IX or ANSI/A WS D 1.1.

• Personnel performing weld examinations shall be qualified in accordance with the NAC International Quality Assurance Program and SNT-TC-lA [13].

• Weld inspection and examination requirements and acceptance criteria are specified in Chapter 10.

Fabrication

• Cutting, welding, and forming shall be in accordance with ASME Code,Section VIII

[26] or ANSI/AWS Dl.1.

• Surfaces shall be cleaned to a surface cleanness classification D, or better, as defined in ANSI N45.2.1 [14].

• Fabrication tolerances shall meet the requirements of the referenced drawings after fabrication.

Packaging

• Packaging and shipping shall be in accordance with ANSI N45.2.2 [15].

Quality Assurance

• The MSO shall be fabricated under a quality assurance program that meets IO CFR 72, Subpart G, and 10 CFR 71, Subpart H.

• NAC International 1.3-23

MAGNASTOR System FSAR February 2009 Docket No. 72-1031 Revision 0 1.7 References

1. 10 CPR 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste and Reactor-Related Greater Than Class C Waste," Code of Federal Regulations, US Nuclear Regulatory Commission, Washington, DC.

2. NUREG-1536, "Standard Review Plan for Dry Cask Storage Systems," US Nuclear Regulatory Commission, Washington, DC, January 1997.

3. 10 CFR 71, Packaging and Transportation of Radioactive Materials," Code of Federal Regulations, US Nuclear Regulatory Commission, Washington, DC.

4. Regulatory Guide 3.61, "Standard Format and Content for a Topical Safety Analysis Report for a Spent Fuel Dry Concrete Cask," US Nuclear Regulatory Commission, Washington, DC, February 1989.

5. ISG-15, "Materials Evaluation," US Nuclear Regulatory Commission, Washington, DC, Revision 0, January 10, 2001.

6. ANSI/ANS 57 .9-1992, "Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type)," American Nuclear Society, La Grange Park, IL, May 1992.

7. ACI 318-95, Building Code Requirements for Structural Concrete," American Concrete Institute, Farmington Hills, MI .

8. ASME Boiler and Pressure Vessel Code,Section III, Subsection NB, "Class I Components,"

American Society of Mechanical Engineers, New York, NY, 2001 Edition with 2003 Addenda.

9. ASME Boiler and Pressure Vessel Code,Section III, Subsection NG, "Core Support Structures," American Society of Mechanical Engineers, New York, NY, 2001 Edition with 2003 Addenda.

10. ISG-11, "Cladding Considerations for the Transport and Storage of Spent Fuel," US Nuclear Regulatory Commission, Washington, DC, Revision 3, November 17, 2003.

11. ANSI Nl4.6-1993, "American National Standard for Radioactive Materials- Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4,500 kg) or More," American National Standards Institute, Inc., Washington, DC, June 1993.

12. ASME Boiler and Pressure Vessel Code,Section IX, "Qualification Standards for Welding and Brazing Procedures, Welders, Brazers, and Welding and Brazing Operators," American Society of Mechanical Engineers, New York, NY, 2001 Edition with 2003 Addenda.

13. Recommended Practice No. SNT-TC-lA, "Personnel Qualification and Certification in Nondestructive Testing," The American Society for Nondestructive Testing, Inc., Columbus OH, edition as invoked by the applicable ASME Code.

NAC International 1.7-1

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A

14. ANSI N45.2.l-1973, "Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants," American National Standards Institute, Inc.,

Washington, DC.

15. ANSI N45 .2.2-1978, "Packaging, Shipping, Receiving, Storage, and Handling of Items for Nuclear Power Plants," American National Standards Institute, Inc., Washington, DC.

16. ASTM C94a, "Standard Specification for Ready-Mixed Concrete," American Society for Testing and Materials, West Conshohocken, PA.

17. ASTM Cl5C>8', "Standard Specification for Portland Cement," American Society for Testing and Materials, West Conshohocken, PA.

18. ASTM C33a, "Standard Specification for Concrete Aggregates," American Society for Testing and Materials, West Conshohocken, PA.

19. ASTM C637\ "Specification for Aggregates for Radiation-Shielding Concrete," American Society for Testing and Materials, West Conshohocken, PA.

20. ASTM C494\ "Standard Specification for Chemical Admixtures for Concrete," American Society for Testing and Materials, West Conshohocken, PA.

21. ASTM C618\ "Specification for Fly Ash and Raw or Calcined Natural Pozzolan for Use as a Mineral Admixture in Portland Cement Concrete," American Society for Testing and Materials, West Conshohocken, PA.

22. ASTM Cl 72\ "Standard Practice for Sampling Freshly Mixed Concrete," American Society for Testing and Materials, West Conshohocken, PA.

23. ASTM C31 a, Method of Making and Curing Concrete Test Specimens in the Field,"

American Society for Testing and Materials, West Conshohocken, PA.

24. ASTM C39\ "Standard Test Method for Compressive Strength of Cylindrical Concrete Specimens," American Society for Testing and Materials, West Conshohocken, PA.

25. ANSI/AWS Dl.1, "Structural Welding Code - Steel," American National Standards Institute, Inc., Washington, DC, 1998.

26. ASME Boiler and Pressure Vessel Code,Section VIII, "Rules for Construction of Pressure Vessels", American Society of Mechanical Engineers, New York, NY, 2001 Edition with 2003 Addenda.

• Current edition of testing standards at time of fabrication/construction is to be used.

NAC International 1.7-2

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A 1.8 License Drawings This section presents the list of License Drawings for MAGNASTOR.

Drawing Revision Number Title No.

71160-551 Fuel Tube Assembly, MAGNASTOR - 37 PWR 10NP*

71160-556 Assembly, MAGNASTOR Transfer Cask (MTC), Stainless Steel 4 71160-560 Assembly, Standard Transfer Cask, MAGNASTOR 2 71160-561 Structure, Weldment, Concrete Cask, MAGNASTOR 9 71160-562 Reinforcing Bar and Concrete Placement, Concrete Cask, MAGNASTOR 9 71160-565 Body, Lid and Details, Metal Storage Overpack (MSO), MAGNASTOR 0NP*

71160-567 Loaded MSO Metal Storage Overpack (MSO), MAGNASTOR 0NP" 71160-571 Details, Neutron Absorber, Retainer, MAGNASTOR - 37 PWR 8 71160-572 Details, Neutron Absorber, Retainer, MAGNASTOR - 87 BWR BNP*

71160-574 Basket Support Weldments, MAGNASTOR - 37 PWR 6 71160-575 Basket Assembly, MAGNASTOR - 37 PWR 11NP*

• 71160-581 71160-584 71160-585 71160-590 Shell Weldment, TSC, MAGNASTOR Details, TSC, MAGNASTOR TSC Assembly, MAGNASTOR Loaded Concrete Cask, MAGNASTQR 5

9 12 8

71160-591 Fuel Tube Assembly, MAGNASTOR - 87 BWR BNP*

71160-598 Basket Support Weldments, MAGNASTOR - 87 BWR ?NP*

71160-599 Basket Assembly, MAGNASTOR - 87 BWR BNP*

71160-600 Basket Assembly, MAGNASTOR - 82 BWR 5NP" 71160-601 Damaged Fuel Can (DFC), Assembly, MAGNASTOR 0 71160-602 Damaged Fuel Can (DFC), Details, MAGNASTOR 1 71160-656 Cask Body Weldment, Passive Transfer Cask, MAGNASTOR 1NP*

71160-657 Passive Transfer Cask, Assembly, MAGNASTOR 1NP*

71160-671 Details, Neutron Absorber, Retainer, For OF Comer Weldment, 0 MAGNASTOR - 37 PWR 71160-673 Damaged Fuel Can (DFC), Spacer, MAGNASTOR 0 71160-674 OF Comer Weldment, MAGNASTOR 3NP*

71160-675 OF Basket Assembly, 37 Assembly PWR, MAGNASTOR 3NP*

71160-681 OF, Shell Weldment, TSC, MAGNASTOR 1 NAC International 1.8-1

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Drawing Revision Number Title No.

71160-684 Details, DF Closure Lid, MAGNASTOR 2 71160-685 DF, TSC Assembly, MAGNASTOR 6

• Proprietary drawing replaced by nonproprietary version.

NAC International 1.8-2

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A

• Figure 3.11.1-1 Figure 3.11.4-1 Figure 3.11.4-2 Pedestal Finite Element Model .............................................................. 3 .11.1-7 Half-Symmetry Finite Element Model for MSO 24-inch Drop Analysis ................................................................................................ 3 .11.4-18 Acceleration Time History of the Upper-Bound TSC Weight inch Drop ............................................................................................. 3.11.4-19 Figure 3.11.4-3 Acceleration Time History of the Lower-Bound TSC Weight inch Drop ............................................................................................. 3.11.4-20 Figure 3 .11.4-4 Half-Symmetry Finite Element Model for MSO Tip-over Analysis ... 3.11.4-21 Figure 3 .11.4-5 Acceleration Time Histories at Top of the Basket and TSC Lid for MSO Tip-Over Event ........................................................................... 3.44.4-22

• NAC International 3-vii

MAGNASTOR System FSAR November 2019 Docket No. 72-1031 Revision 19C List of Tables Table 3.2.1-1 MAGNASTOR Storage Weight and Center of Gravity Summary ............. 3.2-2 Table 3.2.1-2 MAGNASTOR Storage Weight and Center of Gravity Summary-MSO ............................................................................................................ 3.2-5 Table 3.4.3-1 Stress Intensity for MTCl Trunnions and Top Ring ................................ 3.4-27 Table 3.4.3-2 Stress Intensity for MTCl Shells and Bottom Ring ................................. 3.4-27 Table 3.4.3-3 Stress Intensity for MTC2 Trunnions and Top Ring ................................ 3.4-41 Table 3.4.3-4 Stress Intensity for MTC2 Shells and Bottom Ring ................................. 3 .4-41 Table 3.4.3-5 Stress Intensity for Transfer Cask Retaining Ring ................................... 3.4-42 Table 3.5.1-1 TSC Thermal Stress, Q ............................................................................... 3.5-7 Table 3.5.1-2 TSC Normal Conditions, Pm Stresses ......................................................... 3.5-7 Table 3.5.1-3 TSC Normal Conditions, Pm+ Pb Stresses ................................................. 3.5-7 Table 3.5.1-4 TSC Normal Conditions, P + Q Stresses .................................................... 3.5-7 Table 3.5.3-1 Concrete Cask Vertical Stress Summary- Outer Surface, psi ................. 3.5-30 Table 3.5.3-2 Concrete Cask Vertical Stress Summary- Inner Surface, psi.. ................ 3.5-30 Table 3.5.3-3 Concrete Cask Circumferential Stress Summary- Inner Surface, psi ..... 3.5-30 Table 3.6.1-1 TSC Off-Normal Events, Pm Stresses ......................................................... 3.6-5 Table 3.6.1-2 TSC Off-Normal Events, Pm+ Pb Stresses ................................................. 3.6-5 Table 3.6.1-3 TSC Off-Normal Events, P + Q Stresses .................................................... 3.6-5 Table 3.7.1-1 TSC Accident Events, Pm Stresses .............................................................. 3.7-6 Table 3.7.1-2 Table 3.7.2-1 Table 3.7.2-2 Table 3.7.2-3 TSC Accident Events, Pm+ Pb Stresses ...................................................... 3.7-6 PWR Fuel Tube Stress Intensity - Storage Cask Tip-over Accident, 0° Orientation ............................................................................................ 3.7-47 PWR Fuel Tube Stress Intensity - Storage Cask Tip-over Accident, 45° Orientation .......................................................................................... 3.7-47 PWR Comer Weldment Mounting Plate Stress Intensity- Storage Cask Tip-over Accident, 0° Orientation ................................................... 3.7-48 Table 3.7.2-4 PWR Comer Weldment Mounting Plate Stress Intensity- Storage Cask Tip-over Accident, 45° Orientation ................................................. 3.7-48 Table 3.7.2-5 PWR Corner Support Bar Stress Intensity- Storage Cask Tip-over Accident, 0° Orientation ........................................................................... 3.7-49 Table 3.7.2-6 PWR Comer Support Bar Stress Intensity- Storage Cask Tip-over Accident, 45° Orientation ......................................................................... 3.7-49 Table 3.7.2-7 PWR Side Weldment Stress Intensity- Storage Cask Tip-over Accident, 0° Orientation ........................................................................... 3.7-50 Table 3.7.2-8 PWR Side Weldment Stress Intensity- Storage Cask Tip-over Accident, 45° Orientation ......................................................................... 3.7-50 Table 3.7.2-9 PWR Fuel Tube Stress Intensity- Storage Cask Tip-over Accident, Basket with Damaged Fuel Cans, 0° Orientation ..................................... 3.4-51 Table 3.7.2-10 PWR Fuel Tube Stress Intensity- Storage Cask Tip-over Accident, Basket with Damaged Fuel Cans, 45° Orientation ................................... 3.7-51 Table 3.7.2-11 PWR Corner Weldment Plate Stress Intensity- Storage Cask Tip-over Accident, Basket with Damaged Fuel Cans, 0° Orientation ............. 3.7-52 NAC International 3-viil

MAGNASTOR System FSAR November 2019 Docket No. 72-1031 Revision 19C List of Tables (cont'd)

Table 3.7.2-12 PWR Comer Weldment Plate Stress Intensity - Storage Cask Tip-over Accident, Basket with Damaged Fuel Cans, 45° Orientation ........... 3.7-52 Table 3.7.2-13 PWR Comer Weldment Ridge Gussets Stress Intensity- Storage Cask Tip-over Accident, Basket with Damaged Fuel Cans, 0° Orientation ................................................................................................ 3.7-53 Table 3.7.2-14 PWR Comer Weldment Ridge Gussets Stress Intensity- Storage Cask Tip-over Accident, Basket with Damaged Fuel Cans, 45° Orientation ................................................................................................ 3.7-53 Table 3.7.2-15 PWR Side Weldment Stress Intensity - Storage Cask Tip-over Accident, Basket with Damaged Fuel Cans, 0° Orientation ..................... 3.7-54 Table 3.7.2-16 PWR Side Weldment Stress Intensity - Storage Cask Tip-over Accident, Basket with Damaged Fuel Cans, 45° Orientation ................... 3.7-54 Table 3.7.2-17 BWR Fuel Tube Stress Intensity- Storage Cask Tip-over Accident.. ..... 3.7-55 Table 3.7.2-18 BWR Comer Support Welment Stress Intensity - Storage Cask Tip-over Accident ............................................................................................ 3.7-55 Table 3.7.2-19 BWR Side Support Weldment Stress Intensity- Storage Cask Tip-over Accident ............................................................................................ 3.7-56 Table 3.7.3-1 Concrete Cask Vertical Stress Summary - Inner Surface, psi .................. 3. 7-80 Table 3.7.3-2 Concrete Cask Circumferential Stress Summary- Inner Surface, psi ..... 3.7-80

• Table 3.7.3-3 Table 3.7.3-4 Table 3.10.3-1 Table 3.10.3-2 Table 3.10.3-3 Table 3.10.3-4 Basket Modal Frequency for Concrete Cask Tip-over ............................. 3.7-81 DLF and Amplified Accelerations for Concrete Cask Tip-over ............... 3.7-81 TSC1/TSC2 Normal Pressure plus Handling, Pm, ksi ........................... 3.10.3-7 TSC1/TSC2 Normal Pressure plus Handling, Pm+ Pb, ksi .................... 3.10.3-8 TSC1/fSC2 Normal Pressure plus Handling, P + Q, ksi ...................... 3.10.3-9 TSC1/TSC2 Normal Pressure, Pm, ksi ................................................. 3.10.3-10 Table 3.10.3-5 TSC l!TSC2 Normal Pressure, Pm + Pb, ksi ......................................... 3 .10.3-11 Table 3.10.3-6 TSC1/TSC2 Thermal Stresses, Q, ksi .................................................. 3.10.3-12 Table 3.10.3-7 TSC1/TSC2 Off-Normal Pressure plus Handling, Pm, ksi.. ................. 3.10.3-13 Table 3.10.3-8 TSCl/fSC2 Off-Normal Pressure plus Handling, Pm+ Pb, ksi ........... 3.10.3-14 Table 3.10.3-9 TSC1/TSC2 Off-Normal Pressure plus Handling, P + Q, ksi ............. 3.10.3-15 Table 3.10.3-10 TSC1/TSC2 Normal Pressure plus Off-Normal Handling, Pm, ksi ..... 3.10.3-16 Table 3.10.3-11 TSC1/fSC2 Normal Pressure plus Off-Normal Handling, Pm+ Pb, ksi ........................................................................................... 3.10.3-17 Table 3.10.3-12 TSC1/fSC2 Normal Pressure plus 24-inch Drop, Pm, ksi ................... 3.10.3-18 Table 3.10.3-13 TSC1/fSC2 Normal Pressure plus 24-inch Drop, Pm+ Pb, ksi ........... 3.10.3-19 Table 3.10.3-14 TSC1/TSC2 Accident Pressure plus Dead Weight, Pm, ksi ................. 3.10.3-20 Table 3.10.3-15 TSC1/TSC2 Accident Pressure plus Dead Weight, Pm+ Pb, ksi ......... 3.10.3-21 Table 3.10.3-16 TSC1/TSC2 Tip-Over plus Normal Pressure, Pm, ksi ......................... 3.10.3-22 Table 3.10.3-17 TSC1/fSC2 Tip-Over plus Normal Pressure, Pm+Pb, ksi .................... 3.10.3-23 Table 3.10.3-18 TSC3/TSC4 Normal Pressure plus Handling, Pm, ksi ......................... 3.10.3-29 Table 3.10.3-19 TSC3/TSC4 Normal Pressure plus Handling, Pm+ Pb, ksi .................. 3.10.3-29 Table 3.10.3-20 TSC3/fSC4 Normal Pressure plus Handling, P + Q, ksi .................... 3.10.3-29

• Table 3.10.3-21 TSC3/TSC4 Normal Pressure, Pm, ksi ................................................. 3.10.3-30 NAC International 3-ix

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A List of Tables (cont'd)

Table 3.10.3-22 TSC3/fSC4 Normal Pressure, Pm+ Pb. ksi ......................................... 3.10.3-30 Table 3.10.3-23 TSC3/fSC4 Thermal Stresses, Q, ksi .................................................. 3.10.3-31 Table 3.10.3-24 TSC3/fSC4 Off-Normal Pressure plus Handling, Pm, ksi ................... 3.10.3-32 Table 3.10.3-25 TSC3/fSC4 Off-Normal Pressure plus Handling, Pm+ Pb, ksi ........... 3.10.3-32 Table 3.10.3-26 TSC3/fSC4 Off-Normal Pressure plus Handling, P + Q, ksi ............. 3.10.3-32 Table 3.10.3-27 TSC3/fSC4 Normal Pressure plus Off-Normal Handling, Pm, ksi ..... 3.10.3-33 Table 3.10.3-28 TSC3/fSC4 Normal Pressure plus Off-Normal Handling, Pm+ Pb, ksi ........................................................................................... 3.10.3-33 Table 3.10.3-29 TSC3/fSC4 Normal Pressure plus 24-inch Drop, Pm, ksi ................... 3.10.3-34 Table 3.10.3-30 TSC3/fSC4 Normal Pressure plus 24-inch Drop, Pm+ Pb, ksi ........... 3.10.3-34 Table 3.10.3-31 TSC3/TSC4 Accident Pressure plus Dead Weight, Pm, ksi ................. 3.10.3-35 Table 3.10.3-32 TSC3/TSC4 Accident Pressure plus Dead Weight, Pm+ Pb, ksi ......... 3.10.3-35 Table 3.10.3-33 TSC3/TSC4 Tip-Over plus Normal Pressure, Pm, ksi ......................... 3.10.3-36 Table 3.10.3-34 TSC3/TSC4 Tip-Over plus Normal Pressure, Pm+Pb, ksi.. .................. 3.10.3-36 Table 3.10.3-35 TSC3/TSC4 Shield Plate Attachment Bolt Stress Summary, ksi ........ 3.10.3-37 Table 3.10.3-36 TSC3/TSC4 Shield Plate Maximum Tensile Stresses, ksi ................... 3.10.3-38 Table 3.10.6-1 Load Cases Evaluated for PWR Fuel Basket Stability ........................ 3.10.6-31 Table 3.10.6-2 Load Cases Evaluated for BWR Fuel Basket Stability ........................ 3 .10.6-32 Table 3.10.6-3 Summary of Maximum Gap Changes at Pin-Slot Connections for Table 3.10.6-4 Table 3.10.9-1 Table 3.10.9-2 PWR Basket ......................................................................................... 3.10.6-33 Summary of Maximum Gap Changes at Pin-Slot Connections for BWR Basket. ........................................................................................ 3.10.6-34 Canister Shell Displacements Used as Boundary Conditions for the LS-DYNA Models for PWR Basket Stability Evaluation ................... 3.10.9-10 Canister Shell Displacements Used as Boundary Conditions for the LS-DYNA Models for BWR Basket Stability Evaluation .................. 3.10.9-11 Table 3 .11.2-1 MSO Inner Liner Vertical Stress Summary- Outer Surface, psi .......... 3.11.2-4 Table 3.11.2-2 MSO Inner Liner Vertical Stress Summary - Inner Surface, psi .......... 3 .11.2-4 Table 3.11.2-3 MSO Outer Liner Vertical Stress Summary - Outer Surface, psi ......... 3 .11.2-4 Table 3.11.2-4 MSO Outer Liner Vertical Stress Summary - Inner Surface, psi .......... 3 .11.2-4 Table 3 .11.3-1 Inner Liner Vertical Stress Summary - Outer Surface, psi ................... 3.11.3-3 Table 3.11.3-2 Inner Liner Vertical Stress Summary - Inner Surface, psi .................... 3.11.3-3 Table 3.11.4-1 Inner Liner Vertical Stress Summary- Outer Surface, psi ................. 3.11.4-23 Table 3.11.4-2 Inner Liner Vertical Stress Summary - Inner Surface, psi .................. 3 .11.4-23 Table 3.11.4-3 Outer Liner Vertical Stress Summary- Outer Surface, psi ................. 3.11.4-23 Table 3.11.4-3 Outer Liner Vertical Stress Summary - Inner Surface, psi ................... 3.11.4-23 NAC International 3-x

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A ODmner = 92.1 in IDmner = 79.5 in Pedestal Crush Evaluation Upon a bottom-end impact of the MSO, the TSC produces a force on the pedestal (base weldment) located near the bottom of the cask. The ring above the air inlets is expected to yield.

To determine the resulting acceleration of the TSC and deformation of the pedestal, a half-symmetry model of the MSO, including the base weldment, is used to perform an impact analysis using the LS-DYNA program. The model is shown in Figure 3.11.4-1.

The model is constructed of 4-node shell elements and 8-node brick elements. Symmetry conditions are applied along the planes of symmetry. 8-node solid elements located in the canister bottom plate represent the loaded canister. The inner and outer shells along with the neutron shield are connected to the top of the inlet top plate using LSDYNA tied contact definitions. The TSC is modeled as an inelastic plate with the loaded TSC weight uniformly distributed at the surface of the plate. The impact plane is represented as a rigid plane To ensure that maximum deformations and accelerations are determined, two 24-in drop analyses are performed. The first analysis uses the upper-bound TSC weight of 105 kips and envelops the maximum deformation of the pedestal. The second analysis employs the lower-bound TSC weight of 60 kips to account for maximum acceleration.

The maximum accelerations of the TSC during the 24-inch bottom-end impact are calculated to be 16.6g and 24.5g for the upper-bound TSC weight and lower-bound TSC weight, respectively.

The acceleration time histories of the TSC, which are filtered at a frequency of 200 Hz, are shown in Figure 3.11.4-2 for the analysis using the upper-bound weight model and Figure 3.11.4-3 for the lower-bound weight model. The dynamic load factor (DLF) for the TSC is determined to be less than 1.0 (1.0 is used) for the upper-bound TSC weight and 1.15 for the lower-bound TSC weight, based on the response of one-degree systems subjected to a triangular load pulse [22]. Therefore, the accelerations for the upper-bound TSC weight and lower-bound TSC weight are 16.6g and 28.2g, respectively. These accelerations are significantly less than the 60g design basis acceleration used in the TSC evaluation in Section 3. 7 .1.2.1.

Elements in the pedestal components in the model with the highest calculated plastic strain are selected for the Triaxiality Factor based strain limit evaluation for protection against local failure per ASME B&PV Code,Section VIII, Division 2, Part 5, Sub-section 5.3.3 [33] ASME Boiler and Pressure Vessel Code,Section VIII Division 2 Rules for Construction of Pressure Vessels.

2010 Edition]. The local failure criterion limits the plastic strain as defined in paragraph 5.3.3.1 (c). The minimum factor of safety is 2.97, where the factor of safety is defined as the

• NAC International 3.11.4-15

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A ratio of the limiting triaxial strain to the calculated effective plastic strain from the analysis. This occurs for the 24-in drop case with the upper-bound canister weight.

The maximum vertical displacement of the air inlet is calculated to be 0.62-inch for the upper-bound and lower-bound TSC. The original opening is 4.4 inches and, therefore, the minimum air inlet opening is 3.78 inches (4.4--0.62), which is approximately 86% of the original air inlet opening. This condition is bounded by the consequences of the loss of one-half of the air inlets off-normal event.

Two additional drop cases are performed to evaluate that the plastic instability load limit per ASME B&PV Code,Section III, Division 1, Appendix F, Sub-section F-1341(d) [8]. In these analyses, the maximum canister weight of 105 kips is used and drop heights of 34.3-in and 40-in are selected (the applied loading at a 24-in drop height is 0.7 of the loading at a 34.3-in drop height per Sub-section F-1341.4, and 0.6 of the loading at a drop height of 40-in.). The maximum vertical deflections of the pedestal at these applied loads show no unbounded plastic deformation without an increase in load. Accordingly, the design-based drop height of 24-in is below 70% loading of the structural instability load and in compliance with Sub-section F-1341.4.

3.11.4.6 MSO Tip-Over Tip-over of the MSO is a non.mechanistic, hypothetical accident condition that presents a bounding case for evaluation. Existing postulated design basis accidents do not result in the tip-over of the MSO. Functionally, the MSO does not suffer significant adverse consequences due to this event The MSO, TSC, and basket maintain design basis shielding, geometry control of contents, and contents confinement performance requirements.

For a tip-over event to occur, the center of gravity of the MSO and loaded TSC must be displaced beyond its outer radius, i.e., the point of rotation. When the center of gravity passes beyond the point of rotation, the potential energy of the cask and TSC is converted to kinetic energy as the cask and TSC rotate toward a horizontal orientation on the ISFSI pad. The subsequent motion of the cask is governed by the structural characteristics of the cask, the ISFSI pad and the underlying soil.

The MSO tip-over analysis is performed using LS-DYNA. As shown in Figure 3.11.4-4, a half symmetry finite element model is used for the MSO, the ISFSI concrete pad and the soil. The ISFSI concrete pad in the model is 15 feet x 60 feet x 3 feet. The soil below the concrete pad is 17.5 feet wide x 70 feet long and 18 feet deep. Not all components within the MSO are modeled and equivalent densities are assigned to ensure that all component weights are accounted for.

The inner layer of elements within the MSO represent the steel liner. The loaded canister, MSO NAC International 3.11.4-16

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A lid and pedestal are conservatively treated as rigid bodies in the analysis. The material properties used to model the MSO, the concrete pad, and the soil are identical to those used for the model for concrete cask tip-over analysis in Section 3.10.4.4.

The acceleration time histories for the MSO tip-over for locations at the top of the basket and at the top of the TSC lid are shown in Figure 3.11.4-5. A cut-off frequency of200 Hz is applied to filter the analysis results. Two peaks for each acceleration curve are shown in the figure. The first and second peak accelerations are 34.8g and 30.0g for the top of the basket. The dynamic load factors (DLF) for the top of the basket are calculated to be 0.71 and 1.1 for the first and second peaks, respectively, and are based on the response of one-degree systems subjected to a triangular load pulse [22]. The maximum accelerations for the top of the basket at the two peaks are then 24.7g and 33.0g. The first and second peak accelerations from the figure for the top of the TSC lid are 36.2g and 31.2g, respectively. The DLF for the TSC lid is 1.0. A summary of the maximum accelerations is shown in the following table. The maximum accelerations of the basket and TSC are 33.0g and 36.2g, respectively. These are below the design basis values of

)

35g for the basket in Section 3.7.1.3 and 40g for the TSC in Section 3.10.1.3.3.

Position from Peak Maximum

• Location Top of basket Top of TSC closure Base of MSC (in) 188.8 197.8 Peak 1st 2nd 1st 2nd Acceleration (g) 34.8 30.0 36.2 DLF 0.71 1.1 1.0 Acceleration (Q}

24.7 33.0 36.2 lid 31.2 1.0 31.2

• NAC International 3.11.4-17

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Figure 3.11.4-1 Half-Symmetry Finite Element Model for MSO 24-inch Drop Analysis NAC lnternatlonal 3.11.4-18

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A

• Figure 3.11.4-2 Acceleration Time History of the Upper-Bound TSC Weight-24-Inch Drop 20 CASE 1, MAGNASTOR MSO 24-IN DROP, Heavy TSC load Matld 0-----------------------------

0.05 mln--1.0035 11me (aecond) max=1U15

• NAC International 3.11.4-19

MAG NASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Figure 3.11.4-3 Acceleration Time History of the Lower-Bound TSC Weight-24-Inch Drop

25 CASE 2, MAGNASTOR MSO 24-IH DROP, Ught TSC load Matld 20 /\-- r\ ..AJ>3 15

-I "-- ~

0 \

5 \

0

\- . a

. I) 0.11

0. 12

o. >3 0.04 0.1)5 mfn=-1.o-17 lime (second) max=24.548 NAC International 3.11.4-20

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Figure 3.11.4-4 Half-Symmetry Finite Element Model for MSO Tip-Over Analysis Concrete Pad

• NAC International 3.11.4-21

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Figure 3.11.4-5 Acceleration Time Histories at Top of the Basket and TSC Lid for MSO Tip-over Event MAGNASTOR MSO OVERPACK, run no. 53 40 Node Location 30

\ B- -,

-A.. Top of Basket JL Top of TSC Lid

~-

/, - ~

-s./ ~ ~

~ ~-, :{!

Cl 20 N:::.

~

r:

.!:?

e.,

N V

V 10 0

I

' "~ ~

I

~

• 10 I 0. 1 0. )2 o. 3 0.)4 0. 5 0. 6 min=-6.8027 Time, seconds max=36.206 NAC International 3.11.4-22

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Table 3.11.4-1 Inner Liner Vertical Stress Summary- Outer Surface, psi Combination NS Drop/ Tip-Dead Live Wind Handling Seismic Flood Total Number Pressure Impact Over D1 124 6030 96 6250 D2 124 6030 769 6923 D3 124 6030 88 6242 D4 124 6030 3675 9829 D5 124 6030 5622 11 ,776 D6 124 6030 6154 Table 3.11.4-2 Inner Liner Vertical Stress Summary - Inner Surface, psi Combination NS Drop/ Tip-Dead Live Wind Handling Seismic Flood Total Number Pressure Impact Over D1 124 6030 83 6237 D2 124 6030 702 6856 D3 124 6030 76 6230 D4 124 6030 3675 9829 D5 124 6030 5622 11,776 D6 124 6030 6154

• Number D1 D2 Table 3.11.4-3 Combination Dead 124 124 Live Outer Liner Vertical Stress Summary - Outer Surface, psi NS Pressure 6030 6030 Wind 132 Handling Seismic 1234 Flood Drop/

Impact Tip-Over Total 6286 7388 D3 124 6030 118 6272 D4 124 6030 3675 9829 D5 124 6030 5622 11,776 D6 124 6030 6154 Table 3.11.4-4 Outer Liner Vertical Stress Summary - Inner Surface, psi Combination NS Drop/ Tip-Dead Live Wind Handling Seismic Flood Total Number Pressure Impact Over D1 124 6030 126 6280 D2 124 6030 1206 7360 D3 124 6030 113 6267 D4 124 6030 3675 9829 D5 124 6030 5622 11 ,776 D6 124 6030 6154

• NAC International 3.11.4-23

MAGNASTOR System FSAR November 2019

• Docket No. 72-1031 List of Figures (cont'd)

Figure 5.8.12-17 Dose Rate Profile at Radial Surface of CC4 - Lower End Fitting Revision 19C Damaged PWR Fuel ............................................................................ 5.8.12-14 Figure 5.8.12-18 CC4 Inlet Dose Rate Profile - Lower End Fitting Damaged PWR Fuel ...................................................................................................... 5.8.12-14 Figure 5.8.13-1 Reconstituted Assembly Radial Dose Rate Comparison - Storage Cask ........................................................................................................ 5.8.13-4 Figure 5.8.13-2 Reconstituted Assembly Radial Dose Rate Comparison - Transfer Cask........................................................................................................ 5.8.13-4 Figure 5.8.13-3 SAS2H Input for HFRA Source ............................................................ 5.8.13-5 Figure 5.9.3-1 Concrete Cask Side Dose Rate Profile at Various Distances - PWR (CC4) ........................................................................................................ 5.9.3-3 Figure 5.9.3-2 Concrete Cask Side Surface Dose Rate Profile by Source - PWR (CC4) ........................................................................................................ 5.9.3-4 Figure 5.9.6-1 Schematic of PWRFuel 1.8 kW Preferential Loading Pattern ................ 5.9.6-3 Figure 5.9.7-1 Transfer Cask Sample Input File -Preferential Zone Bl ........................ 5.9.7-2 Figure 5.9.7-2 Storage Cask Sample Input File - Preferential Zone B2 ....................... 5 .9. 7-10 Figure 5.9.9-1 Schematic of DF Basket Assembly Configuration for PWR SNF with DFCs ................................................................................................ 5.9.9-4 Figure 5.10.3-1 Schematic of PWR Fuel 1.8 kW Preferential Loading Pattern .............. 5.10.3-2

• Figure 5.10.5-1 Schematic of DF Basket Assembly Configuration for PWR SNF with DFCs .............................................................................................. 5.10.5-2 Figure 5.11.4-1 PMTC/TSC Model-Axial Sketch ........................................................ 5.11.4-3 Figure 5.11.4-2 PMTC/fSC Model- Shield/Seal Insert Assembly ............................... 5.11.4-4 Figure 5.11.4-3 PMTC/TSC Model - Radial Sketch ...................................................... 5 .11.4-5 Figure 5.11.4-4 PMTC/TSC Model-Inlet Sketch .......................................................... 5.11.4-6 Figure 5.11.6-1 Comparison of Response Method to Direct Solution: PMTC Radial Surface ................................................................................................... 5.11.6-1 Figure 5.11.8-1 PMTC Side Dose Rate Profile at Various Distances ............................. 5.11.8-2 Figure 5.11.8-2 PMTC Top Dose Rate Profile at Various Distances -TSC Closure Operations .............................................................................................. 5 .11. 8-3 Figure 5.11.8-3 PMTC Top Dose Rate Profile at Various Distances -Transfer Operations .............................................................................................. 5.11. 8-4 Figure 5.11.8-4 PMTC Bottom Dose Rate Profile at Various Distances ........................ 5.11.8-5 Figure 5.11.8-5 PMTC Side Surface Dose Rate Profile by Source Type ........................ 5.11.8-6 Figure 5 .11.8-6 PMTC Top Surface Dose Rate Profile by Source Type - TSC Closure Operations ................................................................................. 5.11.8-7 Figure 5 .11.8-7 PMTC Top Surface Dose Rate Profile by Source Type - Transfer Operations .............................................................................................. 5.11.8-8 Figure 5.11.8-8 PMTC Bottom Surface Dose Rate Profile by Source Type ................... 5.11.8-9 Figure 5.11.8-9 Vent Shield Label Identification ............................................................ 5.11.8-9 Figure 5.11.8-10 PMTC Vent Shield Maximum Dose Rate (mrem/hr) Contour Plot-Vent B, Top .......................................................................................... 5.11.8-10

• Figure 5.11.8-11 PMTC Door Boundary Dose Rate (mrem/hr) Contour Plot ................ 5.11.8-11 NAC International 5-ix

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A List of Figures (cont'd)

Figure 5.11.10-1 Dose Rate Profile Comparison at Radial Surface of PMTC -Active Fuel Damaged - Fuel Source Only ...................................................... 5 .11.10-3 Figure 5.11.10-2 Dose Rate Profile Comparison at Top Surface of PMTC-TSC Closure Operations - Active Fuel Damaged - Fuel Source Only ....... 5.11.10-4 Figure 5 .11.10-3 Dose Rate Profile Comparison at Top Surface of PMTC-TSC Transfer Operations -Active Fuel Damaged-Fuel Source Only ...... 5.11.10-5 Figure 5.11.10-4 Dose Rate Profile Comparison at Bottom Surface of PMTC-Active Fuel Damaged-Fuel Source Only ...................................................... 5.11.10-6 Figure 5.11.10-5 Dose Rate Profile Comparison at Radial Surface of PMTC - Lower End Fitting Damaged - Total Dose Rates ............................................ 5 .11.10-7 Figure 5.11.10-6 Dose Rate Profile Comparison at Bottom Surface of PMTC- Lower End Fitting Damaged-Total Dose Rates ............................................ 5.11.10-8 Figure 5.11.10-7 Dose Rate Profile Comparison at Door Boundary of PMTC - Lower End Fitting Damaged-Total Dose Rates ............................................ 5.11.10-9 Figure 5.11.11-1 PMTC Sample Input File- Undamaged Fuel.. .................................... 5.11.11-2 Figure 5.11.11-2 PMTC Sample Input File - Damaged Fuel.. ...................................... 5.11.11-14 Figure 5.11.11-3 PMTC Sample Input File-Bottom Forging Mesh Detectors ........... 5.11.11-28 Figure 5.12.4-1 MSO Model- Cask Body ...................................................................... 5.12.4-5 Figure 5.12.4-2 MSO Model-Cask Lid ......................................................................... 5.12.4-6 Figure 5.12.4-3 Normal/Off-Normal Side Temperature Results ..................................... 5.12.4-7 Figure 5.12.4-4 Normal/Off-Normal Top Temperature Results ..................................... 5.12.4-8 Figure 5.12.4-5 Accident (Extreme Heat) Side Temperature Results ............................. 5.12.4-9 Figure 5.12.4-6 Accident (8 Minute Fire) Side Temperature Results ........................... 5.12.4-10 Figure 5.12.4-7 Accident (1 Hour Fire) Side Temperature Results .............................. 5.12.4-11 Figure 5.12.4-8 Accident (Extreme Heat) Top Temperature Results ............................ 5.12.4-12 Figure 5.12.8-1 MSO Side Dose Rates by Distance ......................................................... 5.12.8-2 Figure 5.12.8-2 MSO Top Axial Dose Rates by Distance .............................................. 5.12.8-2 Figure 5.12.8-3 MSO Side Surface Dose Rates by Source ............................................. 5.12.8-3 Figure 5.12.8-4 MSO Top Axial Surface Dose Rates by Source .................................... 5.12.8-3 Figure 5.12.8-5 MSO Inlet Dose Rates ........................................................................... 5.12.8-4 Figure 5.12.8-6 MSO Outlet Dose Rates ......................................................................... 5.12.8-4 Figure 5.12.8-7 MSO Radial Surface Normal/Off-Normal versus Accident Conditions .............................................................................................. 5.12.8-5 Figure 5.12.8-8 MSO Top Surface Normal/Off-Normal versus Accident Condition ..... 5.12.8-5 NAC International 5-x

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A List of Tables (cont'd)

Table 5.11.1-3 Summary of PMTC Maximum Dose Rates at Vent Shield Surface ....... 5.11.1-5 Table 5.11.1-4 Summary of PMTC Maximum Dose Rates at Door Boundary ............... 5.11.1-5 Table 5.11.1-5 Summary of PMTC Maximum Dose Rates for CEAs ............................ 5.11.1-5 Table 5.11.1-6 Summary of PMTC Maximum Dose Rates for Damaged Fuel -

Surface Tallies ......................................................................................... 5 .11.1-6 Table 5.11.1-7 Summary of PMTC Maximum Dose Rates for Damaged Fuel-Mesh Tallies ............................................................................................ 5.11.1-6 Table 5 .11.3-1 Gamma Source Spectrum - PMTC Maximum Radial Dose Rate Configuration ........................................................................................... 5 .11.3-2 Table 5.11.3-2 Neutron Source Spectrum - PMTC Maximum Radial Dose Rate Configuration ........................................................................................... 5.11.3-3 Table 5.11.3-3 Source Terms for Maximum PMTC Dose Rates - Surface Tallies ........ 5.11.3-4 Table 5.11.3-4 Source Terms for Maximum PMTC Dose Rates - Maximum Mesh Tallies ...................................................................................................... 5.11.3-4 Table 5.11.4-1 Key PMTC Shielding Features ................................................................ 5.11.4-7 Table 5.11.4-2 Fuel Basket, TSC, and PMTC Material Description ............................... 5.11.4-7 Table 5.11.4-3 CE16x16 Fuel Region Homogenized Material Description ................... 5.11.4-8 Table 5.11.5-1 PMTC Top and Bottom Surface Detector Division ................................ 5.11.5-2 Table 5.11.5-2 PMTC Radial Surface Detector Division ................................................ 5.11.5-2

• Table 5.11.5-3 PMTC Bottom Forging and Vent Shield Detector Division ................... 5.11.5-2 Table 5.11.7-1 Low Burnup CE 16x16 Fuel in the PMTC Loading Table ..................... 5.11.7-2 Table 5.11.7-2 Loading Table for CE 16x16 Fuel in the PMTC ..................................... 5.11.7-2 Table 5.11.10-1 Damaged Fuel Material Summary- CE 16x16 PWR Fuel ................ 5.11.10-10 Table 5.12.1-1 Summary ofMSO Maximum Dose Rates ............................................... 5.12.1-3 Table 5.12.1-3 MSO Air Inlet Maximum Dose Rates ..................................................... 5.12.1-3 Table 5.12.1-3 MSO Air Outlet Maximum Dose Rates .................................................. 5.12.1-3 Table 5.12.4-1 Key MSO Shielding Features ................................................................ 5.12.4-13 Table 5.12.4-2 NS-3 Material Description .................................................................... 5.12.4-13 Table 5.12.4-3 NS-3 Weight Reduction ........................................................................ 5.12.4-13 Table 5 .12.5-1 MSO Radial Detector Matrix .................................................................. 5.12.5-2 Table 5.12.5-2 MSO Top Axial Detector Matrix ............................................................ 5.12.5-2 Table 5.12.5-3 MSO Inlet Detector Matrix ..................................................................... 5.12.5-2 Table 5.12.5-4 MSO Outlet Detector Matrix ................................................................... 5.12.5-2 Table 5.12.8-1 MSO Maximum Fuel Type Dependent Surface Dose Rates by Source ...................................................................................................... 5.12.8-6 Table 5.12.8-2 MSO Maximum Detector Dose Rates Summary .................................... 5.12.8-6 Table 5.12.8-3 MSO Air Inlet Maximum Dose Rates ..................................................... 5.12.8-6 Table 5.12.8-4 MSO Air Outlet Maximum Dose Rates .................................................. 5.12.8-6 Table 5.12.8-5 MSO Accident Condition Dose Rates using Normal/Off-Normal Bounding Source and a High Bumup Source Term ................................ 5.12.8-7

• NAC International 5-xv

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR November 2019

• Docket No. 72-1031 5.12.4 Model Specification Revision 19C The MSO is evaluated using the MCNP three-dimensional Monte Carlo code. In the MCNP fuel assembly model, the fuel and hardware source regions are homogenized within a volume defined by the fuel assembly width and height. This volume is subdivided axially into active fuel, upper plenum, and upper and lower end fitting source regions. Within these axial volumes, the material masses of the fuel assembly are homogenized.

The three-dimensional shielding analysis allows detailed modeling of the shield regions, including streaming paths. In all models, the cask and TSC shield thicknesses and axial extents are explicitly represented, including streaming paths.

The geometric description of an MCNP model is based on the combinatorial geometry system embedded in the code. In this system, surfaces and bodies, such as cylinders and rectangular parallelepipeds, and their logical intersections and unions, are used to describe the extent of material zones.

The MCNP code employs an automated biasing technique for the Monte Carlo calculation based on weight window adjustments in mesh cells. Radial biasing is performed to estimate dose rates

• at the MSO radial surface, including air inlets and outlets. Axial biasing is used for cask top surface dose rates. Exponential transforms are used to direct particles in the area of interest.

5.12.4.1 TSC, Basket, and Fuel Assembly Model Description The fuel assembly model described in Section 5.8.3.1.1 is retained. The 37-assembly PWR basket model described in Section 5.8.3.1.2 is retained. The TSC model described in Section 5.5.1.1 is retained. The TSC lid is modeled as stainless steel for the MSO dose rate evaluation.

5.12.4.2 Model Description The MSO is evaluated in detail for TSC storage. The TSC and basket, except for the fuel assembly, are discretely modeled. Key MSO shield features, i.e., those associated with the radial shielding, are listed in Table 5.12.4-1. Figure 5.12.4-1 and Figure 5.12.4-2 provide a model sketch of the MSO .

• NAC International 5.12.4-1

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A NAC International 5.12.4-2

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A

• NAC International 5.12.4-3

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A NAC International 5.12.4-4

• NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Figure 5.12.4-1 MSO Model-Cask Body

• NAC International 5.12.4-5

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Figure 5.12.4-2 MSO Model - Cask Lid NAC International 5.12.4-6

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A

• NAC International 5.12.4-7

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A NAC International 5.12.4-8

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Figure 5.12.4-5 Accident (Extreme Heat) Side Temperature Results

• NAC International 5.12.4-9

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Figure 5.12.4-6 Accident (8 Minute Fire) Side Temperature Results NAG International 5.12.4-10

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A

• NAC International 5.12.4-11

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Figure 5.12.4-8 Accident (Extreme Heat) Top Temperature Results NAC International 5.12.4-12

NAC PROPRIETARY INFORMATION REMOVED MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Table 5.12.4-1 Key MSO Shielding Features

• Table 5.12.4-3 NS-3 Weight Reduction

• NAC International 5.12.4-13

MAGNASTOR System FSAR August2013 Docket No. 72-1031 Revision 5 8.1 Material Selection Type 304 stainless steel is used in the TSC, except for the shield plate and shield plate bolts of the composite closure lid assembly. It is selected for this use because of its high strength, ductility, resistance to corrosion and brittle fracture, and metallurgical stability for long-term storage. The steels used in the fabrication of the TSC are as follows.

Shell ASME SA240, Type 304/3041 dual-certified, stainless steel Bottom ASME SA240, Type 304/3041 dual-certified, stainless steel Closure Lid ASME SA240, Type 304 stainless steel Closure Ring ASME SA479/SA240, Type 304/3041 dual-certified, stainless steel Port Covers ASME SA240, Type 304/3041 dual-certified, stainless steel Shield Plate ASTM A36 carbon steel Shield Plate Bolts ASME SA193, Grade B6 high alloy bolting steel Lifting Lug-PWR/BWR ASTM A240/A276, Type 304/3041 dual-certified stainless steel Lifting Lug -

PWR Damaged Fuel ASTM A240/276, Type 347 stainless steel Note: SA182/SA336, Type F304/F304L and SA240, Type 3041 stainless steel may be substituted for SA240, Type 304 stainless steel for the closure lid, provided that their material yield and ultimate strengths are greater than, or equal to, those of SA240, Type 304 stainless steel.

The carbon steels used in the fuel baskets are selected based on their strength and thermal conductivity. After fabrication, the basket components are electroless nickel-coated to improve resistance to corrosion and to significantly reduce the potential for the formation of flammable gases during in-pool loading. The materials used in the fabrication of the fuel baskets are:

Basket Supports, Plates and Gussets ASME SA537, Class 1, carbon steel Corner Support Bars ASME SA695, Type B, Grade 40, SA696, Grade C or SA5 l 6, Grade 70 carbon steel Fuel Tubes ASME SA537, Class 1, carbon steel Pins SA696, Grade C or ASME SA36 carbon steel (PWRonly)

Mounting Bolts ASME SAl 93, Grade B6 stainless steel Neutron Absorber Borated Metal Matrix Composite, borated aluminum alloy or Boral

• NAC International 8.1-1

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A The materials used in the concrete cask fabrication are:

Shell ASTM A36 Carbon Steel Pedestal Plate ASTM A36 Carbon Steel Base and Top Plates ASTM A537, Class 2, Carbon Steel Lift Lugs and Anchors ASTM A537, Class 2, Carbon Steel Lift Lug Bolts ASME SB637, Grade NO7718 nickel alloy Reinforcing bar ASTM A615/A615M Carbon Steel Concrete ASTM C150 Type II Portland Cement The materials used in the Metal Storage Overpack (MSO) are:

Inner Liner ASTM SA350 LF2, Carbon Steel, Forging Outer Liner ASTM SA516 Gr 70 Base and Top Plates ASTM SA5 l 6 Gr 70 Trunnions ASTM SA696 Gr C Standoffs ASTM A36/A992 Shielding Material NS-3 Lid ASTM SA516 Gr 70 The materials used in the MTCl transfer cask fabrication are:

Inner Shell Outer Shell Bottom Forging ASTM A588 low alloy steel ASTM A588 low alloy steel ASTM AS 16, Grade 70 Top Forging ASTM AS 16, Grade 70 Trunnions ASTM A350, LF2 low alloy steel Shield Doors and Rails ASTM A350, LF2 low alloy steel Retaining Block Pins ASTM AS 16, Grade 70 Retaining Block ASTM A693/A564 17-4 PH stainless steel Gamma Shield Brick ASTM B29 Lead-Chemical Copper Grade Neutron Shield NS-4-FR The materials used in the MTC2 transfer cask fabrication are:

Inner Shell ASTM A240, Type 304 stainless steel Outer Shell ASTM A240, Type 304 stainless steel Bottom Forging ASTM A182, Type F304 stainless steel Top Forging ASTM Al 82, Type F304 stainless steel Trunnions ASTM A182, Type F304 stainless steel Shield Doors and Rails NAC International ASTM A182, Type F304 stainless steel 8.1-2

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A Retaining Ring Bolts ASTM A193 Grade B8 bolting steel Retaining Ring ASTM A240, Type 304 stainless steel Gamma Shield Brick ASTM B29 Lead-Chemical Copper Grade Neutron Shield NS-4-FR 8.1.1 Fracture Toughness The TSC structural material is austenitic stainless steel, except for the shield plate and shield plate bolts of the composite closure lid assembly. In accordance with ASME Code,Section III, Subsection NB, Paragraph NB-2311, these materials do not require testing for fracture toughness. The carbon steel shield plate and bolts of the composite closure lid assembly do not perform a pressure-retaining function and are not in the canister support load path and, therefore, are considered a nonstructural attachment. In accordance with ASME Code,Section III, Subsection NB, Subsubarticle NB-1130, the shield plate and bolts may be classified as an internal structure with material and design requirements outside code jurisdiction. Consistent with the discussion of bolting design considerations provided in Section 5 ofNUREG/CR-1815

[41], impact testing of the attachment bolts is deemed not required due to the multiple load paths and redundancy in the bolted design. Consistent with ASME Code,Section III, Subsection NF, Paragraph NF-2311, the carbon steel shield plate of the composite closure lid assembly does not require impact testing since the maximum stress does not exceed 6,000 psi tension .

The fuel basket is comprised of welded tubes and supports primarily fabricated from ASME Code SA537, Class 1, carbon steel. Fuel basket materials will meet ASME Code,Section III, Subsection NG, Subarticle NG-2300 requirements for impact tests and will be tested in accordance with paragraph NG-2320. A procurement/fabrication specification will describe fracture toughness testing of these materials for each heat of material subjected to the equivalent forming/bending process or heat-treated condition. Acceptance values shall be per ASTM A370, Section 26.1, with values meeting the requirements of Table NG-233 l(a)(l) at a Lowest Service Temperature (LST) of -40°F.

The concrete cask lift lugs and anchors are fabricated from two-inch thick, ASTM A537 Class 2, carbon steel plate. Utilization of the lift lugs and anchors for handling the concrete cask is considered a noncritical lift and will be restricted for use only when the surrounding air temperature is 2: 0°F. Therefore, impact testing of the material is not required.

The Metal Storage Overpack (MSO) trunnions are fabricated from bar stock machined to a diameter of 7.9 inches, ASME SA696 Gr C, carbon steel. Utilization of the trunnions for handling the MSO is considered a noncritical lift and will be restricted for use only when the surrounding air temperature is 2: 0°F. MSO trunnion material will meet ASME Code,Section III, Subsection NF, Subarticle NF-2300 requirements for impact tests and will be tested in NAC International 8.1-3

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A accordance with paragraph NF-2320. Acceptance values shall be per AS1M A370, Section 26.1, with values meeting the requirements of Table NF-233 l(a)-1 at a test temperature of -40°F.

The structural components of the MTCl transfer cask are fabricated from low alloy carbon steels selected based on their low-temperature facture toughness. The nil ductility transition temperature for these steels is established as -40°F. Based on Regulatory Guide 7 .11 [1], the minimum temperature for use is 40°F above the transition temperature, with no credit taken for heat produced by the contents of the transfer cask. Consequently, a minimum ambient temperature of 0°F for use of the MTCl transfer cask is established. This condition is administratively controlled by procedure and is consistent with the analysis. Since the use of the MTC 1 transfer cask is restricted to conditions when the surrounding air temperature is greater than, or equal to, 0°F, impact testing of the MTC 1 transfer cask materials is not required. The structural components of the MTC2 transfer cask are fabricated from austenitic stainless steel. In accordance with ASME Code,Section III, Subsection NB, Article NB-2311, these materials do not require testing for fracture toughness.

NAC International 8.1-4

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A 8.2 Applicable Codes and Standards The principal codes and standards applied to MAGNASTOR components are the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, the American Society for Testing and Materials (ASTM), and the American Concrete Institute (ACI).

Materials meeting the requirements of these codes and/or standards conform to acceptable minimum thickness, chemical content and formulation specifications and are fabricated using controlled processes and procedures.

The TSC steel components, except the shield plate and shield plate attachment bolts used for the composite closure lid assembly, and associated weld filler materials are procured in accordance with the ASME Code,Section III, Subsection NB [3] requirements, except as listed in the Code Alternatives in Table 2.1-2. The materials for the shield plate and shield plate attachment bolts used for the composite closure lid assembly materials are procured in accordance with the requirements of the applicable ASTM and ASME standards, respectively. The fuel basket steel components and associated weld filler materials are procured in accordance with ASME Code,Section III, Subsection NG [4] requirements, except as stated in the Code Alternatives in Table 2.1-2 .

• The transfer cask steel components, associated weld filler materials and lead gamma shield materials are procured in accordance with the requirements of the applicable ASTM standards.

The NS-4-FR material in the transfer cask is a commercially available product specifically designed for neutron attenuation and absorption.

The concrete cask steel components and associated weld filler materials are procured in accordance with the requirements of the applicable ASTM standards. The vertically reinforced concrete portion of the cask is procured in accordance with the requirements of ACI-318 [2], as supplemented by applicable ASTM standards. ACI-318 is not applicable to the concrete cask lid or upper segment, if equipped.

The Metal Storage Overpack (MSO) steel components and associated weld filler materials are procured in accordance with the requirements of the applicable ASTM standards. The NS-3 material in the MSO is a commercially available product specifically designed for gamma and neutron shielding .

• NAC International 8.2-1

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A 8.4 Weld Design and Specification The welding operations of the MAGNASTOR components are performed in accordance with the requirements of a number of codes and standards depending on the design and functional requirements of the specific component. The specific requirements met by each component are provided herein.

The TSC and fuel basket assemblies are welded using welding procedures, processes, and welders prepared and qualified in accordance with the ASME Code,Section IX [29]

requirements. The specific weld designs and examination requirements for the TSC and fuel basket comply with the applicable subsection of the ASME Code,Section III, which are Subsection NB for the TSC and Subsection NG for the fuel baskets. Alternatives to the Code requirements applicable to these system components are listed in Table 2.1-2. Weld filler materials and processes used in the fabrication of the TSC are in accordance with ASME Code Section II-C requirements for SFA 5.9 and SFA 5.22. For SFA 5.9 and SFA 5.22, respectively, AWS ER 308L and AWS E308LTX-X will be specifically identified in the approved welding procedures.

The steel components of the concrete casks (i.e., liner, baseplate, etc.), Metal Storage Overpack (MSO) and the transfer cask are welded using procedures, processes, and welders prepared, qualified, and certified in accordance with either ASME Section IX or ANSUA WS Dl.1 [28].

The weld design and specification requirements for the steel components of the concrete cask are in accordance with the weld design criteria of the ASME Code,Section VIII, Division 1, Part UW [31] or ANSUANS D 1.1. The weld design and specification requirements for the transfer cask are in accordance with the weld design criteria of the ASME Code,Section III, Subsection NF [32].

The inspection and examination requirements for all MAGNASTOR component welds, inspector qualification requirements, and the applicable acceptance criteria are specified in Chapter 10 of this SAR.

• NAC International 8.4-1

MAGNASTOR System FSAR November 2014 Docket No. 72-1031 Revision 6 The TSC confinement boundary uses Type 304/304L dual-certified stainless steel for all components except the closure lid. The MTC2 transfer cask structural components are fabricated primarily from ASTM A240/A182 Type 304 stainless steel. No coatings are applied to the stainless steels. Type 304/304L stainless steel resists chromium-carbide precipitation at the grain boundaries during welding and assures that degradation from intergranular stress corrosion will not be a concern over the life of the TSC. Fabrication specifications control the maximum interpass temperature for austenitic steel welds to less than 350°F. The material will not be heated to a temperature above 800°F, other than by welding or thermal cutting. Minor sensitization of Type 304/304L stainless steel that may occur during welding will not affect the material performance over the design life.

8.10.2.2 Carbon Steel Carbon steel is used to fabricate all of the structural components of the PWR and BWR baskets, and the shield plate of the TSC composite closure lid assembly. There is a small electrocbemical potential difference between carbon steel and the stainless steel of the TSC shell and the stainless steel sheet used to protect the neutron absorber in the fuel tubes. However, the carbon steel basket components and the shield plate of the TSC composite closure lid assembly are coated

• with electroless nickel using an immersion process. The immersion process ensures that the carbon steel is appropriately coated, reducing the possibility of corrosion due to exposure to air or pool water. When in contact with stainless steel in water, the carbon steel exhibits a limited electrochemically driven corrosion. Typically, BWR pool water is demineralized, and is not sufficiently conductive to promote detectable corrosion for these metal couples. Once the TSC is loaded, the water is drained from the cavity, the air is removed, and the TSC is backfilled with helium and sealed. Removal of the water and the moisture eliminates the catalyst for galvanic corrosion between the carbon and stainless steels. In addition, the displacement of oxygen by helium effectively inhibits oxidation.

The MTCl transfer cask structural components are fabricated primarily from ASTM A588 and A36 carbon steel. The exposed carbon steel components are coated with an epoxy enamel coating system tested and certified for use in Nuclear Service Level 1 conditions to protect the components during in-pool use and to provide a smooth surface to facilitate decontamination.

The concrete shell of the concrete cask contains an ASTM A36 carbon steel liner, as well as other carbon steel components. The exposed surfaces of the carbon steel liner and air inlets and outlets are coated to provide protection from weather-related moisture. The coating is formulated for use in continuous high- temperature environments .

• NAC International 8.10-3

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A The MSO contains a carbon steel ASTM SA350 inner shell and a ASTM SA516 outer shell, as well as other carbon steel components. The exposed surfaces of the carbon steel inner and outer shells, the lid, and the air inlets and outlets are coated to provide protection from weather-related moisture. The coating is formulated for use in continuous high- temperature environments.

No potential reactions associated with the shield plate of the TSC composite closure lid assembly, basket supports and fuel tubes, the transfer cask components, MSO components or concrete cask components are expected to occur.

8.10.2.3 Nonferrous Metals Aluminum is used in the neutron absorber material. The aluminum material in electrical contact with the stainless steel cover and carbon steel fuel tube could experience corrosion driven by an electrochemically induced electromotive force when immersed in water, where the conductivity of the water is the dominant factor. Typically, BWR fuel pool water is demineralized and is not sufficiently conductive to promote detectable corrosion for these metal couples. PWR pool water, however, does provide a conductive medium.

Shortly after fabrication, aluminum produces a thin surface film of oxidation that effectively inhibits further oxidation of the surface. This oxide layer adheres tightly to the base metal and does not react readily with the materials or environments to which the fuel basket will be exposed. The volume of the aluminum oxide does not increase significantly over time. Thus, binding due to corrosion product build-up during future removal of spent fuel assemblies is not a concern. The borated water in a PWR fuel pool is an oxidizing-type acid with a pH on the order of 4.5. However, aluminum is generally passive in pH ranges down to about 4 [11]. Data provided by the Aluminum Association [12] shows that aluminum alloys are resistant to aqueous solutions (1-15%) of boric acid (at 140°F). Based on these considerations and the very short exposure of the aluminum in the fuel basket to the borated water, oxidation of the aluminum is not likely to occur beyond the formation of a thin surface film. No observable degradation of aluminum is expected as a result of exposure to BWR or PWR pool water at temperatures up to 200°F, which is higher than the normal condition permissible fuel pool water temperature.

Aluminum is high on the electromotive potential table, and it becomes anodic when in electrical contact with stainless or carbon steel in the presence of water. BWR pool water is demineralized and is not sufficiently conductive to promote detectable corrosion for these metal couples. PWR pool water is sufficiently conductive to allow galvanic activity to begin. However, exposure time of the aluminum to the PWR pool environment is short. The long-term storage environment is sufficiently dry to inhibit galvanic corrosion.

NAC International 8.10-4

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A 10.1 Acceptance Criteria This section provides the workmanship and acceptance tests to be performed on the MAGNASTOR components and systems during their fabrication, as well as prior to and during loading of the system. These tests and inspections provide assurance that the components and systems have been procured, fabricated, assembled, inspected, tested, and accepted for use under the conditions and controls specified in this document and the Certificate of Compliance.

10.1.1 Visual Inspection and Nondestructive Examination Fabrication, inspection, and testing are performed in accordance with the applicable design criteria, codes and standards specified in Chapter 2 and on the license drawings.

The following fabrication controls and inspections shall be performed to assure compliance with this document and the license drawings:

a) Materials of construction for the MAGNASTOR are identified on the license drawings and shall be procured with certification and supporting documentation as required by the ASME Code,Section II [1], when applicable; and the requirements of ASME Code,Section III, Subsection NB [2], Subsection NF [4] and Subsection NG [3], when applicable.

• b) Materials and components shall be receipt inspected for visual and dimensional acceptability, material conformance to the applicable Code specification and traceability markings, as applicable. Materials for the TSC confinement boundary (e.g., TSC shell plates, base plate, closure lid, and port covers) shall also be inspected per the requirements of ASME Code,Section III, Subsection NB-2500.

c) The confinement boundary shall be fabricated and inspected in accordance with ASME Code,Section III, Subsection NB, with the code alternatives as listed in Chapter 2, Table 2.1-2. The TSC fuel basket, damaged fuel cans (DFCs) and basket supports shall be fabricated and inspected in accordance with the ASME Code,Section III, Subsection NG, with the alternatives listed in Table 2.1-2.

d) The steel components of the transfer cask shall be in accordance with ASTM specifications and fabricated in accordance with ANSI N14.6 [11]. Inspections and NDE of the transfer cask shall be in accordance with ASME Code,Section III, Subsection NF.

e) The steel components of the concrete cask and Metal Storage Overpack (MSO) shall be in accordance with ASTM specifications and fabricated in accordance with ASME Code,Section VIII [6] (or fabrication may be in accordance with ANSI/A WS D 1.1 ).

Inspections of the welded steel components of the concrete cask shall be in accordance with ASME Code,Section VIII or ANSI/A WS D 1.1.

f) ASME Code welding shall be performed using welders and weld procedures qualified in accordance with ASME Code,Section IX [7] and the ASME Code,Section III subsection

• 'applicable to the component (e.g., NB, NG or NF). ANSI/AWS code welding may be NAC International 10.1-1

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A performed using welders and procedures qualified in accordance with the applicable A WS requirements or in accordance with ASME Code,Section IX.

g) Construction and inspections of the concrete component of the concrete cask shall be performed in accordance with the applicable sections and requirements of ACI-318 [8].

h) Visual examinations of the welds of the confinement boundary shall be performed in accordance with ASME Code,Section V, Articles 1 and 9 [9], with acceptance per Section III, Subsection NF, Article NF-5360. The final surface of TSC shell welds shall be dye penetrant examined (PT) in accordance with ASME Code,Section V, Articles 1, 6 and 24, with acceptance per Section ill, Subsection NB, Article NB-5350. The TSC shell longitudinal and circumferential welds shall be radiographic examined (RT) in accordance with ASME Code,Section V, Articles 1 and 2, with acceptance per Section III, Subsection NB, Article NB-5320. The weld of the TSC baseplate to the TSC shell shall be ultrasonic examined (UT) in accordance with ASME Code,Section V, Articles 1 and 4, with acceptance per Section III, Subsection NB, Article NB-5330. In accordance with ISG-15 [14], the TSC closure lid to shell weld, performed following fuel loading, shall be dye penetrant (PT) examined at the root, mid-plane and final surface in accordance with ASME Code,Section V, Articles 1, 6 and 24, with acceptance per Section III, Subsection NB, Article NB-5350. The closure ring to TSC shell and the closure ring to closure lid welds shall be PT examined in accordance with the same code and acceptance criteria as the closure lid to TSC shell weld, except that only the weld final surface will be examined. The inner and outer (redundant) port covers to closure lid welds shall be PT examined at the final surface in accordance with the same code and acceptance criteria as for the closure lid to shell weld. Repairs to TSC vessel welds shall be performed in accordance with ASME Code,Section III, Subsection NB, Article NB-4450, and the welds reinspected per the original acceptance criteria applicable to the examination method.

i) Visual examinations of the welds of the fuel baskets, DFCs and basket supports shall be performed in accordance with ASME Code,Section V, Articles 1 and 9, with acceptance per Section III, Subsection NG, Article NG-5360. The fuel tube welds shall be magnetic particle examined (MT) in accordance with ASME Code,Section V, Articles 1, 7 and 25, with acceptance criteria per Section III, Subsection NG, Article NG-5340. Repairs to fuel basket welds shall be performed in accordance with ASME Code, Section ill, Subsection NG, Article NG-4450, and the welds reinspected per the original acceptance criteria applicable to the examination method.

j) Visual examinations of the concrete cask and MSO structural steel weldments shall be performed in accordance with the ASME Code,Section V, Articles 1 and 9, or ANS/AWS D1.1, Section 6.9, with acceptance per Section VIII, Division 1, Part UW, Articles UW-35 and UW-36, or Table 6.1 of ANSI/AWS D1.1, respectively. Repairs to concrete cask structural weldment welds shall be performed in accordance with ANSI/A WS D 1.1, and the welds reinspected per the original acceptance criteria.

NAC International 10.1-2

MAGNASTOR System FSAR February 2021 Docket No. 72-1031 Revision 21 A k) Visual examination of the welds of the transfer cask shall be performed in accordance with ASME Code,Section V, Articles I and 9, or ANSI/AWS DI .1, Section 6.9, with acceptance per Section III, Subsection NF, Article NF-5360. Following structural load testing of the transfer cask, the final surface of all critical load-bearing welds shall be either dye penetrant (PT) or magnetic particle (MT) examined in accordance with ASME Code,Section V, Articles I, 6 and 24 for PT and Articles 1, 7 and 25 for MT. The acceptance criteria for the weld examinations shall be in accordance with Section ill, Subsection NF, Article NF-5350 for PT and NF-5340 for MT. Repairs to the transfer cask vertical load-bearing welds shall be performed in accordance with ASME Code,Section III, Subsection NF, Article NF-4450 or ANSI/AWS Dl.l. Repaired welds shall be reinspected per the original acceptance criteria applicable to the examination method.

1) Dimensional inspections of components shall be performed in accordance with written and approved procedures to verify compliance to the license drawings and fit-up of individual components. All dimensional inspections and functional fit-up tests shall be documented.

m) All components shall be inspected for cleanliness and proper packaging for shipping in accordance with written and approved procedures. All components will be free of any foreign material, oil, grease, and solvents.

n) Inspection and nondestructive examination personnel shall be qualified in accordance with the requirements of SNT-TC-lA [10].

10.1.2 Structural and Pressure Tests 10.1.2.1 Load Testing of Transfer Casks The transfer cask is designed, fabricated, and tested to the requirements of ANSI N14.6 [11].

The transfer cask is provided with two lifting trunnions near the top of the cask for lifting and handling. The transfer cask shield doors and supporting door rails are designed to retain and support the maximum TSC loaded weight.

Following completion of fabrication, the load-bearing components of the transfer cask, including the lifting trunnions, shield doors, and rails, are load tested to verify their structural integrity to lift and retain the applicable loads.

The lifting and handling of the transfer cask and loaded TSC are defined as critical lifting loads per NUREG-0612 [12] at a number of nuclear facilities. In accordance with ANSI N14.6, special lifting devices for critical loads shall be provided with redundant lifting paths, or be designed and tested to higher safety factors. The transfer cask lifting trunnions, shield doors, and rails are designed to higher safety factors and are load tested to 300% of the maximum service load for each type of component.

• NAC International 10.1-3

MAGNASTOR System FSAR November 2019 Docket No. 72-1031 Revision 19C The lifting trunnion pair shall have a load equal to three times their maximum service load applied for a minimum of 10 minutes. Likewise, the transfer cask shield doors and rails shall have a load equal to three times their maximum service load applied for a minimum of 10 minutes. After release of the test loads, the accessible portions of the trunnions and the adjacent areas, and the shield doors and rails and adjacent areas shall be visually examined to verify no deformation, distortion, or cracking occurred. The critical load-bearing welds of the transfer cask shall be examined by the methods and acceptance criteria defined in Section 10.1.1, Item k).

Any evidence of deformation, distortion, or cracking of the loaded components, critical load-bearing welds or adjacent areas shall be cause for failure of the load test, and repair and/or replacement of the component. Following repair or replacement, the applicable portions of the load test shall be performed again and the components reexamined in accordance with the original procedure and acceptance criteria.

Load testing of the transfer cask shall be performed in accordance with written and approved procedures, and the test results shall be documented.

10.1.2.2 Load Testing of Concrete Cask Lifting Lugs and Anchors / Metal Storage Overpack (MSO) Trunnions The concrete cask is designed to be lifted and transported using one of two optional pin lift configurations. The optional pin lift configurations are two lifting anchors imbedded in the reinforced con~rete shell or two lifting lugs bolted to anchors that are imbedded in the reinforced concrete shell. Either configuration provides a pin connection to a lifting system. The concrete lifting anchors, lifting lugs and attachment bolting are designed, fabricated, and tested in accordance with the requirements of ANSI N14.6 for lifts not made over safety-related equipment (noncritical lifts).

The concrete cask lifting lug load test shall be performed on the lugs independently of the concrete cask. The test will consist of applying a vertical load to the individual lugs at a value that is equal to one-half of 150% of the maximum concrete cask weight The test load shall be applied for a minimum of 10 minutes. After the release of the test load, the accessible portions of the lifting anchors shall be visually examined to verify no deformation, distortion, or cracking occurred. Critical load-bearing welds of the lifting anchors shall be magnetic particle (MT) examined in accordance with ASME Code,Section V, Articles 1, 7 and 25, or liquid penetrant (PT) examined in accordance with ASME Code,Section V, Articles 1, 6 and 24, with acceptance criteria per Section III, Subsection NF, Article NF-5340 or NF-5350.

Any evidence of deformation, distortion, or cracking of the loaded components, critical load-bearing welds or adjacent areas shall be cause for failure of the load test, and repair and/or NAC International 10.1-4