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NAC International, Inc., Final Safety Analysis Report, Revision 23C, Amendment 14
	ML23207A112
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Site:	07201031
Issue date:	07/31/2023
From:	; NAC International
To:	; Office of Nuclear Material Safety and Safeguards
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	ED20230100
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Atlanta Corporate Headquarters: 3930 East Jones Bridge Road, Norcross, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1797, www.nacintl.com July 2023 Docket No. 72-1031 MAGNASTOR (Modular Advanced Generation Nuclear All-purpose STORage)

FINAL SAFETY ANALYSIS REPORT Amendment 14 Initial Submittal NON-PROPRIETARY VERSION Revision 23C

to ED20230100 Page 1 of 3 List of Changes for MAGNASTOR FSAR, Revision 23C (Docket No 72-1031)

NAC International July 2023 to ED20230100 Page 2 of 3 List of Changes, MAGNASTOR FSAR, Revision 23C Note: The List of Effective Pages and the Chapter Tables of Contents, including the List of Figures and the List of Tables, were revised as needed to incorporate the following changes.

Chapter 1 Pages 1.1-3, revised definition of Damaged fuel where indicated.

Pages 1.1-4 thru 1.1-6, text flow Pages 1.1-7, revised definition of Undamaged fuel where indicated.

Chapter 2 - no changes Chapter 3 Pages 3.8-1 thru 3.8-3, revised Section 3.8 and 3.8.1 where indicated.

Page 3.8-6, revised Section 3.8.2 where indicated.

Pages 3.8-8 thru 3.8-10, revised Section 3.8.4 where indicated.

Page 3.9-2, updated reference 27 Page 3.9-3, added reference 33, 34, and 35 Chapter 4 Page 4.11.3-1, added a paragraph to the end of Section 4.11.3.1 Chapter 5 - no changes Chapter 6-no changes Chapter 7 - no changes Chapter 8 Page 8.3-1, revised last paragraph in Section 8.3.

Page 8.12-3, deleted reference 36.

Chapter 9 - no changes Chapter 10 - no changes Chapter 11 - no changes to ED20230100 Page 3 of 3 Chapter 12 Page 12.1-3, Revised section 12.1.2.4 Chapter 13 Pages 13C-15 thru 13C-19, revised bases 3.1.2 for the CONCRETE CASK or MSO Heat Removal System throughout.

to ED20230100 Page 1 of 2 Supporting Calculations for MAGNASTOR FSAR Amendment 14 Initial Submittal Revision 23C (Docket No 72-1031)

NAC International July 2023 to ED20230100 Page 2 of 2 List of Calculations:

71160-2026 Revision 1 71160-2049 Revision 3 30076-3001 Revision 7 CALCULATIONS WITHHELD IN THEIR ENTIRETY PER 10 CFR 2.390 to ED20230100 Page 1 of 1 Proposed Technical Specification Changes for MAGNASTOR Certificate of Compliance, Amendment 14 (Docket No 72-1031)

NAC International July 2023

Certificate of Compliance No. 1031 A-1 Amendment No. 14 PROPOSED APPENDIX A TECHNICAL SPECIFICATIONS AND DESIGN FEATURES FOR THE MAGNASTOR SYSTEM AMENDMENT NO. 14

Certificate of Compliance No. 1031 A-2 Amendment No. 14 Appendix A Table of Contents 1.0 USE AND APPLICATION........................................................................................... A1-1 1.1 Definitions............................................................................................................... A1-1 1.2 Logical Connectors................................................................................................. A1-7 1.3 Completion Times................................................................................................... A1-9 1.4 Frequency............................................................................................................. A1-13 2.0

[Reserved].................................................................................................................. A2-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.......................... A3-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY......................................... A3-2 3.1 MAGNASTOR SYSTEM Integrity........................................................................ A3-3 3.1.1 Transportable Storage Canister (TSC)........................................................... A3-3 3.1.2 CONCRETE CASK or MSO Heat Removal System.................................... A3-10 3.2 MAGNASTOR SYSTEM Criticality Control for PWR Fuel................................. A3-11 3.2.1 Dissolved Boron Concentration.................................................................... A3-11 3.3 MAGNASTOR SYSTEM Radiation Protection................................................... A3-13 3.3.1 CONCRETE CASK or MSO Maximum Surface Dose Rate......................... A3-13 3.3.2 TSC Surface Contamination.......................................................................... A3-17 4.0 DESIGN FEATURES................................................................................................. A4-1 4.1 Design Features Significant to Safety.................................................................... A4-1 4.1.1 Criticality Control............................................................................................ A4-1 4.1.2 Fuel Cladding Integrity................................................................................... A4-1 4.1.3 Transfer Cask Shielding................................................................................. A4-1 4.1.4 TSC Confinement Integrity............................................................................. A4-2 4.2 Codes and Standards............................................................................................ A4-2 4.2.1 Alternatives to Codes, Standards, and Criteria.............................................. A4-3 4.2.2 Construction/Fabrication Alternatives to Codes, Standards, and Criteria...... A4-4 4.3 Site-Specific Parameters and Analyses................................................................. A4-4 4.3.1 Design Basis Specific Parameters and Analyses........................................... A4-4 4.4 TSC Handling and Transfer Facility....................................................................... A4-6 5.0 ADMINISTRATIVE CONTROLS AND PROGRAMS.................................................. A5-1 5.1 Radioactive Effluent Control Program................................................................... A5-1 5.2 TSC Loading, Unloading, and Preparation Program............................................. A5-1 5.3 Transport Evaluation Program............................................................................... A5-2 5.4 ISFSI Operations Program.................................................................................... A5-2 5.5 Radiation Protection Program................................................................................ A5-3 5.6 Deleted.................................................................................................................. A5-4 5.7 Training Program.................................................................................................... A5-4 5.8 Pre-operational Testing and Training Exercises..................................................... A5-5

Certificate of Compliance No. 1031 A-3 Amendment No. 14 List of Figures Figure A3-1 CONCRETE CASK Surface Dose Rate Measurement................................. A3-15 Figure A3-2 MSO Surface Dose Rate Measurement........................................................ A3-16 List of Tables Table A3-1 Helium Mass per Unit Volume for MAGNASTOR TSCs................................... A3-9 Table A4-1 Load Combinations and Service Condition Definitions for the TSC Handling and Transfer Facility Structure........................................................................... A4-7

Definitions 1.1 Certificate of Compliance No. 1031 A1-1 Amendment No. 14 1.0 USE AND APPLICATION 1.1 Definitions NOTE The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

ASSEMBLY AVERAGE FUEL ENRICHMENT Value calculated by averaging the 235U wt % enrichment over the entire fuel region (UO2) of an individual fuel assembly, including axial blankets, if present.

BREACHED SPENT FUEL ROD Spent fuel with cladding defects that permit the release of gas from the interior of the fuel rod. A fuel rod breach may be a minor defect (i.e., hairline crack or pinhole), allowing the rod to be classified as undamaged, or be a gross breach requiring a damaged fuel classification.

BURNUP a) Assembly Average Burnup:

Value calculated by averaging the burnup over the entire fuel region (UO2) of an individual fuel assembly, including axial blankets, if present. Assembly average burnup represents the reactor record, nominal, value. The assembly average burnup is equal to the reactor record, nominal, energy production (MWd) over the life of the fuel assembly divided by the fuel assembly pre-irradiation heavy metal (U) mass in metric tons.

b) Nonfuel Hardware Burnup:

Equivalent accumulated irradiation exposure for activation evaluation.

COMPOSITE CLOSURE LID A closure lid assembly, consisting of a stainless steel TRANSPORTABLE STORAGE CANISTER closure lid and a separate shield plate bolted together, that provides closure of a TRANSPORTABLE STORAGE CANISTER.

CONCRETE CASK The CONCRETE CASK is the vertical storage module that receives, holds and protects the sealed TSC for storage at the ISFSI. The CONCRETE CASK passively provides the radiation shielding, structural protection, and heat dissipation capabilities for the safe storage of spent fuel in a TSC. Closure for the CONCRETE CASK is provided by the CONCRETE CASK LID.

(continued)

Definitions 1.1 Certificate of Compliance No. 1031 A1-2 Amendment No. 14 CONCRETE CASK LID The CONCRETE CASK LID is a thick concrete and steel closure for the CONCRETE CASK. The CONCRETE CASK LID precludes access to the TSC and provides radiation shielding.

DAMAGED FUEL SPENT NUCLEAR FUEL (SNF) assembly that cannot fulfill its fuel-specific or system-related function. SNF is classified as damaged under the following conditions.

1.

There is visible deformation of the rods in the SNF assembly.

Note: This is not referring to the uniform bowing that occurs in the reactor; this refers to bowing that significantly opens up the lattice spacing.

2.

Individual fuel rods are missing from the SNF assembly and the missing rods are not replaced by a solid stainless steel or zirconium dummy rod that displaces a volume equal to, or greater than, the original fuel rod.

3.

The SNF assembly has missing, displaced or damaged structural components such that:

3.1. Radiological and/or criticality safety is adversely affected (e.g., significantly changed rod pitch); or 3.2. The SNF assembly cannot be handled by normal means (i.e., crane and grapple); or 3.3. The PWR SNF assembly contains fuel rods with damaged or missing grids, grid straps, and/or grid springs producing an unsupported length greater than 60 inches.

Note: PWR SNF assemblies with the following structural defects meet MAGNASTOR system-related functional requirements and are, therefore, classified as undamaged: Assemblies with missing or damaged grids, grid straps and/or grid springs resulting in an unsupported fuel rod length not to exceed 60 inches.

4.

Any SNF assembly that contains fuel rods for which reactor operating records (or other records or tests) cannot support the conclusion that they do not contain gross breaches.

Note: BREACHED SPENT FUEL RODs with minor cladding defects (i.e., pinhole leaks or hairline cracks that will not permit significant release of particulate matter from the spent fuel rod) meet MAGNASTOR system-related functional requirements and are, therefore, classified as undamaged.

5.

FUEL DEBRIS such as ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting loose PWR fuel assembly parts.

(continued)

Definitions 1.1 Certificate of Compliance No. 1031 A1-3 Amendment No. 14 DAMAGED FUEL CAN (DFC)

A specially designed stainless steel screened can sized to hold UNDAMAGED PWR FUEL, DAMAGED PWR FUEL, and/or FUEL DEBRIS. The screens preclude the release of gross particulate from the DFC into the canister cavity. DFCs are only authorized for loading in specified locations of a DF Basket Assembly.

FUEL DEBRIS FUEL DEBRIS is ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting loose PWR fuel assembly parts.

GROSSLY BREACHED SPENT FUEL ROD A breach in the spent fuel cladding that is larger than a pinhole or hairline crack. A gross cladding breach may be established by visual examination with the capability to determine if the fuel pellet can be seen through the cladding, or through a review of reactor operating records indicating the presence of heavy metal isotopes.

INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

The facility within the perimeter fence licensed for storage of spent fuel within MAGNASTOR SYSTEMS (see also 10 CFR 72.3).

INITIAL PEAK PLANAR-AVERAGE ENRICHMENT The INITIAL PEAK PLANAR-AVERAGE ENRICHMENT is the maximum planar-average enrichment at any height along the axis of the fuel assembly. The INITIAL PEAK PLANAR-AVERAGE ENRICHMENT may be higher than the bundle (assembly) average enrichment.

LOADING OPERATIONS LOADING OPERATIONS include all licensed activities while a MAGNASTOR SYSTEM is being loaded with fuel assemblies.

LOADING OPERATIONS begin when the first assembly is placed in the TSC and end when the TSC is lowered into a CONCRETE CASK or MSO.

MAGNASTOR SYSTEM (MAGNASTOR)

The MAGNASTOR (Modular Advanced Generation Nuclear All-purpose STORage) SYSTEM includes the components certified for the storage of spent fuel assemblies at an ISFSI.

The MAGNASTOR SYSTEM consists of a STORAGE CASK and a TSC. A MAGNASTOR TRANSFER CASK (MTC),

Passive MAGNASTOR TRANSFER CASK (PMTC), or Lightweight MTC (LMTC) is provided and utilized to load and place a TSC in a CONCRETE CASK or MSO or to remove a TSC from a CONCRETE CASK or MSO.

(continued)

Definitions 1.1 Certificate of Compliance No. 1031 A1-4 Amendment No. 14 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.

NONFUEL HARDWARE NONFUEL HARDWARE is defined as reactor control components (RCCs), burnable poison absorber assemblies (BPAAs), 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 (BPAAs) 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). BPAAs 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.

(continued)

Definitions 1.1 Certificate of Compliance No. 1031 A1-5 Amendment No. 14 OPERABLE A system, component, or device is OPERABLE when it is capable of performing its specified safety functions.

PARTIAL LENGTH SHIELD ASSEMBLIES (PLSA)

PWR fuel assemblies that contain stainless steel inserts in the bottom of each fuel rod, reducing the active fuel length, and a natural uranium blanket at the top of the active core. PLSAs are sometimes used in reactors to reduce fast neutron fluence reaching the pressure vessel wall.

SPENT NUCLEAR FUEL (SNF)

Irradiated fuel assemblies consisting of end-fittings, grids, fuel 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 with a CONCRETE CASK LID or an MSO.

STORAGE OPERATIONS STORAGE OPERATIONS include all licensed activities that are performed at the ISFSI following placement of a STORAGE CASK 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 the TSC during LOADING OPERATIONS, TRANSFER OPERATIONS, and UNLOADING OPERATIONS. Either an MTC, PMTC, or LMTC may be used.

TRANSFER OPERATIONS TRANSFER OPERATIONS include all licensed activities involved in using an MTC, PMTC, or LMTC to move a loaded and sealed TSC from a CONCRETE CASK to another CONCRETE CASK or from an MSO to another MSO or from either a CONCRETE CASK or MSO to a TRANSPORT CASK.

TRANSPORT CASK TRANSPORT CASK is the transport packaging system for the high-capacity MAGNASTOR System TSCs that consists of a MAGNATRAN transport cask body, a bolted closure lid, and energy-absorbing upper and lower (front and rear) impact limiters. The MAGNATRAN packaging is used to transport a TSC containing spent fuel assemblies or Greater Than Class C (GTCC) waste.

(continued)

Definitions 1.1 Certificate of Compliance No. 1031 A1-6 Amendment No. 14 TRANSPORT OPERATIONS TRANSPORT OPERATIONS include all licensed activities performed on a loaded MAGNASTOR STORAGE CASK when it is being moved to and from its designated location on the ISFSI. TRANSPORT OPERATIONS begin when the loaded STORAGE CASK is placed on or lifted by a transporter and end when the STORAGE CASK is set down in its storage position on the ISFSI pad.

TRANSPORTABLE STORAGE CANISTER (TSC)

The TRANSPORTABLE STORAGE CANISTER (TSC) is the welded container consisting of a basket in a weldment 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 Part 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) For PWR SNF: 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.

Logical Connectors 1.2 Certificate of Compliance No. 1031 A1-7 Amendment No. 14 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in Technical Specifications are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

EXAMPLES The following examples illustrate the use of logical connectors.

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

LCO not met A.1 Verify...

AND A.2 Restore...

In this example, the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

(continued)

Logical Connectors 1.2 Certificate of Compliance No. 1031 A1-8 Amendment No. 14 EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

LCO not met A.1 Stop...

OR A.2.1 Verify...

AND A.2.2 A.2.2.1 Reduce...

OR A.2.2.2 Perform...

OR A.3 Remove...

This example represents a more complicated use of logical connectors. Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2.

The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Completion Times 1.3 Certificate of Compliance No. 1031 A1-9 Amendment No. 14 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify the lowest functional capability or performance levels of equipment required for safe operation of the facility. The ACTIONS associated with an LCO state conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, provided that MAGNASTOR is in a specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or MAGNASTOR is not within the LCO Applicability.

Once a Condition has been entered, subsequent subsystems, components, or variables expressed in the Condition, discovered to be not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

(continued)

Completion Times 1.3 Certificate of Compliance No. 1031 A1-10 Amendment No. 14 EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time not met B.1 Perform Action B.1 AND B.2 Perform Action B.2 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours Condition B has two Required Actions. Each Required Action has its own Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to complete action B.1 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND complete action B.2 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed for completing action B.1 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for completing action B.2 from the time that Condition B was entered. If action B.1 is completed within six hours, the time allowed for completing action B.2 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for completing action B.2 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

(continued)

Completion Times 1.3 Certificate of Compliance No. 1031 A1-11 Amendment No. 14 EXAMPLES (continued)

EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One system not within limit.

A.1 Restore system to within limit.

7 days B. Required Action and associated Completion Time not met.

B.1 Complete action B.1 AND B.2 Complete action B.2 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours When a system is determined not to meet the LCO, Condition A is entered. If the system is not restored within 7 days, Condition B is also entered, and the Completion Time clocks for Required Actions B.1 and B.2 start. If the system is restored after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

(continued)

Completion Times 1.3 Certificate of Compliance No. 1031 A1-12 Amendment No. 14 EXAMPLES (continued)

EXAMPLE 1.3-3 ACTIONS NOTE Separate Condition entry is allowed for each component.

CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met A.1 Restore compliance with LCO.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and associated Completion Time not met.

B.1 Complete action B.1 AND B.2 Complete action B.2 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours The Note above the ACTIONS table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each component, and Completion Times to be tracked on a per component basis. When a component is determined to not meet the LCO, Condition A is entered and its Completion Time starts. If subsequent components are determined to not meet the LCO, Condition A is entered for each component and separate Completion Times are tracked for each component.

IMMEDIATE COMPLETION TIME When Immediately is used as a Completion Time, the Required Action should be pursued without delay and in a controlled manner.

Frequency 1.4 Certificate of Compliance No. 1031 A1-13 Amendment No. 14 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting Condition for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

Each specified Frequency is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR) Applicability. The specified Frequency consists of requirements of the Frequency column of each SR.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only required when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

The use of met or performed in these instances conveys specific meanings. Surveillance is met only after the acceptance criteria are satisfied. Known failure of the requirements of Surveillance, even without Surveillance specifically being performed, constitutes a Surveillance not met.

(continued)

Frequency 1.4 Certificate of Compliance No. 1031 A1-14 Amendment No. 14 EXAMPLES The following examples illustrate the various ways that Frequencies are specified.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify pressure within limit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment or variables are outside specified limits, or the facility is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the facility is in a condition specified in the Applicability of the LCO, the LCO is not met in accordance with SR 3.0.1.

If the interval as specified by SR 3.0.2 is exceeded while the facility is not in a condition specified in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2, prior to entry into the specified condition. Failure to do so would result in a violation of SR 3.0.4.

(continued)

Frequency 1.4 Certificate of Compliance No. 1031 A1-15 Amendment No. 14 EXAMPLES (continued)

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limit Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to starting activity AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one-time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector AND indicates that both Frequency requirements must be met. Each time the example activity is to be performed, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to starting the activity.

The use of once indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by AND). This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2.

Thereafter indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the once performance in this example). If the specified activity is canceled or not performed, the measurement of both intervals stops. New intervals start upon preparing to restart the specified activity.

2.0 Certificate of Compliance No. 1031 A2-1 Amendment No. 14 2.0

[Reserved]

LCO Applicability 3.0 Certificate of Compliance No. 1031 A3-1 Amendment No. 14 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during specified conditions in the Applicability, except as provided in LCO 3.0.2.

LCO 3.0.2 Upon failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

LCO 3.0.3 Not applicable to MAGNASTOR.

LCO 3.0.4 When an LCO is not met, entry into a specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in specified conditions in the Applicability that are required to comply with ACTIONS or that are related to the unloading of MAGNASTOR.

Exceptions to this Condition are stated in the individual Specifications.

These exceptions allow entry into specified conditions in the Applicability where the associated ACTIONS to be entered allow operation in the specified conditions in the Applicability only for a limited period of time.

LCO 3.0.5 This exception to LCO 3.0.2 is not applicable for the MAGNASTOR SYSTEM to return to service under administrative control to perform the testing.

SR Applicability 3.0 Certificate of Compliance No. 1031 A3-2 Amendment No. 14 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be a failure to meet the LCO. Failure to perform Surveillance within the specified Frequency shall be a failure to meet the LCO, except as provided in SR 3.0.3. Surveillances do not have to be performed on equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as once, the above interval extension does not apply. If a Completion Time requires periodic performance on a once per basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed from the time of discovery up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is less.

This delay period is permitted to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered. When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

SR 3.0.4 Entry into a specified Condition in the Applicability of an LCO shall not be made, unless the LCOs Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with Actions or that are related to the unloading of MAGNASTOR.

Transportable Storage Canister (TSC) 3.1.1 Certificate of Compliance No. 1031 A3-3 Amendment No. 14 3.1 MAGNASTOR SYSTEM Integrity 3.1.1 Transportable Storage Canister (TSC)

LCO 3.1.1 The TSC shall be dry and helium filled. The following vacuum drying times, helium backfill and TSC transfer times shall be met as appropriate to the fuel content type and heat load:

1.

The time durations covering the beginning of canister draining through completion of vacuum drying and helium backfill, minimum helium backfill times, and TSC transfer times shall meet the following:

A. PWR TSC Transfer Using MTC or LMTC Reduced Helium Backfill Time Heat Load (kW)

Maximum Vacuum Time Limit (hours)

Minimum Helium Backfill Time (hours)

Maximum TSC Transfer Time (hours) 20 No limit 0

600 25 50 7

70.5 30 19 7

8 35.5 15 7

8 B. PWR Using MTC or LMTC with Maximum TSC Transfer Heat Load (kW)

Maximum Vacuum Time Limit (hours)

Minimum Helium Backfill Time (hours)

Maximum TSC Transfer Time (hours) 25 No limit 24 48 30 32 24 22 35.5 24 24 22 C. BWR Using MTC or LMTC with 8 Hours TSC Transfer Heat Load (kW)

Maximum Vacuum Time Limit (hours)

Minimum Helium Backfill Time (hours)

Maximum TSC Transfer Time (hours) 25 No limit 0

8 29 34 6

8 30 31 6

8 33 26 6

8 (continued)

Transportable Storage Canister (TSC) 3.1.1 Certificate of Compliance No. 1031 A3-4 Amendment No. 14 D. BWR Using MTC or LMTC with Maximum TSC Transfer Heat Load (kW)

Maximum Vacuum Time Limit (hours)

Minimum Helium Backfill Time (hours)

Maximum TSC Transfer Time (hours) 25 No limit 24 65 29 No limit 24 32 30 44 24 32 33 33 24 32 E. PWR TSC Transfer Using PMTC1 Heat Load (kW)

Maximum Vacuum Time Limit (hours)

Minimum Helium Backfill Time (hours)

Maximum TSC Transfer Time (hours) 20 No limit 0

600 25 54 0

600 30 32 0

600 F. PWR TSC Transfer Using LMTC Heat Load (HL)

(kW)

Maximum Vacuum Time Limit (hours)

Minimum Helium Backfill Time (hours)

Maximum TSC Transfer Time (hours) 35.5<HL 42.5 19 12 16 G. BWR TSC Transfer Using LMTC Heat Load (HL)

(kW)

Maximum Vacuum Time Limit (hours)

Minimum Helium Backfill Time (hours)

Maximum TSC Transfer Time (hours) 33< HL 42.0 27 12 22 (continued) 1 CE 16 x 16 fuel only, with a maximum storage cell location heat load of 811 watts.

Transportable Storage Canister (TSC) 3.1.1 Certificate of Compliance No. 1031 A3-5 Amendment No. 14 H. BWR DF TSC Transfer Using LMTC Heat Load (kW)

Maximum Vacuum Time Limit (hours)

Minimum Helium Backfill Time (hours)

Maximum TSC Transfer Time (hours) 41.0 24 12 22

2. The time duration from the end of TSC annulus cooling, either by 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in the pool or by the annulus circulating water system, through completion of vacuum drying and helium backfill using a MTC shall not exceed the following:

Heat Load (HL) kW Time Limit (hours)

PWR 35.5 11 BWR 33 16 PWR (LMTC) 35.5<HL42.5 9

BWR (LMTC) 33<HL42.0 14 BWR-DF (LMTC) 41 13 Note:

For PWR TSCs with heat loads 35.5 kW using the MTC or LMTC Transfer Cask, the approved minimum helium backfill and transfer times shown in Table 1.B shall be used for operations for second and subsequent vacuum drying cycles.

For BWR TSC's with heat loads 33.0 kW using the MTC or LMTC Transfer Cask, the approved minimum helium backfill and transfer times shown in Table 1.D shall be used for operations for second and subsequent vacuum drying cycles.

For PWR TSCs with heat loads > 35.5 kW the approved minimum helium backfill and transfer times shown in Tables 1.F are applicable for second and subsequent vacuum drying cycles.

For BWR and BWR-DF TSCs with heat loads > 33.0 kW the approved minimum helium backfill and transfer times shown in Tables 1.G and 1.H respectively are applicable for second and subsequent vacuum drying cycles.

(continued)

Transportable Storage Canister (TSC) 3.1.1 Certificate of Compliance No. 1031 A3-6 Amendment No. 14

3. The time duration from the end of TSC annulus cooling, either by 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in the pool or by the annulus circulating water system, through completion of vacuum drying and helium backfill using a PMTC shall not exceed the following:

Heat Load Time Limit (hours)

PWR 25 34 PWR 30 17 Note: The helium backfill times and TSC transfer times provided in Table 1.E shall be used for operations following the second or subsequent vacuum drying cycles using the PMTC.

APPLICABILITY:

Prior to TRANSPORT OPERATIONS (continued)

Transportable Storage Canister (TSC) 3.1.1 Certificate of Compliance No. 1031 A3-7 Amendment No. 14 ACTIONS NOTE Separate Condition entry is allowed for each TSC.

CONDITION REQUIRED ACTION COMPLETION TIME A. TSC cavity vacuum drying pressure limit not met.

A.1 Perform an engineering evaluation to determine the quantity of moisture remaining in the TSC.

AND 7 days A.2 Develop and initiate corrective actions necessary to return the TSC to an analyzed condition.

30 days B. TSC helium backfill density limit not met.

B.1 Perform an engineering evaluation to determine the effect of helium density differential.

AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.2 Develop and initiate corrective actions necessary to return the TSC to an analyzed condition.

14 days C. Required Actions and associated Completion Times not met.

C.1 Remove all fuel assemblies from the TSC.

30 days (continued)

Transportable Storage Canister (TSC) 3.1.1 Certificate of Compliance No. 1031 A3-8 Amendment No. 14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify TSC cavity vacuum drying pressure is less than or equal to 10 torr for greater than or equal to 10 minutes with the vacuum pump turned off and isolated.

Once, prior to TRANSPORT OPERATIONS.

SR 3.1.1.2 Following vacuum drying and evacuation to

< 3 torr, backfill the cavity with high purity helium until a mass Mhelium corresponding to the free volume of the TSC measured during draining (VTSC), multiplied by the helium density (Lhelium) required for the design basis heat load and specified in Table A3-1, is reached.

Once, prior to TRANSPORT OPERATIONS.

Transportable Storage Canister (TSC) 3.1.1 Certificate of Compliance No. 1031 A3-9 Amendment No. 14 Table A3-1 Helium Mass per Unit Volume for MAGNASTOR TSCs Fuel Type Heat Load (HL)

(kW)

Helium Density (g/liter)

PWR 35.5 0.694 - 0.802 35.5 <HL<42.5 0.760 - 0.802 BWR 33.0 0.704 - 0.814 33.0 <HL<42.0 0.760 - 0.802

STORAGE CASK Heat Removal System 3.1.2 Certificate of Compliance No. 1031 A3-10 Amendment No. 14 3.1 MAGNASTOR SYSTEM Integrity 3.1.2 STORAGE CASK Heat Removal System LCO 3.1.2 The STORAGE CASK Heat Removal System shall be OPERABLE.

APPLICABILITY:

During STORAGE OPERATIONS ACTIONS NOTE Separate Condition entry is allowed for each MAGNASTOR SYSTEM.

CONDITION REQUIRED ACTION COMPLETION TIME A. STORAGE CASK Heat Removal System not OPERABLE.

A.1 Ensure adequate heat removal to prevent exceeding short-term temperature limits.

AND Immediately A.2 Restore STORAGE CASK Heat Removal System to OPERABLE status.

30 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify that the difference between the average STORAGE CASK air outlet temperature and ISFSI ambient temperature indicates that the STORAGE CASK Heat Removal System is operable in accordance with the FSAR thermal evaluation.

OR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months For PWR system 35.5 kW or BWR system 33 kW, visually verify more than 50% of each air inlet screen and air outlet screen of the STORAGE CASK are free of blockage.

For PWR system > 35.5 kW or BWR system > 33 kW, visually verify more than 50% of each air inlet screen and all of the air outlet screens of the STORAGE CASK are free of blockage.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Dissolved Boron Concentration 3.2.1 Certificate of Compliance No. 1031 A3-11 Amendment No. 14 3.2 MAGNASTOR SYSTEM Criticality Control for PWR Fuel 3.2.1 Dissolved Boron Concentration LCO 3.2.1 The dissolved boron concentration in the water in the TSC cavity shall be greater than, or equal to, the concentration specified in Appendix B, Table B2-4. A minimum concentration of 1,500 ppm is required for all PWR fuel types. Higher concentrations are required, depending on the fuel type and enrichment.

APPLICABILITY:

During LOADING OPERATIONS and UNLOADING OPERATIONS with water and at least one fuel assembly in the TSC.

ACTIONS NOTE Separate Condition entry is allowed for each TSC.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Dissolved boron concentration not met.

A.1 Suspend LOADING OPERATIONS or UNLOADING OPERATIONS AND Immediately A.2 Suspend positive reactivity additions.

AND Immediately A.3 Initiate action to restore boron concentration to within limits.

Immediately (continued)

Dissolved Boron Concentration 3.2.1 Certificate of Compliance No. 1031 A3-12 Amendment No. 14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify the dissolved boron concentration is met using two independent measurements.

Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to commencing LOADING OPERATIONS, UNLOADING OPERATIONS or adding/recirculating water through the TSC.

AND Every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months thereafter while the TSC contains water and is submerged in the spent fuel pool.

STORAGE CASK or MSO Maximum Surface Dose Rate 3.3.1 Certificate of Compliance No. 1031 A3-13 Amendment No. 14 3.3 MAGNASTOR SYSTEM Radiation Protection 3.3.1 STORAGE CASK Maximum Surface Dose Rate LCO 3.3.1 The maximum surface dose rates for the STORAGE CASK (Reference Figure A3-1) or (Reference Figure A3-2), shall not exceed the following limits:

a.

PWR and BWR - 120 mrem/hour gamma and 5 mrem/hour neutron on the vertical surfaces (at locations specified on Figures A3-1 and A3-2); and

b. PWR and BWR - 900 mrem/hour (neutron + gamma) on the top.

APPLICABILITY:

Prior to start of STORAGE OPERATIONS ACTIONS

NOTE----------------------------------------------------------------

Separate Condition entry is allowed for each MAGNASTOR SYSTEM.

CONDITION REQUIRED ACTION COMPLETION TIME A.

STORAGE CASK maximum surface dose rate limits not met A.1 Administratively verify correct fuel loading AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months A.2 Perform analysis to verify compliance with the ISFSI radiation protection requirements of 10 CFR Part 20 and 10 CFR Part 72 7 days B. Required Action and associated Completion Time not met B.1 Perform (and document) an engineering assessment and take appropriate corrective action to ensure the dose limits of 10 CFR Part 20 and 10 CFR Part 72 are not exceeded 60 days (continued)

STORAGE CASK or MSO Maximum Surface Dose Rate 3.3.1 Certificate of Compliance No. 1031 A3-14 Amendment No. 14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1 Verify maximum surface dose rates of STORAGE CASK loaded with a TSC containing fuel assemblies are within limits. Dose rates shall be measured at the locations shown in Figures A3-1 or A3-2.

Prior to start of STORAGE OPERATIONS of each loaded STORAGE CASK before or after placement on the ISFSI pad.

STORAGE CASK or MSO Maximum Surface Dose Rate 3.3.1 Certificate of Compliance No. 1031 A3-15 Amendment No. 14 Figure A3-1 STORAGE (CONCRETE) CASK Surface Dose Rate Measurement TSC mid-plane - approximately 92 inches from bottom. Measure dose rates at four target points (approximately 0, 90, 180 & 270 degrees) on the mid-plane.

Measure dose rates at approximate 70-inch diameter at four points approximately on 90-degree axes.

STORAGE CASK or MSO Maximum Surface Dose Rate 3.3.1 Certificate of Compliance No. 1031 A3-16 Amendment No. 14 Figure A3-2 MSO Surface Dose Rate Measurement

TSC Surface Contamination 3.3.2 Certificate of Compliance No. 1031 A3-17 Amendment No. 14 3.3 MAGNASTOR SYSTEM Radiation Protection 3.3.2 TSC Surface Contamination LCO 3.3.2 Removable contamination on the exterior surfaces of the TSC shall not exceed:

a.

10,000 dpm/100 cm2 from beta and gamma sources; and

b.

100 dpm/100 cm2 from alpha sources.

APPLICABILITY:

During LOADING OPERATIONS ACTIONS

NOTE-----------------------------------------------------

Separate Condition entry is allowed for each MAGNASTOR SYSTEM.

CONDITION REQUIRED ACTION COMPLETION TIME A. TSC removable surface contamination limits not met A.1 Restore TSC removable surface contamination to within limits Prior to TRANSPORT OPERATIONS (continued)

TSC Surface Contamination 3.3.2 Certificate of Compliance No. 1031 A3-18 Amendment No. 14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2 Verify by either direct or indirect methods that the removable contamination on the exterior surfaces of the TSC is within limits Once, prior to TRANSPORT OPERATIONS

Design Features 4.0 Certificate of Compliance No. 1031 A4-1 Amendment No. 14 4.0 DESIGN FEATURES 4.1 Design Features Significant to Safety 4.1.1 Criticality Control a) Minimum 10B loading in the neutron absorber material:

Neutron Absorber Type Required Minimum Effective Areal Density (10B g/cm2)

% Credit Used in Criticality Analyses Required Minimum Actual Areal Density (10B g/cm2)

PWR Fuel BWR Fuel PWR Fuel BWR Fuel Borated Aluminum Alloy 0.036 0.027 0.04 0.03 0.030 0.0225 90 0.0334 0.025 0.027 0.020 0.03 0.0223 Borated MMC 0.036 0.027 0.04 0.03 0.030 0.0225 90 0.0334 0.025 0.027 0.020 0.03 0.0223 Boral 0.036 0.027 0.048 0.036 0.030 0.0225 75 0.04 0.030 0.027 0.020 0.036 0.0267 Enrichment/soluble boron limits for PWR systems and enrichment limits for BWR systems are incorporated in Appendix B Section 2.0.

b) Acceptance and qualification testing of borated aluminum alloy and borated MMC neutron absorber material shall be in accordance with Sections 10.1.6.4.5, 10.1.6.4.6 and 10.1.6.4.7. Acceptance testing of Boral shall be in accordance with Section 10.1.6.4.8. These sections of the FSAR are hereby incorporated into the MAGNASTOR CoC.

c) Soluble boron concentration in the PWR fuel pool and water in the TSC shall be in accordance with LCO 3.2.1, with a minimum water temperature 5-10°F higher than the minimum needed to ensure solubility.

d) Minimum fuel tube outer diagonal dimension PWR basket 13.08 inches BWR basket 8.72 inches Note: Not applicable to DFC locations of the DF Basket Assembly.

4.1.2 Fuel Cladding Integrity The licensee shall ensure that fuel oxidation and the resultant consequences are precluded during canister loading and unloading operations.

(continued)

Design Features 4.0 Certificate of Compliance No. 1031 A4-2 Amendment No. 14 4.1.3 Transfer Cask Shielding For the MTC and PMTC Transfer Casks, the nominal configuration transfer cask radial bulk shielding (i.e., shielding integral to the transfer cask; excludes supplemental shielding) must provide a 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).

For the LMTC Transfer Cask the nominal configuration transfer cask radial bulk shielding (i.e., shielding integral to the transfer cask, excludes supplemental shielding) is variable to permit maximizing the LMTC shielding configuration to take advantage of the Site's architecture while complying with the host Site's ALARA evaluation as required in Section 5.5 - Radiation Protection Program. This design and evaluation approach permits the quantity of shielding around the body of the transfer cask to be maximized for a given length and weight of fuel specific to the host Site.

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).

4.2 Codes and Standards The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2001 Edition with Addenda through 2003,Section III, 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 III, Subsection NG, is the governing Code for the design, material procurement, fabrication and testing of the spent fuel baskets.

The American Concrete Institute Specifications ACI-349 and ACI-318 govern the CONCRETE CASK design and construction, respectively

Design Features 4.0 Certificate of Compliance No. 1031 A4-3 Amendment No. 14 The concrete used in the construction of the CONCRETE CASK LID, at minimum, shall be of a commercial grade ready-mix type that can develop a density of 140 pcf. The mix and batching should meet the purchasers requirement of unit weight (i.e., density) and any additional purchaser indicated attributes (e.g., air content),

as allowed by ASTM C94.

The unit weight (i.e., density) of the concrete in the CONCRETE CASK LID can be verified by either test method ASTM C138 or an approved shop fabrication procedure by following the basic equation of =W/V. The shop procedure shall include steps to weigh the lid before and after concrete placement and in calculating the actual volume (V) of the cavity to be filled with a record of the weight (W) of concrete placed into the cavity.

The CONCRETE CASK LID concrete placement shall be in a dry and clean cavity or form with procedures and equipment that ensure the concrete placed is thoroughly consolidated and worked around any reinforcement and/or embedded fixtures and into the corners of the cavity or form.

The CONCRETE CASK LID concrete shall be protected from the environment during curing to minimize development of cracks by one or more of various methods such as moist cure or liquid membrane forming chemicals. Type II Portland cement may be substituted by an alternate cement type for the CONCRETE CASK LID if the density requirement can be met.

The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2001 Edition with Addenda through 2003,Section III, 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 (AWS) 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)

Design Features 4.0 Certificate of Compliance No. 1031 A4-4 Amendment No. 14 4.2.2 Construction/Fabrication Alternatives to Codes, Standards, and Criteria Proposed alternatives to ASME Code,Section III, 2001 Edition with Addenda through 2003, other than the alternatives listed in Table 2.1-2 of the FSAR, may be used when authorized by the Director of the Office of Nuclear Material Safety and Safeguards or designee. The request for such alternatives should demonstrate that:

1.

The proposed alternatives would provide an acceptable level of quality and safety, or 2.

Compliance with the specified requirements of ASME Code,Section III, Subsections NB and NG, 2001 Edition with Addenda through 2003, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Requests for alternatives shall be submitted in accordance with 10 CFR 72.4.

4.3 Site-Specific Parameters and Analyses This section presents site-specific parameters and analytical bases that must be verified by the MAGNASTOR SYSTEM user. The parameters and bases presented in Section 4.3.1 are those applied in the design bases analysis.

4.3.1 Design Basis Specific Parameters and Analyses The design basis site-specific parameters and analyses that require verification by the MAGNASTOR SYSTEM user are:

a.

A temperature of 76ºF is the maximum average yearly temperature. The three-day average ambient temperature shall be 106ºF.

b.

The allowed temperature extremes, averaged over a three-day period, shall be

-40ºF and 133ºF.

c.

The analyzed flood condition of 15 fps water velocity and a depth of 50 ft of water (full submergence of the loaded cask) are not exceeded.

d.

The potential for fire and explosion shall be addressed, based on site-specific considerations. This includes the condition that the fuel tank(s) of the cask handling equipment used to move the loaded STORAGE CASK or MSO onto or from the ISFSI site contains a total of no more than 50 gallons of fuel.

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.

(Continued)

Design Features 4.0 Certificate of Compliance No. 1031 A4-5 Amendment No. 14 f.

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

g.

The STORAGE CASK shall not be lifted by the lifting lugs with surrounding air temperatures < 0ºF.

h.

Loaded STORAGE CASK lifting height limit 24 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.

In cases where the TRANSFER CASK or STORAGE CASK containing the loaded TSC must be tilted or down-ended to clear an obstruction (e.g., a low door opening) during on-site transport operations, a site specific safety evaluation of the system in the non-vertical orientation is required in accordance with 10 CFR 72.212 to demonstrate compliance with the thermal limits of ISG-11.

(Continued)

Design Features 4.0 Certificate of Compliance No. 1031 A4-6 Amendment No. 14 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 Part 50 licensed facility or for utilizing an external crane structure integral to a 10 CFR Part 50 licensed facility.

Movements of the TRANSFER CASK and TSC outside of a 10 CFR Part 50 licensed facility are not permitted unless a TSC TRANSFER FACILITY is designed, operated, fabricated, tested, inspected, and maintained in accordance with the following requirements. These requirements do not apply to handling heavy loads under a 10 CFR Part 50 license.

The permanent or stationary weldment structure of the TSC TRANSFER FACILITY shall be designed to comply with the stress limits of ASME Code,Section III, Subsection NF, Class 3 for linear structures. All compression loaded members shall satisfy the buckling criteria of ASME Code,Section III, Subsection NF.

The reinforced concrete structure of the facility shall be designed in accordance with ACI-349 and the factored load combinations set forth in ACI-318 for the loads defined in Table A4-1 shall apply. TRANSFER CASK and TSC lifting devices installed in the handling facility shall be designed, fabricated, operated, tested, inspected, and maintained in accordance with NUREG-0612, Section 5.1.

If mobile load lifting and handling equipment is used at the facility, that equipment shall meet the guidelines of NUREG-0612, Section 5.1, with the following conditions:

a. The mobile lifting device shall have a minimum safety factor of two over the allowable load table for the lifting device in accordance with the guidance of NUREG-0612, Section 5.1.6 (1)(a), and shall be capable of stopping and holding the load during a design earthquake event;

b. The mobile lifting device shall contain 50 gallons of fuel during operation inside the ISFSI;

c. Mobile cranes are not required to meet the guidance of NUREG-0612, Section 5.1.6(2) for new cranes;

d. The mobile lifting device shall conform to the requirements of ASME B30.5, Mobile and Locomotive Cranes;

e. Movement of the TSC or STORAGE CASK in a horizontal orientation is not permitted.

(Continued)

Design Features 4.0 Certificate of Compliance No. 1031 A4-7 Amendment No. 14 Table A4-1 Load Combinations and Service Condition Definitions for the TSC Handling and Transfer Facility Structure Load Combination ASME Section III Service Condition for Definition of Allowable Stress Note D*

D + S Level A All primary load bearing members must satisfy Level A stress limits D + M + W1 D + F D + E D + Y Level D Factor of safety against overturning shall be 1.1, if applicable.

D

=

Crane hook dead load D*

=

Apparent crane hook dead load S

=

Snow and ice load for the facility site M

=

Tornado missile load of the facility site1 W

=

Tornado wind load for the facility site1 F

=

Flood load for the facility site E

=

Seismic load for the facility site Y

=

Tsunami load for the facility site 1.

Tornado missile load may be reduced or eliminated based on a Probabilistic Risk Assessment for the facility site.

Administrative Controls and Programs 5.0 Certificate of Compliance No. 1031 A5-1 Amendment No. 14 5.0 ADMINISTRATIVE CONTROLS AND PROGRAMS 5.1 Radioactive Effluent Control Program 5.1.1 A program shall be established and maintained to implement the requirements of 10 CFR 72.44 (d) or 10 CFR 72.126, as appropriate.

5.1.2 The MAGNASTOR SYSTEM does not create any radioactive materials or have any radioactive waste treatment systems. Therefore, specific operating procedures for the control of radioactive effluents are not required. LCO 3.3.2, TSC Surface Contamination, provides assurance that excessive surface contamination is not available for release as a radioactive effluent.

5.1.3 This program includes an environmental monitoring program. Each general license user may incorporate MAGNASTOR SYSTEM operations into their environmental monitoring program for 10 CFR Part 50 operations.

5.2 TSC Loading, Unloading, and Preparation Program A program shall be established to implement the FSAR, Chapter 9 general procedural guidance for loading fuel and components into the TSC, unloading fuel and components from the TSC, and preparing the TSC and STORAGE CASK for storage. The requirements of the program for loading and preparing the TSC shall be completed prior to removing the TSC from the 10 CFR Part 50 structure. The program requirements for UNLOADING OPERATIONS shall be maintained until all spent fuel is removed from the spent fuel pool and TRANSPORT OPERATIONS have been completed on the last STORAGE CASK. The program shall provide for evaluation and control of the following requirements during the applicable operation:

a. Verify that no TRANSFER CASK handling or STORAGE CASK handling using the lifting lugs occurs when the ambient temperature is < 0°F. This limit is NOT applicable to the stainless steel MTC or PMTC.

b. The water temperature of a water-filled, or partially filled, loaded TSC shall be shown by analysis and/or measurement to be less than boiling at all times.

c. Verify that the drying time, cavity vacuum pressure, and component and gas temperatures ensure that the fuel cladding temperature limit of 400°C is not exceeded during TSC preparation activities, including TRANSFER OPERATIONS, and that the TSC is adequately dry. For fuel with burnup

> 45 GWd/MTU, limit cooling cycles to 10 for temperature changes greater than 65ºC.

d. Verify that the helium backfill purity and mass assure adequate heat transfer and preclude fuel cladding corrosion.

e. The integrity of the inner port cover welds to the closure lid at the vent port and at the drain port shall be verified in accordance with the procedures in Section 9.1.1 for the MTC or 9.4.1 for the PMTC.

(continued)

Administrative Controls and Programs 5.0 Certificate of Compliance No. 1031 A5-2 Amendment No. 14 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 STORAGE CASK are adequate to allow proper storage and to assure consistency with the offsite dose analysis.

h.

The equipment used to move the loaded STORAGE CASK 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 or STORAGE CASK using devices that are integral to a structure governed by 10 CFR Part 50 regulations, 10 CFR Part 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 STORAGE CASK 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 STORAGE CASK lift heights ensure that the g-load limits analyzed in the FSAR are not exceeded.

(continued)

Administrative Controls and Programs 5.0 Certificate of Compliance No. 1031 A5-3 Amendment No. 14 5.5 Radiation Protection Program 5.5.1 Each cask user shall ensure that the 10 CFR Part 50 radiation protection program appropriately addresses dry storage cask loading and unloading, and ISFSI operations, including transport of the loaded STORAGE CASK outside of facilities governed by 10 CFR Part 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 users 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 STORAGE CASK, TSC and TRANSFER CASK, and procedures for the verification of meeting the established limits prior to removal of the components from the 10 CFR Part 50 structure. Surface contamination limits for the TSC prior to placement in STORAGE OPERATIONS shall meet the limits established in LCO 3.3.2.

5.5.5 The nominal configuration transfer cask radial bulk shielding (i.e., shielding integral to the transfer cask, excludes supplemental shielding) is variable to permit maximizing the LMTC shielding configuration to take advantage of the Site's architecture while complying with the host Site's ALARA evaluation as required in Section 5.5 - Radiation Protection Program. This design and evaluation approach permits the quantity of shielding around the body of the transfer cask to be maximized for a given length and weight of fuel specific to the host Site.

5.5.6 Supplemental shielding used, credited, or otherwise incorporated into the analysis as the basis of complying with the LMTC surface dose rate analysis in section 5.5.5 shall be referenced in the licensee's evaluation and required for use. This shall include material, thickness, specific shape and configuration and location the Supplemental Shielding was used in the evaluation.

5.5.7 Supplemental shielding used for the LMTC dose rate analysis as described in 5.5.6 shall be implemented by the licensee for the condition(s) it was evaluated for.

Administrative Controls and Programs 5.0 Certificate of Compliance No. 1031 A5-4 Amendment No. 14 5.5.8 If draining the LMTC Neutron Shield is required to meet the plant architectural limits, the LMTC Neutron Shield shall be verified to be filled after completion of the critical lift. If TSC cavity draining or transfer cask/dry storage cask annulus draining operations, as applicable, are initiated after the completion of the critical lift, the LMTC Neutron Shield shall be verified to be filled before these draining operations are initiated and continually monitored during the first five minutes of the draining evolution to ensure the Neutron Shield remains filled. Observation of water level in the expansion tank or some other means can be used to verify compliance to this requirement.

5.6

[Deleted]

5.7 Training Program A training program for the MAGNASTOR system shall be developed under the general licensees systematic approach to training (SAT). Training modules shall include comprehensive instructions for the operation and maintenance of the MAGNASTOR system and the independent spent fuel storage installation (ISFSI) as applicable to the status of ISFSI operations.

(Continued)

Administrative Controls and Programs 5.0 Certificate of Compliance No. 1031 A5-5 Amendment No. 14 5.8 Preoperational Testing and Training Exercises A dry run training exercise on loading, closure, handling, unloading, and transfer of the MAGNASTOR system shall be conducted by the licensee prior to the first use of the system to load spent fuel assemblies. The training exercise shall not be conducted with spent fuel in the TSC. The dry run may be performed in an alternate step sequence from the actual procedures, but all steps must be performed. The dry run shall include, but is not limited to, the following:

a.

Moving the STORAGE CASK or MSO into its designated loading area b.

Moving the TRANSFER CASK containing the empty TSC into the spent fuel pool c.

Loading one or more dummy fuel assemblies into the TSC, including independent verification d.

Selection and verification of fuel assemblies to ensure conformance with appropriate loading configuration requirements e.

Installing the closure lid f.

Removal of the TRANSFER CASK from the spent fuel pool g.

Closing and sealing of the TSC to demonstrate pressure testing, vacuum drying, helium backfilling, welding, weld inspection and documentation, and leak testing h.

TRANSFER CASK movement through the designated load path i.

TRANSFER CASK installation on the CONCRETE CASK or MSO j.

Transfer of the TSC to the CONCRETE CASK or MSO k.

CONCRETE CASK LID or MSO lid assembly installation l.

Transport of the STOREAGE CASK to the ISFSI

m. TSC removal from the STORAGE CASK n.

TSC unloading, including reflooding and weld removal or cutting Appropriate mock-up fixtures may be used to demonstrate and/or to qualify procedures, processes or personnel in welding, weld inspection, vacuum drying, helium backfilling, leak testing and weld removal or cutting. Previously completed and documented demonstrations of specific processes and procedures may be used, as applicable, for implementation of the MAGNASTOR SYSTEM at a specific loading facility.

THIS PAGE INTENTIONALLY LEFT BLANK to ED20230100 Page 1 of 1 FSAR Changed Pages and LOEP for MAGNASTOR FSAR Amendment 14 Initial Submittal Revision 23C (Docket No 72-1031)

NAC International July 2023

Atlanta Corporate Headquarters: 3930 East Jones Bridge Road, Norcross, Georgia 30092 USA Phone 770-447-1144, Fax 770-447-1797, www.nacintl.com July 2023 Docket No. 72-1031 MAGNASTOR (Modular Advanced Generation Nuclear All-purpose STORage)

FINAL SAFETY ANALYSIS REPORT NON-PROPRIETARY VERSION Revision 23C

MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C List of Effective Pages Page 1 of 7 Chapter 1 Page 1-i...................................... Revision 13 Page 1-1..................................... Revision 13 Page 1.1-1.................................. Revision 13 Page 1.1-2.................................... Revision 5 Page 1.1-4 thru 1.1-7................ Revision 23C Page 1.2-1.................................. Revision 13 Page 1.2-2.................................... Revision 5 Page 1.3-1.................................. Revision 13 Page 1.3-2 thru 1.3-3.................... Revision 5 Page 1.3-4 thru 1.3-23................ Revision 13 Page 1.4-1.................................. Revision 11 Page 1.5-1.................................. Revision 13 Page 1.6-1.................................. Revision 13 Page 1.6-2.................................... Revision 0 Page 1.7-1.................................... Revision 0 Page 1.7-2.................................. Revision 13 Page 1.8-1 thru 1.8-2.................. Revision 13 36 drawings (see Section 1.8)

Chapter 2 Page 2-i thru 2-ii........................ Revision 13 Page 2-1....................................... Revision 5 Page 2.1-1.................................... Revision 5 Page 2.1-2.................................. Revision 13 Page 2.1-3.................................... Revision 5 Page 2.1-4.................................. Revision 11 Page 2.1-5.................................... Revision 5 Page 2.2-1.................................... Revision 5 Page 2.2-2 thru 2.2-7.................. Revision 11 Page 2.2-8.................................... Revision 6 Page 2.3-1 thru 2.3-10................ Revision 13 Page 2.4-1.................................... Revision 0 Page 2.4-2 thru 2.4-7.................. Revision 13 Page 2.5-1.................................. Revision 13 Page 2.6-1.................................... Revision 0 Page 2.6-2.................................. Revision 13 Chapter 3 Page 3-i...................................... Revision 11 Page 3-ii..................................... Revision 13 Page 3-iii...................................... Revision 9 Page 3-iv...................................... Revision 5 Page 3-v thru 3-vi......................... Revision 9 Page 3-vii thru 3-x..................... Revision 13 Page 3-1....................................... Revision 0 Page 3.1-1 thru 3.1-6.................. Revision 13 Page 3.2-1 thru 3.2-2.................. Revision 13 Page 3.2-3 thru 3.2-6.................. Revision 11 Page 3.2-7.................................. Revision 13 Page 3.3-1.................................... Revision 0 Page 3.4-1 thru 3.4-2.................. Revision 13 Page 3.4-3.................................... Revision 6 Page 3.4-4.................................... Revision 1 Page 3.4-5.................................... 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 3.4-50................ Revision 9 Page 3.4-51 thru 3.4-54.............. Revision 11 Page 3.4-55 thru 3.4-57................ Revision 9 Page 3.4-58 thru 3.4-64.............. Revision 11 Page 3.5-1.................................. Revision 13 Page 3.5-2 thru 3.5-4.................... Revision 9 Page 3.5-5.................................... Revision 6 Page 3.5-6.................................. Revision 13 Page 3.5-7 thru 3.5-9.................... Revision 6 Page 3.5-10................................ Revision 13 Page 3.5-11 thru 3.5-13................ Revision 6 Page 3.5-14................................ Revision 13 Page 3.5-15................................ Revision 11 Page 3.5-16 thru 3.5-17................ Revision 6 Page 3.5-18................................ Revision 13 Page 3.5-19.................................. Revision 6 Page 3.5-20................................ Revision 13 Page 3.5-21 thru 3.5-26................ Revision 6 Page 3.5-27................................ Revision 11 Page 3.5-28 thru 3.5-30................ Revision 8 Page 3.6-1 thru 3.6-2.................. Revision 13 Page 3.6-3 thru 3.6-4.................... Revision 9 Page 3.6-5 thru 3.6-19.................. Revision 6 Page 3.7-1.................................. Revision 13 Page 3.7-2.................................... Revision 9 Page 3.7-3 thru 3.7-5.................. Revision 13 Page 3.7-6.................................... Revision 6 Page 3.7-7.................................. Revision 13 Page 3.7-8 thru 3.7-9.................... Revision 6

MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C List of Effective Pages (contd)

Page 2 of 7 Page 3.7-10................................ Revision 13 Page 3.7-11................................ Revision 11 Page 3.7-12 thru 3.7-13................ Revision 6 Page 3.7-14................................ Revision 13 Page 3.7-15.................................. Revision 6 Page 3.7-16................................ Revision 13 Page 3.7-17 thru 3.7-21................ Revision 6 Page 3.7-22................................ Revision 13 Page 3.7-23 thru 3.7-25................ Revision 6 Page 3.7-26................................ Revision 13 Page 3.7-27.................................. Revision 6 Page 3.7-28 thru 3.7-30.............. Revision 13 Page 3.7-31.................................. Revision 6 Page 3.7-32................................ Revision 13 Page 3.7-33.................................. Revision 6 Page 3.7-34................................ Revision 13 Page 3.7-35 thru 3.7-37................ Revision 6 Page 3.7-38 thru 3.7-40.............. Revision 13 Page 3.7-41 thru 3.7-46................ Revision 6 Page 3.7-47 thru 3.7-56.............. Revision 13 Page 3.7-57 thru 3.7-59.............. Revision 11 Page 3.7-60 thru 3.7-61................ Revision 8 Page 3.7-62 thru 3.7-64................ Revision 6 Page 3.7-65.................................. Revision 8 Page 3.7-66.................................. Revision 6 Page 3.7-67 thru 3.7-68................ Revision 8 Page 3.7-69.................................. Revision 6 Page 3.7-70 thru 3.7-72................ Revision 8 Page 3.7-73 thru 3.7-80................ Revision 6 Page 3.7-73 thru 3.7-78................ Revision 6 Page 3.7-79 thru 3.7-80................ Revision 8 Page 3.7-81.................................. Revision 6 Page 3.8-1 thru 3.8-3................ Revision 23C Page 3.8-4 thru 3.8-5.................... Revision 0 Page 3.8-6................................ Revision 23C Page 3.8-7.................................... Revision 0 Page 3.8-8 thru 3.8-10.............. Revision 23C Page 3.9-1.................................... Revision 0 Page 3.9-2 thru 3.9-3................ Revision 23C Page 3.10-1.................................. Revision 0 Page 3.10.1-1............................... Revision 5 Page 3.10.1-2 thru 3.10.1-4.......... Revision 2 Page 3.10.1-5............................... Revision 1 Page 3.10.1-6 thru 3.10.1-32........ Revision 5 Page 3.10.2-1 thru 3.10.2-26........ Revision 4 Page 3.10.3-1 thru 3.10.3-2.......... Revision 8 Page 3.10.3-3............................... Revision 0 Page 3.10.3-4 thru 3.10.3-23........ Revision 1 Page 3.10.3-24............................. Revision 8 Page 3.10.3-25 thru 3.10.3-38...... Revision 1 Page 3.10.4-1 thru 3.10.4-2.......... Revision 1 Page 3.10.4-3 thru 3.10.4-9.......... Revision 0 Page 3.10.4-10............................. Revision 1 Page 3.10.4-11 thru 3.10.4-14...... Revision 0 Page 3.10.5-1............................... Revision 1 Page 3.10.5-2............................... Revision 2 Page 3.10.5-3 thru 3.10.5-4........ Revision 11 Page 3.10.5-5 thru 3.10.5-9.......... Revision 9 Page 3.10.6-1 thru 3.10.6-2.......... Revision 5 Page 3.10.6-3............................... Revision 4 Page 3.10.6-4 thru 3.10.6-6.......... Revision 5 Page 3.10.6-7 thru 3.10.6-10........ Revision 4 Page 3.10.6-11 thru 3.10.6-13...... Revision 2 Page 3.10.6.14 thru 3.10.6-16...... Revision 4 Page 3.10.6-17 thru 3.10.6-18...... Revision 2 Page 3.10.6-19............................. Revision 4 Page 3.10.6-20 thru 3.10.6-21...... Revision 2 Page 3.10.6-22 thru 3.10.6-34...... Revision 4 Page 3.10.7-1 thru 3.10.7-2.......... Revision 0 Page 3.10.8-1............................... Revision 4 Page 3.10.8-2............................... Revision 2 Page 3.10.8-3 thru 3.10.8-8.......... Revision 0 Page 3.10.9-1............................... Revision 6 Page 3.10.9-2............................... Revision 4 Page 3.10.9-3 thru 3.10.9-11........ Revision 0 Page 3.10.10-1 thru 3.10.10-8...... Revision 5 Page 3.11-1 thru 3.11-28............ Revision 11 Page 3.12-1................................ Revision 13 Page 3.12.1-1 thru 3.12.1-7........ Revision 13 Page 3.12.2-1 thru 3.12.2-4........ Revision 13 Page 3.12.3-1 thru 3.12.3-3........ Revision 13 Page 3.12.4-1 thru 3.12.4-23...... Revision 13 Chapter 4 Page 4-i........................................ Revision 9 Page 4-ii..................................... Revision 13 Page 4-iii...................................... Revision 9 Page 4-iv.................................... Revision 11

MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C List of Effective Pages (contd)

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MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C List of Effective Pages (contd)

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MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C List of Effective Pages (contd)

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MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C List of Effective Pages (contd)

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MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C List of Effective Pages (contd)

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MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C NAC International 1.1-3 The BWR DF Basket Assembly has a capacity of up to 81 undamaged BWR fuel assemblies, including twelve DFC locations. BWR DFCs may be placed in up to twelve of the DFC locations. Each of the twelve DFC locations may contain an undamaged BWR fuel assembly, a damaged BWR fuel assembly, an unchanneled CILC fuel assembly, or BWR fuel debris equivalent to one BWR fuel assembly. A damaged BWR fuel assembly, BWR fuel debris, or an unchanneled CILS fuel assembly must be stored inside a BWR DFC in a DFC location. Undamaged BWR fuel assemblies, with or without channels, and channeled CILC fuel may be placed directly in the DFC locations.

Damaged Fuel (DF)

Spent nuclear fuel (SNF) that cannot fulfill its fuel-specific or system-related function. Spent fuel is classified as damaged under the following conditions.

1) There is visible deformation of the rods in the SNF assembly.

Note: This is not referring to the uniform bowing that occurs in the reactor; this refers to bowing that significantly opens up the lattice spacing.

2) Individual fuel rods are missing from the assembly and the missing rods are not replaced by a solid stainless steel or zirconium dummy rod that displaces a volume equal to, or greater than, the original fuel rod.

3) The SNF assembly has missing, displaced or damaged structural components such that:

3.1) Radiological and/or criticality safety is adversely affected (e.g., significantly changed rod pitch); or 3.2) The assembly cannot be handled by normal means (i.e., crane and grapple); or 3.3) The PWR SNF assembly contains fuel rods with damaged or missing grids, grid straps, and/or grid springs producing an unsupported length greater than 60 inches.

Note: PWR SNF assemblies with the following structural defects meet MAGNASTOR system-related functional requirements and are, therefore, classified as undamaged: Assemblies with missing or damaged grids, grid straps and/or grid springs resulting in an unsupported fuel rod length not to exceed 60 inches.

4) Any SNF assembly that contains fuel rods for which reactor operating records (or other records or tests) cannot support the conclusion that they do not contain gross breaches.

Note: Breached fuel rods with minor cladding defects (i.e, pinhole leaks or hairline cracks that will not permit significant release of particulate matter from the spent fuel rod) meet MAGNASTOR system-related functional requirements and are, therefore, classified as undamaged. BWR fuel assemblies identified as subjected to CILC failure are not considered damaged fuel provided the fuel assemblies is channeled.

5) FUEL DEBRIS such as ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting loose BWR or PWR fuel assembly parts.

MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C NAC International 1.1-4 Damaged Fuel Can (DFC)

A specially designed stainless steel screened can sized to hold an undamaged BWR or PWR fuel assembly, a damaged BWR or PWR fuel assembly, and/or fuel debris. The DFC screens preclude the release of gross particulate from the DFC into the canister cavity. BWR and PWR DFCs are only authorized for loading in specified locations of the respective BWR and PWR DF Basket Assemblies.

Factor of Safety An analytically determined value defined as the allowable stress or displacement of a material divided by its calculated stress or displacement.

Fuel Basket (Basket)

The structure inside the TSC that provides structural support, criticality control, and heat transfer paths for the fuel assemblies.

Developed Cell A basket opening formed by either four fuel tubes or fuel tubes and basket weldments.

Fuel assemblies are loaded into the developed cells.

Fuel Tube A carbon steel tube with a square cross-section. Fuel assemblies are loaded into the fuel tubes. A fuel tube may have neutron absorber material attached on its interior faces.

Neutron Absorber A borated aluminum metal matrix or composite with neutron absorption capability.

Grossly Breached Spent Fuel Rod A breach in the spent fuel cladding that is larger than a pinhole or hairline crack. A gross cladding breach may be established by visual examination with the capability to determine if the fuel pellet can be seen through the cladding, or through a review of reactor operating records indicating the presence of heavy metal isotopes.

MAGNASTOR (Modular Advanced Generation, Nuclear, All-purpose STORage)

SYSTEM The components certified for the storage of spent fuel assemblies at an ISFSI. The MAGNASTOR System consists of a storage cask and a TSC. A transfer cask is provided and utilized to load and place a TSC in a storage cask or to remove a TSC from a storage cask.

Metal Storage Overpack (MSO)

The metal vertical storage module that receives, holds and protects the sealed TSC for storage at the ISFSI. The Metal Storage Overpack passively provides the radiation shielding, structural protection and heat dissipation capabilities for the safe storage of spent fuel in the TSC.

MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C NAC International 1.1-5 Base A carbon steel weldment incorporating the air inlets and the pedestal that supports the TSC inside of the MSO.

Lid A thick carbon steel closure with encapsulated NS-3 shielding material for the MSO.

The lid precludes access to the TSC and provides radiation shielding.

Inner and Outer Liners Carbon steel shells that form the inside and outside diameters of the MSO. The annulus formed by the inner and outer liners serves to encapsulate NS-3 shielding material. The liners and NS-3 provide radiation shielding and structural protection for the TSC.

Standoffs (Channels)

Carbon steel weldments attached to the liner that assist in centering the TSC in the MSO and supporting the TSC and its contents in a nonmechanistic tip-over event.

Nonfuel Hardware Nonfuel hardware is defined as reactor control components (RCCs), burnable poison absorber assemblies (BPAAs), guide tube plug devices (GTPDs), neutron sources/neutron source assemblies (NSAs), hafnium absorber assemblies (HFRAs), instrument tube tie components, in-core instrument thimbles, and 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 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 (BPAAs) 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). BPAAs 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.

MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C NAC International 1.1-6 Part Length Shield Assemblies (PLSAs)

PWR fuel assemblies that contain stainless steel inserts in the bottom of each fuel rod, reducing the active fuel length, and a natural uranium blanket at the top of the active core.

PLSAs are sometimes used in reactors to reduce fast neutron fluence reaching the pressure vessel wall.

Spent Nuclear Fuel (SNF), Spent Fuel Irradiated fuel assemblies consisting of end-fittings, grids, fuel 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 (fueled, stainless steel, or zirconium alloy). 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 a Metal Storage Overpack.

Transfer Cask A shielded device used to lift and handle the TSC during fuel loading and closure operations, as well as to transfer the TSC in/out of the storage cask during storage or in/out of a transport cask. The transfer cask includes two lifting trunnions and two shield doors that can be opened to permit the vertical transfer of the loaded TSC into the CC. There are three types of transfer cask, the first is the standard MAGNASTOR Transfer Cask (MTC) with solid neutron shielding. The MTC structural components are fabricated from either high-strength carbon steel (MTC1) or stainless steel (MTC2). The second type is the Passive MTC (PMTC) with demineralized water filled neutron shield tank. The PMTC is specifically designed for use in a high ambient temperature environment ( 104°F) and to passively cool the loaded TSC during transfer operations by convective air cooling equivalent to that provided by the storage cask. The PMTC is fabricated from stainless steel. The third type is the Lightweight MTC (LMTC), intended for use at facilities with limited crane capacity and for TSCs with high-heat loads. The LMTC includes a demineralized water-filled neutron shield tank that can be drained for pool loading operations to reduce the hook wet weight, then refilled to restore neutron shielding prior to performing canister draining, drying, and closure operations. The LTMC structural components are all fabricated from stainless steel.

Lifting Trunnions Two low-alloy steel components used to lift the transfer cask in a vertical orientation via a lifting assembly.

TSC (Transportable Storage Canister)

The stainless steel cylindrical shell, bottom-end plate, closure lid, closure ring, and redundant port covers that contain the fuel basket structure and the spent fuel contents.

MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C NAC International 1.1-7 Closure Lid A thick, stainless steel disk or a composite closure lid consisting of stainless steel and carbon steel plates bolted together and installed directly above the fuel basket following fuel loading. The closure lid is welded to the TSC shell and provides the confinement boundary for storage and operational shielding during TSC closure.

Drain and Vent Ports Penetrations located in the closure lid to permit draining, drying, and helium backfilling of the TSC.

Port Cover The stainless steel plates covering the vent and drain ports that are welded in place following draining, drying, and backfilling operations.

Shield Plate An electroless nickel-plated carbon steel disk that is bolted to the bottom of the closure lid of the composite closure lid assembly. The shield plate is installed directly above the fuel basket following fuel loading. The shield plate provides operational shielding during TSC closure.

Closure Ring A stainless steel ring welded to the closure lid and TSC shell to provide a double weld redundant sealing closure of the TSC satisfying 10 CFR 72.236(e) requirements.

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) For PWR SNF: Grid, grid strap and/or grid spring damage, provided that the unsupported length of the fuel rod does not exceed 60 inches.

MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C NAC International 3-i Chapter 3 Structural Evaluation Table of Contents 3

STRUCTURAL EVALUATION.................................................................................... 3-1 3.1 MAGNASTOR Structural Design................................................................................ 3.1-1 3.1.1 Major Components............................................................................................ 3.1-1 3.1.2 Discussion of MAGNASTOR.......................................................................... 3.1-3 3.1.3 Design Criteria Summary................................................................................. 3.1-6 3.2 Weights and Centers of Gravity.................................................................................... 3.2-1 3.2.1 Calculated Maximum Weights and Centers of Gravity.................................... 3.2-1 3.3 Materials....................................................................................................................... 3.3-1 3.4 General Standards for Casks......................................................................................... 3.4-1 3.4.1 Chemical and Galvanic Reactions.................................................................... 3.4-1 3.4.2 Positive Closure................................................................................................ 3.4-1 3.4.3 Lifting Devices.................................................................................................. 3.4-1 3.5 Normal Operating Conditions....................................................................................... 3.5-1 3.5.1 TSC Evaluation for Normal Operating Conditions.......................................... 3.5-1 3.5.2 Fuel Basket Evaluation for Normal Operating Conditions............................... 3.5-8 3.5.3 Concrete Cask Evaluations for Normal Operating Conditions....................... 3.5-27 3.6 Off-Normal Operating Events....................................................................................... 3.6-1 3.6.1 TSC Evaluations for Off-Normal Operating Events......................................... 3.6-1 3.6.2 Fuel Basket Evaluation for Off-Normal Operating Events............................... 3.6-6 3.6.3 Concrete Cask Evaluation for Off-Normal Operating Events....................... 3.6-19 3.7 Storage Accident Events............................................................................................... 3.7-1 3.7.1 TSC Evaluations for Storage Accident Conditions.......................................... 3.7-1 3.7.2 Fuel Baskets Evaluation for Storage Accident Events..................................... 3.7-7 3.7.3 Concrete Cask Evaluation for Storage Accident Events................................. 3.7-57 3.8 Fuel Rods...................................................................................................................... 3.8-1 3.8.1 PWR Fuel Rod Buckling Evaluation................................................................ 3.8-1 3.8.2 BWR Fuel Rod Buckling Evaluation................................................................ 3.8-6 3.8.3 Thermal Evaluation of Fuel Rods..................................................................... 3.8-7 3.8.4 Tip-over Evaluation.......................................................................................... 3.8-8 3.9 References..................................................................................................................... 3.9-1 3.10 Structural Evaluation Detail........................................................................................ 3.10-1 3.10.1 PWR Fuel Basket Finite Element Models................................................... 3.10.1-1 3.10.2 BWR Fuel Basket Finite Element Models................................................... 3.10.2-1

MAGNASTOR System FSAR October 2023 Docket No. 72-1031 Revision 14 NAC International 3-ii Table of Contents (cont'd) 3.10.3 TSC Finite Element Models......................................................................... 3.10.3-1 3.10.4 Concrete Cask Finite Element Models........................................................ 3.10.4-1 3.10.5 Transfer Cask Finite Element Models......................................................... 3.10.5-1 3.10.6 Basket Stability Evaluation for Concrete Cask Tip-Over Accident Condition...................................................................................................... 3.10.6-1 3.10.7 Fuel Tube Plastic Analysis for Concrete Cask Tip-Over Accident Condition...................................................................................................... 3.10.7-1 3.10.8 Basket Pin-Slot Connection Evaluation for Concrete Cask Tip-Over Accident Condition...................................................................................... 3.10.8-1 3.10.9 TSC-Basket Finite Element Models............................................................ 3.10.9-1 3.10.10 Structural Evaluation of the Damaged Fuel Can....................................... 3.10.10-1 3.11 Structural Evaluation for CC6 Concrete Cask............................................................ 3.11-1 3.11.1 Concrete Cask Lift.......................................................................................... 3.11-1 3.11.2 Normal Operating Conditions......................................................................... 3.11-9 3.11.3 Off-Normal Operating Events....................................................................... 3.11-14 3.11.4 Storage Accident Events............................................................................... 3.11-14 3.12 Structural Evaluation of the Metal Storage Overpack (MSO).................................... 3.12-1 3.12.1 MSO Lift...................................................................................................... 3.12.1-1 3.12.2 Normal Operating Conditions...................................................................... 3.12.2-1 3.12.3 Off-Normal Operating Events...................................................................... 3.12.3-1 3.12.4 Storage Accident Events.............................................................................. 3.12.4-1 3.13 Structural Evaluation for MAGNASTOR System with High Heat Loading.............. 3.13-1 3.13.1 TSC Evaluation............................................................................................ 3.13.1-1 3.13.2 Fuel Basket Evaluation................................................................................ 3.13.2-1 3.13.3 Concrete Cask Evaluation............................................................................ 3.13.3-1

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 3.8-1 3.8 Fuel Rods This section presents an evaluation of the design basis PWR and BWR fuel rods for the storage conditions of the MAGNASTOR system. Maximum stresses are shown to remain below the yield strength of the zirconium based alloy fuel rod cladding material. For PWR rods Zircaloy-4, ZIRLO, and M5 cladding materials are considered. For BWR rods Zircaloy-2 cladding material is considered.

3.8.1 PWR Fuel Rod Buckling Evaluation This section presents the buckling evaluation for MAGNASTOR high burnup PWR fuel (burnup greater than 45,000 MWd/MTU). A 120 micron reduction in cladding thickness is considered to account for the cladding oxide layer. These analyses show that the maximum stresses in the high burnup PWR fuel remain below the yield strength in the design basis accident events and confirm that the fuel rods will return to their original configuration. A 24-inch end drop orientation of the concrete cask subjects the fuel rods to axial loading. The 24-inch drop evaluation employs two acceleration time histories. The 24-inch concrete cask end drop described in Section 3.10.4.3 resulted in the acceleration time history shown in Figure 3.7.3-2.

The maximum acceleration for the time history shown in Figure 3.7.3-2 is 25.3gs (the strong segment of the pulse lasts for 0.015 second). A bounding triangular-shaped time history with a maximum acceleration of 45gs for a duration of 0.02 second is also used.

In the end drop orientation, the fuel rods are laterally restrained by the grids and come into contact with the fuel assembly base. The only vertical constraint for the fuel rod is the base of the assembly. As opposed to employing a straight fuel assembly in the evaluation with all the grids present, the fuel assembly is considered to be bowed, and a fuel assembly grid may be missing and still meet the acceptable configuration for undamaged fuel. The evaluation of the PWR fuel rods is based on the following representative samples.

Fuel Assembly Cladding Diameter (in)

Cladding Thickness (in)

Fuel Rod Pitch (in)

Gap Between Fuel Assembly and Fuel Tube Wall (in)

We 17x17 0.360 0.021 0.496 0.564 We 15x15 0.417 0.024 0.563 0.561 We 14x14 0.400 0.022 0.556 1.232 CE16x16 0.382 0.025 0.506 0.888 CE14x14 0.440 0.026 0.580 0.880 BW17x17 0.377 0.022 0.502 0.451 BW15x15 0.414 0.022 0.568 0.494

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 3.8-2 Review of the design basis fuel inventory indicates that the largest gap between the enveloping of the fuel rods of a straight fuel assembly and the basket fuel tube inner wall could be 1.23 inches, corresponding to a 14x14 rod array having a minimum rod pitch of 0.556 inch and a minimum rod diameter of 0.40 inch inside a maximum basket fuel cell with an inside dimension of 8.86 inches. In this evaluation, an assembly with an initial bow of 0.55 inch is permitted to displace an additional 0.68 inch to the full gap displacement of 1.23 inches. A PWR 17x17 fuel assembly with a bow of 0.55 inch (less than the gap of 0.564 inch, as shown in the preceding table) can still fit into a MAGNASTOR basket fuel tube. To implement a bow of 0.55 inch into the fuel assembly, the half-symmetry ANSYS model corresponding to a row of fuel rods (Figure 3.8.1-1) is used. The clad is modeled with shell elements (Figure 3.8.1-2). Each grid is modeled using brick elements to maintain the spacing between the fuel rods at the grid (Figure 3.8.1-2).

The fuel tube is modeled using brick elements to restrict the lateral motion of the fuel assembly.

Each of the fuel rods in the ANSYS model is simply supported at each end. A static force is applied to the ANSYS model at the grid nearest the axial center to develop a 0.55-inch lateral displacement. The purpose of the ANSYS model and solution is to provide the coordinates of the fuel clad for the LS-DYNA model. This is accomplished by obtaining a static solution with the ANSYS model, and then using the option to update the coordinates of the nodes based on the displacements from the solution.

Five LS-DYNA models are considered for the 24-inch cask end drop conditions. All models incorporate a bow of 0.55 inch. These cases envelop the range of the cross-sectional moments for the PWR fuel rods and the grid spacing at the bottom of the fuel assembly as summarized in the following table.

The 60-inch spacing corresponds to the fuel rod configuration with two missing grids at the bottom of the fuel assembly (grids 1 and 2 in Figure 3.8.1-1).

- Spacing between grids 1 and 2 in Figure 3.8.1-1.

Case Fuel Assembly Lowest Grid Spacing (inch)

Acceleration Definition 1

14x14 60*

45g 2

14x14 29.6 45g 3

17x17 60*

45g 4

17x17 29.6 45g 5

17x17 60*

25.3g

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 3.8-3 In all cases, the thickness of the clad was reduced by 120 microns (0.0047 inch). Cases 1 through 4 require a separate ANSYS model and LS-DYNA model to represent unique coordinates or boundary conditions (geometry of Case 5 is the same as for Case 3). The LS-DYNA model employs the same nodes and elements as the ANSYS model (with the incorporation of the 0.55-inch bow). Elastic properties are used in the ANSYS model and the bilinear properties are employed in the LS-DYNA model. An initial downward velocity of 136 in/sec (corresponding to a 24-inch end drop for the storage condition) is assigned to all nodes in the model. The deceleration time history is applied to the nodes of the brick elements representing the fuel tube. The side walls of the fuel tube are restrained in the lateral direction to maximize the effect of the fuel rods impacting the fuel tube side wall.

The LS-DYNA analyses for Cases 1 through 4 were performed for the duration of 0.08 second to capture the response of the fuel after the 0.02 second loading duration. Post-processing each analysis result identifies the maximum shear stress occurring at the shell surface. The maximum shear stress result from LS-DYNA is factored by two to determine the maximum stress intensity.

The following table contains the maximum stress intensity for the five cases.

Maximum Stress Intensity for the Five LS-DYNA Analyses Case Maximum Stress Intensity (ksi)

Factor of Safety Against Yield Strength 1

25.4 2.93 2

21.8 3.41 3

41.9 1.77 4

34.7 2.14 5

22.0 3.38 The case using the 60-inch spacing in conjunction with the minimal cross-section (Case 3) is identified as the bounding case. All stresses were shown to be less than the yield strength of 74.3 ksi. This yield strength corresponds to high burnup M5 cladding at a temperature of 350°C based on published test data [34] and temperature dependency [35]. The reported factors of safety are bounding for other cladding materials, as the yield strength of high burnup Zircaloy-4 and ZIRLO at 350°C exceeds that of M5.

The results confirm that high burnup PWR fuel with a maximum distance of 60 inches from the bottom to the first grid will remain structurally adequate for the storage design basis cask end drop load conditions.

MAGNASTOR System FSAR February 2009 Docket No. 72-1031 Revision 0 NAC International 3.8-4 Figure 3.8.1-1 Overall Model Plot for a Typical PWR Fuel Assembly

MAGNASTOR System FSAR February 2009 Docket No. 72-1031 Revision 0 NAC International 3.8-5 Figure 3.8.1-2 Detailed View of the PWR 14x14 Fuel Assembly

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 3.8-6 3.8.2 BWR Fuel Rod Buckling Evaluation The evaluation of the BWR fuel rod is based on the following representative samples of BWR fuel rods.

Fuel Assembly Cladding Diameter (in)

Cladding Thickness (in)

GE 7x7 0.563 0.032 GE 8x8-2 0.483 0.032 GE 8x8-4 0.484 0.032 GE 9x9-2 0.441 0.028 GE 10x10-2 0.378 0.024 The location of the lateral constraints in the BWR fuel are: 0.00 in, 22.88 in, 43.03 in, 63.18 in, 83.33 in, 103.48 in, 122.3 in, 143.78 in, and 163.42 inches.

For the PWR fuel rod (with all grids and with the 120-micron thickness reduction), the largest ratio of unsupported length (L) to radius of gyration of the cladding cross-section (r) is:

L/r =

29.6 0.5x(0.360-2x.)/2)(./)= 250 The ratio (L/r) for a BWR fuel rod (considering a 125-micron thickness reduction for the high burnup BWR fuel) is:

L/r =

(

)

(

)

185 2

/

330

.0 2

/)

0049

.0 2

378

.0

(

5.0 88 22 2

2

=

+

x

x The analysis presented in Section 3.8.1 is bounding for both PWR and BWR fuel rods because the L/r for the PWR fuel rod is larger than the L/r for the BWR fuel rod. Additionally, the yield strength of the BWR Zircaloy-2 cladding at 350°C is 78.3 ksi [27], which exceeds the yield strength used in Section 3.8.1. Therefore, no further evaluation of the BWR fuel rod for the 24-inch end drop condition is required.

MAGNASTOR System FSAR February 2009 Docket No. 72-1031 Revision 0 NAC International 3.8-7 3.8.3 Thermal Evaluation of Fuel Rods MAGNASTOR limits normal storage condition fuel cladding temperatures to be 400ºC (752ºF) in accordance with ISG-11, Rev 3. Zirconium alloy or stainless steel cladding degradation is not expected to occur below this temperature in an inert gas environment.

The fuel cladding temperature limit for short-term off-normal and accident events is 570°C (1,058ºF). Refer to Chapter 4, which demonstrates that the maximum fuel cladding temperatures are well below the temperature limits for all design conditions of storage.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 3.8-8 3.8.4 Tip-over Evaluation A structural evaluation is performed for PWR and BWR high burnup fuel rods for the non-mechanistic tip-over accident of the MAGNASTOR storage cask.

"NAC PROPRIETARY INFORMATION REMOVED"

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 3.8-9 "NAC PROPRIETARY INFORMATION REMOVED"

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 3.8-10 Figure 3.8.4-1 ANSYS Model for the PWR Fuel Rod High Burnup Condition

MAGNASTOR System FSAR February 2009 Docket No. 72-1031 Revision 0 NAC International 3.9-1 3.9 References

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

2. American National Standard for Radioactive Materials N14.6-1993, Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500 kg) or More, American National Standard Institute, Inc., Washington, DC, 1993.

3. NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, U. S. Nuclear Regulatory Commission, Washington, D.C., 1980.

4. ANSI/ANS-57.9-1992, American National Standard Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type), American Nuclear Society, La Grange Park, IL, May 1992.

5. Code Requirements for Nuclear Safety Related Concrete Structures (ACI 349-85) and Commentary (ACI 349R), American Concrete Institute, Farmington Hills, MI.

6. ASME Boiler and Pressure Vessel Code,Section III, Subsection NB, Class 1 Components, American Society of Mechanical Engineers, New York, NY, 2001 Edition with 2003 Addenda.

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

8. ASME Boiler and Pressure Vessel Code, Appendix F, Rules for Evaluation of Service Loadings with Level D Service Limits, The American Society of Mechanical Engineers, New York, NY, 2001, with 2003 Addenda.

9. NUREG/CR-6322, Buckling Analysis of Spent Fuel Basket, Lawrence Livermore National Laboratory, Livermore, CA, 1995.

10. AFFDL-TR-69-42, Stress Analysis Manual, Air Force Flight Dynamics Laboratory, Dayton, Ohio, 1969.

11. Steel Structures Design and Behavior, C.G. Salmon and J.E. Johnson, Harper and Row Publishers, New York, NY, Second Edition, 1980.

12. Machinerys Handbook, Industrial Press, New York, NY, 25th Edition, 1996.

13. Roarks Formulas for Stress & Strain, Warren C. Young, McGraw Hill, New York, NY, Sixth Edition, 1989.

14. Reinforced Concrete Design, Kenneth Leet, McGraw-Hill, New York, NY, Second Edition, 1991.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 3.9-2

15. Practical Stress Analysis in Engineering Design, Alexander Blake, Marcel Dekker, Inc., New York, NY, Second Edition, 1990.

16. NUREG-0800, Standard Review Plan, U.S. Nuclear Regulatory Commission Draft, Washington, DC, June 1987.

17. ASCE 7-93, Minimum Design Loads for Buildings and Other Structures, American Society of Civil Engineers, New York, NY, March 12, 1994.

18. NSS 5-940.1, A Review of Procedures for the Analysis and Design of Concrete Structures to Resist Missile Impact Effects, Nuclear and Systems Sciences Group, Holmes & Narver, Inc., Anaheim, CA, September 1975.

19. BC-TOP-9A, Revision 2, Topical Report, Design of Structures for Missile Impact, Bechtel Power Corporation, San Francisco, CA, September 1974.

20. Engineering Fluid Mechanics, J. A. Roberson and C. T. Crowe, Houghton Mifflin Co.,

Boston, MA, 1975.

21. ASCE 4-86, Seismic Analysis of Safety-Related Nuclear Structures and Commentary on Standard for Seismic Analysis of Safety-Related Nuclear Structures, American Society of Civil Engineers, New York, NY, 1986.

22. Structural Dynamics, John M. Biggs, McGraw-Hill, New York, NY, 1964.

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

24. Dynamics of Structures, R. W. Clough and Joseph Penzien, 2nd Edition, McGraw-Hill, Inc., New York, NY, 1993.

25. Nuclear Power Plant Engineering, J. H. Rust, Georgia Institute of Technology, 1979.

26. ISG-12, Revision 1, Buckling of Irradiated Fuel under Bottom End Drop Conditions, US Nuclear Regulatory Commission, Washington, DC, January 15, 2001.

27. Mechanical Properties for Irradiated Zircaloy, K. J. Geelhood and C. E. Beyer, Transactions - American Nuclear Society, 2005, Vol. 93, pages 707-708.

28. NUREG/CR-5009, Assessment of the Use of Extended Burnup Fuel in Light Water Power Reactors, Battelle Pacific Northwest Labs, Richland, Washington, February 1998.

29. ANSI N45.2.15 - 1981, Hoisting, Rigging and Transporting of Items for Nuclear Power Plants.

30. NUREG/CR-6007, Stress Analysis of Closure Bolts for Shipping Casks, January 1993.

31. ASME Boiler and Pressure Vessel Code,Section III, Subsection NF, Supports, American Society of Mechanical Engineers, New York, NY, 2001 Edition with 2003 Addenda.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 3.9-3

32. Volterra, Enrico and Gaines, J. H., Advanced Strength of Materials, Prentice-Hall, Inc.,

Englewood Cliffs, NJ, 1971.

33. U.S. Department of Energy, PNNL-17700, PNNL Stress/Strain Correlation for Zircaloy, Geelhood, K.J, et al., July 2008.

34. B. Cazalis, C., et al., The PROMETRA Program: A Reliable Material Database for Highly Irradiated ZIRCALOY-4, ZIRLOTM, and M5TM Fuel Claddings, Proceedings of the 18th International Conference on Structural Mechanics in Reactor Technology, Beijing, China, August 2005.

35. Bourdiliau, B, et al., Impact of Irradiation Damage Recovery During Transportation of the Subsequent Room Temperature Tensile Behavior of Irradiated Zirconium Alloys, JAI Vol. 7 No. 9.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 4.11.3-1 4.11.3 Off-Normal Events 4.11.3.1 Off-Normal Storage Events This section evaluates postulated off-normal storage conditions. The off-normal storage events include severe ambient temperature (106°F and -40°F) and half inlets blocked conditions. The evaluation of the off-normal events for variations in the ambient temperature only requires a change to the boundary condition temperature. For the half-blocked air inlets condition, the air inlet condition is modified to permit air flow through half of the inlet area. The heat load pattern Z is used for these analyses since it is the bounding case (see Table 4.11-1). The temperatures of different components for off-normal storage conditions are shown below.

Component 106°F Ambient, Maximum Temperatures

(°F)

-40°F Ambient, Maximum Temperatures

(°F) 76°F Ambient/Half Blocked Air Inlets Temperatures (°F)

Allowable Temperature

(°F)

Fuel Cladding 756 622 730 1,058 Fuel Basket 756 622 730 1,000 TSC Shell 461 330 439 800 Concrete 277 66 243 350 The maximum average helium temperature is 484°F for all off-normal conditions. This temperature is bounded by the average temperature of 495°F used in the internal pressure calculation shown in Section 4.5.1 for PWR fuel assemblies for off-normal events. Therefore, the maximum TSC internal pressure for off-normal events for the TSC containing the preferential loaded B&W 15x15 fuel is bounded by the internal pressure of 118 psig as calculated in Section 4.5.1.

Additionally, a sensitivity analysis is performed for an off-normal condition with half of the air inlets and half of the air outlets blocked for heat load pattern Z. The analysis is the same as the half inlets blocked case above, except that the outlet area is also reduced by half. The calculated maximum fuel cladding temperature and concrete temperature are 738°F and 253°F, respectively, which remain well below their allowable temperatures as listed in the table above.

The average helium temperature is calculated to be 468°F, which is also bounded by the temperature used in TSC internal pressure calculation in Section 4.5.1, as discussed above.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23C NAC International 8.3-1 8.3 Material Properties The mechanical properties of steels used in the fabrication of the MAGNASTOR components are presented in Table 8.3-1 through Table 8.3-21. The thermal properties of materials used in the fabrication and evaluation of the storage system are shown in Table 8.3-22 through Table 8.3-33. Derivation of effective thermal conductivities is described in Chapter 4. Table 8.3-22 through Table 8.3-33 include only the materials that form the heat transfer pathways employed in the thermal analysis models. Materials for small components, which are not explicitly modeled, are not included in the property tabulation.

Applicable mechanical material properties for irradiated zirconium based alloy fuel claddings are discussed in the fuel rod evaluations contained in Section 3.8.

MAGNASTOR System FSAR January 2011 Docket No. 72-1031 Revision 1 NAC International 8.3-2 Table 8.3-1 Mechanical Properties of SA240, Type 304, Stainless Steel Value at Temperature (°F)

Property (units)

-40

-20 70 200 300 400 500 650 800 900 Ultimate strength, Su (ksi) a 75.0 75.0 75.0 71.0 66.2 64.0 63.4 63.4 62.8 60.8 Yield Stress, Sy (ksi) a 30.0 30.0 30.0 25.0 22.4 20.7 19.4 18.0 16.9 16.2 Design Stress Intensity, Sm (ksi) a 20.0 20.0 20.0 20.0 20.0 18.7 17.5 16.2 15.2 14.6 b Modulus of Elasticity, E (x 106 psi) a 28.8 28.7 28.3 27.6 27.0 26.5 25.8 25.1 24.1 23.5 Coefficient of Thermal Expansion, (x10-6 in/in/°F) a 8.13b 8.2b 8.5 8.9 9.2 9.5 9.7 9.9 10.1 10.2 Poissons Ratio a 0.31 Density (lb/in3) c 0.29 Table 8.3-2 Mechanical Properties of SA182, Type F304 Stainless Steel (Size > 5 in)

Value at Temperature (°F)

Property (units)

-40 70 200 300 400 500 750 Ultimate strength, Su (ksi) a 70.0 70.0 66.3 61.8 59.7 59.2 59.0 Yield Stress, Sy (ksi) a 30.0 30.0 25.0 22.4 20.7 19.4 17.2 Design Stress Intensity, Sm (ksi) a 20.0 20.0 20.0 20.0 18.6 17.5 15.5 Modulus of Elasticity, E (x 106 psi) a 28.8 28.3 27.6 27.0 26.5 25.8 24.4 Coefficient of Thermal Expansion, (x10-6 in/in/°F) a 8.1 b 8.5 8.9 9.2 9.5 9.7 10.0 Poissons Ratio a 0.31 Density (lb/in3) c 0.29 Note: For thickness less than, or equal to, five inches, SA182, Type F304 stainless steel has equivalent mechanical properties to SA240, Type 304 stainless steel.

a ASME Boiler and Pressure Vessel Code [5]

b Extrapolated value c Metals Handbook Desk Edition [23]

MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C NAC International 8.12-3

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

32. ASME Boiler and Pressure Vessel Code,Section III, Subsection NF, American Society of Mechanical Engineers, New York, NY, 2001 Edition with 2003 Addenda.

33. ASTM B29-03, Standard Specification for Refined Lead, American Society for Testing and Materials, West Conshohocken, PA, 2003.

34. Cases of ASME Boiler and Pressure Vessel Code, Case N-707, Use of SA-537, Class A Plate for Spent-Fuel Containment Internals in Non-pressure Retaining Applications Above 700ºF (370ºC),Section III, Division 3.

35. B.F. Kammenzind, B. M. Berquist and R. Bajaj, The Long Range Migration of Hydrogen Through Zircaloy in Response to Tensile and Compressive Stress Gradients, Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, G.P. Sabol and G.D. Moan, Eds., American Society for Testing and Materials, pp. 196-233, 2000.

36. [DELETED]

37. Interim Staff Guidance -22, Potential Rod Splitting due to Exposure to an Oxidizing Atmosphere During Short-term Cask Loading Operations in LWR or Other Uranium Oxide Based Fuel, U.S. Nuclear Regulatory Commission, May 8, 2006.

38. Interim Staff Guidance-11, Revision 3, Cladding Considerations for the Transportation and Storage of Spent Fuel, U.S. Nuclear Regulatory Commission, November 17, 2003.

39. NUREG-1536, Standard Review Plan for Dry Cask Storage Systems, U.S. Nuclear Regulatory Commission, Washington, DC, January 1997.

40. PNL-6365, Evaluation of Cover Gas Impurities and Their Effects on the Dry Storage of LWR Spent Fuel, Pacific Northwest Laboratory, Richland, WA, November 1987.

41. NUREG/CR-1815, Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick, U.S. Nuclear Regulatory Commission, Washington, DC, June, 1981.

42. Emissivity Report Form, Petersen Incorporated, Procedure Number PSP-100189-02, Revision 2, February 5, 2018.

MAGNASTOR System FSAR July 2023 Docket No. 72-1031 Revision 23C NAC International 12.1-3 As shown in Section 4.4.1 and Section 4.4.3, the thermal analysis temperature results for the standard PWR basket bound the temperature results for the damaged fuel basket for normal operating conditions due to the higher thermal conductivity of the damaged fuel basket. For the same reasons, the temperature results for the blockage of one-half of the air inlets event are also bounded.

The thermal stress evaluation for the concrete cask for the one-half of the air inlets blocked event is bounded by those for the accident event of Maximum Anticipated Heat Load (133°F Ambient Temperature) as reported in Section 12.2.7. Note that evaluation of thermal stress is not required for the MSO. Thermal stress analyses for the TSC and the basket components are performed using ANSYS finite element models as described in Section 3.6. For the TSC and baskets, bounding temperature gradients are used to bound the one-half of the air inlets blocked condition. A summary of thermal stresses is presented in Section 3.6.

12.1.2.4 Corrective Actions No immediate corrective action is required for this event since the storage casks heat removal system is operable under one-half air inlet blocked conditions. However, the debris blocking the air inlet screens should be removed to ensure continued operability of the storage casks heat removal system. The nature of the debris may indicate that other actions are required to prevent recurrence of the blockage.

12.1.2.5 Radiological Impact There are no significant radiological consequences for the one-half of the air inlets blocked event on the concrete cask.

Personnel will be subject to an estimated maximum contact dose rate of 448 mrem/hr when clearing the inlet screens of a concrete cask containing a conservative 37 kW payload of PWR fuel. If it is assumed that a worker kneeling, with his hands at the inlet screens, would require 15 minutes to clear the screens, the estimated maximum extremity dose is 112 mrem. For clearing the inlet screens of a concrete cask containing a conservative 35 kW payload of BWR fuel, the maximum contact dose rate and the maximum extremity dose are estimated to be 364 mrem/hr and 91 mrem, respectively. The whole body dose in both the PWR and the BWR cases will be significantly less than the extremity doses.

Because the dose rates are based on a hybrid CC1/CC2 model without inlet shield, they bound dose rates calculated for the remaining concrete cask types, even those evaluated with higher heat loads, as all other cask types contain inlet shields as a required, not optional, component.

Impact of the one-half of the air inlets blockage event on the MSO is addressed within Chapter 5, Section 5.13, by applying NS-3 material properties bounded by those produced by this event. As the reported MSO air inlet dose rates of 323 mrem/hr is bounded by the 448 mrem/hr PWR concrete cask value the MSO impact is bounded by the PWR concrete cask.

Transportable Storage Canister (TSC) 3.1.1 NAC International 13C-15 MAGNASTOR FSAR, Revision 23C 3.1 MAGNASTOR SYSTEM Integrity 3.1.2 CONCRETE CASK or MSO Heat Removal System BASES BACKGROUND The heat removal system for the CONCRETE CASK or MSO containing a loaded TSC is a passive, convective air-cooled heat transfer system that ensures that the decay heat emitted from the TSC is transferred to the environment by the upward flow of air through the CONCRETE CASK or MSO annulus. During STORAGE OPERATIONS, ambient air is drawn into the CONCRETE CASK or MSO annulus through the four air inlets located at the base of the CONCRETE CASK or MSO. The heat from the TSC surfaces is transferred to the air flow via natural circulation. The buoyancy of the heated air creates a chimney effect forcing the heated air upward and drawing additional ambient air into the annulus through the air inlets. The heated air flows back to the ambient environment through the four air outlets located at the top of CONCRETE CASK or MSO.

APPLICABLE SAFETY ANALYSIS The thermal analyses of the MAGNASTOR SYSTEM take credit for the decay heat from the TSC contents being transferred to the ambient environment surrounding the CONCRETE CASK or MSO. Transfer of heat from the TSC contents ensures that the fuel cladding and TSC component temperatures do not exceed established limits. During normal STORAGE OPERATIONS, the four air inlets and four air outlets are unobstructed and full natural convection heat transfer occurs (i.e.,

maximum heat transfer for a given ambient temperature and decay heat load). Vent obstruction can be any type of accumulation within the vent that restricts airflow.

As presented in FSAR Section 4.5.1, steady state analyses were performed for an off-normal condition with half air Inlets blocked for MAGNASTOR PWR and BWR configurations with 35.5 kW and 33 kW respectively. The calculated maximum temperatures for the fuel cladding and concrete (720°F and 274°F respectively) are well below their temperature limits for off-normal conditions (1,058°F and 350°F respectively). It should be noted that the maximum temperatures for fuel and concrete are also below the corresponding temperature limits for normal conditions (752°F and 300°F for fuel cladding and concrete respectively). As shown in FSAR Section 4.11.3.1, a sensitivity analysis was performed for an additional off-normal steady state condition with two air inlets blocked and two air outlets blocked for a PWR system with a heat load of 35.5 kW. The analysis results show the increase in maximum temperatures due to the additional outlet vent blockage is 8°F for the fuel cladding and 10°F for the concrete which demonstrates that temperatures remain below the temperature limits for both normal and off-normal conditions. As shown in FSAR Section 4.13.3, steady state analyses were performed for the off-normal

Transportable Storage Canister (TSC) 3.1.1 NAC International 13C-16 MAGNASTOR FSAR, Revision 23C (continued)

BASES (continued)

APPLICABLE SAFETY ANALYSIS (cont.)

condition of half air inlets blocked for the PWR and BWR systems with heat loads of 42.5 kW and 42 kW respectively. The analysis results show that the maximum temperatures for the fuel cladding and concrete (752°F and 202°F respectively) are also within the temperature limits for both normal and off-normal conditions. Note that the TSC internal pressures for all the analyses described above are also less than analyzed maximum pressures for normal and off-normal conditions of storage. Based on the steady state analyses described above, the heat removal system is OPERABLE (fuel and system components meeting the temperature limits for off-normal condition) and provides sufficient heat removal function even for an indefinite time (fuel and system components meeting the temperature limits for normal condition) when the air inlets or outlets are in the following partially blocked condition:

For PWR system 35.5 kW or BWR system 33 kW, the heat removal system is OPERABLE when more than 50% of the air inlet area and more than 50% of the air outlet area are free of blockage.

For PWR system > 35.5 kW or BWR system > 33 kW, the heat removal system is OPERABLE when more than 50% of the air inlet area and all the air outlet area are free of blockage.

The complete blockage of all four air inlets effectively stops the transfer of the decay heat from the TSC due to the elimination of the convective air flow. The TSC will continue to radiate heat to the liner of the CONCRETE CASK or MSO. Upon loss of air cooling, the MAGNASTOR SYSTEM component temperatures will increase toward their respective established accident temperature limits. The spent fuel cladding and fuel basket and CONCRETE CASK or MSO structural component temperatures do not exceed their accident limits and the internal pressure in the TSC cavity will not reach the analyzed maximum pressure condition for approximately 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months after a complete blockage condition occurs. For the MAGNASTOR system with the MSO, the spent fuel cladding and fuel basket temperatures do not reach their accident limits and the TSC internal pressure will not reach the analyzed maximum pressure condition for a time period of approximately 80 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months .

Therefore, following the identification of a reduction in the heat dissipation capabilities of the CONCRETE CASK or MSO by the temperature-monitoring program or the visual inspection of the air inlet and outlet screens as described above for different blockage and heat load conditions, actions are to be taken immediately to ensure adequate heat removal to prevent the fuel cladding and system components from exceeding short-term temperature limits. Efforts to (continued)

Transportable Storage Canister (TSC) 3.1.1 NAC International 13C-17 MAGNASTOR FSAR, Revision 23C BASES (continued)

APPLICABLE SAFETY ANALYSIS (cont.)

reestablish full OPERABLE status for the CONCRETE CASK or MSO can then be undertaken in a controlled manner. If necessary, the TSC may be transferred into the TRANSFER CASK to permit full access to the base of the CONCRETE CASK or MSO for repairs with minimal radiological effects.

LCO The CONCRETE CASK or MSO heat removal system is to be verified to be OPERABLE to preserve the applicability of the design bases thermal analyses. The continued operability of the heat removal system ensures that the decay heat generated by the TSC contents is transferred to the ambient environment to maintain the fuel cladding and CONCRETE CASK or MSO and TSC temperatures within established limits.

APPLICABILITY The LCO is applicable during STORAGE OPERATIONS. Once the CONCRETE CASK or MSO lid is installed following transfer of a loaded TSC, the heat removal system is required to be OPERABLE to ensure adequate heat transfer.

ACTIONS A Note has been added to the Actions that states for this LCO, separate condition entry is allowed for each CONCRETE CASK or MSO. This is acceptable, as the Required Actions for each Condition provide appropriate compensatory measures for each CONCRETE CASK or MSO not meeting the LCO. Other CONCRETE CASK or MSO that do not meet the LCO are addressed by independent Condition entry and application of the associated Required Actions.

(continued)

Transportable Storage Canister (TSC) 3.1.1 NAC International 13C-18 MAGNASTOR FSAR, Revision 23C BASES (continued)

ACTIONS (cont.)

A.1 If the CONCRETE CASK or MSO heat removal system has been determined to be not OPERABLE, actions are to be taken immediately to ensure adequate heat removal capability to prevent exceeding fuel cladding and critical component short-term temperature limits. For PWR system 35.5 kW or BWR system 33 kW, adequate heat removal capability is ensured by having at least the equivalent area of two air inlets and two air outlets of the CONCRETE CASK or MSO unobstructed based on the analyzed steady state conditions previously discussed. For PWR system > 35.5 kW or BWR system > 33 kW, adequate heat removal capability is ensured by having at least the equivalent area of two air inlets and all air outlets of the CONCRETE CASK unobstructed. Alternatively, adequate heat removal can be verified by measuring the exit air temperature from the four air outlets and determining the temperature rise over the ISFSI ambient air temperature.

The restoration or verification must be completed immediately where immediately is defined as the required action should be pursued without delay in a controlled manner. Restoration of adequate heat removal must be completed within 58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months of the last operability determination to ensure the TSC internal pressure limit is not exceeded per the analysis in FSAR Section 12.2.13.3, which is the most restrictive time limit.

Thermal analyses of a fully blocked CONCRETE CASK air inlet condition show that fuel cladding and critical basket material accident temperatures and internal pressure limits could be exceeded over time.

As a result, requiring immediate verification, or restoration, of adequate heat removal capability will ensure that accident temperature and pressure limits are not exceeded. Once adequate heat removal has been reestablished or verified, the additional actions required to restore the CONCRETE CASK or MSO to OPERABLE status can be completed under A.2.

AND A.2 In addition to Required Action A.1, efforts are required to be continued to restore the CONCRETE CASK or MSO heat removal system to OPERABLE.

As long as adequate heat removal capability has been verified to exist, restoring the CONCRETE CASK or MSO heat removal system to fully OPERABLE is not an immediate concern. Therefore, restoring it to OPERABLE within 30 days is a reasonable Completion Time.

(continued)

Transportable Storage Canister (TSC) 3.1.1 NAC International 13C-19 MAGNASTOR FSAR, Revision 23C BASES (continued)

SURVEILLANCE REQUIREMENTS SR 3.1.2.1 The long-term integrity of the stored spent fuel is dependent on the continuing ability of the CONCRETE CASK or MSO to reject decay heat from the TSC to the ambient environment. Routine verification that the four air inlets and four air outlets are unobstructed and intact ensures that convective airflow through the CONCRETE CASK or MSO/TSC annulus is occurring and performing effective heat transfer.

Alternatively, the Surveillance Requirement can be fulfilled by measuring the exit air temperature from the four air outlets and determining the temperature rise over the ISFSI ambient air temperature. A minimum of two outlet air temperatures must be measured to provide an average outlet temperature to comply with Technical Specifications SURVEILLANCE REQUIREMENT 3.1.2.1. As long as the temperature increase of the convective airflow is less than the surveillance limits, adequate heat transfer is occurring to maintain CONCRETE CASK, TSC, and spent fuel cladding temperatures below their limits for normal and off-normal conditions of storage.

For PWR system 35.5 kW or BWR system 33 kW, if more than half of the air flow area at the inlets and more than half of the air flow area at the outlets of the CONCRETE CASK or MSO are blocked, the heat removal system will be rendered not OPERABLE and this LCO is not met. For PWR system > 35.5 kW or BWR system > 33 kW, if more than half of the air flow area at the inlets and any of the air flow area at the outlets of the CONCRETE CASK or MSO are blocked, the heat removal system will be rendered not OPERABLE and this LCO is not met. Actions are to be taken immediately to ensure adequate heat removal capability to prevent exceeding fuel cladding and critical component short-term temperature limits. Additional corrective actions are to be taken to remove all air inlet and outlet obstructions and return the CONCRETE CASK or MSO to a fully OPERABLE status.

The Frequency of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is reasonable based on the time necessary for the spent fuel cladding and CONCRETE CASK or MSO and TSC component temperatures to reach their short-term temperature limits and the internal pressure to increase to the accident condition pressure limit. The Frequency will allow appropriate corrective actions to be completed in a timely manner.

REFERENCES FSAR Section 4.4.

Dissolved Boron Concentration 3.2.1 NAC International 13C-20 MAGNASTOR FSAR, Revision 5 3.2 MAGNASTOR SYSTEM Criticality Control for PWR Fuel 3.2.1 Dissolved Boron Concentration BASES BACKGROUND A TRANSFER CASK with an empty TSC is placed into a spent fuel pool and loaded with fuel assemblies and associated NONFUEL HARDWARE meeting the requirements of Appendix B, Approved Contents for the MAGNASTOR SYSTEM.

After loading the TSC, a closure lid is installed on the TSC, the closure lid is welded to the TSC shell, and the water in the cavity is drained.

For those TSCs to be loaded with PWR fuel assemblies, credit is taken in the criticality analyses for boron dissolved in the water within the TSC cavity during the loading and TSC preparation up through the draining of the cavity water. To preserve the analyses bases, the dissolved boron concentration of the TSC cavity water must be verified to meet specified limits when there are fuel assemblies and water in the TSC.

This may occur during LOADING OPERATIONS and UNLOADING OPERATIONS.

APPLICABLE SAFETY ANALYSIS The spent fuel stored in the MAGNASTOR SYSTEM is required to remain subcritical (keff < 0.95) under all conditions of storage. The MAGNASTOR SYSTEM is analyzed to safely store a wide variety of spent fuel assembly types with differing initial enrichments and associated nonfuel hardware. For PWR SNF assemblies to be loaded in the TSCs, credit has been taken in the criticality analyses for neutron poison in the form of soluble boron in the water in the TSC cavity.

Compliance with this LCO preserves the assumptions made in the criticality analyses and ensures that the stored PWR SNF assemblies will remain subcritical with a keff < 0.95 while water is in the TSC.

LCO Compliance with this LCO ensures that the stored PWR SNF will remain subcritical with a keff < 0.95 while water is in the TSC. The LCO provides the minimum concentration of soluble boron required to be in the TSC cavity water based on the type, initial enrichment, and contained nonfuel hardware of the PWR fuel assembly.

All UNDAMAGED SNF ASSEMBLIES loaded into the TSC are limited by analysis to the maximum enrichments of 5.0 wt% 235U.

(continued)

ML23207A112

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