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NAC International, Inc., Final Safety Analysis Report, TMI Amendment 13 RAI Response Supplement, Revision 23D
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Site:	07201031
Issue date:	08/31/2023
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To:	; Office of Nuclear Material Safety and Safeguards
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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 August 2023 Docket No. 72-1031 MAGNASTOR (Modular Advanced Generation Nuclear All-purpose STORage)

FINAL SAFETY ANALYSIS REPORT TMI Amendment 13 RAI Response Supplement Revision 23D to ED20230118 Page 1 of 1 MAGNASTOR FSAR Amendment 13 Supplemental RAI Response Submittal Revision 23D (Docket No 72-1031)

NAC International August 2023

MAGNASTOR Docket No.: 72-1031 CoC No.: 1031 NAC INTERNATIONAL SUPPLEMENTAL RESPONSE TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION REQUEST FOR ADDITIONAL INFORMATION #1 July 2023 FOR REVIEW OF THE MAGNASTOR (CoC NO. 1031, DOCKET NO. 72-1031)

August 2023 Page 1 of 8

MAGNASTOR Docket No.: 72-1031 CoC No.: 1031 Page 2 of 8 TABLE OF CONTENTS MATERIALS EVALUATION.............................................................................................................................. 3 OPERATING PROCEDURES EVALUATION...................................................................................................... 6 CHANGES NOT RELATED TO QUESTIONS...................................................................................................... 8

NAC International MAGNASTOR Page 3 of 8 NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION MATERIALS EVALUATION 8-1.

Physical and Chemical Form of Filter Media: Please supplement the application to specify the physical and chemical form of the filter media associated with the FBM contents by including the following information:

A. Describe the components, parts, and/or materials that constitute the filter media.

B. Describe the physical and chemical form of the filter media (e.g., solids, liquids, gases, metallic materials and items, organic compounds, hydrogenous materials, water, etc.).

C. Describe how the filter media originated and are associated with FBM. For example, address whether the filter media were used during reactor operation; during the reactor accident; or whether they were used to facilitate removal of the damaged fuel and/or FBM from the reactor during the post-accident cleanup and decontamination.

D. Clarify whether the filter media are categorized as part of the FBM contents; whether they are considered separate from the FBM contents; whether they contain or are attached to the FBM contents; or whether they are categorized as WBL-internal dunnage components similar to the STA and DMC.

E. Clarify whether the filter media to be stored inside the FBM TSC and WBL are authorized for storage only with FBM or whether they may also be stored with actual intact spent fuel rods or segments of spent fuel rods.

FSAR section 1.4.2 states that filter media containing FBM or used fuel ((emphasis added)) may be loaded into the FBM TSC provided the filter media is metallic. The application then states that non-metallic media ((emphasis added)) may be permitted subject to gas generation limitations. The application states that filter media may account for potential sources of gas, in particular hydrogen, as a result of water retention. The application states that any potential retention must be accounted for within total allowed hydrogen generation; maximum hydrogen generation during storage and transportation will not exceed the lower explosive limit (4 percent molar volume). FSAR section 7.2.2 states that a limited quantity of moisture may remain trapped within the FBM, or within the filter media, post vacuum drying.

Based on review of this description of filter media, the staff identified that physical and chemical form of the filter media contents are not sufficiently described in the application such that staff can adequately evaluate physical and chemical stability of the filter media and their chemical compatibility with the FBM and the TSC internal components (WBL and dunnage) in the nitrogen gas environment.

The NRC staff is requesting this information to verify that the application includes an adequate description of the contents such that the staff can fully evaluate the physical and chemical stability of the filter media and FBM contents and verify that there will be no adverse reactions amongst the FBM and filter media contents, or between the contents and the TSC internal components (WBL and dunnage) in the nitrogen gas environment. The staff determined that this information is needed to evaluate the compliance of the MAGNASTOR FBM

NAC International MAGNASTOR Page 4 of 8 NAC International Response to Materials Evaluation RAI 8-1:

A. Descriptions of the components, parts, and materials that constitute the filter media are provided in Attachment 1 of this RAI response (TMI2 Primary Water Treatment System Waste Handling and Disposal, TMI2-EN-EV A-M-0042, Revision 0.). Updated the definition of FBM in FSAR Chapter 1 and the Technical Specifications to include FBM may be collected in Stainless Steel filter housings which are directly loaded into the FBM TSC.

B. Descriptions of the physical and chemical form of the filter media are provided in Attachment 1.

C. The filter media discussed in this application will have originated and are associated with post-accident cleanup and decontamination activities.

D. After the filter media can no longer be used for cleanup and decontamination activities, it will be considered FBM contents.

E. If it is determined during loading operations any of the materials are not associated with the TMI-2 cleanup and decontamination activities this would fall under proposed LCO 3.4.1 and would not be permitted to be loaded into and FBM TSC.

NAC International MAGNASTOR Page 5 of 8 NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION MATERIALS EVALUATION 8-2 Chemical Reactions in the Nitrogen Gas Environment: Considering the elemental and molecular contents of the FBM and filter media, please justify why nitrogen is an acceptable environment for the interior of the cask and provide information to demonstrate that the use of nitrogen as the TSC fill gas will not result in adverse chemical reactions with and amongst the FBM and filter media contents inside the WBL.

FSAR section 1.4.2 of the application includes a description of the physical and chemical form of the FBM contents and describes FBM as consisting of components or pieces of components associated with reactor operations that have been contaminated by spent nuclear fuel and/or the associated isotopes of spent nuclear fuel, including fission product contamination. The detailed description of the FBM in FSAR section 1.4.2 addresses a number of potential metallic materials, non-metallic materials, organic compounds, and hydrogenous compounds that may be intermixed with fission products and other radioisotopes from damaged fuel and activated non-fuel materials.

The application states that non-metallic FBM may be loaded into the FBM TSC provided that maximum hydrogen generation during storage and transportation will not exceed the lower explosive limit (4 percent molar volume) and system pressure is evaluated as acceptable. As addressed above for Materials Review RAI 8-1, the application also includes some description of filter media associated with the FBM; however, per RAI 8-1, the staff identified that the physical and chemical form of the filter media are not sufficiently described in the application.

FSAR section 8.10.1 of the application discusses the interior storage environment inside the sealed TSC. The TSC containing FBM is to be backfilled with nitrogen gas. This section of the application indicates that nitrogen backfill gas displaces oxygen inside the TSC, similar to how helium is used in backfilling the TSC. However, the application does not include specific information that demonstrates that adverse chemical reactions in the nitrogen environment are not a concern for the chemical elements and compounds that constitute the FBM and filter media.

The staff noted that, while nitrogen gas is sufficiently inert for many applications, unlike helium gas it cannot be assumed to be completely unreactive when used as a cover gas for all types of contents. Therefore, the staff determined that additional information is needed to evaluate the chemical stability of FBM and filter media contents in the nitrogen gas environment.

The NRC staff is requesting this information to verify that the application includes an adequate description of the contents such that the staff can fully evaluate the physical and chemical stability of the FBM and filter media contents and verify that there will be no adverse reactions amongst the FBM and filter media contents, or between the contents and the TSC internal components (WBL and dunnage) in the nitrogen gas environment. The staff determined that this information is needed to evaluate the compliance of the MAGNASTOR FBM storage system with the regulatory requirements of 10 CFR sections 72.120(d) and 72.236(h).

NAC International Response to Materials Evaluation RAI 8-2:

NAC has chosen to use a helium, as the backfill gas and for vacuum drying of the TSC and made the appropriate modification in FSAR Sections. Further information on the filter media is included as a response to RAI 8-1.

NAC International MAGNASTOR Page 6 of 8 NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION OPERATING PROCEDURES EVALUATION 9-1.

Provide information for justification on using heated nitrogen in the vacuum drying.

The applicant performed thermal analyses of vacuum drying using non-heated nitrogen gas in the TSC and presented the maximum temperatures in FSAR table 4.12-2 and then notes, in step 56 of FSAR section 9.7.1, that vacuum drying efficiency may be improved by injection of heated nitrogen followed by re-establishment of vacuum condition. This process may be repeated as needed.

Injection of heated nitrogen in loading operations may result in the temperatures greater than the maximum temperatures, as shown in FSAR table 4.12-2, which were calculated assuming non-heated nitrogen for vacuum phase. The applicant may need to setup a temperature limit of heated nitrogen and limit the number of repeated cycles.

The staff needs this information to determine compliance with 10 CFR 72.236(f).

NAC International Response to Operating Procedures Evaluation RAI 9-1:

The note was revised to clearly state the injection of helium (heated or non-heated) is done only when the FBM TSC internal pressure is under a vacuum condition (i.e., below atmospheric pressure).

Since the TSC/WBL remain under vacuum conditions during the introduction of heated helium to facilitate drying, the total mass of helium introduced into the system is limited. Based upon an energy balance, the limited mass of the injected helium, which is negligible compared to the mass of the system (FBM TSC and contents) would result in an insignificant change in the steady state conditions reported in FSAR Table 4.12-2.

The limitation of thermal cycles as applicable to HBU fuel are to ensure that the cladding is not damaged.

Given that the fuel within the TMI-2 core was not operated long enough prior to the accident to be classified as HBU fuel, the need to limit any thermal cycle events does not appear to be applicable. As described above, the total mass of helium introduced is limited and therefore is negligible with respect to thermal cycling of the FBM TSC and contents during the introduction of heated helium during the drying process.

NAC International MAGNASTOR Page 7 of 8 Section B

NAC International MAGNASTOR Page 8 of 8 NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CHANGES NOT RELATED TO QUESTIONS Section 9.7.2, Non-submerged (Dry) Loading and Closing the FBM TSC Using Standard MTC has been added to Chapter 9. This section describes the sequence of operations to perform the loading of FBM in a nonsubmerged (dry) configuration and subsequent closure of the FBM TSC in preparation for transferring the FBM TSC to the concrete cask. The empty FBM TSC is assumed to be positioned inside the transfer cask located at the designated workstation. This process is needed to load the FBM filter media collected in stainless steel filter housings, dried and inerted. Once dried the filter media will not be rewetted.

Chapter 9 Page 9.7-6, modified Step 41 where indicated.

Page 9.7-7, modified Step 48, 49,50, 51, 52 and 54 where indicated.

Page 9.7-8, modified Step 56 and 58 where indicated.

Page 9.7-10, modified Step 10 where indicated.

Page 9.7-11, modified Step 35 where indicated.

Page 9.7-12, modified Step 36, 38 and 40 where indicated.

Page 9.7-18, modified Step 18 where indicated.

Page 9.7-19, modified Step 25 where indicated.

Chapter 13 Page 13C-14, moved Action C.1 to the page 13C-15 Page 13C-15, added Action C.2 Page 13C-25, added FBM TSC to SR 3.3.1.1 Page 13C-26, clarified Background section to include TSC (with fuel or FBM) and updated LCO section surface contamination dose limits to align with limits presented in the Technical Specifications.

to ED20230118 Page 1 of 1 Proposed CoC Changes for MAGNASTOR FSAR Amendment 13 Supplemental RAI Response Submittal Revision 23D (Docket No 72-1031)

NAC International August 2023

Certificate of Compliance No. 1031 A-1 Amendment No. 13 APPENDIX A PROPOSED TECHNICAL SPECIFICATIONS AND DESIGN FEATURES FOR THE MAGNASTOR SYSTEM AMENDMENT 13

Certificate of Compliance No. 1031 A-2 Amendment No. 13 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 STORAGE CASK 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 STORAGE CASK Maximum Surface Dose Rate.......................................... A3-13 3.3.2 TSC Surface Contamination.......................................................................... A3-17 3.4 MAGNASTOR SYSTEM TMI-2 Fuel Bearing Material (FBM).............................. A3-18 3.4.1 FBM TSC Loading......................................................................................... A3-18 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...... A4-3 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. 13 List of Figures Figure A3-1 STORAGE 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. 13 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.

(continued)

Definitions 1.1 Certificate of Compliance No. 1031 A1-2 Amendment No. 13 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.

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 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: 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 (continued)

Definitions 1.1 Certificate of Compliance No. 1031 A1-3 Amendment No. 13 DAMAGED FUEL (CONTINUED) 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.

FUEL BEARING MATERIAL (FBM)

Fuel Bearing Material (FBM) is any component or pieces of components associated with Three Mile Island Unit 2 (TMI-2) reactor operations that have been contaminated by used (spent) nuclear fuel and or the associated isotopes in used (spent) nuclear fuel. The FBM is not capable of being separated between SNF and GTCC material, and the FBM contains fuel fragments with non-trivial quantities of SNF. Fission product contamination is included in the definition of FBM regardless of the location of the fission products (either associated with used fuel or has separated from used fuel within facilities via material volatility during and post reactor fuel melt). FBM may be associated with fuel assembly hardware components, non-fuel hardware (i.e., fuel assembly control components), or significantly activated non-fuel materials (e.g., reactor barrel) or be located away from the high activation region (e.g., heat exchangers). The FBM used fuel component may be present in forms ranging from thin coatings to chips and fines and up to larger adhered or loose debris. FBM may contain limited amount of non-metallic, non-spent fuel components (e.g.,

seals/wiring within pump or valves that have been contaminated). FBM may be collected in Stainless Steel filter housings which are directly loaded into the FBM TSC.

Fuel Bearing Material (FBM)

TSC TSC that contains FBM 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.

(continued)

Definitions 1.1 Certificate of Compliance No. 1031 A1-4 Amendment No. 13 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.

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.

(continued)

Definitions 1.1 Certificate of Compliance No. 1031 A1-5 Amendment No. 13 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 A1-6 Amendment No. 13 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 a 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 A1-7 Amendment No. 13 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. The FBM TSC contains a waste basket liner rather than a spent fuel basket.

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

UNDAMAGED FUEL SNF that can meet all fuel specific and system-related functions. UNDAMAGED FUEL is SNF that is not DAMAGED FUEL, as defined herein, and does not contain assembly structural defects that adversely affect radiological and/or criticality safety. As such, UNDAMAGED FUEL may contain:

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

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

Logical Connectors 1.2 Certificate of Compliance No. 1031 A1-8 Amendment No. 13 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 A1-9 Amendment No. 13 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 A1-10 Amendment No. 13 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 A1-11 Amendment No. 13 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 A1-12 Amendment No. 13 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 A1-13 Amendment No. 13 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 A1-14 Amendment No. 13 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 A1-15 Amendment No. 13 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 A1-16 Amendment No. 13 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. 13 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. 13 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. 13 3.1 MAGNASTOR SYSTEM Integrity 3.1.1 Transportable Storage Canister (TSC)

LCO 3.1.1 The TSC shall be dry and helium filled, as applicable. 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 0

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. 13 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 (kW)

Maximum Vacuum Time Limit (hours)

Minimum Helium Backfill Time (hours)

Maximum TSC Transfer Time (hours)

> 35.5 - 42.5 19 12 16 G. BWR TSC Transfer Using LMTC Heat Load (kW)

Maximum Vacuum Time Limit (hours)

Minimum Helium Backfill Time (hours)

Maximum TSC Transfer Time (hours)

> 33.0 - 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. 13 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 Time Limit (hours)

PWR 35.5 11 BWR 33 16 PWR (LMTC)

> 35.5 - 42.5 9

BWR (LMTC)

> 33.0 - 42.0 14 BWR-DF (LMTC) 41.0 13 Notes:

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 TSCs 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.

The FBM TSC has been evaluated at steady state conditions through all operations steps from canister draining through ISFSI placement LCO 3.1.1 time limits are not applicable to the FBM TSC.

(continued)

Transportable Storage Canister (TSC) 3.1.1 Certificate of Compliance No. 1031 A3-6 Amendment No. 13

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. 13 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.

FBM TSC is pressure backfilled and backfill density limit is not applicable.

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 C.2 Remove FBM from the FBM TSC 180 days (continued)

Transportable Storage Canister (TSC) 3.1.1 Certificate of Compliance No. 1031 A3-8 Amendment No. 13 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.

For FBM TSC cavity vacuum drying pressure is less than or equal to 3 torr for greater than or equal to 30 minutes with the vacuum pump turned off and isolated.

Once, prior to TRANSPORT OPERATIONS.

SR 3.1.1.2 For spent fuel 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.

For FBM following vacuum drying and evacuation to < 3 torr, backfill the cavity with helium to 1 atm (0 +2/-0psig)

Once, prior to TRANSPORT OPERATIONS.

Transportable Storage Canister (TSC) 3.1.1 Certificate of Compliance No. 1031 A3-9 Amendment No. 13 Table A3-1 Helium Mass per Unit Volume for MAGNASTOR TSCs Table A3-1 is not applicable to FBM TSCs.

Fuel Type & Heat Load Helium Density (g/liter)

PWR 35.5 kW 0.694 - 0.802

> 35.5 kW - < 42.5 kW 0.760 - 0.802 BWR 33.0 kW 0.704 - 0.814

> 33.0 kW - < 42.0 kW 0.760 - 0.802

STORAGE CASK Heat Removal System 3.1.2 Certificate of Compliance No. 1031 A3-10 Amendment No. 13 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 NOTES Separate Condition entry is allowed for each MAGNASTOR SYSTEM.

LCO 3.1.2 is not applicable to FBM TSC CONCRETE CASKS because an OPERABLE Heat Removal System is not required.

CONDITION REQUIRED ACTION COMPLETION TIME A. STORAGE CASK or Heat Removal System inoperable.

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 Visually verify all STORAGE CASK air inlet and outlet screens 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. 13 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 PWR 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.

LCO 3.2.1 is not applicable to the FBM 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. 13 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, 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 Maximum Surface Dose Rate 3.3.1 Certificate of Compliance No. 1031 A3-13 Amendment No. 13 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, BWR and FBM - 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, BWR and FBM - 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 20 and 10 CFR 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 20 and 10 CFR 72 are not exceeded 60 days (continued)

STORAGE Cask Maximum Surface Dose Rate 3.3.1 Certificate of Compliance No. 1031 A3-14 Amendment No. 13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1 Verify maximum surface dose rates of STORAGE CASK loaded with a TSC containing fuel assemblies or FBM are within limits. Dose rates shall be measured at the locations shown in Figure 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 Maximum Surface Dose Rate 3.3.1 Certificate of Compliance No. 1031 A3-15 Amendment No. 13 Figure A3-1 CONCRETE CASK Surface Dose Rate Measurement Measure dose rates at approximate 70-inch diameter at four points approximately on 90-degree axes.

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.

STORAGE Cask Maximum Surface Dose Rate 3.3.1 Certificate of Compliance No. 1031 A3-16 Amendment No. 13 Figure A3-2 MSO Surface Dose Rate Measurement

TSC Surface Contamination 3.3.2 Certificate of Compliance No. 1031 A3-17 Amendment No. 13 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 (with fuel or FBM) shall not exceed:

a.

20,000 dpm/100 cm2 from beta and gamma sources; and

b.

200 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 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.1 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

FBM TSC Loading 3.4.1 Certificate of Compliance No. 1031 A3-18 Amendment No. 13 3.4 MAGNASTOR SYSTEM TMI-2 Fuel Bearing Material (FBM) 3.4.1 FBM TSC Loading LCO 3.4.1 Non-TMI-2 originating fuel bearing material loaded into a TMI-2 FBM TSC.

APPLICABILITY:

During LOADING OPERATIONS for TMI-2 Decommissioning Activities.

ACTIONS

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

LCO is only applicable to TMI-2 FBM TSCs Separate Condition entry is allowed for each MAGNASTOR SYSTEM.

CONDITION REQUIRED ACTION COMPLETION TIME A. Non-TMI-2 originating fuel bearing material loaded into a TMI-2 FBM TSC A.1 Suspend LOADING OPERATIONS Immediately AND A.2 Remove material from FBM TSC and disposed of in accordance with applicable regulations Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 None Required None

DESIGN FEATURES 4.0 Certificate of Compliance No. 1031 A4-1 Amendment No. 13 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 0.036 0.027 0.04 0.03 Aluminum Alloy 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 5-10oF 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.

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 (continued)

DESIGN FEATURES 4.0 Certificate of Compliance No. 1031 A4-2 Amendment No. 13 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 Sites architecture while complying with the host Sites 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, the COMPOSITE CLOSURE LID and the FBM TSC 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.

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.

(continued)

DESIGN FEATURES 4.0 Certificate of Compliance No. 1031 A4-3 Amendment No. 13 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.

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.

(continued)

DESIGN FEATURES 4.0 Certificate of Compliance No. 1031 A4-4 Amendment No. 13 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 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.

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.

(continued)

DESIGN FEATURES 4.0 Certificate of Compliance No. 1031 A4-5 Amendment No. 13

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. 13 4.4 TSC Handling and Transfer Facility The TSC provides a leaktight confinement boundary and is evaluated for normal and off-normal handling loads. A handling and transfer facility is not required for TSC and TRANSFER CASK handling and transfer operations within a 10 CFR 50 licensed facility or for utilizing an external crane structure integral to a 10 CFR 50 licensed facility.

Movements of the TRANSFER CASK and TSC outside of a 10 CFR 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 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. 13 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. 13 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 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, 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. This does not apply to the FBM TSC.

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. This does not apply to the FBM TSC.

d. Verify that the helium backfill purity and mass assure adequate heat transfer and preclude fuel cladding corrosion. Note, only helium backfill pressure is applicable to FBM TSCs.

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.

(continued)

ADMINISTRATIVE CONTROLS AND PROGRAMS 5.0 Certificate of Compliance No. 1031 A5-2 Amendment No. 13

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. This does not apply to the FBM TSC.

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

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

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

a. Minimum 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. 13 5.5 Radiation Protection Program 5.5.1 Each cask user shall ensure that the 10 CFR 50 radiation protection program appropriately addresses dry storage cask loading and unloading, and ISFSI operations, including transport of the loaded STORAGE CASK outside of facilities governed by 10 CFR 50 as applicable. The radiation protection program shall include appropriate controls and monitoring for direct radiation and surface contamination, ensuring compliance with applicable regulations, and implementing actions to maintain personnel occupational exposures ALARA. The actions and criteria to be included in the program are provided as follows.

5.5.2 Each user shall perform a written evaluation of the TRANSFER CASK and associated operations, 30 days prior to first use, to verify that it meets public, occupational, and ALARA requirements (including shielding design and dose characteristics) in 10 CFR Part 20, and that it is consistent with the program elements of each 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 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 Sites architecture while complying with the host Sites 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 licensees 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. 13 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 TC/DSC 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. 13 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 CONCRETE CASK or MSO into its designated loading area

b. Moving the TRANSFER CASK containing the empty TSC into the spent fuel pool or fuel transfer canal, as applicable. The FBM TSCs may be loaded at a location not within the spent fuel pool or fuel transfer canal.

c. Loading one or more dummy fuel assemblies into the TSC, (or WBL into FBM TSC) including independent verification

d. Selection and verification of fuel assemblies to ensure conformance with appropriate loading configuration requirements or proper load distribution, as applicable.

e. Installing the closure lid

f. Removal of the TRANSFER CASK from the spent fuel pool or fuel transfer canal, as applicable. The FBM TSCs may be loaded at a location not within the spent fuel pool or fuel transfer canal.

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 or MSO lid assembly installation

l. Transport of the STORAGE 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.

Certificate of Compliance No. 1031 Amendment No. 13 APPENDIX B PROPOSED APPROVED CONTENTS FOR THE MAGNASTOR SYSTEM AMENDMENT 13

Certificate of Compliance No. 1031 B-1 Amendment No. 13 Appendix B Table of Contents 1.0 FUEL SPECIFICATIONS AND LOADING CONDITIONS......................................................... B1-1 2.0 FUEL TO BE STORED IN THE MAGNASTOR SYSTEM......................................................... B2-1 3.0 FUEL BEARING MATERIAL TO BE STORED IN THE MAGNASTOR SYSTEM................... B3-1 List of Figures Figure B2-1 Schematic of 37 - Fuel Storage Location Map......... B2-13 Figure B2-2

[DELETED].................................................................................................................. B2-14 Figure B2-3

[DELETED].... B2-14 Figure B2-4 Schematic of 89-Assembly BWR Basket.....................B2-31 Figure B2-5 Schematic of 81-Assembly BWR Basket................................................................... B2-32 Figure B2-6 BWR Partial Length Fuel Rod Location Sketches...................................................... B2-33 List of Tables Table B2-1 TSC with PWR Fuel Limits............................................................................................ B2-2 Table B2-2 PWR Fuel Loading Patterns......................................................................................... B2-5 Table B2-3 Bounding PWR Fuel Assembly Physical Characteristics............................................. B2-7 Table B2-4 Bounding PWR Fuel Assembly Loading Criteria - Enrichment/Soluble Boron Limits...................................................................................................................B2-8 Table B2-5 Additional SNF Assembly Cool Time Required to Load NONFUEL HARDWARE................................................................................................................. B2-9 Table B2-6 Allowed BPAA/NSA Burnup and Cool Time Combinations........................................ B2-10 Table B2-7 Allowed GTPD/NSA Burnup and Cool Time Combinations........................................ B2-10 Table B2-8 Minimum Cool Time Summary Table.......................................................................... B2-11 Table B2-9 TSC with BWR Fuel Limits.......................................................................................... B2-15 Table B2-10 BWR SNF Assembly Characteristics.......................................................................... B2-17 Table B2-10a BWR 89-Assembly Basket Fuel Loading Patterns..................................................... B2-18 Table B2-10b BWR 81-Assembly Basket Fuel Loading Patterns..................................................... B2-19 Table B2-10c BWR 89-Assembly Basket Minimum Cool Time Summary Table.............................. B2-20 Table B2-10d BWR 81-Assembly DF Basket Minimum Cool Time Summary Table........................ B2-20 Table B2-11 BWR SNF Assembly Loading Criteria........................................................................ B2-21 Table B2-12 BWR SNF Assembly Loading Criteria - Enrichment Limits for 87-Assembly and 82-Assembly Configurations.......................................................... B2-22 Table B2-12a BWR 89-Assembly Basket SNF Assembly Loading Criteria - Reduced Neutron Absorber Content - Enrichment Limits........................................................................................ B2-23 Table B2-12b BWR 89-Assembly Basket SNF Assembly Loading Criteria Assembly Load -

Absorber 0.027 10B g/cm2 - Preferential Loading Enrichment Limits....................... B2-24 Table B2-12c BWR 89-Assembly Basket SNF Assembly Loading Criteria -

Absorber 0.027 10B g/cm2 - Preferential Load/Underload Combination Enrichment Limits........................................................................................................................... B2-25 Table B2-12d BWR 81-Assembly Basket SNF Assembly Loading Criteria - Enrichment Limits..... B2-26 Table B2-12e BWR 81-Assembly Basket SNF Assembly Loading Criteria -

81-Assembly Load - Preferential Loading Enrichment Limits..................................... B2-27 Table B2-12f BWR 81-Assembly Basket SNF Assembly Loading Criteria -

Preferential Load/Underload Combination Enrichment Limits.................................... B2-28 Table B2-12g BWR Load Pattern Identifier Underload/Empty Location Key.................................... B2-29 Table B2-12h BWR CILC Fuel Assembly Enrichment Limits............................................................ B2-30 Table B2-13 PWR Loading Table - Low SNF Assembly Average Burnup Enrichment Limits........................................................................................................................... B2-34 Table B2-14 BWR Loading Table - Low SNF Assembly Average Burnup Enrichment Limits........................................................................................................................... B2-34 Table B2-15 Loading Table for PWR Fuel - 959 W/Assembly....................................................... B2-35

Certificate of Compliance No. 1031 B-2 Amendment No. 13 Table B2-16 Loading Table for PWR Fuel - 911 W/Assembly....................................................... B2-40 Table B2-17 Loading Table for PWR Fuel - 1,200 W/Assembly.................................................... B2-48 Table B2-18 Loading Table for PWR Fuel - 1,140 W/Assembly.................................................... B2-53 Table B2-19 Loading Table for PWR Fuel - 922 W/Assembly....................................................... B2-61 Table B2-20 Loading Table for PWR Fuel - 876 W/Assembly....................................................... B2-66 Table B2-21 Loading Table for PWR Fuel - 800 W/Assembly....................................................... B2-74 Table B2-22 Loading Table for PWR Fuel - 760 W/Assembly....................................................... B2-79 Table B2-23 Loading Table for BWR Fuel - 379 W/Assembly....................................................... B2-87 Table B2-24 Loading Table for BWR Fuel - 360 W/Assembly............................................................. B2-92 Table B2-25 Loading Table for PWR Fuel - 959 W/Assembly - WE 14x14 Fuel............................ B2-100 Table B2-26 Loading Table for PWR Fuel - 513 W/Assembly - WE 14x14 Fuel............................ B2-103 Table B2-27 Loading Table for PWR Fuel - 1300 W/Assembly - WE 14x14 Fuel......................... B2-106 Table B2-28 Loading Table for PWR Fuel - 1800 W/Assembly - WE 14x14 Fuel......................... B2-109 Table B2-29 Loading Table for PWR Fuel - 830 W/Assembly - WE 14x14 Fuel............................ B2-112 Table B2-30 Loading Table for PWR Fuel - 487 W/Assembly - WE 14x14 Fuel............................ B2-115 Table B2-31 Loading Table for PWR Fuel - 1235 W/Assembly - WE 14x14 Fuel......................... B2-118 Table B2-32 Loading Table for PWR Fuel - 1710 W/Assembly - WE 14x14 Fuel......................... B2-121 Table B2-33 Loading Table for PWR Fuel - 788 W/Assembly - WE 14x14 Fuel............................ B2-124 Table B2-34 Loading Table for PWR Fuel - 513 W/Assembly - CE 16x16 Fuel............................ B2-127 Table B2-35 Loading Table for PWR Fuel - 1300 W/Assembly - CE 16x16 Fuel.......................... B2-130 Table B2-36 Loading Table for PWR Fuel - 1800 W/Assembly - CE 16x16 Fuel.......................... B2-133 Table B2-37 Loading Table for PWR Fuel - 830 W/Assembly - CE 16x16 Fuel............................ B2-136 Table B2-38 Loading Table for PWR Fuel - 487 W/Assembly - CE 16x16 Fuel............................ B2-139 Table B2-39 Loading Table for PWR Fuel - 1235 W/Assembly - CE 16x16 Fuel.......................... B2-142 Table B2-40 Loading Table for PWR Fuel - 1710 W/Assembly - CE 16x16 Fuel.......................... B2-145 Table B2-41 Loading Table for PWR Fuel - 788 W/Assembly - CE 16x16 Fuel............................ B2-148 Table B2-42 Low SNF Assembly Average Burnup Enrichment Limits for CE 16x16 Fuel Loaded via the PMTC.............................................................................................. B2-151 Table B2-43 Loading Table for CE 16x16 Fuel Loaded via the PMTC........................................ B2-151 Table B3-1 TSC with FBM Limits..................................................................................................... B3-2 Table B3-2 FBM TSC with Fuel Bearing Material Limits.................................................................B3-3

Appendix B Approved Contents Certificate of Compliance No. 1031 B1-1 Amendment No. 13 1.0 FUEL SPECIFICATIONS AND LOADING CONDITIONS The MAGNASTOR SYSTEM is designed to safely store up to 37 undamaged PWR fuel assemblies in the 37 PWR Basket Assembly or up to 89 undamaged BWR fuel assemblies in the BWR Basket Assembly. The PWR DF basket has a capacity of up to 37 undamaged PWR fuel assemblies including 4 DFC locations.

The BWR DF basket has a capacity of up to 81 undamaged BWR fuel assemblies including 12 DFC locations. Each DFC may contain an undamaged fuel assembly, a damaged fuel assembly, or FUEL DEBRIS equivalent to one fuel assembly. FUEL DEBRIS is included in the definition of DAMAGED FUEL (Appendix A, Section 1.1). UNDAMAGED FUEL assemblies may be placed directly in the DFC locations of a DF Basket Assembly without the use of a DFC.

The FBM TSC is designed to safely store Fuel Bearing Material (FBM) in a Waste Basket Liner (WBL) within the FBM TSC.

The system requires few operating controls. The principal controls and limits for MAGNASTOR are satisfied by the selection of fuel for storage that meets the Approved Contents presented in this section and in the tables for MAGNASTOR design basis spent fuels.

If any Fuel Specification or Loading Condition of this section is violated, the following actions shall be completed:

The affected fuel assemblies or FBM shall be placed in a safe condition.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , notify the NRC Operations Center.

Within 60 days, submit a special report that describes the cause of the violation and actions taken to restore or demonstrate compliance and prevent reoccurrence.

Appendix B Approved Contents Certificate of Compliance No. 1031 B2-1 Amendment No. 13 2.0 FUEL TO BE STORED IN THE MAGNASTOR SYSTEM UNDAMAGED PWR FUEL ASSEMBLIES, DAMAGED PWR FUEL ASSEMBLIES, PWR FUEL DEBRIS (PWR DAMAGED FUEL), UNDAMAGED BWR FUEL ASSEMBLIES, DAMAGED BWR FUEL ASSEMBLIES, BWR FUEL DEBRIS (BWR DAMAGED FUEL), NONFUEL HARDWARE meeting the limits specified in this section may be stored in the MAGNASTOR SYSTEM.

Appendix B Approved Contents Certificate of Compliance No. 1031 B3-1 Amendment No. 13 3.0 FUEL BEARING MATERIAL TO BE STORED IN THE MAGNASTOR SYSTEM Fuel Bearing Material (FBM) is any component or pieces of components associated with Three Mile Island Unit 2 (TMI-2) reactor operations that have been contaminated by used (spent) nuclear fuel and or the associated isotopes in used (spent) nuclear fuel. The FBM is not capable of being separated between SNF and GTCC material, and the FBM contains fuel fragments with non-trivial quantities of SNF. Fission product contamination is included in the definition of FBM regardless of the location of the fission products (either associated with used fuel or has separated from used fuel within facilities via material volatility during and post reactor fuel melt). FBM may be associated with fuel assembly hardware components, non-fuel hardware (i.e., fuel assembly control components), or significantly activated non-fuel materials (e.g., reactor barrel) or be located away from the high activation region (e.g., heat exchangers). The FBM used fuel component may be present in forms ranging from thin coatings to chips and fines and up to larger adhered or loose debris. FBM may contain limited amount of non-metallic, non-spent fuel components (e.g., seals/wiring within pump or valves that have been contaminated). FBM may be collected in Stainless Steel filter housings which are directly loaded into the FBM TSC.

Appendix B Approved Contents Certificate of Compliance No. 1031 B3-2 Amendment No. 13 Table B3-1 TSC with FBM Limits I. TSC with FBM A. Allowable Contents

1. Fuel Bearing Material (FBM) is any component or pieces of components associated with Three Mile Island Unit 2 (TMI-2) reactor operations that have been contaminated by used (spent) nuclear fuel and or the associated isotopes in used (spent) nuclear fuel. The FBM is not capable of being separated between SNF and GTCC material, and the FBM contains fuel fragments with non-trivial quantities of SNF. Fission product contamination is included in the definition of FBM regardless of the location of the fission products (either associated with used fuel or has separated from used fuel within facilities via material volatility during and post reactor fuel melt). FBM may be associated with fuel assembly hardware components, non-fuel hardware (i.e., fuel assembly control components), or significantly activated non-fuel materials (e.g., reactor barrel) or be located away from the high activation region (e.g., heat exchangers). The FBM used fuel component may be present in forms ranging from thin coatings to chips and fines and up to larger adhered or loose debris. FBM may contain limited amount of non-metallic, non-spent fuel components (e.g., seals/wiring within pump or valves that have been contaminated). FBM may be collected in Stainless Steel filter housings which are directly loaded into the FBM TSC.

2. FBM Vessels FBM Vessels fabricated from Stainless Steel, containing no liner, and sealed with mechanical closures containing used filter-media used to extract FBM are approved contents for loading into the MAGNASTOR FBM TSC provided that they have demonstrated to be free of moisture and hydrogen generating materials as described below prior to being sealed within the FBM TSC.

A.

All vessels containing Zeolite/Apatite shall be:

Dewatered and demonstrate dryness by maintaining at an internal pressure of no more than 3 torr for at least 30 minutes with the vacuum pump turned off with the suction valve closed, AND Upon completion of the dryness verification, the Vessel shall be backfilled with Ultra-High Purity Helium (minimum 99.999% helium) starting at no more than 3 torr and backfilled to 1 ATM (+1/-0 psig)

B. All vessels containing Solids Filter, AMFM Sacrificial Filter and Carbon shall:

Demonstrate the removal of hydrogen producing material by undergoing the Vacuum Thermal Desorption (VTD). process to remove hydrogen producing organic material, AND Demonstrate dryness by maintaining at an internal pressure of no more than 3 torr for at least 30 minutes with the vacuum pump isolated and turned off and prior to initiating backfill of the Vessel, AND Upon completion of the dryness verification, the Vessel shall be backfilled with Ultra-High Purity Helium (minimum 99.999% helium) starting at no more than 3 torr and backfilled to 1 ATM (+1/-0 psig)

Appendix B Approved Contents Certificate of Compliance No. 1031 B3-3 Amendment No. 13 Table B3-2 FBM TSC with Fuel Bearing Material Limits I. FBM TSC with Waste Basket Liner A. Allowable Contents

1. Fuel Bearing Material (FBM) that meet the following specifications:

Characteristic Value Maximum Heat Load 139W Maximum Uranium Mass 840 kg Maximum Payload Weight Within WBLa 76,599 lb Maximum Curie Content b (characterization date 1/1/1990) 150,000 Ci a Payload weight includes FBM and dunnage. Dunnage includes, but is not limited to, the Segmented Tube Assembly (STA) and Debris Material Container (DMC) and any additional support (furniture) or containers used to facilitate loading operations.

b Minimum 33 year cooled from characterization date. At characterization date inventory to be less than 47 kCi Cs-137 (41 kCi Ba-137m) and less than 25 kCi Co-60.

to ED20230118 Page 1 of 3 List of Changes for MAGNASTOR FSAR Amendment 13 Supplemental RAI Response Submittal Revision 23D (Docket No 72-1031)

NAC International August 2023 to ED20230118 Page 2 of 3 List of Changes for the MAGNASTOR FSAR, Revision 23D Note: The List of Effective Pages and the Chapter Table of Contents, List of Figures, and List of Tables have been revised accordingly to reflect the list of changes detailed below.

Chapter 1

Page 1.1-3, modified the definition of FBM where indicated.

Page 1.1-4 thru 1.1-6, text flow changes.

Chapter 2

No changes Chapter 3

No changes Chapter 4

No changes Chapter 5

No changes Chapter 6

No changes Chapter 7

No changes Chapter 8

No changes Chapter 9

Page 9.7-6, modified Step 41 where indicated.

Page 9.7-7, modified Step 48, 49,50, 51, 52 and 54 where indicated.

Page 9.7-8, modified Step 56 and 58 where indicated.

Page 9.7-10, modified Step 10 where indicated.

Page 9.7-11, modified Step 35 where indicated.

Page 9.7-12, modified Step 36, 38 and 40 where indicated.

Page 9.7-18, modified Step 18 where indicated.

to ED20230118 Page 3 of 3

Page 9.7-19, modified Step 25 where indicated.

Chapter 10

No changes Chapter 11

No changes Chapter 12

No changes Chapter 13

Page 13C-14, moved Action C.1 to the page 13C-15

Page 13C-15, added Action C.2

Page 13C-25, added FBM TSC to SR 3.3.1.1

Page 13C-26, clarified Background section to include TSC (with fuel or FBM) and updated LCO section surface contamination dose limits to align with limits presented in the Technical Specifications.

Chapter 14

No changes Chapter 15

No changes to ED20230118 Page 1 of 1 FSAR Changed Pages and LOEP for MAGNASTOR FSAR Amendment 13 Supplemental RAI Response Submittal Revision 23D (Docket No 72-1031)

NAC International August 2023

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

FINAL SAFETY ANALYSIS REPORT Revision 23D

MAGNASTOR System FSAR August 2023 Docket No. 72-1031 Revision 23D List of Effective Pages Page 1 of 7 Chapter 1 Page 1-i................................... Revision 22A Page 1-1.................................. Revision 22A Page 1.1-1 thru 1.1-2.................... Revision 5 Page 1.1-3 thru 1.1-6............... Revision 23D Page 1.2-1 thru 1.2-2............... Revision 22A Page 1.3-1 thru 1.3-3................ Revision 23B Page 1.3-4 thru 1.3-21............. Revision 22A Page 1.4-1 thru 1.4-2............... Revision 22A Page 1.5-1............................... Revision 22A Page 1.6-1.................................... Revision 9 Page 1.6-2.................................... Revision 0 Page 1.7-1.................................... Revision 0 Page 1.7-2............................... Revision 22A Page 1.8-1 thru 1.8-2............... Revision 22A 41 drawings (see Section 1.8)

Chapter 2 Page 2-i thru 2-ii..................... Revision 22A Page 2-1.................................. Revision 22A Page 2.1-1 thru 2.1-2............... Revision 22A Page 2.1-3.................................... Revision 5 Page 2.1-4 thru 2.1-6............... Revision 22A Page 2.2-1 thru 2.2-4............... Revision 22A Page 2.2-5 thru 2.2-7.................. Revision 11 Page 2.2-8.................................... Revision 6 Page 2.2-9............................... Revision 22A Page 2.3-1 thru 2.3-4.................... Revision 0 Page 2.3-5.................................... Revision 5 Page 2.3-6.................................... Revision 0 Page 2.3-7............................... Revision 22A Page 2.3-8.................................... Revision 0 Page 2.4-1............................... Revision 23B Page 2.4-2 thru 2.4-4............... Revision 22A Page 2.4-5.................................... Revision 0 Page 2.4-6................................ Revision 23B Page 2.4-7............................... Revision 22A Page 2.4-8................................ Revision 23B Page 2.5-1.................................... Revision 0 Page 2.6-1.................................... Revision 0 Page 2.6-2............................... Revision 22A Chapter 3 Page 3-i...................................... Revision 11 Page 3-ii.................................. Revision 22A Page 3-iii...................................... Revision 9 Page 3-iv...................................... Revision 5 Page 3-v thru 3-vi......................... Revision 9 Page 3-vii thru 3-ix................. Revision 22A Page 3-1....................................... Revision 0 Page 3.1-1.................................... Revision 9 Page 3.1-2.................................... Revision 0 Page 3.1-3 thru 3.1-6............... Revision 22A Page 3.2-1............................... Revision 22A Page 3.2-2 thru 3.2-6.................. Revision 11 Page 3.2-7............................... Revision 22A Page 3.3-1.................................... Revision 0 Page 3.4-1 thru 3.4-2.................. Revision 11 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 22A Page 3.5-2 thru 3.5-4.................... Revision 9 Page 3.5-5 thru 3.5-14.................. Revision 6 Page 3.5-15................................ Revision 11 Page 3.5-16 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 5 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 5 Page 3.7-2 thru 3.7-3.................... Revision 9 Page 3.7-4 thru 3.7-10.................. Revision 6 Page 3.7-11................................ Revision 11 Page 3.7-12 thru 3.7-56................ Revision 6 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

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

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

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

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

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

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MAGNASTOR System FSAR August 2023 Docket No. 72-1031 Revision 23D NAC International 1.1-3 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.

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

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.

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 Bearing Material (FBM)

Fuel Bearing Material (FBM) is any component or pieces of components associated with reactor operations that have been contaminated by used (spent) nuclear fuel and or the associated isotopes in used (spent) nuclear fuel. Fission product contamination is included in the definition of FBM regardless of the location of the fission products (either associated with used fuel or has separated from used fuel within facilities via material volatility during and post reactor fuel melt). FBM may be associated with fuel assembly hardware components, non-fuel hardware (i.e., fuel assembly control components), or significantly activated non-fuel materials (e.g., reactor barrel) or be located away from the high activation region (e.g., heat exchangers). The FBM used fuel component may be present in forms ranging from thin coatings to chips and fines and up to larger adhered or loose debris. FBM may contain limited amount of non-metallic, non-spent fuel components (e.g., seals/wiring within pump or valves that have been contaminated). FBM may be collected in Stainless Steel filter housings which are directly loaded into the FBM TSC.

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.

MAGNASTOR System FSAR August 2023 Docket No. 72-1031 Revision 23D NAC International 1.1-4 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 concrete cask and a TSC. A transfer cask is provided and utilized to load and place a TSC in a concrete cask or to remove a TSC from a concrete cask.

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 August 2023 Docket No. 72-1031 Revision 23D NAC International 1.1-5 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.

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 concrete 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 TSC. There are two types of transfer cask, the first is the standard MAGNASTOR Transfer Cask (MTC) with solid neutron shielding. The MTC can be supplied fabricated from high-strength carbon steel (MTC1) or stainless steel (MTC2). The second type is the Passive MTC (PMTC) with demineralized water filled 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 concrete cask. The PMTC is 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.

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

MAGNASTOR System FSAR August 2023 Docket No. 72-1031 Revision 23D NAC International 1.1-6 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.

Fuel Bearing Material (FBM) TSC TSC that contains FBM.

Waste Basket Liner (WBL)

The structure inside the FBM TSC that provides the means to position the FBM inside the FBM TSC.

Undamaged Fuel SNF that can meet all fuel-specific and system-related functions. Undamaged fuel is SNF that is not Damaged Fuel, as defined herein, and does not contain assembly structural defects that adversely affect radiological and/or criticality safety. As such, undamaged fuel may contain:

a) Breached spent fuel rods (i.e, rods with minor defects up to hairline cracks or pinholes),

but cannot contain grossly breached fuel rods; b) Grid, grid strap and/or grid spring damage, provided that the unsupported length of the fuel rod does not exceed 60 inches.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23B NAC International 9.7-5

22. Rinse and flush the top of the MTC and FBM TSC with clean water as necessary to remove any radioactive particles. Survey the top of the FBM TSC closure lid and the top of the MTC to check for radioactive particles.

23. As the MTC is removed from the designated loading area, terminate the annulus fill water supply, remove the annulus fill system hoses, and allow annulus water to drain into the designated loading area.

24. Following the prescribed load path, move the MTC to the designated workstation for FBM TSC closure operations.

Note: At the option of the user, the FBM TSC closure operations may be performed with the MTC partially submerged in the designated loading area, cask loading pit, or an equivalent structure. This operational alternative provides additional shielding for the cask operators.

25. Disengage the three-legged sling set from the closure lid and the lift yoke from the MTC trunnions. Place lift yoke and sling set in storage/lay-down area.

26. Inflate the MTC lower annulus seal with air or nitrogen. Disconnect the gas supply from the transfer cask.

Note: The installation, use, and operational sequence of the lower annulus seal is at the discretion of the user based on approved site-specific procedures. At the option of the user, the gas supply can be maintained continuously to the annulus seals. Use of the ACWS, or similar system, is optional for the FBM TSC as safe operating temperatures are maintained with air or stagnant water in the TSC to MTC annulus. Annulus may be water filled for contamination control only. Steps 27, 28 and 68 may be skipped or modified depending on site requirements at this stage (i.e., air filled annulus., annulus water filled with or without flow).

27. Install the ACWS, R-ACWS or alternative annulus flush/circulating water system, to the lower and upper annulus fill lines. Unused fill lines are to be closed or capped.

Note: For FBM TSCs prepared with the MTC partially submerged on an in-designated loading area shelf, partially drained cask loading pit or equivalent partial submerged condition, or in an ACWS catch basin, alternative ACWS operations (e.g., reverse flow ACWS [R-ACWS]) may be utilized.

Note: ACWS or R-ACWS operation may be used to enhance vacuum drying times of the FBM TSC via application of heated water (maximum water temperature 200°F).

28. Initiate clean water flow into the MTC lower fill lines with annulus water discharging through the upper fill lines.

29. Detorque and remove the lifting hoist rings from the closure lid.

30. Using a portable suction pump, remove any standing water from the closure lid weld groove, and the vent and drain ports.

MAGNASTOR System FSAR August 2023 Docket No. 72-1031 Revision 23D NAC International 9.7-6

31. Decontaminate the top of the MTC and FBM TSC closure lid to allow installation of the welding equipment. Decontaminate external surfaces of the MTC and remove the bottom protective cover, if installed.

32. Insert the drain line with a quick-connector attached through the drain port opening and into the basket drain port sleeve. Remove the quick-disconnect and any contaminated water displaced from the cavity.

33. Torque the drain tube connector to the drain opening to the value specified in Table 9.1-2.

Verify quick-disconnect is installed and properly torqued in the vent port opening.

34. Install a venting device to the vent port quick-disconnect to prevent combustible gas or pressure buildup below the closure lid.

35. Verify that the top of the closure lid is level (flush) with, or slightly above, the top of the FBM TSC shell.

36. At the discretion of the user, establish foreign material exclusion controls to prevent objects from being dropped into the annulus or FBM TSC.

37. Install the welding system, including supplemental shielding, to the top of the closure lid.

Note: At the discretion of the user, supplemental shielding may be installed around the transfer cask to reduce operator dose. Use of supplemental shielding shall be evaluated to ensure its use does not adversely affect the safety performance of MAGNASTOR.

38. Connect a suction pump to the drain port quick-disconnect and verify venting through the vent port quick-disconnect.

39. Operate the suction pump to remove approximately 70 gallons of water from the FBM TSC.

Disconnect the suction pump.

Note: The radiation level will increase as water is removed from the FBM TSC cavity, as shielding material is being removed.

40. Attach a hydrogen detector to the vent line. Ensure that the vent line does not interfere with the operation of the weld machine.

41. Sample the gas volume below the closure lid and observe hydrogen detector for H2 concentration prior to commencing closure lid welding operations. Monitor H2 concentration in the FBM TSC until the mid-plane layer of the closure lid-to-shell weld is completed.

Note: If H2 concentration exceeds 2.4%, immediately stop welding operations. Evacuate the FBM TSC gas volume or purge the gas volume with helium. Verify H2 levels are

<2.4% prior to restarting welding operations.

Note: In place of continuous H2 monitoring, continuous gas purging of the volume below the lid may be used in concert with initial (prior to start of welding) and intermittent H2 monitoring (upon termination of gas purging and prior to re-starting welding operations).

MAGNASTOR System FSAR August 2023 Docket No. 72-1031 Revision 23D NAC International 9.7-7

42. Install shims into the closure lid-to-FBM TSC shell gap, as necessary, to establish a uniform gap for welding. Tack weld the closure lid and shims, as required.

43. Operate the welding equipment to complete the closure lid-to-FBM TSC shell root pass weld in accordance with the approved weld procedure.

44. Perform visual and liquid penetrant (PT) examinations of the root pass and record the results.

45. Operate the welding equipment to perform the closure lid-to-shell weld to the midplane between the root and final weld surfaces. Perform visual and PT examinations for the midplane weld pass, and record the results.

46. Remove the H2 detector from the vent line while ensuring the FBM TSC cavity vent line remains installed and allows venting of gases from the cavity.

47. Complete welding through the completion of the final pass of the closure lid weld, perform final visual and PT examinations, and record the results.

48. Install and tack the closure ring in position in the closure lid-to-FBM TSC shell weld groove.

Note: At the option of the user, the installation and tacking of the closure ring may be performed immediately after helium backfill (Step 58) or after completion of the welding, testing, and NDE of the vent and drain inner or outer port covers (Step 64 or 66).

49. Weld the closure ring to the FBM TSC shell and to the closure lid. Perform visual and PT examinations of the final surfaces of the welds and record the results.

Note: At the option of the user, the installation, welding, and NDE of the closure ring may be performed immediately after helium backfill (Step 58) or after completion of the welding, testing, and NDE of the vent and drain inner or outer port covers (Step 64 or 66).

50. Remove the water from the FBM TSC using one of the following methods: drain down using a suction pump with a pressurized helium cover gas; or blow down using pressurized helium gas.

51. Connect a drain line with or without suction pump to the drain port connector.

52. Connect a regulated helium gas supply to the vent port connector.

53. Open gas supply valve and start suction pump, if used, and drain water from the FBM TSC until water ceases to flow out of the drain line. Close gas supply valve and stop suction pump.

54. At the option of the user, disconnect suction pump, close discharge line isolation valve, and open helium gas supply line. Pressurize FBM TSC to approximately 20 psig and open discharge line isolation valve to blow down the FBM TSC. Repeat blow down operations until no significant water flows out of the drain line.

55. Disconnect the drain line and gas supply line from the drain and vent port quick-disconnects.

56. Dry the FBM TSC cavity using vacuum drying methods as follows.

a. Connect the vacuum drying system to the vent and drain port openings.

MAGNASTOR System FSAR August 2023 Docket No. 72-1031 Revision 23D NAC International 9.7-8

b. Operate the vacuum pump until a vapor pressure of < 3 torr is achieved in the FBM TSC.

c. Isolate the vacuum pump from the FBM TSC and turn off the vacuum pump.

Observe the vacuum gauge connected to the FBM TSC for an increase in pressure for a minimum period of 30 minutes.

Note: If the FBM TSC pressure is < 3 torr at the end of 30 minutes, the FBM TSC is dry of free water.

Note: Moisture removal during vacuum drying may be improved by injection of helium (heated or non-heated) during the vacuum drying process (i.e., while the FBM TSC internal pressure is under a vacuum condition). This process may be repeated as needed.

57. Upon satisfactory completion of the dryness verification, backfill and pressurize the FBM TSC cavity with helium as follows:

a. Set the helium bottle regulator to 20 (+5,-0) psig.

b. Connect the helium backfill system to the vent port.

c. Slowly open the helium supply valve and backfill the FBM TSC with helium until the FBM TSC is at a pressure of 0 (+2/-0) psig.

58. Disconnect the vacuum drying helium backfill system from the vent and drain openings.

Note: At the option of the user, Steps 48 and 49 can alternatively be performed at this point or immediately following Steps 64 or 66. The user to establish appropriate radiological controls to maintain operator dose ALARA.

59. Install and tack weld the inner port cover to the FBM TSC closure lid vent port opening.

60. Purge the vent port cavity with high-purity helium.

61. Weld the inner port cover to the FBM TSC closure lid.

62. Perform visual and PT examinations of the final surface of the vent port inner cover weld and record the results.

63. Perform helium leak test on the vent port inner cover weld to verify the absence of helium leakage past the vent port inner cover weld.

64. Repeat steps 59 thru 63 for the FBM TSC inner port cover on the drain port opening.

65. Install and weld the outer port cover on the drain port opening. Perform visual and PT examinations of the final weld surface and record the results.

66. Install and weld the outer port cover on the vent port opening. Perform visual and PT examinations of the final weld surface and record the results.

67. Using an appropriate crane, remove the weld machine and supplemental shield.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23B NAC International 9.7-9

68. Drain the FBM TSC/MTC annulus by stopping ACWS flow to the annulus and connecting one or more drain lines to the lower annulus fill ports. Once the annulus is drained, deflate the top and bottom annulus seals.

69. If using MTC1 or MTC2 with retaining blocks, remove the lock pins and move the MTC retaining blocks inward into their functional position, and reinstall the lock pins. If using MTC2 with retaining ring, install the transfer cask retaining ring and torque the retaining ring bolts to the value specified in Table 9.1-2.

70. Install the TSC Adapter Assembly and secure using the six threaded holes in the closure lid.

Torque the bolts to the designated value listed in Table 9.1-2.

Note: Complete final decontamination of the MTC exterior surfaces. Final FBM TSC contamination surveys may be performed after FBM TSC transfer following Step 21 in Section 9.7.3 when FBM TSC surfaces are more accessible.

71. Proceed to Section 9.7.3.

9.7.2 Non-submerged (Dry) Loading and Closing the FBM TSC Using Standard MTC This section describes the sequence of operations to perform the loading of FBM in a non-submerged (dry) configuration and subsequent closure of the FBM TSC in preparation for transferring the FBM TSC to the concrete cask. The empty FBM TSC is assumed to be positioned inside the transfer cask located at the designated workstation.

1. Visually inspect the FBM TSC internals for foreign materials or debris.

2. Visually inspect the top of the FBM TSC shell and closure lid weld preps.

3. Inflate the upper MTC annulus seal with air or nitrogen gas. Disconnect the gas supply.

Note: Gas supply lines may be left connected to ensure against unintended deflation.

Note: The sequence and use of upper and lower annulus seals are at the discretion of the Licensee/User based on selected in-plant operational procedures.

Note: Optional FBM TSC annulus shims may be utilized at the discretion of the user to assist in centering the FBM TSC in the MTC annulus.

4. Verify the three FBM TSC retaining blocks (MTC1/MTC2) are pinned in the retracted position or the retaining ring (MTC2) is removed.

5. Verify that at least one lock pin is installed on each MTC shield door.

6. Connect the clean water lines to the lower annulus fill ports of the MTC.

7. Using the slings attached to the WBL, load the WBL into the FBM TSC basket.

8. Install the appropriate WBL internal(s) for loading of vessel(s) containing FBM.

9. Verify the closure seals of the vessel(s) containing FBM are intact.

10. Select and install the vessel(s) containing FBM into the WBL.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23D NAC International 9.7-10

11. Install three swivel hoist rings hand tight in the three closure lid lifting holes or in three of the six FBM TSC lift holes, and torque to the value specified in Table 9.1-2. Install a three-legged sling set to the hoist rings and connect the sling set to the crane hook.

12. Raise the closure lid. Adjust closure lid rigging to level the closure lid.

13. Move the closure lid over the designated loading area and align the closure lid to the match marks of the FBM TSC.

14. Lower the closure lid until it enters the FBM TSC and seats in the top of the FBM TSC.

Visually verify closure lid alignment using the match marks (+/- 1/2 inch).

15. Disconnect the three-legged sling set from the closure lid. Place the sling set in storage/lay-down area.

16. Inflate the MTC lower annulus seal with air or nitrogen. Disconnect the gas supply from the transfer cask.

Note: The installation, use, and operational sequence of the lower annulus seal is at the discretion of the user based on approved site-specific procedures. At the option of the user, the gas supply can be maintained continuously to the annulus seals. Use of the ACWS, or similar system, is optional for the FBM TSC as safe operating temperatures are maintained with air or stagnant water in the TSC to MTC annulus. Annulus may be water filled for contamination control only. Steps 17, 18 and 50 may be skipped or modified depending on site requirements at this stage (i.e., air filled annulus., annulus water filled with or without flow).

17. Install the ACWS, R-ACWS or alternative annulus flush/circulating water system, to the lower and upper annulus fill lines. Unused fill lines are to be closed or capped.

Note: For FBM TSCs prepared with the MTC in an ACWS catch basin, alternative ACWS operations (e.g., reverse flow ACWS [R-ACWS]) may be utilized.

Note: ACWS or R-ACWS operation may be used to enhance vacuum drying times of the FBM TSC via application of heated water (maximum water temperature 200°F).

18. Initiate clean water flow into the MTC lower fill lines with annulus water discharging through the upper fill lines.

19. Detorque and remove the lifting hoist rings from the closure lid.

20. Insert the drain line with a quick-connector attached through the drain port opening and into the basket drain port sleeve.

21. Torque the drain tube connector to the drain opening to the value specified in Table 9.1-2.

Verify quick-disconnect is installed and properly torqued in the vent port opening.

22. Install a venting device to the vent port quick-disconnect to prevent combustible gas or pressure buildup below the closure lid.

23. Verify that the top of the closure lid is level (flush) with, or slightly above, the top of the FBM TSC shell.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23D NAC International 9.7-11

24. At the discretion of the user, establish foreign material exclusion controls to prevent objects from being dropped into the annulus or FBM TSC.

25. Install the welding system, including supplemental shielding, to the top of the closure lid.

Note: At the discretion of the user, supplemental shielding may be installed around the transfer cask to reduce operator dose. Use of supplemental shielding shall be evaluated to ensure its use does not adversely affect the safety performance of MAGNASTOR.

26. Verify venting through the vent port quick-disconnect.

27. Attach a hydrogen detector to the vent line. Ensure that the vent line does not interfere with the operation of the weld machine.

28. Sample the gas volume below the closure lid and observe hydrogen detector for H2 concentration prior to commencing closure lid welding operations. Monitor H2 concentration in the FBM TSC until the mid-plane layer of the closure lid-to-shell weld is completed.

Note: If H2 concentration exceeds 2.4%, immediately stop welding operations. Evacuate the FBM TSC gas volume or purge the gas volume with helium. Verify H2 levels are

<2.4% prior to restarting welding operations.

Note: In place of continuous H2 monitoring, continuous gas purging of the volume below the lid may be used in concert with initial (prior to start of welding) and intermittent H2 monitoring (upon termination of gas purging and prior to re-starting welding operations).

29. Install shims into the closure lid-to-FBM TSC shell gap, as necessary, to establish a uniform gap for welding. Tack weld the closure lid and shims, as required.

30. Operate the welding equipment to complete the closure lid-to-FBM TSC shell root pass weld in accordance with the approved weld procedure.

31. Perform visual and liquid penetrant (PT) examinations of the root pass and record the results.

32. Operate the welding equipment to perform the closure lid-to-shell weld to the midplane between the root and final weld surfaces. Perform visual and PT examinations for the midplane weld pass, and record the results.

33. Remove the H2 detector from the vent line while ensuring the FBM TSC cavity vent line remains installed and allows venting of gases from the cavity.

34. Complete welding through the completion of the final pass of the closure lid weld, perform final visual and PT examinations, and record the results.

35. Install and tack the closure ring in position in the closure lid-to-FBM TSC shell weld groove.

Note: At the option of the user, the installation and tacking of the closure ring may be performed immediately after helium backfill (Step 40) or after completion of the welding, testing, and NDE of the vent and drain inner or outer port covers (Step 46 or 48).

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23D NAC International 9.7-12

36. Weld the closure ring to the FBM TSC shell and to the closure lid. Perform visual and PT examinations of the final surfaces of the welds and record the results.

Note: At the option of the user, the installation, welding, and NDE of the closure ring may be performed immediately after helium backfill (Step 40) or after completion of the welding, testing, and NDE of the vent and drain inner or outer port covers (Step 46 or 48).

37. Disconnect the vent line from the vent port quick-disconnect.

38. Evacuate the FBM TSC cavity using vacuum drying methods as follows.

a. Connect the vacuum drying system to the vent and drain port openings.

b. Operate the vacuum pump until a vapor pressure of < 3 torr is achieved in the FBM TSC.

c. Isolate the vacuum pump from the FBM TSC and turn off the vacuum pump. Observe the vacuum gauge connected to the FBM TSC for an increase in pressure for a minimum period of 30 minutes.

Note: If the FBM TSC pressure is < 3 torr at the end of 30 minutes, the FBM TSC has been evacuated.

Note: Moisture removal during vacuum drying may be improved by injection of helium (heated or non-heated) during the vacuum drying process (i.e., while the FBM TSC internal pressure is under a vacuum condition). This process may be repeated as needed.

39. Upon satisfactory completion of the dryness verification, backfill and pressurize the FBM TSC cavity with helium as follows:

a. Set the helium bottle regulator to 20 (+5,-0) psig.

b. Connect the helium backfill system to the vent port.

c. Slowly open the helium supply valve and backfill the FBM TSC with helium until the FBM TSC is at a pressure of 0 (+2/-0) psig.

40. Disconnect the vacuum drying helium backfill system from the vent and drain openings.

Note: At the option of the user, Steps 35 and 36 can alternatively be performed at this point or immediately following Steps 46 or 48 The user to establish appropriate radiological controls to maintain operator dose ALARA.

41. Install and tack weld the inner port cover to the FBM TSC closure lid vent port opening.

42. Purge the vent port cavity with high-purity helium.

43. Weld the inner port cover to the FBM TSC closure lid.

44. Perform visual and PT examinations of the final surface of the vent port inner cover weld and record the results.

45. Perform helium leak test on the vent port inner cover weld to verify the absence of helium leakage past the vent port inner cover weld.

46. Repeat steps 41 thru 45 for the FBM TSC inner port cover on the drain port opening.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23B NAC International 9.7-13

47. Install and weld the outer port cover on the drain port opening. Perform visual and PT examinations of the final weld surface and record the results.

48. Install and weld the outer port cover on the vent port opening. Perform visual and PT examinations of the final weld surface and record the results.

49. Using an appropriate crane, remove the weld machine and supplemental shield.

50. Drain the FBM TSC/MTC annulus by stopping ACWS flow to the annulus and connecting one or more drain lines to the lower annulus fill ports. Once the annulus is drained, deflate the top and bottom annulus seals.

51. If using MTC1 or MTC2 with retaining blocks, remove the lock pins and move the MTC retaining blocks inward into their functional position, and reinstall the lock pins. If using MTC2 with retaining ring, install the transfer cask retaining ring and torque the retaining ring bolts to the value specified in Table 9.1-2.

52. Install the TSC Adapter Assembly and secure using the six threaded holes in the closure lid.

Torque the bolts to the designated value listed in Table 9.1-2.

Note: Complete final decontamination of the MTC exterior surfaces. Final FBM TSC contamination surveys may be performed after FBM TSC transfer following Step 21 in Section 9.7.3 when FBM TSC surfaces are more accessible.

53. Proceed to Section 9.7.3.

9.7.3 Transferring the FBM TSC to the Concrete Cask Using a Standard MTC This section describes the sequence of operations required to complete the transfer of a loaded FBM TSC from the MTC into a concrete cask, and preparation of the concrete cask for movement to the ISFSI pad.

1. Position an empty concrete cask with the upper segment removed in the designated FBM TSC transfer location.

Note: The concrete cask can be positioned on the ground, or on a deenergized air pad set, roller skid, heavy-haul trailer, rail car, or transfer cart. The transfer location can be inside the loading facility or an external area accessed by the facility cask handling crane.

Note: The minimum ambient air temperature (either in the facility or external air temperature, as applicable for the handling sequence) must be > 0ºF for lifting the concrete cask with lifting plugs, per Section 4.3.1.g. of the Technical Specifications.

2. Inspect all concrete cask openings for foreign objects and remove if present.

3. Install a four-legged sling set to the lifting points on the transfer adapter.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23B NAC International 9.7-14

4. Using the crane, lift the transfer adapter and place it on top of the concrete cask ensuring that the guide ring sits inside the concrete cask lid flange. Remove the sling set from the crane and move the slings out of the operational area.

5. Connect a hydraulic supply system to the hydraulic cylinders of the transfer adapter.

6. Verify the movement of the connectors and move the connector tees to the fully extended position.

7. Connect the Secure Lift Handling System to the crane and engage the lift yoke to the MTC trunnions. Ensure all lines, temporary shielding and work platforms are removed to allow for the vertical lift of the transfer cask.

Note: The minimum ambient air temperature (either in the facility or external air temperature, as applicable for the handling sequence) must be > 0ºF for the use of the carbon steel MTC, per Section 4.3.1.f. of the Technical Specifications (not applicable to stainless steel MTC2).

8. Lower the SLHS equalizer beam to permit engagement of the TSC Locking Pin with the TSC Adapter Assembly.

9. Actuate the TSC locking pin to securely couple the equalizer beam to the TSC Adapter Assembly.

10. Raise the MTC and move it into position over the empty concrete cask.

11. Slowly lower the MTC into the engagement position on top of the transfer adapter to align with the door rails and engage the connector tees.

12. Following set down, remove the lock pins from the shield door lock tabs.

13. Using the SLHS redundant hoists, lift the FBM TSC slightly (approximately 1/2-1 inch) to remove the FBM TSC weight from the shield doors.

Note: The lifting system operator must take care to ensure that the FBM TSC is not lifted such that the retaining blocks (MTC1/MTC2) or the retaining ring (MTC2) is engaged by the top of the FBM TSC.

14. Open the MTC shield doors with the hydraulic system to provide access to the concrete cask cavity.

15. Perform FBM TSC contamination surveys on the MTC shield doors to confirm contamination levels are acceptable.

16. Slowly lower the FBM TSC into the concrete cask cavity until the FBM TSC is seated on the pedestal.

Note: The transfer adapter and the standoffs in the concrete cask will ensure the FBM TSC is appropriately centered on the pedestal within the concrete cask.

17. When the FBM TSC is seated, retract the TSC locking pin from the TSC adapter assembly and raise the equalizer beam up into the MTC until the equalize beam has reached full up position.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23B NAC International 9.7-15

18. Close the shield doors using the hydraulic system and reinstall the lock pins into the shield door lock tabs.

19. Lift the MTC from the top of the concrete cask and return it to the cask preparation area for next loading sequence or to its designated storage location.

20. Disconnect hydraulic supply system from the transfer adapter hydraulic cylinders.

21. Loosen and remove the six bolts securing the TSC adapter assembly to the FBM TSC closure lid. Using the designated sling sets, remove from the top of the FBM TSC and store properly.

22. Verify all equipment and tools have been removed from the top of the FBM TSC and transfer adapter.

23. Connect the transfer adapter four-legged sling set to the crane hook and lift the transfer adapter off the concrete cask. Place the transfer adapter in its designated storage location and remove the slings from the crane hook.

24. Using the on-site heavy haul vehicle, remove the concrete cask using the designated conveyance from the FBM TSC transfer station location to permit installation of the concrete cask upper segment.

25. Attach the concrete cask upper segment lift rig. Connect the slings to the overhead crane.

26. Perform visual inspection of the top of the concrete cask and verify all equipment and tools have been removed.

Note: Take care to minimize personnel access to the top of the unshielded loaded concrete cask due to radiation streaming from the FBM TSC.

27. Lift the concrete cask upper segment and move it into position over the concrete cask, ensuring proper alignment.

28. Lower the concrete cask upper segment into position and remove the rig set from the concrete cask upper segment

29. Install four of the concrete cask upper segment bolts and tighten to the torque specified in Table 9.1-2.

30. Perform radiation surveys of the top and sides of the concrete cask. Confirm dose rates are within allowable values.

31. Using the vertical cask transporter lift fixture or device, position the two concrete cask lifting lugs on the concrete cask.

32. Install the lift lug bolts (2 per lift lug) and into the threaded holes in the embedment base.

Torque each of the lug bolts to the value specified in Table 9.1-2.

33. Proceed to Section 9.7.3.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23B NAC International 9.7-16 9.7.4 Transporting and Placing the Loaded Concrete Cask The section describes the general procedures for moving a loaded concrete cask to the ISFSI pad using the vertical cask transporter.

Vertical Cask Transporter

1. Using the cask transporter, lift the loaded concrete cask and move it to the ISFSI pad following the approved onsite transport route.

Note: Ensure vertical cask transporter lifts the concrete cask evenly using the two lifting lugs.

Note: Do not exceed the maximum lift height for a loaded concrete cask of 24 inches, per Section 4.3.1.h. of the Technical Specifications.

2. Move the concrete cask into position over its intended ISFSI pad storage location. Ensure the surface under the concrete cask is free of foreign objects and debris.

3. Using the vertical transporter, slowly lower the concrete cask into position.

4. Loosen and remove the two lift lug bolts from each lifting lug, raise the lift lugs from the top of the concrete cask and move the cask transporter from the area.

5. Install the remaining four concrete cask upper segment bolts into the threaded holes. Torque each bolt to the value specified in Table 9.1-2.

6. For the casks with extensions containing anchor cavities, install the weather seal and cover plates. Install the bolts and washers and torque to the value specified in Table 9.1-2.

7. Install inlet screens to prevent access by debris and small animals.

Note: Screens may be installed on the concrete cask prior to FBM TSC loading to minimize operations personnel exposure.

8. Scribe and/or stamp the concrete cask nameplate, if not already done, with the required information at a minimum.

9. Perform a radiological survey of the concrete cask within the ISFSI array to confirm dose rates comply with ISFSI administrative boundary and site boundary dose limits.

9.7.5 Removing the Loaded FBM TSC from a Concrete Cask Using a Standard MTC This procedure assumes the loaded concrete cask is returned to the reactor loading facility for unloading. However, transfer of the FBM TSC to another concrete cask can be performed at the ISFSI without the need to return to the loading facility, provided a cask transfer facility that meets the requirements specified in the Technical Specifications is available.

As the steps to move a loaded concrete cask are essentially the reverse of the procedures in Section 9.7.2 and Section 9.7.3, the procedural steps are only summarized here.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23B NAC International 9.7-17

1. Remove concrete cask inlet screens.

Note: The minimum ambient air temperature (either in the facility or external air temperature, as applicable for the handling sequence) must be > 0ºF for the use of the concrete cask, per Section 4.3.1.g. of the Technical Specifications.

Remove four of the concrete cask upper segment bolts, and install the lift lugs. Torque the lift lug bolts for each lift lug to the value specified in Table 9.1-2. Attach the concrete cask to the vertical cask transporter.

2. Move the loaded concrete cask to the facility.

3. Remove the concrete cask upper segment.

4. Install the TSC adapter assembly using the six bolts inserted into the canister closure lid threaded holes. Torque the bolts to the prescribed value,

5. Install transfer adapter on top of the concrete cask.

6. Place MTC onto the transfer adapter and engage the shield door connectors.

7. Note: The minimum ambient air temperature (either in the facility or external air temperature, as applicable for the handling sequence) must be > 0ºF for the use of the carbon steel MTC, per Section 4.3.1.f. of the Technical Specifications (not applicable to stainless steel MTCs).

8. Open the shield doors, retrieve the lifting slings, and install the slings on the lifting system.

9. Slowly withdraw the FBM TSC from the concrete cask. The chamfer on the underside of the transfer adapter assists in the alignment into the MTC.

10. Bring the FBM TSC up to just below the retaining blocks (MTC1/MTC2) or the retaining ring (MTC2). Close the MTC shield doors and install the shield door lock pins.

11. Lift MTC off the concrete cask and move to the designated workstation.

12. After the MTC with the loaded FBM TSC is in, or adjacent to, the facility, the operational sequence to load the FBM TSC into another concrete cask is performed in accordance with the procedures in Section 9.7.2.

9.7.6 Wet Unloading a FBM TSC Using a Standard MTC This section provides the basic operational sequence to prepare, open, and unload a FBM TSC in a designated loading area. Due to the rugged design and fabrication of the FBM TSC, users are not expected to perform this operational sequence. However, in accordance with the Technical Specifications, each user shall have the procedures and required equipment available, and perform a dry run of the unloading process.

The procedure that follows assumes that the FBM TSC is in a MTC in the appropriate workstation.

MAGNASTOR System FSAR August 2023 Docket No. 72-1031 Revision 23D NAC International 9.7-18

1. If using MTC1 or MTC2 with retaining blocks, pull the lock pins and retract the retaining blocks in the transfer cask, and reinstall the lock pins. If using MTC2 with retaining ring, detach and remove the retaining ring.

2. Survey the FBM TSC and MTC to establish radiation areas.

3. Install and secure by welding the Port Cover Drill Fixture to the outer vent port cover.

4. Install the Gas Sampling and Pressure Measurement System to the Port Cover Drill Fixture access port.

5. Operate the Port Cover Drill Fixture to remotely drill through the outer and inner vent port covers.

6. Measure cavity gas pressure utilizing the Gas Sampling and Pressure Measurement System.

7. Obtain a cavity gas sample from the Port Cover Drill Fixture connection.

8. Determine total gaseous inventory and connect a venting system to the Gas Sampling and Pressure Measurement System and route to the HEPA filters or to the off-gas system.

9. Vent the FBM TSC cavity gas and reduce FBM TSC pressure to atmospheric.

10. Remove the Port Cover Drill Fixture from the outer vent port cover.

11. Install the weld removal system on the closure lid and bolt the system to the closure lid threaded holes.

12. Establish appropriate airborne radiation controls.

Note: Initial TSC cooling can be provided by an external TSC cooling system prior to port cover removal.

13. Using the weld removal system, remove the outer and inner port covers from the vent and drain ports.

14. Remove the weld removal system.

15. Using appropriate radiological controls, remove the vent and drain quick-disconnects and seals.

16. Replace the vent port quick-connect, drain tube with quick-disconnect, and seals with approved spares, and torque them to the value specified in Table 9.1-2.

17. Attach the cooldown system to the vent and drain connections.

Note: Initial TSC cooling can be provided by an external TSC cooling system prior to port cover removal.

18. Initiate purge gas flow (helium) through the FBM TSC to flush out residual radioactive gases.

Continue helium flow for a minimum of 10 minutes.

19. Initiate the controlled filling (5 +3/-0 gpm) of the FBM TSC with clean water through the drain connector under controlled temperature (minimum 70ºF) and pressure conditions (20

+5/-0 psig).

20. Monitor steam/water temperature of the discharge from the vent connection.

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21. Continue cooldown operations until the discharge water temperature is below 180ºF.

22. Terminate cooling water flow and disconnect the cooldown system from the drain and vent ports. Install a vent line to the vent port.

23. Connect a suction pump to the drain connector. Operate the pump and remove approximately 70 gallons of water from the cavity. Disconnect and remove the pump.

24. Remove the drain line from the closure lid.

25. Install the hydrogen detector to the vent line and verify hydrogen gas concentration in the gas volume in the cavity. If the concentration reaches 2.4%, stop all cutting activities and purge the hydrogen from the FBM TSC using helium.

26. Install the weld removal system on the closure lid. Operate the weld removal system to remove the closure ring-to-FBM TSC shell and closure ring-to-closure lid welds. Remove the closure ring from the lid area.

27. Operate the weld removal system to remove the closure lid-to-shell weld.

28. Remove shims, if installed, to provide a suitable gap to be able to extract the closure lid under water.

29. Remove the weld removal system. Terminate ACWS or R-ACWS, if used.

30. Install three swivel hoist rings into the closure lid threaded holes and torque to value in Table 9.1-2. Attach three-legged sling set to the hoist rings and the lifting system (or, alternately, the MTC lifting yoke).

31. Engage the lift yoke to the MTC trunnions and bring the transfer cask over the designated loading area.

32. Install lower annulus fill lines and fill the annulus with clean water while lowering the MTC.

33. When the trunnions are near the designated loading area surface, install upper annulus fill lines and start clean water flow.

34. Lower the MTC to the bottom of the designated loading area. Disengage the lift yoke.

35. Slowly remove the closure lid and move the lid to an appropriate storage area. Note: The closure lid may be contaminated and slightly activated.

36. Attach slings between the WBL and the crane hook. Remove from the FBM TSC and place in designated location.

37. Following WBL unloading, reengage the lift yoke to the MTC trunnions and remove the MTC from the designated loading area.

38. While the MTC is over the designated loading area, stop the flow of water to the annulus, disconnect the upper and lower fill lines, and allow the water in the annulus to drain back into the designated loading area.

39. Place MTC and empty FBM TSC in the cask decontamination area or other workstation.

MAGNASTOR System FSAR June 2023 Docket No. 72-1031 Revision 23B NAC International 9.7-20

40. Using a suction pump, remove the water from the FBM TSC and pump to radwaste drains or return the water to the designated loading area.

41. Remove and store the contaminated FBM TSC until a determination is made regarding reuse or disposition of the closure lid and FBM TSC.

42. As appropriate, the user may proceed with the loading of the removed WBL into a new FBM TSC in accordance with the procedures in Section 9.7.

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

LCO (continued) time. The minimum 24-hour helium soak would lower and reset the TSC and SNF content temperatures to a value corresponding to the temperatures used in the determination of the Table 1.B and 1.D values for Maximum TSC Transfer Time limits for TSCs being transferred using the MTC. Tables F, G and H are applicable to TSCs being loaded and transferred using the LMTC.

The table in Section 3 is applicable to PWR TSCs prepared in a Passive MAGNASTOR Transfer Cask (PMTC). A Note in Section 3 refers the Licensee to use Table 1.E following additional drying cycle(s) to determine the Minimum Helium Backfill Time and Maximum TSC Transfer Time applicable for the second TSC transfer cycle. As the PMTC is designed to provide efficient convective air cooling of the loaded TSC and its contents, no additional Minimum Helium Backfill Time is required prior to commencing TSC transfer operations following final helium mass backfill. In addition, the PMTC Maximum TSC Transfer Time is 600-hours for all PWR decay heat loads.

Each temperature transient, either resulting from additional water cooling and vacuum drying cycles, or from additional helium soak, cooling and TSC transfer cycles, would need to be accounted for in the 10 allowable thermal transients for SNF assemblies with burnups exceeding 45,000 MWd/MTU.

For FBM containing TSCs, no time limits are specified during any operational steps, including loading, vacuum drying, or transfer to the CONCRETE CASKS. With helium gas cover, at low pressure conditions during vacuum drying or at the 1 atmosphere backfill pressure, the system remains at allowable temperature at steady state conditions.

ACWS may be used to facilitate drying by circulating heated water thru the TSC to MTC annulus. Operation of an annulus cooling system, or water conditions in the TSC to MTC annulus without water circulation, is permitted for the FBM TSCs but is not required for safe operation (i.e.,

air condition is acceptable in the TSC to MTC annulus).

APPLICABILITY The sealed TSC with a dry measured helium mass cavity atmosphere for spent fuel assembly system, or for the FBM system, is required to be established prior to TRANSPORT OPERATIONS to ensure integrity of the fuel contents and the effectiveness of the heat dissipation capability during LOADING OPERATIONS and STORAGE OPERATIONS.

ACTIONS A note has been added to the ACTIONS, which states that, for this LCO, separate Condition entry is allowed for each TSC. This is acceptable as the Required Actions for each Condition provide appropriate compensatory measures for each TSC not meeting the LCO.

Subsequent TSCs that do not meet the LCO are governed by (continued)

Transportable Storage Canister (TSC) 3.1.1 NAC International 13C-14 MAGNASTOR FSAR, Revision 23D BASES (continued)

ACTIONS (continued) subsequent Condition entry and application of associated Required Actions.

A.1 If the cavity vacuum drying pressure with the vacuum pump isolated and turned off is not met prior to TRANSPORT OPERATIONS, an engineering evaluation is necessary to determine the potential quantity of moisture left in the TSC. Since moisture remaining in the cavity during TRANSPORT and STORAGE OPERATIONS may represent a long-term degradation issue, immediate action is not required. The Completion Time is sufficient to complete an engineering evaluation of the safety significance of the Condition.

AND A.2 Upon determination of the mass of water potentially contained in the TSC, a corrective action plan shall be developed and actions initiated, as required, in a timely manner to return the TSC to an analyzed condition.

B.1 If a determination is made that, as applicable, the helium backfill mass or backfill pressure or backfill gas purity requirements are not met prior to TRANSPORT OPERATIONS, an engineering evaluation shall be performed to determine backfill gas quantity in the TSC. As high or low helium mass values could result in TSC over-pressurization or reduced effectiveness of the TSC heat rejection capability, respectively, the engineering evaluation shall be performed in a timely manner. High or low helium pressure will have limited impact on system safe operation of the FBM TSC, but an engineering evaluation of the condition shall be performed in a timely manner. The Completion Time is sufficient to complete an engineering evaluation of the safety significance of the Condition.

AND B.2 When, as applicable, the mass of helium or pressure of helium (FBM contents) in the TSC is determined, a corrective action plan shall be developed and actions implemented, as required, in a timely manner to return the TSC to an analyzed condition.

continued)

Transportable Storage Canister (TSC) 3.1.1 NAC International 13C-15 MAGNASTOR FSAR, Revision 23D BASES (continued)

ACTIONS (continued)

C.1 If the TSC cannot be returned to an analyzed safe condition, the TSC contents are required to be placed in a safe condition in the spent fuel pool. The Completion Time is reasonable based on the time required to plan, train and perform UNLOADING OPERATIONS in an orderly manner.

C.2 If the TSC containing FBM cannot be returned to an analyzed safe condition, the TSC contents are required to be placed in a safe condition. The Completion Time is reasonable based on the time required to evaluate the contents, plan, train and perform UNLOADING OPERATIONS in an orderly manner.

SURVEILLANCE REQUIREMENTS SR 3.1.1.1, and SR 3.1.1.2 The long-term integrity of the TSC and stored contents is dependent on a dry and pressurized helium or atmospheric pressure helium (FBM contents) cavity environment. The dryness of the TSC cavity is demonstrated by evacuation by a vacuum pump to a low vacuum and monitoring the rise in pressure over a specified period with the vacuum pump isolated and turned off.

The establishment of the required helium backfill mass or helium pressure, as applicable, and corresponding operating pressure at operating temperature will ensure the effectiveness of the TSC capability to reject the contents decay heat to the fuel basket and TSC structure.

The decay heat will subsequently be rejected by the cooling air flows provided by the CONCRETE CASK or MSO during STORAGE OPERATIONS (note that FBM contents do not require cooling air flow to demonstrate safe operating conditions).

These two surveillances shall be performed once prior to TRANSPORT OPERATIONS. Successful completion will ensure that the appropriate conditions have been established for long-term storage in compliance with the analyzed design bases.

REFERENCES

1.

FSAR Sections 4.4 and 9.1.

CONCRETE CASK Heat Removal System 3.1.2 NAC International 13C-16 MAGNASTOR FSAR, Revision 22D 3.1 MAGNASTOR SYSTEM Integrity 3.1.2 STORAGE CASK Heat Removal System BASES BACKGROUND The heat removal system for the STORAGE CASK 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 STORAGE CASK annulus. During STORAGE OPERATIONS, ambient air is drawn into the STORAGE CASK annulus through the four air inlets located at the base of the STORAGE CASK. 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 the STORAGE CASK.

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 STORAGE CASK. 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. FBM TSCs do not require air convection through the vents for safe system operations.

For spent fuel assembly systems, analyses have been performed for two scenarios corresponding to the complete obstruction of what is equivalent to two and four air inlets. Blockage of the equivalent area of two air inlets reduces the convective air flow through the STORAGE CASK/TSC annulus and decreases the heat transfer from the TSC surfaces to the ambient environment. Under this off-normal event, no STORAGE CASK or TSC components or fuel cladding exceed established short-term temperature limits, and the TSC internal pressure does not exceed the analyzed maximum pressure.

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 STORAGE CASK. Upon loss of air cooling, the MAGNASTOR SYSTEM component temperatures will increase toward their respective (continued)

CONCRETE CASK Maximum Surface Dose Rates 3.3.1 NAC International 13C-25 MAGNASTOR FSAR, Revision 23D BASES (continued)

SURVEILLANCE REQUIREMENTS SR 3.3.1.1 This SR ensures that the STORAGE CASK maximum neutron and gamma surface dose rates are within the LCO limits after transfer of the TSC or FBM TSC into the STORAGE CASK and prior to the commencement of STORAGE OPERATIONS. This Frequency is acceptable, as corrective actions can be taken before offsite dose limits are compromised. The surface dose rates are measured approximately at the locations indicated on Figure 3-1 of Appendix A of the Technical Specifications.

REFERENCES 1.

10 CFR Parts 20 and 72 2.

SAR Section 5.1

TSC Surface Contamination 3.3.2 NAC International 13C-26 MAGNASTOR FSAR, Revision 23D 3.3 MAGNASTOR SYSTEM Radiation Protection 3.3.2 TSC Surface Contamination BASES BACKGROUND A TRANSFER CASK containing an empty TSC is immersed in the spent fuel pool in order to load the spent fuel assemblies. The external surfaces of the TSC are maintained clean by the application of clean water to the annulus of the TRANSFER CASK. However, there is potential for the surface of the TSC (with fuel or FBM) to become contaminated with the radioactive material. Contamination exceeding LCO limits is removed prior to moving the STORAGE CASK containing the TSC to the ISFSI in order to minimize the radioactive contamination to personnel or the environment. This allows the ISFSI to be entered without additional radiological controls to prevent the spread of contamination and reduces personnel dose due to the spread of loose contamination or airborne contamination. This is consistent with ALARA practices.

APPLICABLE SAFETY ANALYSIS The radiation protection measures implemented at the ISFSI are based on the assumption that the exterior surfaces of the TSC are not significantly contaminated. Failure to decontaminate the surfaces of the TSC to below the LCO limits could lead to higher-than-projected occupational dose and potential site contamination.

LCO Removable surface contamination on the exterior surfaces of the TSC is limited to 20,000 dpm/100 cm2 from beta and gamma sources and 200 dpm/100 cm2 from alpha sources. For a FBM TSC, removable surface contamination on the exterior surfaces is limited to 20,000 dpm/100 cm2 from beta and gamma sources and 200 dpm/100 cm2 from alpha sources. Only loose contamination is controlled, as fixed contamination will not result from the TSC loading process.

Experience has shown that these limits are low enough to prevent the spread of contamination to clean areas and are significantly less than the levels that could cause significant personnel skin dose.

(continued)

ML23229A482

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