Text

HI-STORM 100 Amendment 16 Certificate of Compliance, Appendix B Reorganization
	ML21068A385
Person / Time
Site:	Holtec
Issue date:	03/09/2021
From:	; Holtec
To:	; Office of Nuclear Material Safety and Safeguards
Shared Package
ML21068A360	List: ML21068A361; ML21068A362; ML21068A363; ML21068A364; ML21068A366; ML21068A367; ML21068A368; ML21068A369; ML21068A370; ML21068A372; ML21068A383; ML21068A384; ML21068A385; ML21068A386; ML21068A387; ML21068A388; ML21068A389; ML21068A390; ML21068A391; ML21068A392; ML21068A393; ML21068A394; ML21068A395; ML21068A396; ML21068A397; ML21068A398;
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PROPOSED CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX B TECHNICAL SPECIFICATIONS FOR THE HI-STORM 100 CASK SYSTEM 3 to Holtec Letter 5014917 1 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B i

TABLE OF CONTENTS 1

Definitions, Use, and Application........................................................................................ 1-1 1.1 Definitions.................................................................................................................... 1-1 1.2 Logical Connectors...................................................................................................... 1-7 1.3 Completion Times...................................................................................................... 1-10 1.4 Frequency.................................................................................................................. 1-14 2

Approved Contents............................................................................................................. 2-1 2.1 Fuel Specifications and Loading Conditions................................................................ 2-1 2.1.1 Fuel To Be Stored In The HI-STORM 100 SFSC System.................................... 2-1 2.1.2 Uniform Fuel Loading........................................................................................... 2-1 2.1.3 Regionalized Fuel Loading................................................................................... 2-1 2.2 Decay Heat Limits for ZR-Clad Fuel.......................................................................... 2-48 2.2.1 Uniform Fuel Loading Decay Heat Limits for ZR-clad Fuel for VENTILATED OVERPACK...................................................................................................................... 2-48 2.2.2 Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel for VENTILATED OVERPACK...................................................................................................................... 2-49 2.2.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel for VENTILATED OVERPACK...................................................................................................................... 2-50 2.2.4 Compliance with Maximum Fuel Storage Location Decay Heat Limits.............. 2-51 2.2.5 Fuel Loading Decay Heat Limits for UNVENTILATED OVERPACK.................. 2-51 2.2.6 Burnup and Cooling Time Qualifications for the MPC-68M for UNVENTILATED OVERPACK...................................................................................................................... 2-51 3

Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs).............. 3-1 3.0 Applicability.................................................................................................................. 3-1 3.1 SFSC INTEGRITY....................................................................................................... 3-4 3.1.1 Multi-Purpose Canister (MPC)............................................................................. 3-4 3.1.2 SFSC Heat Removal System............................................................................... 3-7 3.1.3 MPC Cavity Reflooding...................................................................................... 3-10 3.1.4 Supplemental Cooling System........................................................................... 3-12 3.2 SFSC RADIATION PROTECTION............................................................................ 3-14 3.2.1 Deleted............................................................................................................... 3-14 3.2.2 TRANSFER CASK Surface Contamination........................................................ 3-14 3.3 SFSC CRITICALITY CONTROL............................................................................... 3-16 3.3.1 Boron Concentration.......................................................................................... 3-16 4

Administrative Controls....................................................................................................... 4-1 4.1 Radioactive Effluent Control Program......................................................................... 4-1 3 to Holtec Letter 5014917 2 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B ii 4.2 Cask Transport Evaluation Program............................................................................. 4-2 4.2.1 Freestanding Overpacks and the Transfer Cask.................................................. 4-2 4.2.2 Anchored Overpacks............................................................................................ 4-2 4.3 Radiation Protection Program....................................................................................... 4-4 4.4 Fabrication Helium Leak Test...................................................................................... 4-7 4.5 Violations of Fuel Specifications or Loading Conditions.............................................. 4-8 4.6 Heavy Loads Requirements........................................................................................ 4-9 4.7 Aging Management Program..................................................................................... 4-10 FIGURES Figure 2-1: Fuel Loading Regions - MPC-24............................................................................ 2-2 Figure 2-2: Fuel Loading Regions - MPC-24E/24EF................................................................ 2-3 Figure 2-3: Fuel Loading Regions - MPC32/32F...................................................................... 2-4 Figure 2-4: Fuel Loading Regions - MPC-68/68FF/68M............................................................ 2-5 Figure 2-5: QSHL Pattern Per Cell Allowable Heat Loads (kW) - MPC-68M........................... 2-57 Figure 2-6: QSHL-2 Pattern, Per Cell Allowable Heat Loads (kW) - MPC-68M....................... 2-58 Figure 2-7: QSHL-3 Pattern, Per Cell Allowable Heat Loads (kW) - MPC-68M....................... 2-59 Figure 2-8: QSHL-4 Pattern, Per Cell Allowable Heat Loads (kW) - MPC-68M....................... 2-60 TABLES Table 2-1:Fuel Assembly Limits................................................................................................. 2-6 Table 2-2: PWR Fuel Assembly Characteristics...................................................................... 2-36 Table 2-3: BWR Fuel Assembly Characteristics...................................................................... 2-41 Table 2-4: Non-Fuel Hardware Cooling and Average Burnup................................................. 2-47 Table 2-5: Restrictions for Partial Gadolinium Credit in MPC-68M.......................................... 2-48 Table 2-6: Maximum Allowable Decay Heat per Fuel Storage Location (Uniform Loading, ZR-Clad)........................................................................................................................................ 2-49 Table 2-7: Fuel Storage Regions per MPC.............................................................................. 2-50 Table 2-8: Allowable Heat Load for Damaged Fuel Assemblies and Fuel Debris under Regionalized Loading.............................................................................................................. 2-50 Table 2-9: PWR Fuel Assembly Burnup and Cooling Time Limits for VENTILATED OVERPACK

................................................................................................................................................. 2-52 Table 2-10: BWR Fuel Assembly Burnup and Cooling Time Limits for VENTILATED OVERPACK

................................................................................................................................................. 2-53 Table 2-11: MPC-68M Heat Load Data for UNVENTILATED OVERPACK............................. 2-53 Table 2-12: MPC-68M Requirements on Developing Regionalized Heat Load Patterns for UNVENTILATED OVERPACK................................................................................................. 2-54 Table 2-13: Section Heat Load Calculations for MPC=68M for UNVENTILATED OVERPACK.....

................................................................................................................................................. 2-54 Table 2-14: DFC and DFI Storage Locations with Heat Load penalties for MPC-68M for UNVENTILATED OVERPACK................................................................................................. 2-55 Table 2-15: Burnup and Cooling Time Fuel Qualification Requirements for MPC-68M for UNVENTILATED OVERPACK................................................................................................. 2-55 3 to Holtec Letter 5014917 3 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B iii Table 2-16: Regionalized Storage Cell Heat Load Limits........................................................ 2-56 Table 2-17: Uniform Storage Cell Heat Load Limits................................................................ 2-56 Table 3-1: MPC Cavity Drying Limits for all MPC Types for Ventilated Overpack................... 3-20 Table 3-2: MPC Cavity Drying Limits for all MPC Types for Unventilated Overpack............... 3-21 Table 3-3: MPC Helium Backfill Limits for Ventilated Overpack.............................................. 3-22 Table 3-4: MPC Helium Backfill Limits for Unventilated Overpack.......................................... 3-24 Table 3-5: Completion Time for Actions to Restore SFSC Heat Removal System Operable.. 3-24 Table 4-1: Transfer Cask and Free-Standing Overpack Lifting Requirements.......................... 4-3 3 to Holtec Letter 5014917 4 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-1 1 DEFINITIONS, USE, AND APPLICATION 1.1 Definitions 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.

CASK TRANSFER FACILITY (CTF)

A CASK TRANSFER FACILITY is an optional aboveground or underground system used during the transfer of a loaded MPC between a transfer cask and a storage OVERPACK external to 10 CFR Part 50 controlled structures. The CASK TRANSFER FACILITY includes the following components and equipment: (1) a Cask Transfer Structure used to stabilize the OVERPACK, TRANSFER CASK and/or MPC during lifts involving spent fuel not bounded by the regulations of 10 CFR Part 50, and (2) Either a stationary lifting device or a mobile lifting device used in concert with the stationary structure to lift the OVERPACK, TRANSFER CASK, and/or MPC.

DAMAGED FUEL ASSEMBLY DAMAGED FUEL ASSEMBLIES are fuel assemblies with known or suspected cladding defects, as determined by a review of records, greater than pinhole leaks or hairline cracks, empty fuel rod locations that are not filled with dummy fuel rods, missing structural components such as grid spacers, whose structural integrity has been impaired such that geometric rearrangement of fuel or gross failure of the cladding is expected based on engineering evaluations, or that cannot be handled by normal means.

Fuel assemblies that cannot be handled by normal means due to fuel cladding damage are considered FUEL DEBRIS. 3 to Holtec Letter 5014917 5 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-2 Term Definition DAMAGED FUEL CONTAINER (DFC)

DFCs are specially designed enclosures for DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS which permit gaseous and liquid media to escape while minimizing dispersal of gross particulates. DFCs authorized for use in the HI-STORM 100 System are as follows:

1. Holtec Dresden Unit 1/Humboldt Bay design

2. Transnuclear Dresden Unit 1 design

3. Holtec Generic BWR design

4. Holtec Generic PWR design DAMAGED FUEL ISOLATOR (DFI)

DFIs are specially designed barriers installed at the top and bottom of the storage cell space which permit flow of gaseous and liquid media while preventing the potential migration of fissile material from fuel assemblies with cladding damage. DFIs are used ONLY with damaged fuel assemblies which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected. Damaged fuel stored in DFIs may contain missing or partial fuel rods and/or fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks.

FUEL DEBRIS FUEL DEBRIS is ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting these loose fuel assembly parts, or fuel assemblies with known or suspected defects which cannot be handled by normal means due to fuel cladding damage.

FUEL BUILDING The FUEL BUILDING is the site-specific power plant facility, governed by the regulations of 10 CFR Part 50, where the loaded OVERPACK or TRANSFER CASK is transferred to or from the transporter. 3 to Holtec Letter 5014917 6 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-3 Term Definition GROSSLY BREACHED SPENT FUEL ROD Spent nuclear fuel rod with a cladding defect that could lead to the release of fuel particulate greater than the average size fuel fragment for that particular assembly. A gross cladding breach may be confirmed by visual examination, through a review of reactor operating records indicating the presence of heavy metal isotopes, or other acceptable inspection means.

INTACT FUEL ASSEMBLY INTACT FUEL ASSEMBLIES are fuel assemblies without known or suspected cladding defects greater than pinhole leaks or hairline cracks and which can be handled by normal means. Fuel assemblies without fuel rods in fuel rod locations shall not be classified as INTACT FUEL ASSEMBLIES unless dummy fuel rods are used to displace an amount of water greater than or equal to that displaced by the fuel rod(s) in the active region. INTACT FUEL ASSEMBLIES may contain integral fuel absorber rods (IFBA) in PWR fuel, or burnable poison rods in BWR fuel.

LOADING OPERATIONS LOADING OPERATIONS include all licensed activities on an OVERPACK or TRANSFER CASK while it is being loaded with fuel assemblies. LOADING OPERATIONS begin when the first fuel assembly is placed in the MPC and end when the OVERPACK or TRANSFER CASK is suspended from or secured on the transporter. LOADING OPERATIONS does not include MPC TRANSFER.

MINIMUM ENRICHMENT MINIMUM ENRICHMENT is the minimum assembly average enrichment. Natural uranium and low enrichment blankets are not considered in determining minimum enrichment.

MULTI-PURPOSE CANISTER (MPC)

MPCs are the sealed spent nuclear fuel canisters which consist of a honeycombed fuel basket contained in a cylindrical canister shell which is welded to a baseplate, lid with welded port cover plates, and closure ring. The MPC provides the confinement boundary for the contained radioactive materials. 3 to Holtec Letter 5014917 7 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-4 Term Definition MPC TRANSFER MPC TRANSFER begins when the MPC is lifted off the TRANSFER CASK bottom lid and ends when the MPC is supported from beneath by the OVERPACK or VVM (or the reverse).

NON-FUEL HARDWARE NON-FUEL HARDWARE is defined as Burnable Poison Rod Assemblies (BPRAs), Thimble Plug Devices (TPDs),

Control Rod Assemblies (CRAs), Axial Power Shaping Rods (APSRs), Wet Annular Burnable Absorbers (WABAs), Rod Cluster Control Assemblies (RCCAs),

Control Element Assemblies (CEAs), Neutron Source Assemblies (NSAs), water displacement guide tube plugs, orifice rod assemblies, instrument tube tie rods (ITTRs), vibration suppressor inserts, and components of these devices such as individual rods.

OVERPACK OVERPACKs are the casks which receive and contain the sealed MPCs for interim storage on the ISFSI. They provide gamma and neutron shielding, and in some versions, may provide for ventilated air flow to promote heat transfer from the MPC to the environs. The term OVERPACK does not include the TRANSFER CASK.

PLANAR-AVERAGE INITIAL ENRICHMENT PLANAR AVERAGE INITIAL ENRICHMENT is the average of the distributed fuel rod initial enrichments within a given axial plane of the assembly lattice.

REDUNDANT PORT COVER DESIGN REDUNDANT PORT COVER DESIGN refers to two independent port cover plates per port opening, where each port cover plate contains multiple pass closure welds.

REPAIRED/RECONSTITUTED FUEL ASSEMBLY Spent nuclear fuel assembly which contains dummy fuel rod(s) that displaces an amount of water greater than or equal to the original fuel rod(s) and/or which contains structural repairs so it can be handled by normal means. 3 to Holtec Letter 5014917 8 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-5 Term Definition SPENT FUEL STORAGE CASKS (SFSCs)

SFSCs are containers approved for the storage of spent fuel assemblies at the ISFSI. The HI-STORM 100 SFSC System consists of the OVERPACK/VVM and its integral MPC.

STORAGE OPERATIONS STORAGE OPERATIONS include all licensed activities that are performed at the ISFSI while an SFSC containing spent fuel is situated within the ISFSI perimeter. STORAGE OPERATIONS does not include MPC TRANSFER.

TRANSFER CASK TRANSFER CASKs are containers designed to contain the MPC during and after loading of spent fuel assemblies and to transfer the MPC to or from the OVERPACK/VVM. The HI-STORM 100 System employs either the 125-Ton or the 100-Ton HI-TRAC TRANSFER CASK. For use with Appendix D, the definition of TRANSFER CASK also includes the HI-TRAC MS.

TRANSPORT OPERATIONS TRANSPORT OPERATIONS include all licensed activities performed on an OVERPACK or TRANSFER CASK loaded with one or more fuel assemblies when it is being moved after LOADING OPERATIONS or before UNLOADING OPERATIONS.

TRANSPORT OPERATIONS begin when the OVERPACK or TRANSFER CASK is first suspended from or secured on the transporter and end when the OVERPACK or TRANSFER CASK is at its destination and no longer secured on or suspended from the transporter.

TRANSPORT OPERATIONS includes MPC TRANSFER. 3 to Holtec Letter 5014917 9 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-6 Term Definition UNDAMAGED FUEL ASSEMBLY UNDAMAGED FUEL ASSEMBLY is: a) a fuel assembly without known or suspected cladding defects greater than pinhole leaks or hairline cracks and which can be handled by normal means; or b) a BWR fuel assembly with an intact channel, a maximum planar average initial enrichment of 3.3 wt% U-235, without known or suspected GROSSLY BREACHED SPENT FUEL RODS, and which can be handled by normal means.

An UNDAMAGED FUEL ASSEMBLY may be a

REPAIRED/

RECONSTITUTED FUEL ASSEMBLY.

UNLOADING OPERATIONS UNLOADING OPERATIONS include all licensed activities on an SFSC to be unloaded of the contained fuel assemblies. UNLOADING OPERATIONS begin when the OVERPACK or TRANSFER CASK is no longer suspended from or secured on the transporter and end when the last fuel assembly is removed from the SFSC. UNLOADING OPERATIONS does not include MPC TRANSFER.

UNVENTILATED OVERPACK The UNVENTILATED OVERPACK is an aboveground OVERPACK which receives and contains the sealed MPC for interim storage at the ISFSI. The UNVENTILATED OVERPACK design is characterized by its absence of inlet and outlet ventilation passages.

VENTILATED OVERPACK The VENTILATED OVERPACK is an aboveground OVERPACK which receives and contains the sealed MPC for interim storage at the ISFSI. The VENTILATED OVERPACK provides passages for airflow to promote heat transfer from the MPC.

VERTICAL VENTILATED MODULE (VVM) (HI-STORM 100U SYSTEM ONLY)

The VVM is a subterranean type overpack which receives and contains the sealed MPC for interim storage at the ISFSI. The VVM supports the MPC in a vertical orientation and provides air flow through cooling passages to promote heat transfer from the MPC to the environs.

3 to Holtec Letter 5014917 10 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-7 Term Definition ZR ZR means any zirconium-based fuel cladding or fuel channel material authorized for use in a commercial nuclear power plant reactor.

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 TS 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 indentions 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.

(continued) 3 to Holtec Letter 5014917 11 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-8 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) 3 to Holtec Letter 5014917 12 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-9 EXAMPLES (continued)

EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met.

A.1 Stop...

OR A.2.1 Verify...

AND 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.

3 to Holtec Letter 5014917 13 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-10 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 Times(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, providing the HI-STORM 100 System 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 the HI-STORM 100 System 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) 3 to Holtec Letter 5014917 14 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-11 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 separate 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 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) 3 to Holtec Letter 5014917 15 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-12 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) 3 to Holtec Letter 5014917 16 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-13 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 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 start and are tracked for each component.

(continued) 3 to Holtec Letter 5014917 17 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-14 IMMEDIATE COMPLETION TIME When "Immediately" is used as a Completion Time, the Required Action should be pursued without delay and in a controlled manner.

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.

The "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 the 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.

(continued) 3 to Holtec Letter 5014917 18 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-15 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) 3 to Holtec Letter 5014917 19 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 1-16 EXAMPLES (continued)

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits.

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.

3 to Holtec Letter 5014917 20 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-1 2 APPROVED CONTENTS 2.1 Fuel Specifications and Loading Conditions 2.1.1 Fuel To Be Stored In The HI-STORM 100 SFSC System

a.

INTACT FUEL ASSEMBLIES, UNDAMAGED FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, FUEL DEBRIS, and NON-FUEL HARDWARE meeting the limits specified in Table 2-1 and other referenced tables may be stored in the HI-STORM 100 SFSC System.

b.

For MPCs partially loaded with stainless steel clad fuel assemblies, all remaining fuel assemblies in the MPC shall meet the decay heat generation limit for the stainless steel clad fuel assemblies.

c.

For MPCs partially loaded with array/class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A fuel assemblies, all remaining ZR clad INTACT FUEL ASSEMBLIES in the MPC shall meet the decay heat generation limits for the 6x6A, 6x6B, 6x6C, 7x7A and 8x8A fuel assemblies.

d.

All BWR fuel assemblies may be stored with or without ZR channels with the exception of array/class 10x10D and 10x10E fuel assemblies, which may be stored with or without ZR or stainless steel channels.

2.1.2 Uniform Fuel Loading Any authorized fuel assembly may be stored in any fuel storage location, subject to other restrictions related to DAMAGED FUEL, FUEL DEBRIS, and NON-FUEL HARDWARE specified in the CoC.

2.1.3 Regionalized Fuel Loading Users may choose to store fuel using regionalized loading in lieu of uniform loading to allow higher heat emitting fuel assemblies to be stored than would otherwise be able to be stored using uniform loading. Figures 2-1 through 2-4 define the regions for the MPC-24, MPC-24E, MPC-24EF, MPC-32, MPC-32F, MPC-68, MPC-68FF, and MPC-68M models, respectively a. Fuel assembly decay heat limits for regionalized loading are specified in Section 2.2.2 for VENTILATED OVERPACK, and Section 2.2.5 for UNVENTILATED OVERPACK. Fuel assemblies used in regionalized loading shall meet all other applicable limits specified in Tables 2-1 through 2-3.

a These figures are only intended to distinguish the fuel loading regions. Other details of the basket design are illustrative and may not reflect the actual basket design details. The design drawings should be consulted for basket design details. 3 to Holtec Letter 5014917 21 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-2 Figure 2-1: Fuel Loading Regions - MPC-24 3 to Holtec Letter 5014917 22 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-3 Figure 2-2: Fuel Loading Regions - MPC-24E/24EF 3 to Holtec Letter 5014917 23 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-4 Figure 2-3: Fuel Loading Regions - MPC32/32F 3 to Holtec Letter 5014917 24 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-5 Figure 2-4: Fuel Loading Regions - MPC-68/68FF/68M 3 to Holtec Letter 5014917 25 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-6 Table 2-1:Fuel Assembly Limits Table 2-1 (page 1 of 30)

Fuel Assembly Limits I. MPC MODEL: MPC-24 A. Allowable Contents

1.

Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):

a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2-2 for the applicable fuel assembly array/class.

b. Initial Enrichment:

As specified in Table 2-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:

i. Array/Classes 14x14D,14x14E, and 15x15G Cooling time 8 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes Cooling time and average burnup as specified in Section 2.2.

ii. NON-FUEL HARDWARE As specified in Table 2-4.

3 to Holtec Letter 5014917 26 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-7 Table 2-1 (page 2 of 30)

Fuel Assembly Limits I. MPC MODEL: MPC-24 (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G 710 Watts ii. All Other Array/Classes As specified in Section 2.2.

e. Fuel Assembly Length:

176.8 inches (nominal design)

f. Fuel Assembly Width:

8.54 inches (nominal design)

g. Fuel Assembly Weight:

1720 lbs (including NON-FUEL HARDWARE) for assemblies that do not require fuel spacers, otherwise 1680 lbs (including NON-FUEL HARDWARE)

B. Quantity per MPC: Up to 24 fuel assemblies.

C. Deleted.

D. DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS are not authorized for loading into the MPC-24.

E. One NSA is authorized for loading into the MPC-24.

Note 1:

Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing APSRs or NSAs may only be loaded in fuel storage locations 9, 10, 15, and/or 16. Fuel assemblies containing CRAs, RCCAs, CEAs may only be stored in fuel storage locations 4, 5, 8 - 11, 14 - 17, 20 and/or 21 (see Figure 2-1). These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading. 3 to Holtec Letter 5014917 27 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-8 Table 2-1 (page 3 of 30)

Fuel Assembly Limits II. MPC MODEL: MPC-68F A. Allowable Contents

1.

Uranium oxide, BWR INTACT FUEL ASSEMBLIES, with or without ZR channels.

Uranium oxide BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 2-3 for fuel assembly array class 6x6A, 6x6C, 7x7A or 8x8A, and meet the following specifications:

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment:

As specified in Table 2-3 for the applicable fuel assembly array/class.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly:

Cooling time 18 years and an average burnup 30,000 MWD/MTU.

e. Decay Heat Per Assembly 115 Watts

f. Fuel Assembly Length:

135.0 inches (nominal design)

g. Fuel Assembly Width:

4.70 inches (nominal design)

h. Fuel Assembly Weight:

400 lbs, including channels 3 to Holtec Letter 5014917 28 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-9 Table 2-1 (page 4 of 30)

Fuel Assembly Limits II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

2.

Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2-3 for fuel assembly array/class 6x6A, 6x6C, 7x7A, or 8x8A, and meet the following specifications:

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment:

As specified in Table 2-3 for the applicable fuel assembly array/class.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly:

Cooling time 18 years and an average burnup 30,000 MWD/MTU.

e. Decay Heat Per Assembly:

115 Watts

f. Fuel Assembly Length:

135.0 inches (nominal design)

g. Fuel Assembly Width:

4.70 inches (nominal design)

h. Fuel Assembly Weight:

550 lbs, including channels and DFC 3 to Holtec Letter 5014917 29 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-10 Table 2-1 (page 5 of 30)

Fuel Assembly Limits II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

3.

Uranium oxide, BWR FUEL DEBRIS, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the uranium oxide BWR FUEL DEBRIS shall meet the criteria specified in Table 2-3 for fuel assembly array/class 6x6A, 6x6C, 7x7A, or 8x8A, and meet the following specifications:

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2-3 for the applicable original fuel assembly array/class.

c. Initial Maximum Rod Enrichment:

As specified in Table 2-3 for the applicable original fuel assembly array/class.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly Cooling time 18 years and an average burnup 30,000 MWD/MTU for the original fuel assembly.

e. Decay Heat Per Assembly 115 Watts

f. Original Fuel Assembly Length 135.0 inches (nominal design)

g. Original Fuel Assembly Width 4.70 inches (nominal design)

h. Fuel Debris Weight 550 lbs, including channels and DFC 3 to Holtec Letter 5014917 30 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-11 Table 2-1 (page 6 of 30)

Fuel Assembly Limits II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

4.

Mixed oxide (MOX), BWR INTACT FUEL ASSEMBLIES, with or without ZR channels.

MOX BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 2-3 for fuel assembly array/class 6x6B, and meet the following specifications:

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2-3 for fuel assembly array/class 6x6B.

c. Initial Maximum Rod Enrichment:

As specified in Table 2-3 for fuel assembly array/class 6x6B.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly:

Cooling time 18 years and an average burnup 30,000 MWD/MTIHM.

e. Decay Heat Per Assembly 115 Watts

f. Fuel Assembly Length:

135.0 inches (nominal design)

g. Fuel Assembly Width:

4.70 inches (nominal design)

h. Fuel Assembly Weight:

400 lbs, including channels 3 to Holtec Letter 5014917 31 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-12 Table 2-1 (page 7 of 30)

Fuel Assembly Limits II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

5.

Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. MOX BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2-3 for fuel assembly array/class 6x6B, and meet the following specifications:

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2-3 for fuel assembly array/class 6x6B.

c. Initial Maximum Rod Enrichment:

As specified in Table 2-3 for fuel assembly array/class 6x6B.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly:

Cooling time 18 years and an average burnup 30,000 MWD/MTIHM.

e. Decay Heat Per Assembly 115 Watts

f. Fuel Assembly Length:

135.0 inches (nominal design)

g. Fuel Assembly Width:

4.70 inches (nominal design)

h. Fuel Assembly Weight:

550 lbs, including channels and DFC 3 to Holtec Letter 5014917 32 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-13 Table 2-1 (page 8 of 30)

Fuel Assembly Limits II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

6.

Mixed Oxide (MOX), BWR FUEL DEBRIS, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the MOX BWR FUEL DEBRIS shall meet the criteria specified in Table 2-3 for fuel assembly array/class 6x6B, and meet the following specifications:

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2-3 for original fuel assembly array/class 6x6B.

c. Initial Maximum Rod Enrichment:

As specified in Table 2-3 for original fuel assembly array/class 6x6B.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly:

Cooling time 18 years and an average burnup 30,000 MWD/MTIHM for the original fuel assembly.

e. Decay Heat Per Assembly 115 Watts

f. Original Fuel Assembly Length:

135.0 inches (nominal design)

g. Original Fuel Assembly Width:

4.70 inches (nominal design)

h. Fuel Debris Weight:

550 lbs, including channels and DFC 3 to Holtec Letter 5014917 33 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-14 Table 2-1 (page 9 of 30)

Fuel Assembly Limits II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

7.

Thoria rods (ThO2 and UO2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

ZR

b. Composition:

98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U.

OR 98.5 wt.% ThO2, 1.5 wt.% UO2 with an enrichment of 93.5 wt.% 235U

c. Number of Rods Per Thoria Rod Canister:

18

d. Decay Heat Per Thoria Rod Canister:

115 Watts

e. Post-irradiation Fuel Cooling Time and Average Burnup Per Thoria Rod Canister:

A fuel post-irradiation cooling time 18 years and an average burnup 16,000 MWD/MTIHM.

f. Initial Heavy Metal Weight:

27 kg/canister

g. Fuel Cladding O.D.:

0.412 inches

h. Fuel Cladding I.D.:

0.362 inches

i. Fuel Pellet O.D.:

0.358 inches

j. Active Fuel Length:

111 inches

k. Canister Weight:

550 lbs, including fuel 3 to Holtec Letter 5014917 34 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-15 Table 2-1 (page 10 of 30)

Fuel Assembly Limits II. MPC MODEL: MPC-68F (continued)

B. Quantity per MPC (up to a total of 68 assemblies):

(All fuel assemblies must be array/class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A):

Up to four (4) DFCs containing uranium oxide BWR FUEL DEBRIS or MOX BWR FUEL DEBRIS. The remaining MPC-68F fuel storage locations may be filled with fuel assemblies of the following type, as applicable:

1. Uranium oxide BWR INTACT FUEL ASSEMBLIES;

2. MOX BWR INTACT FUEL ASSEMBLIES;

3. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES placed in DFCs;

4. MOX BWR DAMAGED FUEL ASSEMBLIES placed in DFCs; or

5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.

C. Fuel assemblies with stainless steel channels are not authorized for loading in the MPC-68F.

D. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC-68F. The Antimony-Beryllium source material shall be in a water rod location. 3 to Holtec Letter 5014917 35 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-16 Table 2-1 (page 11 of 30)

Fuel Assembly Limits III. MPC MODEL: MPC-68 and MPC-68FF A. Allowable Contents

1. Uranium oxide or MOX BWR INTACT FUEL ASSEMBLIES listed in Table 2-3, with or without channels and meeting the following specifications:

a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2-3 for the applicable fuel assembly array/class

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment As specified in Table 2-3 for the applicable fuel assembly array/class.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly

i. Array/Classes 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A Cooling time 18 years and an average burnup 30,000 MWD/MTU (or MWD/MTIHM).

ii. Array/Class 8x8F Cooling time 10 years and an average burnup 27,500 MWD/MTU.

iii. Array/Classes 10x10D and 10x10E Cooling time 10 years and an average burnup 22,500 MWD/MTU.

iv. All Other Array/Classes As specified in Section 2.2. 3 to Holtec Letter 5014917 36 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-17 Table 2-1 (page 12 of 30)

Fuel Assembly Limits III. MPC MODEL: MPC-68 and MPC-68FF (continued)

A. Allowable Contents (continued)

e. Decay Heat Per Assembly

i. Array/Classes 6x6A, 6X6B, 6x6C, 7x7A, and 8x8A 115 Watts ii. Array/Class 8x8F 183.5 Watts iii. Array/Classes 10x10D and 10x10E 95 Watts iv. All Other Array/Classes As specified in Section 2.2.

f. Fuel Assembly Length

i.

Array/Class

6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 135.0 inches (nominal design) ii. All Other Array/Classes 176.5 inches (nominal design)

g. Fuel Assembly Width

i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 4.70 inches (nominal design) ii. All Other Array/Classes 5.85 inches (nominal design)

h. Fuel Assembly Weight

i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 400 lbs, including channels ii. All Other Array/Classes 730 lbs, including channels 3 to Holtec Letter 5014917 37 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-18 Table 2-1 (page 13 of 30)

Fuel Assembly Limits III. MPC MODEL: MPC-68 and MPC-68FF (continued)

A. Allowable Contents (continued)

2.

Uranium oxide or MOX BWR DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, with or without channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide and MOX BWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2-3, and meet the following specifications:

a. Cladding Type:

ZR or Stainless Steel (SS) in accordance with Table 2-3 for the applicable fuel assembly array/class.

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

i. Array/Classes 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A.

As specified in Table 2-3 for the applicable fuel assembly array/class.

ii. All Other Array Classes 4.0 wt.% 235U.

c. Initial Maximum Rod Enrichment As specified in Table 2-3 for the applicable fuel assembly array/class.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly:

i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A Cooling time 18 years and an average burnup 30,000 MWD/MTU (or MWD/MTIHM).

ii. Array/Class 8x8F Cooling time 10 years and an average burnup 27,500 MWD/MTU.

iii. Array/Class 10x10D and 10x10E Cooling time 10 years and an average burnup 22,500 MWD/MTU.

iv. All Other Array/Classes As specified in Section 2.2. 3 to Holtec Letter 5014917 38 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-19 Table 2-1 (page 14 of 30)

Fuel Assembly Limits III. MPC MODEL: MPC-68 and MPC-68FF (continued)

A. Allowable Contents (continued)

e. Decay Heat Per Assembly

i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 115 Watts ii. Array/Class 8x8F 183.5 Watts iii. Array/Classes 10x10D and 10x10E 95 Watts iv. All Other Array/Classes As specified in Section 2.2.

f. Fuel Assembly Length

i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 135.0 inches (nominal design) ii. All Other Array/Classes 176.5 inches (nominal design)

g. Fuel Assembly Width

i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 4.70 inches (nominal design) ii. All Other Array/Classes 5.85 inches (nominal design)

h. Fuel Assembly Weight

i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 550 lbs, including channels and DFC ii. All Other Array/Classes 830 lbs, including channels and DFC 3 to Holtec Letter 5014917 39 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-20 Table 2-1 (page 15 of 30)

Fuel Assembly limits III. MPC MODEL: MPC-68 and MPC-68FF (continued)

A. Allowable Contents (continued)

3. Thoria rods (ThO2 and UO2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding type ZR

b. Composition 98.2 wt.% ThO2, 1.8 wt.% UO2 with an enrichment of 93.5 wt.% 235U.

OR 98.5 wt.% ThO2, 1.5 wt.% UO2 with an enrichment of 93.5% wt.% 235U

c. Number of Rods per Thoria Rod Canister:

18

d. Decay Heat Per Thoria Rod Canister:

115 Watts

e. Post-irradiation Fuel Cooling Time and Average Burnup per Thoria Rod Canister:

A fuel post-irradiation cooling time 18 years and an average burnup 16,000 MWD/MTIHM

f. Initial Heavy Metal Weight:

27 kg/canister

g. Fuel Cladding O.D.:

0.412 inches

h. Fuel Cladding I.D.:

0.362 inches

i. Fuel Pellet O.D.:

0.358 inches

j. Active Fuel Length:

111 inches

k. Canister Weight:

550 lbs, including fuel 3 to Holtec Letter 5014917 40 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-21 Table 2-1 (page 16 of 30)

Fuel Assembly Limits III. MPC MODEL: MPC-68 and MPC-68FF (continued)

B. Quantity per MPC (up to a total of 68 assemblies)

1. For fuel assembly array/classes 6x6A, 6X6B, 6x6C, 7x7A, or 8x8A, up to 68 BWR INTACT FUEL ASSEMBLIES and/or DAMAGED FUEL ASSEMBLIES. Up to eight (8) DFCs containing FUEL DEBRIS from these array/classes may be stored.

2. For all other array/classes, up to sixteen (16) DFCs containing BWR DAMAGED FUEL ASSEMBLIES and/or up to eight (8) DFCs containing FUEL DEBRIS. DFCs shall be located only in fuel storage locations 1, 2, 3, 8, 9, 16, 25, 34, 35, 44, 53, 60, 61, 66, 67, and/or 68. The remaining fuel storage locations may be filled with fuel assemblies of the following type:

i.

Uranium Oxide BWR INTACT FUEL ASSEMBLIES; or ii.

MOX BWR INTACT FUEL ASSEMBLIES.

3. Up to one (1) Dresden Unit 1 Thoria Rod Canister C. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading. The Antimony-Beryllium source material shall be in a water rod location.

D. Array/Class 10x10D and 10x10E fuel assemblies in stainless steel channels must be stored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 - 50 (see Figure 2-4). 3 to Holtec Letter 5014917 41 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-22 Table 2-1 (page 17 of 30)

Fuel Assembly Limits IV. MPC MODEL: MPC-24E and MPC-24EF A. Allowable Contents

1.

Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):

a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2-2 for the applicable fuel assembly array/class

b. Initial Enrichment:

As specified in Table 2-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:

i. Array/Classes 14x14D, 14x14E, and 15x15G Cooling time 8 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes As specified in Section 2.2.

iii. NON-FUEL HARDWARE As specified in Table 2-4. 3 to Holtec Letter 5014917 42 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-23 Table 2-1 (page 18 of 30)

Fuel Assembly Limits IV. MPC MODEL: MPC-24E and MPC-24EF (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G 710 Watts.

ii. All other Array/Classes As specified in Section 2.2.

e. Fuel Assembly Length:

176.8 inches (nominal design)

f. Fuel Assembly Width:

8.54 inches (nominal design)

g. Fuel Assembly Weight:

1,720 lbs (including NON-FUEL HARDWARE) for assemblies that do not require fuel

spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE) 3 to Holtec Letter 5014917 43 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-24 Table 2-1 (page 19 of 30)

Fuel Assembly Limits IV. MPC MODEL: MPC-24E and MPC-24EF (continued)

A. Allowable Contents (continued)

2. Uranium oxide, PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS, with or without NON-FUEL HARDWARE, placed in DAMAGED FUEL CONTAINERS. Uranium oxide PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2-2 and meet the following specifications (Note 1):

a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2-2 for the applicable fuel assembly array/class

b. Initial Enrichment:

As specified in Table 2-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:

i. Array/Classes 14x14D, 14x14E, and 15x15G Cooling time 8 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes As specified in Section 2.2.

iii. NON-FUEL HARDWARE As specified in Table 2-4. 3 to Holtec Letter 5014917 44 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-25 Table 2-1 (page 20 of 30)

Fuel Assembly Limits IV. MPC MODEL: MPC-24E and MPC-24EF (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G 710 Watts.

ii. All Other Array/Classes As specified in Section 2.2.

e. Fuel Assembly Length 176.8 inches (nominal design)

f. Fuel Assembly Width 8.54 inches (nominal design)

g. Fuel Assembly Weight 1,720 lbs (including NON-FUEL HARDWARE and DFC) for assemblies that do not require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE and DFC)

B. Quantity per MPC: Up to four (4) DAMAGED FUEL ASSEMBLIES and/or FUEL DEBRIS in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 3, 6, 19 and/or 22.

The remaining fuel storage locations may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.

C. One NSA is permitted for loading.

Note 1:

Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing APSRs or NSAs may only be loaded in fuel storage locations 9, 10, 15, and/or 16 (see Figure 2-2). Fuel assemblies containing CRAs, RCCAs, or CEAs may only be stored in fuel storage locations 4, 5, 8 - 11, 14 - 17, 20 and/or 21 (see Figure 2-2). These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading. 3 to Holtec Letter 5014917 45 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-26 Table 2-1 (page 21 of 30)

Fuel Assembly Limits V. MPC MODEL: MPC-32 and MPC-32F A. Allowable Contents

1.

Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):

a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2-2 for the applicable fuel assembly array/class

b. Initial Enrichment:

As specified in Table 2-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:

i. Array/Classes 14x14D, 14x14E, and 15x15G Cooling time 9 years and an average burnup 30,000 MWD/MTU or cooling time 20 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes As specified in Section 2.2.

iii. NON-FUEL HARDWARE As specified in Table 2-4. 3 to Holtec Letter 5014917 46 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-27 Table 2-1 (page 22 of 30)

Fuel Assembly Limits V. MPC MODEL: MPC-32 and MPC-32F (contd)

A. Allowable Contents (contd)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G 500 Watts.

ii. All Other Array/Classes As specified in Section 2.2.

e. Fuel Assembly Length 176.8 inches (nominal design)

f. Fuel Assembly Width 8.54 inches (nominal design)

g. Fuel Assembly Weight 1,720 lbs (including NON-FUEL HARDWARE) for assemblies that do not require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE) 3 to Holtec Letter 5014917 47 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-28 Table 2-1 (page 23 of 30)

Fuel Assembly Limits V. MPC MODEL: MPC-32 and MPC-32F (contd)

A. Allowable Contents (contd)

2.

Uranium oxide, PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS, with or without NON-FUEL HARDWARE, placed in DAMAGED FUEL CONTAINERS.

Uranium oxide PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2-2 and meet the following specifications (Note 1):

a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2-2 for the applicable fuel assembly array/class

b. Initial Enrichment:

As specified in Table 2-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:

i. Array/Classes 14x14D, 14x14E, and 15x15G Cooling time 9 years and an average burnup 30,000 MWD/MTU or cooling time 20 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes As specified in Section 2.2.

iii. NON-FUEL HARDWARE As specified in Table 2-4. 3 to Holtec Letter 5014917 48 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-29 Table 2-1 (page 24 of 30)

Fuel Assembly Limits V. MPC MODEL: MPC-32 and MPC-32F (contd)

A. Allowable Contents (contd)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G 500 Watts.

ii. All Other Array/Classes As specified in Section 2.2.

e. Fuel Assembly Length 176.8 inches (nominal design)

f. Fuel Assembly Width 8.54 inches (nominal design)

g. Fuel Assembly Weight 1,720 lbs (including NON-FUEL HARDWARE and DFC) for assemblies that do not require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE and DFC)

B.

Quantity per MPC: Up to eight (8) DAMAGED FUEL ASSEMBLIES and/or FUEL DEBRIS in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 1, 4, 5, 10, 23, 28, 29, and/or 32. The remaining fuel storage locations may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.

C.

One NSA is permitted for loading.

Note 1:

Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing NSAs may only be loaded in fuel storage locations 13, 14, 19 and/or 20 (see Figure 2-3). Fuel assemblies containing CRAs, RCCAs, CEAs or APSRs may only be loaded in fuel storage locations 7, 8, 12-15, 18-21, 25 and/or 26 (see Figure 2-3). These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading. 3 to Holtec Letter 5014917 49 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-30 Table 2-1 (page 25 of 30)

Fuel Assembly Limits VI. MPC MODEL: MPC-68M A. Allowable Contents

1. Uranium oxide BWR UNDAMAGED FUEL ASSEMBLIES listed in Table 2-3, with or without channels and meeting the following specifications:

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment As specified in Table 2-3 for the applicable fuel assembly array/class.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly

i. Array/Class 8x8F Cooling time 10 years and an average burnup 27,500 MWD/MTU.

ii. All Other Array/Classes As specified in Section 2.2. 3 to Holtec Letter 5014917 50 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-31 Table 2-1 (page 26 of 30)

Fuel Assembly Limits VI. MPC MODEL: MPC-68M (continued)

A. Allowable Contents (continued)

e. Decay Heat Per Assembly

i. Array/Class 8x8F 183.5 Watts ii. All Other Array/Classes As specified in Section 2.2.

f. Fuel Assembly Length 176.5 inches (nominal design)

g. Fuel Assembly Width 5.85 inches (nominal design)

h. Fuel Assembly Weight 730 lbs, including channels 3 to Holtec Letter 5014917 51 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-32 Table 2-1 (page 27 of 30)

Fuel Assembly Limits VI. MPC MODEL: MPC-68M (continued)

A. Allowable Contents (continued)

2.

Uranium oxide BWR DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, with or without channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES whose damage is limited such that the fuel assembly is able to be handled by normal means and whose structural integrity remains intact to the extent that geometric rearrangement of fuel is not expected, with or without channels, placed in basket cell locations containing top and bottom DAMAGED FUEL ISOLATORS. BWR DAMAGED FUEL ASSEMBLIES used with DFIs may contain missing or partial fuel rods and/or fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2-3, and meet the following specifications:

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment As specified in Table 2-3 for the applicable fuel assembly array/class.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly:

i. Array/Class 8x8F Cooling time 10 years and an average burnup 27,500 MWD/MTU.

ii. All Other Array/Classes Cooling time 1 year and an average burnup 65,000 MWD/MTU. 3 to Holtec Letter 5014917 52 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-33 Table 2-1 (page 28 of 30)

Fuel Assembly Limits VI. MPC MODEL: MPC-68M (continued)

A. Allowable Contents (continued)

e. Decay Heat Per Assembly

i. Array/Class 8x8F 183.5 Watts ii. All Other Array/Classes As specified in Section 2.2.

f. Fuel Assembly Length 176.5 inches (nominal design)

g. Fuel Assembly Width 5.85 inches (nominal design)

h. Fuel Assembly Weight 830 lbs, including channels and DFC/DFIs 3 to Holtec Letter 5014917 53 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-34 Table 2-1 (page 29 of 30)

Fuel Assembly Limits VI. MPC MODEL: MPC-68M (continued)

A. Allowable Contents (continued)

3.

Thoria rods (ThO2 and UO2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

ZR

b. Composition 98.2 wt.% ThO2, 1.8 wt.% UO2 with an enrichment of 93.5 wt.%

235 U

OR 98.5 wt.% ThO2, 1.5 wt.% UO2 with an enrichment of 93.5% wt.%

235 U

c. Number of Rods per Thoria Rod Canister:

18

d. Decay Heat Per Thoria Rod Canister:

115 Watts

e. Post-irradiation Fuel Cooling Time and Average Burnup per Thoria Rod Canister:

A fuel post-irradiation cooling time 18 years and an average burnup 16,000 MWD/MTIHM

f. Initial Heavy Metal Weight:

27 kg/canister

g. Fuel Cladding O.D.:

0.412 inches

h. Fuel Cladding I.D.:

0.362 inches

i. Fuel Pellet O.D.:

0.358 inches

j. Active Fuel Length:

111 inches

k. Canister Weight:

550 lbs, including fuel 3 to Holtec Letter 5014917 54 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-35 Table 2-1 (page 30 of 30)

Fuel Assembly Limits VI. MPC MODEL: MPC-68M (continued)

B. Quantity per MPC (up to a total of 68 assemblies)

1. Up to sixteen (16) DFCs or DFIs containing BWR DAMAGED FUEL ASSEMBLIES and/or up to eight (8) DFCs containing FUEL DEBRIS. DFCs/DFIs shall be located only in fuel storage locations 1, 2, 3, 8, 9, 16, 25, 34, 35, 44, 53, 60, 61, 66, 67, and/or 68. Alternatively BWR DAMAGED FUEL ASSEMBLIES using DFCs/DFIs may be stored in inner locations when using the loading pattern in Figure 2-4. The remaining fuel storage locations may be filled with Uranium Oxide BWR UNDAMAGED FUEL ASSEMBLIES.

2. Up to one (1) Dresden Unit 1 Thoria Rod Canister.

3 to Holtec Letter 5014917 55 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-36 Table 2-2 (page 1 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Table 2-2: PWR Fuel Assembly Characteristics Fuel Assembly Array/Class 14x14A 14x14B 14x14C 14x14D 14x14E Clad Material ZR ZR ZR SS SS Design Initial U

(kg/assy.) (Note 3) 365 412 438 400 206 Initial Enrichment (MPC-24, 24E and 24EF without soluble boron credit) (wt %

235U)

(Note 7) 4.6 (24) 5.0 (24E/24EF) 4.6 (24) 5.0 (24E/24EF) 4.6 (24) 5.0 (24E/24EF) 4.0 (24) 5.0 (24E/24EF) 5.0 (24) 5.0 (24E/24EF)

Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F with soluble boron credit -

see Note

5)

(wt % 235U) 5.0 5.0 5.0 5.0 5.0 No.

of Fuel Rod Locations (Note 11) 179 179 176 180 173 Fuel Rod Clad O.D.

(in.)

0.400 0.417 0.440 0.422 0.3415 Fuel Rod Clad I.D.

(in.)

0.3514 0.3734 0.3880 0.3890 0.3175 Fuel Pellet Dia.

(in.)(Note 8) 0.3444 0.3659 0.3805 0.3835 0.3130 Fuel Rod Pitch (in.)

0.556 0.556 0.580 0.556 Note 6 Active Fuel Length (in.)

150 150 150 144 102 No. of Guide and/or Instrument Tubes 17 17 5 (Note 4) 16 0

Guide/Instrument Tube Thickness (in.)

0.017 0.017 0.038 0.0145 N/A 3 to Holtec Letter 5014917 56 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-37 Table 2-2 (page 2 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 15x15A 15x15B 15x15C 15x15D 15x15E 15x15F Clad Material ZR ZR ZR ZR ZR ZR Design Initial U

(kg/assy.) (Note 3)

< 473

< 495

< 495 Initial Enrichment (MPC-24, 24E and 24EF without soluble boron credit)

(wt 235U)

(Note 7)

< 4.1 (24)

< 4.5 (24E/24EF)

< 4.1 (24)

< 4.5 (24E/24EF)

< 4.1 (24)

< 4.5 (24E/24EF)

< 4.1 (24)

< 4.5 (24E/24EF)

< 4.1 (24)

< 4.5 (24E/24EF)

< 4.1 (24)

< 4.5 (24E/24EF)

Initial Enrichment (MPC-24,

24E, 24EF, 32, or 32F with soluble boron credit - see Note 5)(wt % 235U)

< 5.0

< 5.0 No. of Fuel Rod Locations (Note 11) 204 204 204 208 208 208 Fuel Rod Clad O.D. (in.)

> 0.418

> 0.420

> 0.417

> 0.430

> 0.428

> 0.428 Fuel Rod Clad I.D.

(in.)

< 0.3660

< 0.3736

< 0.3640

< 0.3800

< 0.3790

< 0.3820 Fuel Pellet Dia.

(in.) (Note 8)

< 0.3580

< 0.3671

< 0.3570

< 0.3735

< 0.3707

< 0.3742 Fuel Rod Pitch (in.)

< 0.550

< 0.563

< 0.568

< 0.568 Active Fuel Length (in.)

< 150

< 150 No.

of Guide and/or Instrument Tubes 21 21 21 17 17 17 Guide/Instrument Tube Thickness (in.)

> 0.0165

> 0.015

> 0.0165

> 0.0150

> 0.0140

> 0.0140 3 to Holtec Letter 5014917 57 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-38 Table 2-2 (page 3 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/ Class 15x15G 15x15H 15x15I 16x16A 16x16B 16x16C Clad Material SS ZR ZR ZR ZR ZR Design Initial U (kg/assy.)(Note 3)

< 420

< 495 495

< 448

< 448 Initial Enrichment (MPC-24,

24E, and 24EF without soluble boron credit)(wt % 235U)

(Note 7)

< 4.0 (24)

< 4.5 (24E/24 EF)

< 3.8 (24)

< 4.2 (24E/24E F)

N/A (Note 9)

< 4.6 (24)

< 5.0 (24E/24E F)

< 4.6 (24)

< 5.0 (24E/24E F)

< 4.6 (24)

< 5.0 (24E/24E F)

Initial Enrichment (MPC-24,

24E, 24EF, 32, or 32F with soluble boron credit - see Note

5) (wt % 235U)

< 5.0

< 5.0 5.0 (Note 9)

< 5.0

< 5.0 No. of Fuel Rod Locations (Note 11) 204 208 216 236 236 235 Fuel Rod Clad O.D. (in.)

> 0.422

> 0.414 0.413

> 0.382

> 0.374

> 0.374 Fuel Rod Clad I.D. (in.)

0.3890

< 0.3700 0.367

< 0.3350

< 0.3290

< 0.3290 Fuel Pellet Dia.

(in.) (Note 8) 0.3825

< 0.3622 0.360

< 0.3255

< 0.3225

< 0.3225 Fuel Rod Pitch (in.)

< 0.563

< 0.568 0.550

< 0.506

< 0.485 Active Fuel Length (in.)

< 144

< 150 150

< 150

< 150 No.

of Guide and/or Instrument Tubes 21 17 9

(Note 10) 5 (Note 4) 5 (Note 4) 21 Guide/Instrument Tube Thickness (in.)

0.0145

> 0.0140 0.0140

> 0.0350

> 0.0400

> 0.0157 3 to Holtec Letter 5014917 58 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-39 Table 2-2 (page 4 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/ Class 17x17A 17x17B 17x17C Clad Material ZR ZR ZR Design Initial U (kg/assy.)(Note

3)

< 433

< 474

< 480 Initial Enrichment (MPC-24, 24E, and 24EF without soluble boron credit)(wt % 235U) (Note

7)

< 4.0 (24)

< 4.4 (24E/24EF)

< 4.0 (24)

< 4.4 (24E/24EF)

< 4.0 (24)

< 4.4 (24E/24EF)

Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F with soluble boron credit - see Note

5) (wt % 235U)

< 5.0

< 5.0 No. of Fuel Rod Locations (Note 11) 264 264 264 Fuel Rod Clad O.D. (in.)

> 0.360

> 0.372

> 0.377 Fuel Rod Clad I.D. (in.)

< 0.3150

< 0.3310

< 0.3330 Fuel Pellet Dia. (in.) (Note 8)

< 0.3088

< 0.3232

< 0.3252 Fuel Rod Pitch (in.)

< 0.496

< 0.502 Active Fuel Length (in.)

< 150

< 150 No. of Guide and/or Instrument Tubes 25 25 25 Guide/Instrument Tube Thickness (in.)

> 0.016

> 0.014

> 0.020 3 to Holtec Letter 5014917 59 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-40 Table 2-2 (page 5 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS Notes:

1.

All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.

2.

Deleted.

3.

Design initial uranium weight is the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each PWR fuel assembly, the total uranium weight limit specified in this table may be increased up to 2.0 percent for comparison with users fuel records.

4.

Each guide tube replaces four fuel rods.

5.

Soluble boron concentration per LCO 3.3.1.

6.

This fuel assembly array/class includes only the Indian Point Unit 1 fuel assembly. This fuel assembly has two pitches in different sectors of the assembly. These pitches are 0.441 inches and 0.453 inches.

7.

For those MPCs loaded with both INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, the maximum initial enrichment of the INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS is 4.0 wt.% 235U.

8.

Annular fuel pellets are allowed in the top and bottom 12" of the active fuel length.

9.

This fuel assembly array/class can only be loaded in MPC-32.

10. One Instrument Tube and eight Guide Bars (Solid ZR).

11. Any number of fuel rods in an assembly can be replaced by irradiated or unirradiated Steel or Zirconia rods. If the rods are irradiated, the site specific dose and dose rate analyses performed under 10 CFR 72.212 should include considerations for the presence of such rods.

3 to Holtec Letter 5014917 60 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-41 Table 2-3 (page 1 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Table 2-3: BWR Fuel Assembly Characteristics Fuel Assembly Array/Class 6x6A 6x6B 6x6C 7x7A 7x7B 8x8A Clad Material ZR ZR ZR ZR ZR ZR Design Initial U

(kg/assy.) (Note 3)

< 110

< 100

< 198

< 120 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68, 68F, and 68FF)

(wt.%

235U)

(Note 14)

< 2.7

< 2.7 for the UO2 rods.

See Note 4 for MOX rods

< 2.7

< 4.2

< 2.7 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68M)

(wt.%

235U)

(Note 16, 19)

Note 18 Note 18 Note 18 Note 18 4.8 Note 18 Initial Maximum Rod Enrichment (wt.%

235U)

< 4.0

< 5.5

< 5.0

< 4.0 No. of Fuel Rod Locations (Note 20) 35 or 36 35 or 36 (up to 9 MOX rods) 36 49 49 63 or 64 Fuel Rod Clad O.D.

(in.)

> 0.5550

> 0.5625

> 0.5630

> 0.4860

> 0.5630

> 0.4120 Fuel Rod Clad I.D.

(in.)

< 0.5105

< 0.4945

< 0.4990

< 0.4204

< 0.4990

< 0.3620 Fuel Pellet Dia. (in.)

< 0.4980

< 0.4820

< 0.4880

< 0.4110

< 0.4910

< 0.3580 Fuel Rod Pitch (in.)

< 0.710

< 0.740

< 0.631

< 0.738

< 0.523 Active Fuel Length (in.)

< 120

< 77.5

< 80

< 150

< 120 No. of Water Rods (Note 11) 1 or 0 1 or 0 0

0 0

1 or 0 Water Rod Thickness (in.)

> 0

> 0 N/A N/A N/A

> 0 Channel Thickness (in.)

< 0.060

< 0.120

< 0.100 3 to Holtec Letter 5014917 61 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-42 Table 2-3 (2 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 8x8B 8x8C 8x8D 8x8E 8x8F 9x9A Clad Material ZR ZR ZR ZR ZR ZR Design Initial U

(kg/assy.) (Note 3)

< 192

< 190

< 191

< 180 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68, 68F, and 68FF)

(wt.%

235U)

(Note 14)

< 4.2

< 4.0

< 4.2 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68M)

(wt.%

235U)

(Note 16, 19) 4.8 4.8 4.8 4.8 4.5 (Note 15) 4.8 Initial Maximum Rod Enrichment (wt.%

235U)

< 5.0

< 5.0 No. of Fuel Rod Locations (Note 20) 63 or 64 62 60 or 61 59 64 74/66 (Note 5)

Fuel Rod Clad O.D.

(in.)

> 0.4840

> 0.4830

> 0.4930

> 0.4576

> 0.4400 Fuel Rod Clad I.D.

(in.)

< 0.4295

< 0.4250

< 0.4230

< 0.4250

< 0.3996

< 0.3840 Fuel Pellet Dia. (in.)

< 0.4195

< 0.4160

< 0.4140

< 0.4160

< 0.3913

< 0.3760 Fuel Rod Pitch (in.)

< 0.642

< 0.641

< 0.640

< 0.609

< 0.566 Design Active Fuel Length (in.)

< 150

< 150 No. of Water Rods (Note 11) 1 or 0 2

1 - 4 (Note 7) 5 N/A (Note 12) 2 Water Rod Thickness (in.)

> 0.034

> 0.00

> 0.034

> 0.0315

> 0.00 Channel Thickness (in.)

< 0.120

< 0.100

< 0.055

< 0.120 3 to Holtec Letter 5014917 62 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-43 Table 2-3 (page 3 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 9x9B 9x9C 9x9D 9x9E (Note 13) 9x9F (Note 13) 9x9G Clad Material ZR ZR ZR ZR ZR ZR Design Initial U

(kg/assy.)(Note 3)

< 180

< 182

< 183

< 164 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68, 68F, and 68FF)

(wt.%

235U)

(Note 14)

< 4.2

< 4.0

< 4.2 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68M)

(wt.%

235U)

(Note 16, 19) 4.8 4.8 4.8 4.5 (Note 15) 4.5 (Note 15) 4.8 Initial Maximum Rod Enrichment (wt.%

235U)

< 5.0

< 5.0 No. of Fuel Rod Locations (Note 20) 72 80 79 76 76 72 Fuel Rod Clad O.D.

(in.)

> 0.4330

> 0.4230

> 0.4240

> 0.4170

> 0.4430

> 0.4240 Fuel Rod Clad I.D.

(in.)

< 0.3810

< 0.3640

< 0.3860

< 0.3640 Fuel Pellet Dia. (in.)

< 0.3740

< 0.3565

< 0.3530

< 0.3745

< 0.3565 Fuel Rod Pitch (in.)

< 0.572

< 0.572 Design Active Fuel Length (in.)

< 150

< 150 No. of Water Rods (Note 11) 1 (Note 6) 1 2

5 5

1 (Note 6)

Water Rod Thickness (in.)

> 0.00

> 0.020

> 0.0300

> 0.0120

> 0.0320 Channel Thickness (in.)

< 0.120

< 0.100

< 0.120

< 0.120 3 to Holtec Letter 5014917 63 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-44 Table 2-3 (page 4 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 10x10A 10x10B 10x10C 10x10D 10x10E 10x10F 10x10G Clad Material ZR ZR ZR SS SS ZR ZR Design Initial U

(kg/assy.)

(Note 3)

< 188

< 179

< 125

< 125 192 188 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT(MPC-68, 68F, and 68FF)

(wt.% 235U) (Note 14)

< 4.2

< 4.0

< 4.0 Note 17 Note 17 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68M)

(wt.%

235U)

(Note 16, 19) 4.8 4.8 4.8 Note 18 Note 18 4.7 (Note 15) 5.0 (Note 26) 4.75 (Note 21) 5.0 (Note 26)

Initial Maximum Rod Enrichment (wt.% 235U)

< 5.0

< 5.0 No.

of Fuel Rod Locations (Note 20) 92/78 (Note 8) 91/83 (Note 9) 96 100 96 92/78 (Note 8) 96/84 Fuel Rod Clad O.D.

(in.)

0.4040 0.3957

> 0.3780 0.3960 0.3940 0.4035 0.387 Fuel Rod Clad I.D. (in.)

0.3520 0.3480

< 0.3294 0.3560 0.3500 0.3570 0.340 Fuel Pellet Dia. (in.)

0.3455 0.3420

< 0.3224 0.3500 0.3430 0.3500 0.334 Fuel Rod Pitch (in.)

< 0.510

< 0.488

< 0.565

< 0.557 0.510 0.512 Design Active Fuel Length (in.)

< 150

< 83

< 83 150 150 No. of Water Rods (Note 11) 2 1

(Note 6) 5 (Note 10) 0 4

2 5

(Note 10)

Water Rod Thickness (in.)

> 0.030

> 0.00

> 0.031 N/A

> 0.022 0.030 0.031 Channel Thickness (in.)

< 0.120

< 0.055

< 0.080

< 0.080 0.120 0.060 3 to Holtec Letter 5014917 64 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-45 Table 2-3 (page 5 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array and Class 10x10I (Note 17, 22) 10x10J (Note 17, 23) 11x11A (Note 17, 24)

Clad Material Zr Zr Zr Design Initial U (kg/assy.)

(Note 3) 194 194 194 Maximum Planar-Average Initial Enrichment (wt.% 235U)

(Note 16, 19) 4.8 4.8 4.8 Maximum Planar-Average Initial Enrichment with Partial Gadolinium Credit (wt.%235U)

(Note 26) 5.0 5.0 5.0 Initial Rod Maximum Enrichment (wt.% 235U) 5.0 5.0 5.0 No. of Fuel Rod Locations (Note

20) 91/79 96/80 112/92 Fuel Clad O.D. (in.)

> 0.4047

>0.3999

>0.3701 Fuel Clad I.D. (in.)

< 0.3559

< 0.3603

< 0.3252 Fuel Pellet Dia. (in.)

< 0.3492 0.3531

< 0.3193 Fuel Rod Pitch (in.)

< 0.5100 0.5149

< 0.4705 Design Active Fuel Length (in.)

< 150

< 150 No. of Water Rods (Note 25) 1 1

1 Water Rod Thickness (in.)

> 0.0315

> 0.0297

> 0.0340 Channel Thickness (in.)

< 0.100 0.0938

< 0.100 Notes:

1.

All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.

2.

Deleted.

3.

Design initial uranium weight is the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each BWR fuel assembly, the total uranium weight limit specified in this table may be increased up to 1.5 percent for comparison with users fuel records.

4.

0.635 wt. % 235U and 1.578 wt. % total fissile plutonium (239Pu and 241Pu), (wt. % of total fuel weight, i.e., UO2 plus PuO2).

5.

This assembly class contains 74 total rods; 66 full length rods and 8 partial length rods.

6.

Square, replacing nine fuel rods.

7.

Variable. 3 to Holtec Letter 5014917 65 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-46

8.

This assembly contains 92 total fuel rods; 78 full length rods and 14 partial length rods.

9.

This assembly class contains 91 total fuel rods; 83 full length rods and 8 partial length rods.

10.

One diamond-shaped water rod replacing the four center fuel rods and four rectangular water rods dividing the assembly into four quadrants.

11.

These rods may also be sealed at both ends and contain Zr material in lieu of water.

12.

This assembly is known as QUAD+. It has four rectangular water cross segments dividing the assembly into four quadrants.

13.

For the SPC 9x9-5 fuel assembly, each fuel rod must meet either the 9x9E or the 9x9F set of limits for clad O.D., clad I.D., and pellet diameter.

14.

For MPC-68, 68F, and 68FF loaded with both INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, the maximum PLANAR AVERAGE INITIAL ENRICHMENT for the INTACT FUEL ASSEMBLIES is limited to 3.7 wt.% 235U, as applicable.

15.

Fuel assemblies classified as damaged fuel assemblies are limited to 4.6 wt.% 235U for the 10x10F arrays/classes. Fuel assemblies classified as damaged fuel assemblies are limited to 4.0 wt.% 235U for the 8x8F, 9x9E and 9x9F arrays/classes except when loaded to Figure 2-4. Fuel assemblies classified as damaged fuel assemblies are limited to 4.5 wt.% 235U for the 8x8F, 9x9E and 9x9F when loaded to Figure 2-4.

16.

For MPC-68M loaded with both UNDAMAGED FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, the maximum PLANAR AVERAGE INITIAL ENRICHMENT for the UNDAMAGED FUEL ASSEMBLIES is limited to the enrichment limit of the damaged assembly.

17.

This fuel assembly array/class is not allowable contents in MPC-68, 68F, or 68FF.

18.

This fuel assembly array/class is not allowable contents in MPC-68M.

19.

In accordance with the definition of UNDAMAGED FUEL ASSEMBLY, certain assemblies may be limited to up to 3.3 wt.% U-235. When loading these fuel assemblies, all other undamaged fuel assemblies in the MPC are limited to enrichments as specified in this table.

20.

Any number of fuel rods in an assembly can be replaced by irradiated or unirradiated Steel or Zirconia rods. If the rods are irradiated, the site specific dose and dose rate analyses performed under 10 CFR 72.212 should include considerations for the presence of such rods.

21.

Fuel assemblies classified as damaged fuel assemblies are limited to 4.6 wt.% 235U for the 10x10G array/class escept when loaded to Figure 2-4. Fuel assemblies classified as damaged fuel assemblies are limited to 4.5 wt.% 235U for the 10x10G array/class when loaded to Figure 2-4.

22.

Contains in total 91 fuel rods; 79 full length rods, 12 partial length rods, and one square water rod, replacing 9 fuel rods.

23.

Contains in total 96 fuel rods; 80 full length rods, 8 long partial length rods, 8 short partial length rods and one water rod replacing 4 fuel rods.

24.

Contains in total 112 fuel rods; 92 full length rods, 8 long partial length rods, 12 short partial length rods, and one square water rod replacing 9 fuel rods.

25.

These rods may also be sealed at both ends and contain Zr material in lieu of water.

26.

The restrictions in Table 2-5 apply.

3 to Holtec Letter 5014917 66 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-47 Table 2-4 NON-FUEL HARDWARE COOLING AND AVERAGE BURNUP (Notes 1, 2, 3, and 7)

Table 2-4: Non-Fuel Hardware Cooling and Average Burnup Notes: 1. Burnups for NON-FUEL HARDWARE are to be determined based on the burnup and uranium mass of the fuel assemblies in which the component was inserted during reactor operation.

2. Linear interpolation between points is permitted, except that APSR burnups > 180,000 MWD/MTU and < 630,000 MWD/MTU must be cooled > 11 years.

3. Applicable to uniform loading and regionalized loading.

4. Includes Burnable Poison Rod Assemblies (BPRAs), Wet Annular Burnable Absorbers (WABAs), vibration suppressor inserts and Neutron Source Assemblies (NSAs) in combination with other control components (i.e. BPRAs, TPDs, and/or RCCAs).

5. Includes Thimble Plug Devices (TPDs), water displacement guide tube plugs, orifice rod assemblies, Control Rod Assemblies (CRAs), Control Element Assemblies (CEAs), Rod Cluster Control Assemblies (RCCAs) and NSAs without other forms of control components.

6. NA means not authorized for loading at this cooling time.

7. Non-fuel hardware burnup and cooling times are not applicable to ITTRs since they are installed post irradiation.

Post-irradiation Cooling Time (years)

NSA with NFH INSERTS (Note 4)

BURNUP (MWD/MTU)

NSA without NFH, GUIDE TUBE HARDWARE, or CONTROL COMPONENT (Note 5)

BURNUP (MWD/MTU)

APSR BURNUP (MWD/MTU) 3 24,635 NA (Note 6)

NA 4

30,000 NA NA 5

36,748 630,000 45,000 6

44,102 54,500 7

52,900 68,000 8

60,000 83,000 9

79,784 111,000 10 101,826 180,000 11 141,982 630,000 12 360,000

- 3 to Holtec Letter 5014917 67 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-48 Table 2-5 RESTRICTIONS FOR PARTIAL GADOLINIUM CREDIT IN MPC-68M Table 2-5: Restrictions for Partial Gadolinium Credit in MPC-68M FUEL ASSEMBLY ARRAY AND CLASS RESTRICTION All 10x10 and 11x11 The gadolinium rod loading is not less than 3.0 wt%

Gd2O3 All 10x10 and 11x11 The gadolinium rods located in the peripheral row of the fuel lattice cannot be credited All 10x10 and 11x11 Gadolinium rods are NOT required to be present in damaged fuel in DFIs or damaged fuel/fuel debris in DFCs 10x10A, 10x10B, 10x10F, 10x10I, 10x10J, and 11x11A At least one gadolinium rod must be present.

10x10C and 10x10G At least two gadolinium rods must be present 2.2 Decay Heat Limits for ZR-Clad Fuel This section provides the limits on ZR-clad fuel assembly decay heat, burnup, and cooling time for storage in the HI-STORM 100 System. The method to calculate the limits and verify compliance, including examples, is provided in Chapter 12 of the HI-STORM 100 FSAR.

2.2.1 Uniform Fuel Loading Decay Heat Limits for ZR-clad Fuel for VENTILATED OVERPACK Table 2-6 provides the maximum allowable decay heat per fuel storage location for ZR-clad fuel in uniform fuel loading for each MPC model.

3 to Holtec Letter 5014917 68 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-49 Table 2-6: Maximum Allowable Decay Heat per Fuel Storage Location (Uniform Loading, ZR-Clad)

MPC Model Decay Heat per Fuel Storage Location (kW)

Intact or Undamaged Fuel Assemblies Damaged Fuel Assemblies and Fuel Debris MPC-24

< 1.416 Not Permitted MPC-24E/24EF

< 1.416

< 1.114 MPC-32/32F

< 1.062

< 0.718 MPC-68/68FF/68M

< 0.500

< 0.393 2.2.2 Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel for VENTILATED OVERPACK The maximum allowable decay heat per fuel storage location for intact or undamaged fuel assemblies in regionalized loading is determined using the following equations:

Q(X) = 2 x Q0 / (1 + Xy) y = 0.23 / X0.1 q2 = Q(X) / (n1 x X +n2) q1 = q2 x X Where:

Q0 = Maximum uniform storage MPC decay heat (34 kW)

X = Inner region to outer region assembly decay heat ratio (0.5 X 3) n1 = Number of storage locations in inner region from Table 2-7.

n2 = Number of storage locations in outer region from Table 2-7.

Allowable heat loads for Damaged Fuel and Fuel Debris in regionalized loading are shown in Table 2-8.

Optional loading patterns for MPC-68M are shown in Figures 2-5 through 2-8.

3 to Holtec Letter 5014917 69 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-50 Table 2-7: Fuel Storage Regions per MPC MPC Model Number of Storage Locations in Inner Region (Region 1)

Number of Storage Locations in Outer Region (Region 2)

MPC-24 and MPC-24E/EF 12 12 MPC-32/32F 12 20 MPC-68/68FF/68MNote1 32 36 Note 1: For an optional regionalized loading pattern for MPC-68M, see Figures 2-5 through 2-

8.

Table 2-8: Allowable Heat Load for Damaged Fuel Assemblies and Fuel Debris under Regionalized Loading MPC Model Maximum Per Cell Allowable Heat Load for Damaged Fuel Assemblies and Fuel Debris in DFCs Note 1,3 MPC-24E/24EF 0.75*q2 MPC-32/32F 0.65*q2 MPC-68/68FF/68MNote 2 0.75*q2 Note 1: q2 is the maximum permissible heat load in Region 2 for intact fuel assemblies.

Note 2: Optional QSHL loading patterns for MPC-68M including Damaged Fuel and Fuel Debris are shown in Figures 2-5 through 2-8.

Note 3: Damaged fuel stored with DFIs can be stored up to q2 limits.

2.2.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel for VENTILATED OVERPACK The maximum allowable ZR-clad fuel assembly average burnup varies with the minimum required fuel assembly cooling time. Tables 2-9 and 2-10 provide for each MPC the allowable maximum burnup based on the assemblys particular cooling time. 3 to Holtec Letter 5014917 70 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-51 2.2.3.1 Linear interpolation of burnups between cooling times is permitted. For example, the allowable burnup for a cooling time of 4.5 years may be interpolated between those burnups calculated for 4 year and 5 years.

2.2.3.2 Calculated burnup limits shall be rounded down to the nearest integer.

2.2.3.3 Calculated burnup limits greater than 68,200 MWD/MTU for PWR fuel and 65,000 MWD/MTU for BWR must be reduced to be equal to these values.

2.2.4 Compliance with Maximum Fuel Storage Location Decay Heat Limits When complying with the maximum fuel storage location decay heat limits, users must account for the decay heat from both the fuel assembly and any NON-FUEL HARDWARE, as applicable for the particular fuel storage location, to ensure the decay heat emitted by all contents in a storage location does not exceed the limit.

2.2.5 Fuel Loading Decay Heat Limits for UNVENTILATED OVERPACK Tables 2-11 and 2-12 provide the maximum allowable decay heat per fuel storage location for MPC-68M in an UNVENTILATED OVERPACK.

A minor deviation from the prescribed loading pattern in an MPCs permissible contents to allow one slightly thermally-discrepant fuel assembly per quadrant to be loaded as long as the peak cladding temperature for the MPC remains below the ISG-11 Rev 3 requirements is permitted for essential dry storage campaigns to support decommissioning.

2.2.6 Burnup and Cooling Time Qualifications for the MPC-68M for UNVENTILATED OVERPACK The burnup and cooling time for every fuel loaded into the MPC-68M must satisfy the following equation:

= 3 + 2 + +

where, Ct

= Minimum cooling time (years),

Bu

= Assembly-average burnup (MWd/mtU),

A, B, C, D = Polynomial coefficients listed in Table 2-15 3 to Holtec Letter 5014917 71 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-52 Table 2-9: PWR Fuel Assembly Burnup and Cooling Time Limits for VENTILATED OVERPACK (ZR-Clad Fuel)

Minimum Cooling Time (years)

Maximum Allowable Burnup, MWd/mtU MPC-24/24E/24EF 1.0 5,000 1.4 15,000 1.8 25,000 2.0 35,000 2.2 40,000 2.4 45,000 2.6 50,000 2.8 55,000 3.0 60,000 4.0 69,000 5.0 75,000 MPC-32/32F 1.0 5,000 1.4 10,000 1.8 20,000 2.0 25,000 2.2 30,000 2.4 35,000 2.6 40,000 3.0 45,000 4.0 60,000 5.0 69,000 3 to Holtec Letter 5014917 72 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-53 Table 2-10: BWR Fuel Assembly Burnup and Cooling Time Limits for VENTILATED OVERPACK (ZR-Clad Fuel)

Minimum Cooling Time (years)

Maximum Allowable Burnup, MWd/mtU MPC-68/68FF/68M 1.0 10,000 1.2 15,000 1.4 20,000 2.0 25,000 2.2 30,000 2.4 35,000 2.6 40,000 3.0 50,000 4.0 62,000 5.0 65,000 6.0 70,000 Table 2-11: MPC-68M Heat Load Data for UNVENTILATED OVERPACK Number of Regions: 2 Number of Storage Cells:

68 Maximum Total Heat Load (kW):

25 Maximum Section Heat Load (kW): 3.125 (Note 1)

Region No.

Decay Heat Limit per Cell, kW Number of Cells per Region Decay Heat Limit per Region, kW 1 (Inner) 0.368 32 11.765 2 (Outer) 0.368 36 13.325 Note 1: Figure 2-4 identifies the MPC basket regions and cell locations, and Table 2-13 identifies the cells included in each Heat Load for each section.

3 to Holtec Letter 5014917 73 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-54 Table 2-12: MPC-68M Requirements on Developing Regionalized Heat Load Patterns for UNVENTILATED OVERPACK (See Figure 2-4)

1. Total MPC aggregate Heat Load must be equal to 25 kW

2. Maximum Section Heat Load must be equal to 3.125 kW, calculated per Table 2-13, and pattern must be 1/8th symmetric

3. Maximum Heat Load per Cell in Region 1 is 0.368 kW

4. Maximum Heat Load per Cell in Region 2 is 0.735 kW

5. Pattern-specific Decay Heat in a storage cell may need to be adjusted to meet items 1 and 2

6. Pattern-specific Heat Load for storage cells may be determined by reducing the allowable heat load in any Region 1 cell in Table 2-11 by a certain amount () and adding the same to a single cell or distributed amongst multiple cells in Region 2.

i.e. Any reduction of total allowable heat load in Region 1 must be compensated by an equivalent addition in Region 2.

General Notes -

1. Any assembly with a Heat Load less than the limits defined above can be loaded in the applicable cell, provided it meets all other CoC requirements.

2. DFCs/DFIs are permitted in locations denoted in Table 2-14 with the applicable Heat Load penalties identified therein.

Table 2-13: Section Heat Load Calculations for MPC=68M for UNVENTILATED OVERPACK Section Equation for Section Heat Load1 Section 1 Q21 + Q13 + Q14 + Q6 + Q7 + Q8 + Q2 + 1/2Q30 + 1/2Q22 + 1/2Q15 Section 2 Q31 + Q32 + Q23 + Q33 + Q24 + Q16 + Q34 + 1/2Q30 + 1/2Q22 + 1/2Q15 Section 3 Q41 + Q42 + Q51 + Q43 + Q52 + Q60 + Q44 + 1/2Q40 + 1/2Q50 + 1/2Q59 Section 4 Q49 + Q58 + Q57 + Q64 + Q65 + Q66 + Q68 + 1/2Q40 + 1/2Q50 + 1/2Q59 Section 5 Q48 + Q56 + Q55 + Q61 + Q62 + Q63 + Q67 + 1/2Q39 + 1/2Q47 + 1/2Q54 Section 6 Q38 + Q46 + Q37 + Q36 + Q45 + Q53 + Q35 + 1/2Q39 + 1/2Q47 + 1/2Q54 Section 7 Q28 + Q27 + Q18 + Q9 + Q17 + Q26 + Q25 + 1/2Q29 + 1/2Q19 + 1/2Q10 Section 8 Q20 + Q11 + Q12 + Q3 + Q4 + Q5 + Q1 + 1/2Q29 + 1/2Q19 + 1/2Q10 Note:

1. QX-Y is the heat load in kW in cell ID (X-Y), identified in Figure 2-4 3 to Holtec Letter 5014917 74 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-55 Table 2-14: DFC and DFI Storage Locations with Heat Load penalties for MPC-68M for UNVENTILATED OVERPACK MPC Type DFC/DFI (Note 1)

Locations/Storage Cell Numbers (Note 2)

Heat Load Penalty (Note 3)

Min. Soluble Boron Content MPC-68M DFI 1, 2, 3, 8, 9, 16, 25, 34, 35, 44, 53, 60, 61, 66, 67, 68 25%

N/A DFC 25%

DFC or DFI DFCs - 25%

DFIs - 25%

Notes 1: Damaged fuel assemblies or fuel debris can be loaded in DFCs while only damaged fuel assemblies that can be handled by normal means can be loaded in DFIs.

2: DFCs/DFIs are allowed for storage in certain basket peripheral locations as defined herein.

Basket storage cell numbers are identified in Figure 2-4 for the MPC-68M.

3: Heat load penalties are applicable to ONLY those cells where DFCs/DFIs are located and are applied to the allowable undamaged fuel assembly decay heat limit in that storage cell location. The penalties remain the same for all regionalized patterns and discrete loading patterns.

Table 2-15: Burnup and Cooling Time Fuel Qualification Requirements for MPC-68M for UNVENTILATED OVERPACK Cell Decay Heat Load Limit (kW)

Polynomial Coefficients, see Subsection 2.2.3 A

B C

D 0.382 9.44656e-14

-8.01992e-09 2.79524e-04

-4.10441e-01 0.382 < decay heat 1.625 8.59250e-15

-1.40950e-09 9.57523e-05

-1.02585e+00 3 to Holtec Letter 5014917 75 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-56 Table 2-16: Regionalized Storage Cell Heat Load Limits (Note 2)

MPC Type Number of Cells in Inner RegionNote 1 Storage Cell Heat Load (Inner Region)

(kW)

Number of Cells in Outer RegionNote 1 Storage Cell Heat Load (Outer Region)

(kW)

MPC-24 4

1.470 20 0.900 MPC-24E/EF 4

1.540 20 0.900 MPC-32/32F 12 1.131 20 0.600 MPC-68/68F/68FF/68M 32 0.500 36 0.275 Note 1: The location of MPC-32 and MPC-68 inner and outer region cells are defined in Figures 2-3 and 2-4 respectively.

The MPC-24 and MPC-24E/EF cell locations are defined below:

Inner Region Cell numbers 9, 10, 15, 16 in Figures 2-1 and 2-2 respectively.

Outer Region Cell numbers 1-8, 11-14, 17-24 in Figures 2-1 and 2-2 respectively.

Note 2: The storage cell regionalization is defined in Note 1 in accordance with safety analyses under the heat load limits of this Table.

Table 2-17: Uniform Storage Cell Heat Load Limits MPC Type Heat Load (kW)

MPC-24 1.157 MPC-24E/EF 1.173 MPC-68/68F/68FF/68M 0.414 MPC-32 0.898 3 to Holtec Letter 5014917 76 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-57 1

2 0.5*

0.5*

3 4

5 6

7 8

0.5*

0.5 1.2 1.2 0.5 0.5*

9 10 11 12 13 14 15 16 0.5*

0.5 1.2 0.4 0.4 1.2 0.5 0.5*

17 18 19 20 21 22 23 24 0.5 1.2 0.4 0.4 0.4 0.4 1.2 0.5 25 26 27 28 29 30 31 32 33 34 0.5*

1.2 0.4 0.4 0.4 0.4 0.4 0.4 1.2 0.5*

35 36 37 38 39 40 41 42 43 44 0.5*

1.2 0.4 0.4 0.4 0.4 0.4 0.4 1.2 0.5*

45 46 47 48 49 50 51 52 0.5 1.2 0.4 0.4 0.4 0.4 1.2 0.5 53 54 55 56 57 58 59 60 0.5*

0.5 1.2 0.4 0.4 1.2 0.5 0.5*

61 62 63 64 65 66 0.5*

0.5 1.2 1.2 0.5 0.5*

Cell ID 67 68 Heat Load (kW) 0.5*

0.5*

Figure 2-5: QSHL Pattern Per Cell Allowable Heat Loads (kW) - MPC-68M

When DAMAGED FUEL or FUEL DEBRIS is stored in this location (in a DFC), the allowable heat load of the cell is limited to 0.35 kW. When DFIs are utilized for DAMAGED FUEL, the value in the figure applies.

3 to Holtec Letter 5014917 77 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-58 Figure 2-6: QSHL-2 Pattern, Per Cell Allowable Heat Loads (kW) - MPC-68M

DFCs/DFIs are allowed in shaded cells. When DAMAGED FUEL or FUEL DEBRIS (in a DFC) is stored in this location, the allowable heat load of the cell is reduced by 25%. When DFIs are utilized for DAMAGED FUEL, the value in the figure applies.

3 to Holtec Letter 5014917 78 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-59 Figure 2-7: QSHL-3 Pattern, Per Cell Allowable Heat Loads (kW) - MPC-68M

DFCs/DFIs are allowed in shaded cells. When DAMAGED FUEL or FUEL DEBRIS (in a DFC) is stored in this location, the allowable heat load of the cell is reduced by 25%. When DFIs are utilized for DAMAGED FUEL, the value in the figure applies.

3 to Holtec Letter 5014917 79 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 2-60 Figure 2-8: QSHL-4 Pattern, Per Cell Allowable Heat Loads (kW) - MPC-68M

DFCs/DFIs are allowed in shaded cells. Cell IDs 19, 22, 47 and 50 must remain empty.

3 to Holtec Letter 5014917 80 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-1 3 LIMITING CONDITIONS FOR OPERATION (LCOS)

AND SURVEILLANCE REQUIREMENTS (SRS) 3.0 Applicability Limiting Conditions 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 discovery of a 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.

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 an SFSC.

LCO 3.0.5 Equipment removed from service or not in service in compliance with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate it meets the LCO or that other equipment meets the LCO. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing.

3 to Holtec Letter 5014917 81 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-2 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 a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be 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 a 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.

SR 3.0.3 (continued)

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. 3 to Holtec Letter 5014917 82 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-3 SR 3.0.4 Entry into a specified condition in the Applicability of an LCO shall not be made unless the LCO's 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 an SFSC.

3 to Holtec Letter 5014917 83 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-4 3.1 SFSC INTEGRITY 3.1.1 Multi-Purpose Canister (MPC)

LCO 3.1.1 The MPC shall be dry and helium filled.

Tables 3-1 and 3-2 provide decay heat and burnup limits for forced helium dehydration (FHD) and vacuum drying. FHD is not subject to time limits.

Vacuum drying of MPCs may be subject to time limits, from the end of bulk water removal until the start of helium backfill, as shown in Tables 3-1 and 3-2.

APPLICABILITY:

During TRANSPORT OPERATIONS and STORAGE OPERATIONS.

ACTIONS

NOTES---------------------------------------------------------

1. Separate Condition entry is allowed for each MPC.

2. MPC helium leak rate limit for cover plate base metal listed in Condition D and SR 3.1.1.3, is not applicable to casks that were initially loaded to Amendments 2 through 7.

CONDITION REQUIRED ACTION COMPLETION TIME A.

MPC cavity vacuum drying pressure or demoisturizer exit gas temperature limit not met.

A.1 Perform an engineering evaluation to determine the quantity of moisture left in the MPC.

7 days AND A.2 Develop and initiate corrective actions necessary to return the MPC to compliance with Tables 3-1 and 3-2.

30 days 3 to Holtec Letter 5014917 84 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-5 ACTIONS (continued)

B.

MPC cavity vacuum drying acceptance criteria not met during allowable time.

B.1 Backfill the MPC cavity with helium to a pressure of at least 0.5 atm.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months C.

MPC helium backfill limit not met.

C.1 Perform an engineering evaluation to determine the impact of helium differential.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND C.2.1 Develop and initiate corrective actions necessary to return the MPC to an analyzed condition by adding helium to or removing helium from the MPC.

14 days OR C.2.2 Develop and initiate corrective actions necessary to demonstrate through analysis, using the models and methods from the HI-STORM FSAR, that all limits for cask components and contents will be met.

D.

MPC helium leak rate limit for vent and drain port cover plate welds or cover plate base metal not met.

D.1 Perform an engineering evaluation to determine the impact of increased helium leak rate on heat removal capability and offsite dose.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND D.2 Develop and initiate corrective actions necessary to return the MPC to compliance with SR 3.1.1.3.

7 days 3 to Holtec Letter 5014917 85 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-6 E.

Required Actions and associated Completion Times not met.

E.1 Remove all fuel assemblies from the SFSC.

30 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify that the MPC cavity has been dried in accordance with the applicable limits in Tables 3-1 and 3-2, within the specified vacuum drying time limits as applicable.

Once, prior to TRANSPORT OPERATIONS SR 3.1.1.2 Verify MPC helium backfill quantity is within the limit specified in Tables 3-3 and 3-4 for the applicable MPC model. Re-performance of this surveillance is not required upon successful completion of Action C.2.2.

Once, prior to TRANSPORT OPERATIONS SR 3.1.1.3 Verify that the helium leak rate through the MPC vent and drain port cover plates (confinement welds and the base metal) meets the leaktight criteria of ANSI N14.5-1997. This surveillance does not need to be performed in the MPC utilizing the REDUNDANT PORT COVER DESIGN.

Once, prior to TRANSPORT OPERATIONS 3 to Holtec Letter 5014917 86 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-7 3.1.2 SFSC Heat Removal System LCO 3.1.2 The SFSC Heat Removal System shall be operable

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

The SFSC Heat Removal System is operable when 50% or more of the inlet and outlet vent areas are unblocked and available for flow or when air temperature requirements are met. This LCO only applies to the VENTILATED OVERPACKs.

APPLICABILITY:

During STORAGE OPERATIONS.

ACTIONS

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

Separate Condition entry is allowed for each SFSC.

CONDITION REQUIRED ACTION COMPLETION TIME A. SFSC Heat Removal System

operable, but partially (<50%) blocked.

A.1 Remove blockage.

N/A 3 to Holtec Letter 5014917 87 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-8 CONDITION REQUIRED ACTION COMPLETION TIME B. SFSC Heat Removal System inoperable.

B.1 Restore SFSC Heat Removal System to operable status.

Table 3-5 C. Required Action B.1 and associated Completion Time not met.

C.1 Measure SFSC dose rates in accordance with the Radiation Protection Program.

Immediately and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2.1 Restore SFSC Heat Removal System to operable status.

Table 3-5 OR C.2.2 Transfer the MPC into a TRANSFER CASK.

Table 3-5 3 to Holtec Letter 5014917 88 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2 Verify all OVERPACK inlets and outlets are free of blockage from solid debris or floodwater.

Table 3-5 OR For OVERPACKS with installed temperature monitoring equipment, verify that the difference between the average OVERPACK air outlet temperature and ISFSI ambient temperature is

< 155oF for OVERPACKS containing PWR MPCs, <

137oF for OVERPACKS containing BWR MPCs (except MPC-68M) and 164°F for OVERPACKS containing MPC-68M.

Table 3-5 3 to Holtec Letter 5014917 89 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-10 3.1.3 MPC Cavity Reflooding LCO 3.1.3 The MPC cavity pressure shall be < 100 psig

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

The LCO is only applicable to wet UNLOADING OPERATIONS.

APPLICABILITY:

UNLOADING OPERATIONS prior to and during re-flooding.

ACTIONS

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

Separate Condition entry is allowed for each MPC.

CONDITION REQUIRED ACTION COMPLETION TIME A.

MPC cavity pressure not within limit.

A.1 Stop re-flooding operations until MPC cavity pressure is within limit.

Immediately AND A.2 Ensure MPC vent port is not closed or blocked.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 3 to Holtec Letter 5014917 90 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-11 SR 3.1.3.1 Ensure via analysis or direct measurement that MPC cavity pressure is within limit.

Once, prior to MPC re-flooding operations.

AND Once every 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months thereafter when using direct measurement.

3 to Holtec Letter 5014917 91 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-12 3.1.4 Supplemental Cooling System LCO 3.1.4 A supplemental cooling system (SCS) shall be operable

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

Upon reaching steady state operation, the SCS may be temporarily disabled for a short duration

(< 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ) to facilitate necessary operational evolutions, such as movement of the TRANSFER CASK through a door way, or other similar operation.

APPLICABILITY:

This LCO is not applicable to the MPC-68M. For all other MPCs this LCO is applicable when the loaded MPC is in the TRANSFER CASK and:

a.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the completion of MPC drying operations in accordance with LCO 3.1.1 or within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of transferring the MPC into the TRANSFER CASK if the MPC is to be unloaded AND

b.

The MPC contains one or more fuel assemblies with an average burnup

> 45,000 MWD/MTU AND c1. MPC backfilled to higher helium backfill limits in Tables 3-3 and 3-4 AND any storage cell decay heat load exceeds 90% of maximum allowable storage cell heat load defined in Section 2.2.1 or 2.2.2 and FSAR Section 2.1.9.1 procedures.

OR c2. MPC backfilled to lower helium backfill limits in Tables 3-3 and 3-4 AND any storage cell heat load exceeds 90% of storage cell heat load limits defined in Tables 2-16 or 2-17. 3 to Holtec Letter 5014917 92 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-13 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

SFSC Supplemental Cooling System inoperable.

A.1 Restore SFSC Supplemental Cooling System to operable status.

7 days B.

Required Action A.1 and associated Completion Time not met.

B.1 Remove all fuel assemblies from the SFSC.

30 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify SCS is operable.

2 hou rs 3 to Holtec Letter 5014917 93 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-14 3.2 SFSC RADIATION PROTECTION.

3.2.1 Deleted.

LCO 3.2.1 Deleted.

3.2.2 TRANSFER CASK Surface Contamination.

LCO 3.2.2 Removable contamination on the exterior surfaces of the TRANSFER CASK and accessible portions of the MPC shall each not exceed:

a. 1000 dpm/100 cm2 from beta and gamma sources

b. 20 dpm/100 cm2 from alpha sources.

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

This LCO is not applicable to the TRANSFER CASK if MPC TRANSFER operations occur inside the FUEL BUILDING.

APPLICABILITY:

During TRANSPORT OPERATIONS.

ACTIONS

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

Separate Condition entry is allowed for each TRANSFER CASK.

CONDITION REQUIRED ACTION COMPLETION TIME A.

TRANSFER CASK or MPC removable surface contamination limits not met.

A.1 Restore removable surface contamination to within limits.

7 days 3 to Holtec Letter 5014917 94 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify that the removable contamination on the exterior surfaces of the TRANSFER CASK and accessible portions of the MPC containing fuel is within limits.

Once, prior to TRANSPORT OPERATIONS 3 to Holtec Letter 5014917 95 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-16 3.3 SFSC CRITICALITY CONTROL 3.3.1 Boron Concentration LCO 3.3.1 As required by Table 2-2, the concentration of boron in the water in the MPC shall meet the following limits for the applicable MPC model and the most limiting fuel assembly array/class and classification to be stored in the MPC:

a.

MPC-24 with one or more fuel assemblies having an initial enrichment greater than the value in Table 2-2 for no soluble boron credit and <

5.0 wt% 235U: > 400 ppmb

b.

MPC-24E or MPC-24EF (all INTACT FUEL ASSEMBLIES) with one or more fuel assemblies having an initial enrichment greater than the value in Table 2-2 for no soluble boron credit and < 5.0 wt% 235U: >

300 ppmb

c.

MPC-24E or MPC-24EF (one or more DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS) with one or more fuel assemblies having an initial enrichment 4.0 wt%

235U and

< 5.0 wt% 235U: > 600 ppmb

d. MPC-32/32F: Minimum soluble boron concentration as required by the table below.

3 to Holtec Letter 5014917 96 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-17 Array/Class All INTACT FUEL ASSEMBLIES One or more DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS Maximum Initial Enrichment

< 4.1 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb)

Maximum Initial Enrichment

< 4.1 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb) 14x14A/B/C/D/E 1,300 1,900 1,500 2,300 15x15A/B/C/G/I 1,800 2,500 1,900 2,700 15x15D/E/F/H 1,900 2,600 2,100 2,900 16x16A/B/C 1,400 2,000 1,500 2,300 17x17A 1,600 2,200 1,800 2,600 17x17B/C 1,900 2,600 2,100 2,900 For maximum initial enrichments between 4.1 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.1 wt% and 5.0 wt%. 3 to Holtec Letter 5014917 97 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-18 APPLICABILITY:

During PWR fuel LOADING OPERATIONS with fuel and water in the MPC AND During PWR fuel UNLOADING OPERATIONS with fuel and water in the MPC.

ACTIONS

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

Separate Condition entry is allowed for each MPC.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Boron concentration not within limit.

A.1 Suspend LOADING OPERATIONS or UNLOADING OPERATIONS.

Immediately AND A.2 Suspend positive reactivity additions.

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

Immediately 3 to Holtec Letter 5014917 98 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-19 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

This surveillance is only required to be performed if the MPC is submerged in water or if water is to be added to, or recirculated through the MPC.

SR 3.3.1.1 Verify boron concentration is within the applicable limit using two independent measurements.

Once, within 4

hours prior to entering the Applicability of this LCO.

AND Once per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months thereafter. 3 to Holtec Letter 5014917 99 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-20 Table 3-1: MPC Cavity Drying Limits for all MPC Types for Ventilated Overpack Fuel Burnup (MWD/MTU)

MPC Heat Load (kW)

Method of Moisture Removal (Notes 1 and 2)

All Assemblies < 45,000 26 (MPC-24/24E/24EF, MPC-32/32F, MPC-68/68F/68FF)

VDSNote 5 or FHDNote 6 36.9 (MPC-68M)Note 6 VDS or FHD 42.8 (MPC-68M)Note 7 VDS or FHD All Assemblies < 45,000 36.9 (MPC-24/24E/24EF, MPC-32/32F, MPC-68/68F/68FF)Note 6

VDSNote 8 or FHD One or more assemblies >

45,000 29 (MPC-68M)

VDSNote 4 One or more assemblies >

45,000 36.9 (MPC-24/24E/24EF/MPC-32/32F/MPC-68/68F/68FF)Note6 VDSNote8 or FHD 36.9 (MPC-68M)Note6 VDSNote8 or FHD 42.8 (MPC-68M)Note 7 VDSNote8 or FHD Notes:

1.

VDS means a vacuum drying system. The acceptance criterion when using a VDS is MPC cavity pressure shall be < 3 torr for > 30 minutes.

2.

FHD means a forced helium dehydration system. The acceptance criterion when using an FHD system is the gas temperature exiting the demoisturizer shall be

< 21oF for > 30 minutes or the gas dew point exiting the MPC shall be < 22.9oF for > 30 minutes.

3.

Vacuum drying of the system must be performed with the annular gap between the MPC and the TRANSFER CASK filled with water.

4.

The maximum allowable decay heat per fuel storage location is 0.426 kW.

5.

Maximum allowable storage cell heat load is 1.083 kW (MPC-24/24E/24EF), 0.812 kW (MPC-32/32F) and 0.382 kW (MPC-68/68F/68FF).

6.

Maximum per assembly allowable heat loads under uniform or regionalized storage defined in Section 2.2.1 or 2.2.2.

7.

Maximum per assembly allowable heat loads defined in Figures 2-5 through 2-8. 3 to Holtec Letter 5014917 100 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-21

8.

Vacuum drying of the MPC must be performed using cycles of the drying system, according to the guidance contained in ISG-11 Revision 3. The time limit for these cycles shall be determined based on site specific conditions. Applies when any one assembly heat load is greater than 0.426 kW.

Table 3-2: MPC Cavity Drying Limits for all MPC Types for Unventilated Overpack Fuel Burnup (MWD/MTU)

MPC Heat Load (kW)

Method of Moisture Removal (Notes 1 and 2)

All burnups 25 (MPC-68M)Note 4 VDS or FHD Notes:

1.

VDS means a vacuum drying system. The acceptance criterion when using a VDS is MPC cavity pressure shall be < 3 torr for > 30 minutes.

2.

FHD means a forced helium dehydration system. The acceptance criterion when using an FHD system is the gas temperature exiting the demoisturizer shall be

< 21oF for > 30 minutes or the gas dew point exiting the MPC shall be < 22.9oF for > 30 minutes.

3.

Vacuum drying of the system must be performed with the annular gap between the MPC and the TRANSFER CASK filled with water.

4.

Maximum per assembly allowable heat loads under uniform or regionalized storage defined in Section 2.2.5.

3 to Holtec Letter 5014917 101 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-22 Table 3-3: MPC Helium Backfill Limits for Ventilated Overpack (Note 1)

MPC MODEL LIMIT MPC-24/24E/24EF

i.

Cask Heat Load 27.77 kW (MPC-24) or 28.17 kW (MPC-24E/EF) -

uniformly distributed per Table 2-17 or regionalized loading per Table 2-16 0.1212 +/-10% g-moles/l OR 29.3 psig and 48.5 psig ii. Cask Heat Load >27.77 kW (MPC-24) or >

28.17 kW (MPC-24E/EF) -

uniformly distributed or greater than regionalized heat load limits per Table 2-16 45.5 psig and 48.5 psig MPC-68/68F/68FF

i.

Cask Heat Load 28.19 kW -

uniformly distributed per Table 2-17 or regionalized loading per Table 2-16 0.1218 +/-10% g-moles/l OR 29.3 psig and 48.5 psig ii. Cask Heat Load > 28.19 kW -

uniformly distributed or greater than regionalized heat load limits per Table 2-16 45.5 psig and 48.5 psig MPC-32/32F

i.

Cask Heat Load 28.74 kW -

uniformly distributed per Table 2-17 or regionalized loading per Table 2-16 29.3 psig and 48.5 psig ii. Cask Heat Load >28.74 kW -

uniformly distributed or greater than regionalized heat load limits per Table 2-16 45.5 psig and 48.5 psig 3 to Holtec Letter 5014917 102 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-23 MPC-68M

i.

Cask Heat Load 28.19 kW -

uniformly distributed per Table 2-17 or regionalized loading per Table 2-16 0.1218 +/-10% g-moles/l OR 29.3 psig and 48.5 psig ii. Cask Heat Load > 28.19 kW -

uniformly distributed or greater than regionalized heat load limits per Table 2-16 45.5 psig and 48.5 psig iii.

Cask Heat Load 42.8 kW QSHL Loading Pattern shown in Figure 2-5 QSHL patterns shown in Figures 2-6 through 2-8 43.5 psig and 46.5 psig 45.5 psig and 48.5 psig Note:

1. Helium used for backfill of MPC shall have a purity of 99.995%. Pressure range is at a reference temperature of 70oF 3 to Holtec Letter 5014917 103 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-24 Table 3-4: MPC Helium Backfill Limits for Unventilated Overpack MPC MODEL LIMIT MPC-68M

i.

Cask Heat Load 25 kW -

uniformly distributed per Section 2.2.5 or regionalized loading per Section 2.2.5 0.1218 +/-10% g-moles/l OR 42.0 psig and 45.0 psig Note:

1. Helium used for backfill of MPC shall have a purity of 99.995%. Pressure range is at a reference temperature of 70oF Table 3-5: Completion Time for Actions to Restore SFSC Heat Removal System Operable MPC Material MPC Type Decay Heat Limits per Storage Location Condition B Completion Time Condition C Completion Time Surveillance Frequency ce cy Alloy X Except Duplex1 MPC-24/24E/24EF Section 2.2 8 hrs 24 hrs 24 hrs MPC-32/32F MPC-68/68F/68FF/68M MPC-68M Figures 2-5 through 2-8 Alloy X MPC-24/24E/24EF Section 2.2 8 hrs 16 hrs 16 hrs MPC-32/32F MPC-68/68F/68FF/68M Alloy X MPC-68M Figures 2-5 through 2-8 4 hrs 12 hrs 12 hrs Alloy X Except Duplex1 MPC-24 Table 2-16 (Regionalized)

OR Table 2-17 (Uniform) 8 hrs 64 hrs 24 hrs MPC-24E/EF MPC-32/32F MPC-68/68F/68FF/68M MPC-24 Table 2-16 8 hrs 24 hrs 24 hrs MPC-24E/EF 3 to Holtec Letter 5014917 104 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 3-25 Alloy X MPC-32/32F (Regionalized)

OR Table 2-17 (Uniform)

MPC-68/68F/68FF/68M Alloy X MPC-24/24E/24EF 0.75 kW 24 hrs 64 hrs 30 days MPC-32/32F 0.5 kW MPC-68/68F/68FF/68M 0.264 kW Note:

1. If any component of the MPC is made of duplex, these completion times are not applicable.

3 to Holtec Letter 5014917 105 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 4-1 4 ADMINISTRATIVE CONTROLS 4.1 Radioactive Effluent Control Program

a.

The HI-STORM 100 Cask 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. Specification 3.1.1, Multi-Purpose Canister (MPC), provides assurance that there are not radioactive effluents from the SFSC.

b.

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

c.

An annual report shall be submitted pursuant to 10 CFR 72.44(d)(3).

3 to Holtec Letter 5014917 106 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 4-2 4.2 Cask Transport Evaluation Program This program provides a means for evaluating various transport configurations and transport route conditions to ensure that the design basis drop limits are met. For lifting of the loaded TRANSFER CASK or OVERPACK using devices which are integral to a structure governed by 10 CFR Part 50 regulations, 10 CFR 50 requirements apply. This program is not applicable when the TRANSFER CASK or OVERPACK is in the FUEL BUILDING or is being handled by a device providing support from underneath (i.e., on a rail car, heavy haul trailer, air pads, etc...) or is being handled by a device designed in accordance with the increased safety factors of ANSI N14.6 and having redundant drop protection.

Pursuant to 10 CFR 72.212, this program shall evaluate the site-specific transport route conditions.

4.2.1 Freestanding Overpacks and the Transfer Cask For free-standing OVERPACKS and the TRANSFER CASK, the following requirements apply:

4.2.1.1 The lift height above the transport route surface(s) shall not exceed the limits in Table 4-1 except as provided for in Specification 4.2.1.2. Also, if applying the limits in Table 4-1, the program shall ensure that the transport route conditions (i.e., surface hardness and pad thickness) are equivalent to or less limiting than either Set A or Set B in HI-STORM FSAR Table 2.2.9.

4.2.1.2 The program may determine lift heights by analysis based on the site-specific conditions to ensure that the impact loading due to design basis drop events does not exceed 45 gs at the top of the MPC fuel basket. These alternative analyses shall be commensurate with the drop analyses described in the Final Safety Analysis Report for the HI-STORM 100 Cask System. The program shall ensure that these alternative analyses are documented and controlled.

4.2.1.3 The TRANSFER CASK or OVERPACK, when loaded with spent fuel, may be lifted to any height necessary during TRANSPORT OPERATIONS, provided the lifting device is designed in accordance with applicable stress limits from ANSI N14.6, and/or NUREG-0612, and has redundant drop protection features.

4.2.1.4 The TRANSFER CASK and MPC, when loaded with spent fuel, may be lifted to those heights necessary to perform cask handling operations, including MPC TRANSFER, provided the lifts are made with structures and components designed in accordance with the criteria specified in Section 2.3 of Appendix A to Certificate of Compliance No. 1014, as applicable.

4.2.2 Anchored Overpacks For the transport of OVERPACKS to be anchored to the ISFSI pad, the following requirements apply: 3 to Holtec Letter 5014917 107 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 4-3 4.2.2.1 Except as provided in 4.2.2.2, user shall determine allowable OVERPACK lift height limit(s) above the transport route surface(s) based on site-specific transport route conditions. The lift heights shall be determined by evaluation or analysis, based on limiting the design basis cask deceleration during a postulated drop event to 45 gs at the top of the MPC fuel basket. Evaluations and/or analyses shall be performed using methodologies consistent with those in the HI-STORM 100 FSAR.

4.2.2.2 The OVERPACK, when loaded with spent fuel, may be lifted to any height necessary during TRANSPORT OPERATIONS provided the lifting device is designed in accordance with applicable stress limits from ANSI N14.6, and/or NUREG-0612, and has redundant drop protection features.

Table 4-1: Transfer Cask and Free-Standing Overpack Lifting Requirements ITEM ORIENTATION LIFTING HEIGHT LIMIT (in.)

TRANSFER CASK Horizontal 42 Notes 1 and 2 TRANSFER CASK Vertical None Established Note 2 OVERPACK Horizontal Not Permitted OVERPACK Vertical 11 Note 3 Notes:

1.

To be measured from the lowest point on the TRANSFER CASK (i.e., the bottom edge of the cask/lid assemblage)

2.

See Technical Specification 4.2.1.3 and 4.2.1.4

3.

See Technical Specification 4.2.1.3.

3 to Holtec Letter 5014917 108 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 4-4 4.3 Radiation Protection Program 4.3.1.1 Each cask user shall ensure that the Part 50 radiation protection program appropriately addresses dry storage cask loading and unloading, as well as ISFSI operations, including transport of the loaded OVERPACK or TRANSFER CASK outside of facilities governed by 10 CFR Part 50. The radiation protection program shall include appropriate controls for direct radiation and contamination, ensuring compliance with applicable regulations, and implementing actions to maintain personnel occupational exposures As Low As Reasonably Achievable (ALARA). The actions and criteria to be included in the program are provided below.

4.3.1.2 Based on the analysis performed pursuant to 10 CFR 72.212(b)(5)(iii), the licensee shall establish individual cask surface dose rate limits for the HI-TRAC TRANSFER CASK and the HI-STORM OVERPACK to be used at the site. Total (neutron plus gamma) dose rate limits shall be established at the following locations:

a.

The top of the TRANSFER CASK and the OVERPACK.

b.

The side of the TRANSFER CASK and OVERPACK

c.

The inlet and outlet ducts on the OVERPACK (applicable only for VENTILATED OVERPACKS) 3 to Holtec Letter 5014917 109 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 4-5 4.3.1.3 Notwithstanding the limits established in Section 4.3.1.2, the measured dose rates on a loaded OVERPACK shall not exceed the following values:

a.

30 mrem/hr (gamma + neutron) on the top of the OVERPACK

b.

300 mrem/hr (gamma + neutron) on the side of the OVERPACK, excluding inlet and outlet ducts

c.

4000 mrem/hr (gamma + neutron) on the side of the TRANSFER CASK 4.3.1.4 The licensee shall measure the TRANSFER CASK and OVERPACK surface neutron and gamma dose rates as described in Section 4.3.1.7 for comparison against the limits established in Section 4.3.1.2 or Section 4.3.1.3, whichever are lower.

4.3.1.5 If the measured surface dose rates exceed the lower of the two limits established in Section 4.3.1.2 or Section 4.3.1.3, the licensee shall:

a.

Administratively verify that the correct contents were loaded in the correct fuel storage cell locations.

b.

Perform a written evaluation to verify whether an OVERPACK at the ISFSI containing the as-loaded MPC will cause the dose limits of 10 CFR 72.104 to be exceeded.

c.

Perform a written evaluation within 30 days to determine why the surface dose rate limits were exceeded.

4.3.1.6 If the evaluation performed pursuant to Section 4.3.1.5 shows that the dose limits of 10 CFR 72.104 will be exceeded, the MPC shall not be placed into storage or, in the case of the OVERPACK loaded at the ISFSI, the MPC shall be removed from storage until appropriate corrective action is taken to ensure the dose limits are not exceeded.

4.3.1.7 TRANSFER CASK and OVERPACK surface dose rates shall be measured at approximately the following locations:

a.

A minimum of four (4) dose rate measurements shall be taken on the side of the TRANSFER CASK approximately at the cask mid-height plane. The measurement locations shall be approximately 90 degrees apart around the circumference of the cask. Dose rates shall be measured between the radial ribs of the water jacket.

b.

A minimum of four (4) TRANSFER CASK top lid dose rates shall be measured at locations approximately half way between the edge of the hole in the top lid and the outer edge of the top lid, 90 degrees apart around the circumference of the top lid.

c.

A minimum of twelve (12) dose rate measurements shall be taken on the side of the OVERPACK in three sets of four measurements. One measurement set shall be taken approximately at the cask mid-height plane, 90 degrees apart around the circumference of the cask. The second and third measurement sets shall be taken approximately 60 inches above and below the mid-height plane, respectively, also 90 degrees apart around the circumference of the cask.

d.

A minimum of five (5) dose rate measurements shall be taken on the top of the OVERPACK. One dose rate measurement shall be taken at approximately the center of the lid and four measurements shall be taken at locations on the top concrete shield, approximately half way between the center and the edge of the top concrete shield, 90 degrees apart around the circumference of the lid. 3 to Holtec Letter 5014917 110 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 4-6

e.

A dose rate measurement shall be taken on contact at the surface of each inlet and outlet vent duct screen of the OVERPACK (applicable only for VENTILATED OVERPACK).

3 to Holtec Letter 5014917 111 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 4-7 4.4 Fabrication Helium Leak Test At completion of welding the MPC shell to baseplate, an MPC confinement weld helium leak test shall be performed using a helium mass spectrometer. This test shall include the base metals of the MPC shell and baseplate. A helium leak test shall also be performed on the base metal of the fabricated MPC lid. The confinement boundary leakage rate tests shall be performed in accordance with ANSI N14.5 to leaktight criteria. If a leakage rate exceeding the acceptance criteria is detected, then the area of leakage shall be determined and the area repaired per ASME Code Section III, Subsection NB requirements. Re-testing shall be performed until the leakage rate acceptance criterion is met.

Casks initially loaded to Amendments No. 2 through 7 must meet the following:

Casks fabricated on or after July 1, 2009 a fabrication helium leak test at completion of the welding of the MPC shell to baseplate must be performed in accordance with the above requirements.

Casks loaded before July 1, 2009 must meet the fabrication helium leak test requirements of the lid base metal of the amendment to which they were originally loaded.

Casks loaded before July 1, 2009 do not meet the above fabrication helium leak test requirements after MPC shell to baseplate welding. These casks may be upgraded to Amendment 15.

3 to Holtec Letter 5014917 112 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 4-8 4.5 Violations of Fuel Specifications or Loading Conditions If any Fuel Specifications or Loading Conditions of 2.1 are violated, the following actions shall be completed:

a.

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

b.

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

c.

Within 30 days, submit a special report which describes the cause of the violation, and actions taken to restore compliance and prevent recurrence.

3 to Holtec Letter 5014917 113 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 4-9 4.6 Heavy Loads Requirements Each lift of an MPC, a HI-TRAC transfer cask, or any HI-STORM overpack must be made in accordance to the existing heavy loads requirements and procedures of the licensed facility at which the lift is made. A plant specific review (under 10 CFR 50.59 or 10 CFR 72.48, if applicable) is required to show operational compliance with existing plant specific heavy loads requirements.

Lifting operations outside of structures governed by 10 CFR Part 50 must be in accordance with Section 4.2 and Sections 2.1.6 and 2.3 (if applicable) of Appendix A.

3 to Holtec Letter 5014917 114 of 115

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B 4-10 4.7 Aging Management Program Each general licensee shall have a program to establish, implement, and maintain written procedures for each AMP described in the FSAR. The program shall include provisions for changing AMP elements, as necessary, and within the limitations of the approved licensing bases to address new information on aging effects based on inspection findings and/or industry operating experience provided to the general licensee during the renewal period.

The general licensee shall establish and implement these written procedures within 365 days after the effective date of the renewal of the CoC or 365 days of the 20th anniversary of the loading of the first dry storage system at its site, whichever is later.

Each general licensee shall perform tollgate assessments as described in Chapter 9 of the FSAR.

3 to Holtec Letter 5014917 115 of 115

HI-STORM 100 Amendment 16 Certificate of Compliance, Appendix B Reorganization
Person / Time
ML21068A385
Site:	Holtec
Issue date:	03/09/2021
From:	Holtec
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML21068A360	List: ML21068A361 ML21068A362 ML21068A363 ML21068A364 ML21068A366 ML21068A367 ML21068A368 ML21068A369 ML21068A370 ML21068A372 ML21068A383 ML21068A384 ML21068A385 ML21068A386 ML21068A387 ML21068A388 ML21068A389 ML21068A390 ML21068A391 ML21068A392 ML21068A393 ML21068A394 ML21068A395 ML21068A396 ML21068A397 ML21068A398
References
5014917
Download: ML21068A385 (115)
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ML21068A385

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