Text

Attachment 13: HI-STORM FW Amendment 7 Certificate of Compliance, Appendix B Reorganization
	ML21288A536
Person / Time
Site:	07201032
Issue date:	10/15/2021
From:	; Holtec
To:	; Office of Nuclear Material Safety and Safeguards
Shared Package
ML21288A521	List: ML21288A522; ML21288A524; ML21288A525; ML21288A526; ML21288A528; ML21288A534; ML21288A535; ML21288A536; ML21288A537; ML21288A538; ML21288A539; ML21288A540; ML21288A542;
References
	5018091, CAC 001028, CoC No. 1032, EPID L2021-LLA-0053
	Download: ML21288A536 (92)
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PROPOSED CERTIFICATE OF COMPLIANCE NO. 1032 APPENDIX B TECHNICAL SPECIFICATIONS FOR THE HI-STORM FW MPC STORAGE SYSTEM

TABLE OF CONTENTS 1 Definitions, Use, and Application ...................................................................................... 1-5 1.1 Definitions ................................................................................................................. 1-5 1.2 Logical Connectors ................................................................................................. 1-10 1.3 Completion Times.................................................................................................... 1-13 1.4 Frequency ............................................................................................................... 1-17 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 FW MPC Storage System ......................... 2-1 2.1.2 Fuel Loading ...................................................................................................... 2-1 2.2 Decay Heat Limits ................................................................................................... 2-21 2.2.1 Fuel Loading Decay Heat Limits for VENTILATED OVERPACK ...................... 2-21 2.2.2 Fuel Loading Decay Heat Limits for UNVENTILATED OVERPACK ................. 2-21 2.2.3 Variable Fuel Height for MPC-37 and MPC-44................................................... 2-22 2.2.4 Variable Fuel Height for MPC-89 ..................................................................... 2-22 2.2.5 Decay Heat Limit Compliance .......................................................................... 2-22 2.3 Burnup Credit.......................................................................................................... 2-46 2.3.1 Method A: Burnup Verification Through Quantitative Burnup Measurement ..... 2-46 2.3.2 Method B: Burnup Verification Through an Administrative Procedure and Qualitative Measurements ............................................................................................................... 2-46 2.4 Burnup and Cooling Time Qualification Requirements ............................................ 2-49 2.4.1 Burnup and Cooling Time for MPC-32ML ........................................................ 2-49 2.4.2 Burnup and Cooling Time for MPC-37P and MPC-44 ...................................... 2-49 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 TRANSFER CASK Heat Removal System ....................................................... 3-11 3.2 SFSC RADIATION PROTECTION. ......................................................................... 3-13 3.2.1 TRANSFER CASK Surface Contamination. ..................................................... 3-13 3.3 SFSC CRITICALITY CONTROL ............................................................................. 3-14 3.3.1 Boron Concentration ........................................................................................ 3-14 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-1

4 Administrative Controls .................................................................................................... 4-1 4.1 Radioactive Effluent Control Program ....................................................................... 4-1 4.2 Transport Evaluation Program.................................................................................... 4-1 4.3 Radiation Protection Program .................................................................................... 4-2 4.4 Violations of Fuel Specifications or Loading Conditions ............................................ 4-3 4.5 Heavy Loads Requirements ...................................................................................... 4-3 4.6 Combustible Gas Monitoring During MPC Lid Welding and Cutting .......................... 4-4 4.7 Pre-Operational Testing and Training ....................................................................... 4-4 4.7.1 Dry Run Training Exercise ................................................................................. 4-4 FIGURES Figure 2.1-1: MPC-37 Region-Cell Identification ......................................................................2-2 Figure 2.1-2: MPC-89 Region-Cell Identification ......................................................................2-3 Figure 2.1-3: MPC-32ML Cell Identification ..............................................................................2-4 Figure 2.1-4: MPC-37P Cell Identification ................................................................................2-5 Figure 2.1-5: MPC-44 Cell Identification ...................................................................................2-6 Figure 2.3-1: Loading Pattern 37C1 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC Short Fuel per Cell Heat Load Limits ......................2-31 Figure 2.3-2: Loading Pattern 37C2 for MPC-37 Containing Undamaged and Damaged Fuel in DFC/DFI/, Short Fuel per Cell Heat Load Limits ..................................................................2-32 Figure 2.3-3: Loading Pattern 37C3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Short Fuel per Cell Heat Load Limits .....................2-33 Figure 2.3-4: Loading Pattern 37D1 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, Standard Fuel per Cell Heat Load Limits .............2-34 Figure 2.3-5: Loading Pattern 37D2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, Standard Fuel per Cell Heat Load Limits ..........................................................2-35 Figure 2.3-6: Loading Pattern 37D3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Standard Fuel per Cell Heat Load Limits ...............2-36 Figure 2.3-7: Loading Pattern 37E1 for MPC-37 Loading Pattern for MPCs Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, Long Fuel per Cell Heat Load Limits ............................................................................................................2-37 Figure 2.3-8: Loading Pattern 37E2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, Long Fuel per Cell Heat Load Limits ................................................................2-38 Figure 2.3-9: Loading Pattern 37E3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Long Fuel per Cell Heat Load Limits......................2-39 Figure 2.3-10: Loading Pattern 89A1 for MPC-89 Containing Undamaged and Damaged Fuel in Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-2

DFCs/DFIs, and/or Fuel Debris in DFC, per Cell Heat Load Limits.........................................2-40 Figure 2.3-11: Loading Pattern 89A2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, per Cell Heat Load Limits .......................................2-41 Figure 2.3-12: Loading Pattern 89B1 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per cell Heat Load Limits .........................................2-42 Figure 2.3-13: Loading Pattern 89B2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per Cell Heat Load Limits.........................................2-43 Figure 2.3-14: Loading Pattern 1 for MPC-37P ......................................................................2-44 Figure 2.3-15: Loading Pattern 2 for MPC-37P ......................................................................2-45 TABLES Table 2.1-1: Fuel Assembly Limits ...........................................................................................2-7 Table 2.1-2: PWR Fuel Assembly Characteristics ..................................................................2-17 Table 2.1-3: BWR Fuel Assembly Characteristics ..................................................................2-19 Table 2.3-1A: MPC-37 and MPC-37 Heat Load Data .............................................................2-23 Table 2.3-1B: MPC-37 Heat Load Data ..................................................................................2-23 Table 2.3-1C: MPC-37 Heat Load Data .................................................................................2-23 Table 2.3-2A: MPC-89 Heat Load Data ..................................................................................2-24 Table 2.3-2B: MPC-89 Heat Load Data ..................................................................................2-24 Table 2.3-3: MPC-37 Heat Load Data ....................................................................................2-24 Table 2.3-4: MPC-89 Heat Load Data ....................................................................................2-25 Table 2.3-5: MPC-32ML Heat Load Data ...............................................................................2-25 Table 2.3-6: PWR Fuel Length Categories .............................................................................2-25 Table 2.3-7A: MPC-37P Heat Load Data for Ventilated Overpack .........................................2-26 Table 2.3-7B: MPC-37P Heat Load Data for Ventilated Overpack .........................................2-26 Table 2.3-8A: MPC-44 Heat Load Data for Ventilated Overpack ............................................2-26 Table 2.3-8B: MPC-44 Heat Load Data for Ventilated Overpack ............................................2-27 Table 2.3-9A: MPC-37 Heat load Data for Unventilated Overpack .........................................2-27 Table 2.3-9B: MPC-37 Requirements on Developing Regionalized Heat Load Patterns for Unventilated Overpack ...........................................................................................................2-27 Table 2.3-10A: MPC-89 Heat load Data for Unventilated Overpack .......................................2-28 Table 2.3-10B: MPC-89 Requirements on Developing Regionalized Heat Load Patterns for Unventilated Overpack ...........................................................................................................2-28 Table 2.3-11: Section Heat Load Calculations for MPC-37 ....................................................2-29 Table 2.3-12: Section Heat Load Calculations for MPC-89 ....................................................2-30 Table 2.3-13: MPC-44 Heat Load Data for Unventilated Overpack ........................................2-30 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-3

Table 2.4-1: Polynomial Functions for the Minimum Burnup as a Function of Initial Enrichment ...

............................................................................................................2-47 Table 2.4-2: Burnup Credit Configurations .............................................................................2-48 Table 2.4-3: In-Core Operating Requirements........................................................................2-48 Table 2.5-1: Burnup and Cooling Time Fuel Qualification Requirements for MPC-32ML........2-49 Table 2.5-2: Burnup and Cooling Time Fuel Qualification Requirements for MPC-37 and MPC-89

............................................................................................................2-50 Table 2.5-3: Burnup and Cooling Time Fuel Qualification Requirements for MPC-37P and MPC-44 ............................................................................................................2-50 Table 3.3-1: MPC Cavity Drying Limits ...................................................................................3-16 Table 3.3-2: MPC Helium Backfill Limits.................................................................................3-18 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-4

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.

BLEU FUEL Blended Low Enriched Uranium (BLEU) fuel is the same as a commercial spent fuel but with a higher cobalt impurity.

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.

DAMAGED FUEL CONTAINER DFCs are specially designed enclosures for DAMAGED (DFC) 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 FW System are as follows:

1. Holtec Generic BWR design

2. Holtec Generic PWR design Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-5

Term Definition DAMAGED FUEL DFIs are specially designed barriers installed at the top and bottom of the storage cell space which permit flow of ISOLATOR (DFI) 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.

GROSSLY BREACHED SPENT Spent nuclear fuel rod with a cladding defect that could lead FUEL ROD 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.

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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-6

Term Definition MULTI-PURPOSE CANISTER MPCs are the sealed spent nuclear fuel canisters which (MPC) 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.

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

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

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-7

Term Definition REPAIRED/RECONSTITUTED Spent nuclear fuel assembly which contains dummy fuel FUEL ASSEMBLY rods that displaces an amount of water greater than or equal to the original fuel rods and/or which contains structural repairs so it can be handled by normal means.

If irradiated dummy stainless steel rods are present in the fuel assembly, the dummy/replacement rods will be considered in the site specific dose calculations.

SPENT FUEL STORAGE CASKS SFSCs are containers approved for the storage of spent (SFSCs) fuel assemblies at the ISFSI. The HI-STORM FW SFSC System consists of the OVERPACK 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 prior to and during unloading and to transfer the MPC to or from the OVERPACK.

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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-8

Term Definition UNDAMAGED FUEL ASSEMBLY UNDAMAGED FUEL ASSEMBLIES are: a) fuel assemblies 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 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 UNVERNTILATED 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.

ZR ZR means any zirconium-based fuel cladding or fuel channel material authorized for use in a commercial nuclear power plant reactor.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-9

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)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-10

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)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-11

EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Stop . . .

OR A.2.1 Verify . . .

AND A.2.2.1 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-12

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)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-13

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Perform Action B.1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not met. B.2 Perform Action B.2 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-14

EXAMPLES EXAMPLE 1.3-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One system A.1 Restore system to 7 days not within limit. within limit.

B. Required B.1 Complete action 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and B.1.

associated Completion AND Time not met.

B.2 Complete action 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months B.2.

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)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-15

EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS

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

Separate Condition entry is allowed for each component.

CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Restore 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months compliance with LCO.

B. Required B.1 Complete action 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and B.1.

associated Completion AND Time not met.

B.2 Complete action 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B.2.

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)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-16

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

TIME 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)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-17

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)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-18

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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-19

2 APPROVED CONTENTS 2.1 Fuel Specifications and Loading Conditions 2.1.1 Fuel to Be Stored in the HI-STORM FW MPC Storage System

a. UNDAMAGED FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, FUEL DEBRIS, and NON-FUEL HARDWARE meeting the limits specified in Table 2.1-1 and other referenced tables may be stored in the HI-STORM FW MPC Storage System.

b. All BWR fuel assemblies may be stored with or without ZR channels.

2.1.2 Fuel Loading Figures 2.1-1 and 2.1-2 define the regions for the MPC-37 and MPC-89 models, respectively. Figures 2.1-3 defines the cell identifications for the MPC-32ML. Figures 2.1-4 and 2.1-5 defines the cell identifications for the MPC-37P and MPC-44 models, respectively. Fuel assembly decay heat limits are specified in Section 2.2.1. Fuel assemblies shall meet all other applicable limits specified in Tables 2.1-1 through 2.1-3.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-1

3-1 3-2 3-3 3-4 2-1 2-2 2-3 3-5 3-6 2-4 1-1 1-2 1-3 2-5 3-7 3-8 2-6 1-4 1-5 1-6 2-7 3-9 3-10 2-8 1-7 1-8 1-9 2-9 3-11 3-12 2-10 2-11 2-12 3-13 3-14 3-15 3-16 Legend Region-Cell ID Figure 2.1-1: MPC-37 Region-Cell Identification Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-2

3-1 3-2 3-3 3-4 3-5 3-6 2-1 3-7 3-8 3-9 3-10 3-11 2-2 2-3 2-4 2-5 2-6 3-12 3-13 3-14 2-7 2-8 2-9 2-10 2-11 2-12 2-13 3-15 3-16 3-17 2-14 2-15 1-1 1-2 1-3 2-16 2-17 3-18 3-19 3-20 2-18 2-19 2-20 1-4 1-5 1-6 2-21 2-22 2-23 3-21 3-22 3-23 2-24 2-25 1-7 1-8 1-9 2-26 2-27 3-24 3-25 3-26 2-28 2-29 2-30 2-31 2-32 2-33 2-34 3-27 3-28 3-29 2-35 2-36 2-37 2-38 2-39 3-30 3-31 3-32 3-33 3-34 2-40 3-35 3-36 3-37 Legend Region-Cell ID 3-38 3-39 3-40 Figure 2.1-2: MPC-89 Region-Cell Identification Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-3

1-1 1-2 1-3 1-4 1-5 1-6 1-7 1-8 1-9 1-10 1-11 1-12 1-13 1-14 1-15 1-16 1-17 1-18 1-19 1-20 1-21 1-22 1-23 1-24 1-25 1-26 1-27 1-28 1-29 1-30 1-31 1-32 Figure 2.1-3: MPC-32ML Cell Identification Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-4

Quadrant 4 Quadrant 1 3-1 3-2 3-3 3-4 2-1 2-2 2-3 3-5 3-6 2-4 1-1 1-2 1-3 2-5 3-7 3-8 2-6 1-4 1-5 1-6 2-7 3-9 3-10 2-8 1-7 1-8 1-9 2-9 3-11 3-12 2-10 2-11 2-12 3-13 3-14 3-15 3-16 Quadrant 3 Quadrant 2 Figure 2.1-4: MPC-37P Cell Identification Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-5

3-1 3-2 3-3 3-4 2-1 2-2 3-5 3-6 3-7 2-3 2-4 2-5 2-6 3-8 3-9 2-7 2-8 1-1 1-2 2-9 2-10 3-10 3-11 2-11 2-12 1-3 1-4 2-13 2-14 3-12 3-13 2-15 2-16 2-17 2-18 3-14 3-15 3-16 2-19 2-20 3-17 3-18 3-19 3-20 Figure 2.1-4: MPC-44 Cell Identification Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-6

Table 2.1-1 (page 1 of 106)

Fuel Assembly Limits I. MPC MODEL: MPC-37 A. Allowable Contents

1. Uranium oxide PWR UNDAMAGED FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES meeting the criteria in Table 2.1-2 and/or FUEL DEBRIS, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):

a. Cladding Type: ZR

b. Maximum Initial Enrichment: 5.0 wt. % U-235 with soluble boron credit per LCO 3.3.1 OR burnup credit per Section 2.3

c. Post-irradiation Cooling Time and Cooling Time 1 years and meeting the equation Average Burnup Per Assembly: in Section 2.4 Assembly Average Burnup 68.2 GWD/MTU

d. Decay Heat Per Fuel Storage As specified in Section 2.2 Location:

e. Fuel Assembly Weight: 2050 lbs (including NON-FUEL HARDWARE and DFC)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-7

Table 2.1-1 (page 2 of 106)

Fuel Assembly Limits I. MPC MODEL: MPC-37 (continued)

B. Quantity per MPC: 37 FUEL ASSEMBLIES with up to twelve (12) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 3-1, 3-3 through 3-7, 3-10 through 3-14, and 3-16 (see Figure 2.1-1), OR in fuel storage locations 2-1, 2-3, 2-4, 2-5, 2-8, 2-9, 2-10, and 2-12 (see Figure 2.1-1), depending on heat load pattern, see Section 2.2.1. The remaining fuel storage locations may be filled with PWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications. For MPCs utilizing burnup credit, the MPC and DFC loading configuration must also meet the additional requirements of Section 2.3.

C. One (1) Neutron Source Assembly (NSA) is authorized for loading in the MPC-37.

D. Up to thirty (30) BRPAs BPRAs are authorized for loading in the MPC-37.

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, RCCAs, CEAs, CRAs (including, but not limited to those with hafnium), or NSAs may only be loaded in fuel storage Regions 1 and 2 (see Figure 2.1-1).

Note 2: DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected, may be stored in storage locations designated for DFCs using DFIs or DFCs. 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-8

Table 2.1-1 (page 3 of 106)

Fuel Assembly Limits II. MPC MODEL: MPC-89 A. Allowable Contents

1. Uranium oxide BWR UNDAMAGED FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES meeting the criteria in Table 2.1-3 and/or FUEL DEBRIS, with or without channels and meeting the following specifications:

a. Cladding Type: ZR

b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for the applicable INITIAL ENRICHMENT (Note 1): fuel assembly array/class.

c. Initial Maximum Rod Enrichment 5.0 wt. % U-235

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

i. Array/Class 8x8F Cooling time 10 years and an assembly average burnup 27.5 GWD/MTU.

ii. All Other Array Classes Cooling Time 1 years and meeting the equation in Section 2.4 and an assembly average burnup 65 GWD/MTU

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 Weight 850 lbs, including a DFC as well as a channel Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-9

Table 2.1-1 (page 4 of 106)

Fuel Assembly Limits II. MPC MODEL: MPC-89 (continued)

B. Quantity per MPC: 89 FUEL ASSEMBLIES with up to sixteen (16) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 3-1, 3-3, 3-4, 3-9, 3-10, 3-13, 3-16, 3-19, 3-22, 3-25, 3-28, 3-31, 3-32, 3-37, 3-38, and 3-40 (see Figure 2.1-2),

OR in fuel storage locations 2-1, 2-2, 2-6, 2-7, 2-13, 2-18, 2-23, 2-28, 2-34, 2-35, 2-39, and 2-40 (see Figure 2.1-2), depending on heat load pattern, see Section 2.2.1. The remaining fuel storage locations may be filled with BWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications.

Note 1: The lowest maximum allowable enrichment of any fuel assembly loaded in an MPC-89, based on fuel array class and fuel classification, is the maximum allowable enrichment for the remainder of the assemblies loaded in that MPC.

Note 2: DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected, may be stored in storage locations designated for DFCs using DFIs or DFCs. 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-10

Table 2.1-1 (page 5 of 610)

Fuel Assembly Limits III. MPC MODEL: MPC-32ML A. Allowable Contents

1. Uranium oxide PWR UNDAMAGED FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES meeting the criteria for array/class 16x16D in Table 2.1-2 and/or FUEL DEBRIS, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):

a. Cladding Type: ZR

b. Maximum Initial Enrichment: 5.0 wt. % U-235 with soluble boron credit per LCO 3.3.1

c. Post-irradiation Cooling Time and Cooling Time 1 years and meeting the equation Average Burnup Per Assembly: in Section 2.4 Assembly Average Burnup 68.2 GWD/MTU

d. Decay Heat Per Fuel Storage As specified in Section 2.2 Location:

e. Fuel Assembly Weight: 1858 lbs (including NON-FUEL HARDWARE and DFC)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-11

Table 2.1-1 (page 6 of 610)

Fuel Assembly Limits III. MPC MODEL: MPC-32ML (continued)

B. Quantity per MPC: 32 FUEL ASSEMBLIES with up to eight (8) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 1-1, 1-4, 1-5, 1-10, 1-23, 1-28, 1-29, and 1-32 (see Figure 2.1-3). The remaining fuel storage locations may be filled with PWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications.

C. One (1) Neutron Source Assembly (NSA) is authorized for loading in the MPC-32ML.

D. Up to thirty-two (32) BRPAs BPRAs are authorized for loading in the MPC-32ML.

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, RCCAs, CEAs, CRAs, or NSAs may only be loaded in fuel cells 1-6 through 1-9, 1-12 through 1-15, 1-18 through 1-21, and 1-24 through 1-27.

Note 2: DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected, may be stored in storage locations designated for DFCs using DFIs or DFCs. 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-12

Table 2.1-1 (page 7 of 10)

Fuel Assembly Limits IV. MPC MODEL: MPC-37P A. Allowable Contents

1. Uranium oxide PWR UNDAMAGED FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES meeting the criteria for array/class 15x15I in Table 2.1-2 and/or FUEL DEBRIS, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):

a. Cladding Type: ZR

b. Maximum Initial Enrichment: 5.0 wt. % U-235 with soluble boron credit per LCO 3.3.1 Cooling Time 1.6 years and meeting the

c. Post-irradiation Cooling Time and equation in Section 2.4 Average Burnup Per Assembly:

Assembly Average Burnup 68.2 GWD/MTU

d. Decay Heat Per Fuel Storage As specified in Section 2.2 Location:

e. Fuel Assembly Weight: 1610 lbs (including NON-FUEL HARDWARE and DFC)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-13

Table 2.1-1 (page 8 of 10)

Fuel Assembly Limits III. MPC MODEL: MPC-37P (continued)

B. Quantity per MPC: 37 FUEL ASSEMBLIES with up to twelve (12) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 3-1, 3-3 through 3-7, 3-10 through 3-14, and 3-16, OR DFCs may be stored in fuel storage locations 2-1, 2-3, 2-10, and 2-12 (see Figure 2.1-4).

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

Note 1: Fuel assemblies containing 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, RCCAs, CEAs, CRAs (including, but not limited to those with hafnium), or NSAs may only be loaded in fuel storage Regions 1 and 2 (see Figure 2.1-4).

Note 2: DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected, may be stored in storage locations designated for DFCs using DFIs or DFCs. 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-14

Table 2.1-1 (page 9 of 10)

Fuel Assembly Limits V. MPC MODEL: MPC-44 A. Allowable Contents

1. Uranium oxide PWR UNDAMAGED FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES meeting the criteria for array/class 14x14A and 14x14B in Table 2.1-2 and/or FUEL DEBRIS, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):

a. Cladding Type: ZR

b. Maximum Initial Enrichment: 5.0 wt. % U-235

c. Post-irradiation Cooling Time and Cooling Time 3 years and meeting the equation Average Burnup Per Assembly: in Section 2.4 Assembly Average Burnup 60.0 GWD/MTU

d. Decay Heat Per Fuel Storage As specified in Section 2.2 Location:

g. Fuel Assembly Weight: 1250 lbs (including and DFC)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-15

Table 2.1-1 (page 10 of 10)

Fuel Assembly Limits V. MPC MODEL: MPC-44 (continued)

B. Quantity per MPC: 44 FUEL ASSEMBLIES with up to twelve (12) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 3-1 through 3-3, 3-6, 3-9 through 3-12, 3-15, and 3-18 through 3-20 (see Figure 2.1-5). The remaining fuel storage locations may be filled with PWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications.

C. Up to twenty-two (22) BPRAs and/or WABAs are authorized for loading in the MPC-44.

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.

Note 2: DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected, may be stored in storage locations designated for DFCs using DFIs or DFCs. 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-16

Table 2.1-1: PWR Fuel Assembly Characteristics (Note 5)

Fuel Assembly No. of Fuel Rod No. of Guide and/or Array/ Class Locations (Note 4) Instrument Tubes 14x14 A 179 17 14x14 B 179 17 5

14x14 C 176 (Note 1) 15x15 B 204 21 15x15 C 204 21 15x15 D 208 17 15x15 E 208 17 15x15 F 208 17 15x15 H 208 17 216 9 15x15 I (Note 2) (Note 2) 5 16x16 A 236 (Note 1) 5 16x16 B 236 (Note 1) 16x16 C 235 21 16x16 D 236 20 (Note 3) 17x17A 264 25 17x17 B 264 25 17x17 C 264 25 17x17 D 264 25 17x17 E 265 24 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-17

Notes:

1. Each guide tube replaces four fuel rods.

2. Assemblies have one Instrument Tube and eight Guide Bars (Solid ZR). Some assemblies have up to 16 fuel rods removed or replaced by Guide Tubes

3. This fuel array/class only allowable for loading in the MPC-32ML.

4. 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.

5. Any number of fuel rods in an assembly can contain BLEU fuel. If the BLEU rods are present, the site specific dose and dose rate analyses performed under 10 CFR 72.212 should include considerations for the presence of such rods.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-18

Table 2.1-2: BWR Fuel Assembly Characteristics (Note 14)

Maximum Planar- No. of Fuel Rod Fuel Assembly Average Initial Locations (Full Length No. of Water Rods Array and Class Enrichment (wt.% or Total/Full Length) (Note 8) 235 U) (Note 11) (Note 13) 7x7 B < 4.8 49 0 1

7x7 C < 4.8 48 (Note 12) 8x8 B < 4.8 63 or 64 1 or 0 8x8 C < 4.8 62 2 1-4 8x8 D < 4.8 60 or 61 (Note 4) 8x8 E < 4.8 59 5

< 4.5 N/A 8x8 F 64 (Note 9) (Note 1) 4 8x8 G < 4.8 60 (Note 12) 74/66 9x9 A < 4.8 2 (Note 2) 1 9x9 B < 4.8 72 (Note 3) 9x9 C < 4.8 80 1 9x9 D < 4.8 79 2 9x9 E < 4.5 76 5 (Note 1) (Note 9) 9x9 F < 4.5 76 5 (Note 1) (Note 9) 1 9x9 G < 4.8 72 (Note 3) 92/78 10x10 A < 4.8 2 (Note 5) 91/83 1 10x10 B < 4.8 (Note 6) (Note 3) 5 10x10 C < 4.8 96 (Note 7)

< 4.7 92/78 10x10 F 2 (Note 10) (Note 5) 10x10 G < 4.6 96/84 5 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-19

(Note 9) (Note 7) 91/79 1 10x10 I < 4.8 (Note 15) (Note 3) 96/80 10x10 J < 4.8 1 (Note 16) 112/92 1 11x11 A < 4.8 (Note 17) (Note 3)

Notes:

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

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

3. Square, replacing nine fuel rods.

4. Variable.

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

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

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

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

9. When loading fuel assemblies classified as DAMAGED FUEL, all assemblies in the MPC are limited to 4.0 wt.% U-235.

10. When loading fuel assemblies classified as DAMAGED FUEL, all assemblies in the MPC are limited to 4.6 wt.% U-235.

11. In accordance with the definition of UNDAMAGED FUEL, certain assemblies may be limited to 3.3 wt.% U-235. When loading these fuel assemblies, all assemblies in the MPC are limited to 3.3 wt.% U-235.

12. These fuel designs do not have water rods, but instead contain solid zirc rods.

13. 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.

14. Any number of fuel rods in an assembly can be contain BLEU fuel. If the BLEU rods are present, the site specific dose and dose rate analyses performed under 10 CFR 72.212 should include considerations for the presence of such rods.

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

16. 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 or 12 fuel rods.

14.17. 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-20

2.2 Decay Heat Limits This section provides the limits on fuel assembly decay heat for storage in the HI-STORM FW System. The method to verify compliance, including examples, is provided in Chapter 13 of the HI-STORM FW FSAR.

2.2.1 Fuel Loading Decay Heat Limits for VENTILATED OVERPACK Tables 2.3-1A, 2.3-1B, and 2.3-1C provide the maximum allowable decay heat per fuel storage location for MPC-37. Tables 2.3-2A and 2.3-2B provide the maximum allowable decay heat per fuel storage location for MPC-89. Tables 2.3-1A and 2.3-7A provide the maximum allowable decay heat per fuel storage location for MPC-37P. Table 2.3-8A provides the maximum allowable decay heat per fuel storage location for MPC-44. No drying time limits are required for decay heat values meeting the limits in these tables when using FHD to dry moderate or high burnup fuel and when using VDS to dry moderate burnup fuel. Drying time limits apply when using VDS to dry high burnup fuel with decay heat values meeting the limits in these tables. Tables 2.3-3 and 2.3-4 provide the maximum allowable decay heat per fuel storage location for MPC-37 and MPC-89, respectively, with no drying time limits imposed, when using VDS to dry high burnup fuel.

Table 2.3-5 provides the maximum allowable decay heat per fuel storage location for the MPC-32ML for both FHD and VDS drying. Tables 2.3-7B and 2.3-8B provide the maximum allowable decay heat per fuel storage location for the MPC-37P and MPC-44, respectively, with no drying time limits imposed, when using VDS to dry high burnup fuel.

The per cell limits in these tables apply to cells containing undamaged fuel or damaged fuel in DFCs/DFIs or fuel debris in DFCs.

Figures 2.3-1 through 2.3-15 provide alternative loading patterns for the MPC-37 and MPC-89, with undamaged fuel and a combination of undamaged fuel and damaged fuel in DFCs/DFIs and fuel debris in DFCs. The per cell limits in these figures are applicable when using vacuum drying or FHD to dry moderate or high burnup fuel in accordance with Table 3.3-1. The MPC-37 patterns are based on the fuel length to be stored in the MPC, see Table 2.3-6.

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.

2.2.2 Fuel Loading Decay Heat Limits for UNVENTILATED OVERPACK Tables 2.3-9A and 2.3-9B provide the maximum allowable decay heat per fuel storage location for MPC-37. Tables 2.3-10A and 2.3-10B provide the maximum allowable decay heat per fuel storage location for MPC-89. Table 2.3-13 provides the maximum allowable decay heat per fuel storage location for MPC-44. The per cell limits in these tables apply to cells containing undamaged fuel or damaged fuel in DFCs/DFIs or fuel debris in DFCs.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-21

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.

2.2.3 Variable Fuel Height for MPC-37 and MPC-44 2.2.3.1 For fuel with a longer active fuel length than the reference fuel (144 inches), the maximum total heat load, maximum quadrant heat load limits and specific heat load limits in each cell, may be increased by the ratio SQRT(L/144), where L is the active length of the fuel in inches.

2.2.3.2 For fuel with a shorter active fuel length than the reference fuel (144 inches), the maximum total heat load, maximum quadrant heat load limits and specific heat load limits in each cell, shall be reduced linearly by the ratio L/144, where L is the active fuel length of the fuel in inches.

2.2.4 Variable Fuel Height for MPC-89 2.2.4.1 For fuel with a longer active fuel length than the reference fuel (150 inches), the maximum total heat load, maximum quadrant heat load limits and specific heat load limits in each cell, may be increased by the ratio SQRT(L/150), where L is the active length of the fuel in inches.

2.2.1.12.2.4.2 For fuel with a shorter active fuel length than the reference fuel (150 inches), the total heat load, quadrant heat load limits and specific heat load limits in each cell, shall be reduced linearly by the ratio L/150, where L is the active fuel length of the fuel in inches.

2.2.22.2.5 Decay Heat Limit Compliance 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-22

Table 2.3-1A: MPC-37 and MPC-37P Heat Load Data (See Figure 2.1-1)

Number of Regions: 3 Number of Storage Cells: 37 Maximum Design Basis Heat Load (kW): 44.09 (Pattern A); 45.0 (Pattern B)

Region No. Decay Heat Limit per Cell, Number of Cells Decay Heat Limit per kW per Region Region, kW Pattern A Pattern B Pattern A Pattern B 1 1.05 1.0 9 9.45 9.0 2 1.70 1.2 12 20.4 14.4 3 0.89 1.35 16 14.24 21.6 Table 2.3-1B: MPC-37 Heat Load Data (See Figure 2.1-1)

Number of Regions: 3 Number of Storage Cells: 37 90% of Pattern A - Sub-design Heat Load (kW): 39.68 Region No. Decay Heat Limit per Cell, Number of Cells Decay Heat Limit per kW per Region Region, kW 1 0.945 9 8.505 2 1.530 12 18.36 3 0.801 16 12.816 Table 2-.3-1C: MPC-37 Heat Load Data (See Figure 2.1-1)

Number of Regions: 3 Number of Storage Cells: 37 80% of Pattern A - Sub-design Heat Load (kW): 35.27 Region No. Decay Heat Limit per Cell, Number of Cells Decay Heat Limit per kW per Region Region, kW 1 0.84 9 7.56 2 1.36 12 16.32 3 0.712 16 11.392 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-23

Table 2.3-2A: MPC-89 Heat Load Data (See Figure 2.1-2)

Number of Regions: 3 Number of Storage Cells: 89 Maximum Design Basis Heat Load: 46.36 kW Region No. Decay Heat Limit per Number of Cells Decay Heat Limit per Cell, kW per Region Region, kW 1 0.44 9 3.96 2 0.62 40 24.80 3 0.44 40 17.60 Table 2.3-2B: MPC-89 Heat Load Data (See Figure 2.1-2)

Number of Regions: 3 Number of Storage Cells: 89 80% Sub-design Heat Load (kW): 37.1 Region No. Decay Heat Limit per Cell, Number of Cells Decay Heat Limit per kW per Region Region, kW 1 0.352 9 3.168 2 0.496 40 19.84 3 0.352 40 14.08 Table 2.3-3: MPC-37 Heat Load Data (See Figure 2.1-1)

Number of Regions: 3 Number of Storage Cells: 37 Maximum Heat Load: 29.6 Region No. Decay Heat Limit per Number of Cells Decay Heat Limit per Cell, W per Region Region, kW 1 800 9 7.2 2 800 12 9.6 3 800 16 12.8 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-24

Table 2.3-4: MPC-89 Heat Load Data (See Figure 2.1-2)

Number of Regions: 3 Number of Storage Cells: 89 Maximum Heat Load: 30.0kW Region No. Decay Heat Limit per Number of Cells Decay Heat Limit per Cell, W per Region Region, kW 1 337 9 3.03 2 337 40 13.48 3 337 40 13.48 Table 2.3-5: MPC-32ML Heat Load Data Number of Regions: 1 Number of Storage Cells: 32 Pattern Maximum Heat Load, kW Decay Heat Limit per Cell, kW Pattern A 44.16 1.380 Pattern B 28.70 0.897 Table 2.3-6: PWR Fuel Length Categories Category Length Range Short Fuel 128 inches L < 144 inches Standard Fuel 144 inches L < 168 inches Long Fuel L 168 inches Notes:

1. L means "nominal active fuel length". The nominal, unirradiated active fuel length of the PWR fuel assembly is used to designate it as short, standard and long.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-25

Table 2.3-7A: MPC-37P Heat Load Data for Ventilated Overpack (see Figure 2.1-4)

Number of Storage Cells: 37 Maximum Design Basis Heat Load (kW): 45 Maximum Quadrant Heat Load (kW): 11.25 Decay Heat Limit per Cell (kW): See Figures 2-19 and 2-20 Note:

1. Decay heat limit per cell for cells containing damaged fuel or fuel debris is equal to the decay heat limit per cell of the region where the damaged fuel or fuel debris is permitted to be stored.

Table 2.3-7B: MPC-37P Heat Load Data for Ventilated Overpack (see Figure 2.1-4)

Number of Regions: 3 Number of Storage Cells: 37 Maximum Heat Load: 33.3 Region No. Decay Heat Limit per Number of Cells Decay Heat Limit per Cell, W per Region Region, kW 1 900 9 8.1 2 900 12 10.8 3 900 16 14.4 Table 2.3-8A: MPC-44 Heat Load Data for Ventilated Overpack (See Figure 2.1-5)

Number of Regions: 1 Number of Storage Cells: 44 Maximum Total Heat Load (kW): 44 Maximum Decay Heat Limit per Cell (kW): 1.0 Note:

1. There is a 5% decay heat penalty per cell for cells containing DFCs and/or DFIs.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-26

Table 2.3-8B: MPC-44 Heat Load Data for Ventilated Overpack (See Figure 2.1-5)

Number of Regions: 1 Number of Storage Cells: 44 Maximum Total Heat Load (kW): 30 Maximum Decay Heat Limit per Cell (kW): 0.682 Table 2.3-9A: MPC-37 Heat load Data for Unventilated Overpack (See Figure 2.1-1)

Number of Regions: 3 Number of Storage Cells: 37 Maximum Total Heat Load (kW): 29 Maximum Section Heat Load (kW): 3.625 (Note 1)

Region No. Decay Heat Limit per Cell, Number of Cells Decay Heat Limit per kW (Note 2) per Region Region, kW 1 0.784 9 7.054 2 0.784 12 9.405 3 0.784 16 12.541 Note 1: Figure 2.1-1 identifies the cell locations, and Table 2.3-11 identifies the cells included in the heat load for each section Note 2: Maximum total heat load, maximum section heat load and specific cell heat load limits may need to be adjusted in accordance with Section 2.2.3.

Note 3: This pattern can be modified to develop regionalized patterns in accordance with the requirements in Table 2.3-9B.

Table 2.3-9B: MPC-37 Requirements on Developing Regionalized Heat Load Patterns for Unventilated Overpack (See Figure 2.1-1)

1. Pattern-specific total heat load must be equal to 29 kW

2. Section Heat Load must be equal to 3.625 kW, calculated per Table 2.3-11, and pattern must be 1/8th symmetric

3. Maximum Allowable Decay Heat per Cell in Region 1 is 0.784 kW

4. Maximum Allowable Decay Heat per Cell in Region 2 is 1.568 kW

5. Maximum Allowable Decay Heat per Cell in Region 3 is 1.568 kW

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

7. Pattern-specific decay heat for any storage cell in Region 1 may be determined by reducing the allowable in Region 1 of Table 2.3-9A by and pattern-specific decay heat for any storage cell in Regions 2 and 3 may be determined by increasing the allowable in Region 2 and/or Region 3 of Table 2.3-9A by the same .

8. Pattern-specific decay heat for any storage cell in Region 2 may be determined by reducing the allowable in Region 2 of Table 2.3-9A by and pattern-specific decay heat for any storage cell in Region 3 may be determined by increasing the allowable in Region 3 of Table 2.3-9A by the same . This may not be added to other cells in Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-27

Region 2.

9. Items 1 through 8 need to be scaled in accordance with Section 2.2.4 for non-standard active fuel lengths.

General Note - The limits developed for the patterns are maximums, and any assembly with a heat load less than those limits can be loaded in the applicable cell, provided it meets all other CoC requirements.

Table 2.3-10A: MPC-89 Heat load Data for Unventilated Overpack (See Figure 2.1-2)

Number of Regions: 3 Number of Storage Cells: 89 Maximum Total Heat Load (kW): 29 Maximum Section Heat Load (kW): 3.625 (Note 1)

Region No. Decay Heat Limit per Cell, Number of Cells Decay Heat Limit per kW (Note 2) per Region Region, kW 1 0.326 9 2.932 2 0.326 40 13.034 3 0.326 40 13.034 Note 1: Figure 2.1-2 identifies the cell locations, and Table 2.3-12 identifies the cells included in the heat load for each section.

Note 2: Maximum total heat load, maximum section heat load and specific cell heat load limits may need to be adjusted in accordance with Section 2.2.4.

Note 3: This pattern can be modified to develop regionalized patterns in accordance with the requirements in Table 2.3-10B.

Table 2.3-10B: MPC-89 Requirements on Developing Regionalized Heat Load Patterns for Unventilated Overpack (See Figure 2.1-2)

1. Pattern-specific total heat load must be equal to 29 kW

2. Section Heat Load must be equal to 3.625 kW, calculated per Table 2.3-12, and pattern must be 1/8th symmetric

3. Maximum Allowable Decay Heat per Cell in Region 1 is 0.326 kW

4. Maximum Allowable Decay Heat per Cell in Region 2 is 0.652 kW

5. Maximum Allowable Decay Heat per Cell in Region 3 is 0.652 kW

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

7. Pattern-specific decay heat for any storage cell in Region 1 may be determined by reducing the allowable in Region 1 of Table 2.3-10A by and pattern-specific decay heat for any storage cell in Regions 2 and 3 may be determined by increasing the allowable in Region 2 and/or Region 3 of Table 2.3-10A by the same .

8. Pattern-specific decay heat for any storage cell in Region 2 may be determined by Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-28

reducing the allowable in Region 2 of Table 2.3-10A by and pattern-specific decay heat for any storage cell in Region 3 may be determined by increasing the allowable in Region 3 of Table 2.3-10A by the same . This may not be added to other cells in Region 2.

9. Items 1 through 8 need to be scaled in accordance with Section 2.2.4 for non-standard active fuel lengths.

General Note - The limits developed for the patterns are maximums, and any assembly with a heat load less than those limits can be loaded in the applicable cell, provided it meets all other CoC requirements.

Table 2.3-11: Section Heat Load Calculations for MPC-37 Section Equation for Section Heat Load (Note 1)

Section 1 Q3-1 + Q2-1 + 1/2Q3-2 + 1/2Q3-4 + 1/2Q2-2 + 1/2Q1-1 + 1/2Q1-2 + 1/8Q1-5 Section 2 Q3-3 + Q2-3 + 1/2Q3-2 + 1/2Q3-5 + 1/2Q2-2 + 1/2Q1-3 + 1/2Q1-2 + 1/8Q1-5 Section 3 Q2-5 + Q3-7 + 1/2Q1-6 + 1/2Q3-5 + 1/2Q2-7 + 1/2Q1-3 + 1/2Q3-9 + 1/8Q1-5 Section 4 Q2-9 + Q3-11 + 1/2Q1-6 + 1/2Q1-9 + 1/2Q2-7 + 1/2Q3-13 + 1/2Q3-9 + 1/8Q1-5 Section 5 Q2-12 + Q3-16 + 1/2Q1-8 + 1/2Q1-9 + 1/2Q2-11 + 1/2Q3-13 + 1/2Q3-15 + 1/8Q1-5 Section 6 Q2-10 + Q3-14 + 1/2Q1-8 + 1/2Q1-7 + 1/2Q2-11 + 1/2Q3-12 + 1/2Q3-15 + 1/8Q1-5 Section 7 Q2-8 + Q3-10 + 1/2Q1-4 + 1/2Q1-7 + 1/2Q2-6 + 1/2Q3-12 + 1/2Q3-8 + 1/8Q1-5 Section 8 Q2-4 + Q3-6 + 1/2Q1-4 + 1/2Q1-1 + 1/2Q2-6 + 1/2Q3-4 + 1/2Q3-8 + 1/8Q1-5 Note:

1. QX-Y is the heat load in kW in cell ID (X-Y), identified in Figure 2.1-1 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-29

Table 2.3-12: Section Heat Load Calculations for MPC-89 Section Equation for Section Heat Load1 Section 1 Q3-1 + Q3-4 +Q3-5 + Q3-6 +Q2-2 + Q2-3 + Q2-9 + 1/2Q3-2 + 1/2Q2-1 + 1/2Q2-4 + 1/2Q2-10 + 1/2Q1-2 + 1/2Q1-1 +

1/2Q2-8 + 1/2Q2-11 + 1/8Q1-5 Section 2 Q3-3 + Q3-7 +Q3-8 + Q3-9 +Q2-5 + Q2-6 + Q2-11 + 1/2Q3-2 + 1/2Q2-1 + 1/2Q2-4 + 1/2Q2-10 + 1/2Q1-2 + 1/2Q1-3 + 1/2Q2-12 + 1/2Q3-12 + 1/8Q1-5 Section 3 Q3-13 + Q2-13 +Q3-15 + Q2-16 +Q2-17 + Q3-18 + Q3-19 + 1/2Q1-6 + 1/2Q2-21 + 1/2Q2-22 + 1/2Q2-23 + 1/2Q3-21 + 1/2Q1-3 + 1/2Q2-12 + 1/2Q3-12 + 1/8Q1-5 Section 4 Q2-26 + Q2-27 +Q3-24 + Q3-25 +Q2-34 + Q3-27 + Q3-31 + 1/2Q1-6 + 1/2Q2-21 + 1/2Q2-22 + 1/2Q2-23 + 1/2Q3-21 + 1/2Q1-9 + 1/2Q2-33 + 1/2Q3-30 + 1/8Q1-5 Section 5 Q2-32 + Q2-38 +Q2-39 + Q3-35 +Q2-36 + Q3-37 + Q3-40 + 1/2Q1-8 + 1/2Q2-31 + 1/2Q2-37 + 1/2Q2-40 + 1/2Q3-39 + 1/2Q1-9 + 1/2Q2-33 + 1/2Q3-30 + 1/8Q1-5 Section 6 Q2-30 + Q2-35 +Q2-36 + Q3-32 +Q2-33 + Q3-34 + Q3-38 + 1/2Q1-8 + 1/2Q2-31 + 1/2Q2-37 + 1/2Q2-40 + 1/2Q3-39 + 1/2Q1-7 + 1/2Q2-29 + 1/2Q3-29 + 1/8Q1-5 Section 7 Q2-25 + Q2-24 +Q3-23 + Q3-22 +Q2-28 + Q3-26 + Q3-28 + 1/2Q1-4 + 1/2Q2-20 + 1/2Q2-19 + 1/2Q2-18 + 1/2Q3-20 + 1/2Q1-7 + 1/2Q2-29 + 1/2Q3-29 + 1/8Q1-5 Section 8 Q2-15 + Q2-14 +Q3-17 + Q3-16 +Q2-7 + Q3-14 + Q3-10 + 1/2Q1-4 + 1/2Q2-20 + 1/2Q2-19 + 1/2Q2-18 + 1/2Q3-20

+ 1/2Q1-1 + 1/2Q2-8 + 1/2Q3-11 + 1/8Q1-5 Note:

1. QX-Y is the heat load in kW in cell ID (X-Y), identified in Figure 2.1-2 Table 2.3-13: MPC-44 Heat Load Data for Unventilated Overpack (See Figure 2.1-5)

Number of Regions: 1 Number of Storage Cells: 44 Maximum Total Heat Load (kW): 28 Maximum Decay Heat Limit per Cell (kW): 0.636 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-30

0.45 0.45 0.45 (D/F) (D/F) 0.45 0.45 3.2 0.5 3.2 (D/F) (D/F) 0.6 0.6 2.4 0.5 0.6 0.5 2.4 (D/F) (D/F) 0.6 0.5 0.6 0.5 0.6 0.5 0.6 0.6 0.6 2.4 0.5 0.6 0.5 2.4 (D/F) (D/F) 0.45 0.45 3.2 0.5 3.2 (D/F) (D/F) 0.45 0.45 0.45 (D/F) (D/F)

Figure 2.3-1: Loading Pattern 37C1 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC Short Fuel per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-31

0.45 0.45 0.45 3.2 3.2 0.45 Empty 0.45 (D) (D) 2.4 2.4 0.6 Empty 0.6 Empty 0.6 (D) (D) 0.6 0.5 0.6 0.5 0.6 0.5 0.6 2.4 2.4 0.6 Empty 0.6 Empty 0.6 (D) (D) 3.2 3.2 0.45 Empty 0.45 (D) (D) 0.45 0.45 0.45 Figure 2.3-2: Loading Pattern 37C2 for MPC-37 Containing Undamaged and Damaged Fuel in DFC/DFI/, Short Fuel per Cell Heat Load Limits (All storage cell heat loads are in kW, Undamaged Fuel or Damaged Fuel in a DFC and/or using DFIs may be stored in cells denoted by D. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-32

0.45 0.45 0.45 3.2 3.2 0.45 Empty 0.45 (D/F) (D/F) 0.6 2.4 Empty 0.6 Empty 2.4 0.6 0.6 0.5 0.6 0.5 0.6 0.5 0.6 0.6 2.4 Empty 0.6 Empty 2.4 0.6 3.2 3.2 0.45 Empty 0.45 (D/F) (D/F) 0.45 0.45 0.45 Figure 2.3-3: Loading Pattern 37C3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Short Fuel per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-33

0.55 0.55 0.55 (D/F) (D/F) 0.55 0.55 3.2 0.55 3.2 (D/F) (D/F) 0.75 0.75 2.4 0.55 0.65 0.55 2.4 (D/F) (D/F) 0.75 0.55 0.65 0.55 0.65 0.55 0.75 0.75 0.75 2.4 0.55 0.65 0.55 2.4 (D/F) (D/F) 0.55 0.55 3.2 0.55 3.2 (D/F) (D/F) 0.55 0.55 0.55 (D/F) (D/F)

Figure 2.3-4: Loading Pattern 37D1 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, Standard Fuel per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-34

0.55 0.55 0.55 3.2 3.2 0.55 Empty 0.55 (D) (D) 2.4 2.4 0.75 Empty 0.65 Empty 0.75 (D) (D) 0.75 0.55 0.65 0.55 0.65 0.55 0.75 2.4 2.4 0.75 Empty 0.65 Empty 0.75 (D) (D) 3.2 3.2 0.55 Empty 0.55 (D) (D) 0.55 0.55 0.55 Figure 2.3-5: Loading Pattern 37D2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, Standard Fuel per Cell Heat Load Limits (All storage cell heat loads are in kW, D Undamaged Fuel or Damaged Fuel in a DFC and/or using DFIs may be stored in cells denoted by D. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-35

0.55 0.55 0.55 3.2 3.2 0.55 Empty 0.55 (D/F) (D/F) 0.75 2.4 Empty 0.65 Empty 2.4 0.75 0.75 0.55 0.65 0.55 0.65 0.55 0.75 0.75 2.4 Empty 0.65 Empty 2.4 0.75 3.2 3.2 0.55 Empty 0.55 (D/F) (D/F) 0.55 0.55 0.55 Figure 2.3-6: Loading Pattern 37D3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Standard Fuel per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-36

0.65 0.65 0.65 (D/F) (D/F) 0.65 0.65 3.5 0.65 3.5 (D/F) (D/F) 0.85 0.85 2.6 0.65 0.75 0.65 2.6 (D/F) (D/F) 0.85 0.85 0.65 0.75 0.65 0.75 0.65 0.85 0.85 2.6 0.65 0.75 0.65 2.6 (D/F) (D/F) 0.65 0.65 3.5 0.65 3.5 (D/F) (D/F) 0.65 0.65 0.65 (D/F) (D/F)

Figure 2.3-7: Loading Pattern 37E1 for MPC-37 Loading Pattern for MPCs Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, Long Fuel per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-37

0.65 0.65 0.65 3.5 3.5 0.65 Empty 0.65 (D) (D) 2.6 2.6 0.85 Empty 0.75 Empty 0.85 (D) (D) 0.85 0.65 0.75 0.65 0.75 0.65 0.85 2.6 2.6 0.85 Empty 0.75 Empty 0.85 (D) (D) 3.5 3.5 0.65 Empty 0.65 (D) (D) 0.65 0.65 0.65 Figure 2.3-8: Loading Pattern 37E2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, Long Fuel per Cell Heat Load Limits (All storage cell heat loads are in kW, D means Undamaged Fuel or Damaged Fuel in a DFC and/or using DFIs may be stored in cells denoted by D. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-38

0.65 0.65 0.65 3.5 3.5 0.65 Empty 0.65 (D/F) (D/F) 0.85 2.6 Empty 0.75 Empty 2.6 0.85 0.85 0.65 0.75 0.65 0.75 0.65 0.85 0.85 2.6 Empty 0.75 Empty 2.6 0.85 3.5 3.5 0.65 Empty 0.65 (D/F) (D/F) 0.65 0.65 0.65 Figure 2.3-9: Loading Pattern 37E3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Long Fuel per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-39

0.25 0.25 0.25 (D/F) (D/F) 0.25 0.25 0.25 0.25 1.45 0.25 0.25 (D/F) (D/F) 0.25 0.25 0.25 1.45 0.9 0.9 0.9 1.45 0.25 (D/F) (D/F) 0.25 1.45 0.32 0.32 0.32 0.32 0.32 1.45 0.25 0.25 0.25 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 (D/F) (D/F) 0.25 1.45 0.9 0.32 0.32 0.32 0.32 0.32 0.9 1.45 0.25 0.25 0.25 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 (D/F) (D/F) 0.25 1.45 0.32 0.32 0.32 0.32 0.32 1.45 0.25 0.25 0.25 0.25 1.45 0.9 0.9 0.9 1.45 0.25 (D/F) (D/F) 0.25 0.25 0.25 0.25 1.45 0.25 0.25 (D/F) (D/F) 0.25 0.25 0.25 (D/F) (D/F)

Figure 2.3-10: Loading Pattern 89A1 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-40

0.25 0.25 0.25 1.45 0.25 0.25 0.25 0.25 0.25 0.25 (D/F) 1.45 1.45 0.25 0.25 0.9 0.9 0.9 0.25 0.25 (D/F) (D/F) 1.45 1.45 0.25 Empty 0.32 0.32 0.32 Empty 0.25 (D/F) (D/F) 0.25 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 0.25 1.45 1.45 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 (D/F) (D/F) 0.25 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 0.25 1.45 1.45 0.25 Empty 0.32 0.32 0.32 Empty 0.25 (D/F) (D/F) 1.45 1.45 0.25 0.25 0.9 0.9 0.9 0.25 0.25 (D/F) (D/F) 1.45 0.25 0.25 0.25 0.25 0.25 0.25 (D/F) 0.25 0.25 0.25 Figure 2.3-11: Loading Pattern 89A2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-41

0.11 0.11 0.47 (D/F) (D/F) 0.19 0.19 0.23 0.68 1.46 0.68 0.23 (D/F) (D/F) 0.25 0.25 0.27 1.42 1.05 0.40 1.05 1.42 0.27 (D/F) (D/F) 0.23 1.44 0.29 0.31 0.33 0.31 0.29 1.44 0.23 0.10 0.10 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 (D/F) (D/F) 0.40 1.46 0.47 0.33 0.21 0.10 0.21 0.33 0.47 1.46 0.40 0.10 0.10 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 (D/F) (D/F) 0.23 1.44 0.29 0.31 0.33 0.31 0.29 1.44 0.23 0.25 0.25 0.27 1.42 1.05 0.40 1.05 1.42 0.27 (D/F) (D/F) 0.19 0.19 0.23 0.68 1.46 0.68 0.23 (D/F) (D/F) 0.11 0.11 0.47 (D/F) (D/F)

Figure 2.3-12: Loading Pattern 89B1 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-42

0.11 0.47 0.11 1.46 0.19 0.23 0.68 0.68 0.23 0.19 (D/F) 1.42 1.42 0.25 0.27 1.05 0.40 1.05 0.27 0.25 (D/F) (D/F) 1.44 1.44 0.23 Empty 0.31 0.33 0.31 Empty 0.23 (D/F) (D/F) 0.10 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 0.10 1.46 1.46 0.40 0.47 0.33 0.21 0.10 0.21 0.33 0.47 0.40 (D/F) (D/F) 0.10 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 0.10 1.44 1.44 0.23 Empty 0.31 0.33 0.31 Empty 0.23 (D/F) (D/F) 1.42 1.42 0.25 0.27 1.05 0.40 1.05 0.27 0.25 (D/F) (D/F) 1.46 0.19 0.23 0.68 0.68 0.23 0.19 (D/F) 0.11 0.47 0.11 Figure 2.3-13: Loading Pattern 89B2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-43

0.64 0.64 0.95 (D/F) (D/F) 1.37 1.37 3.03 1.7 3.03 (D/F) (D/F) 0.86 0.86 2.64 Empty 0.73 Empty 2.64 (D/F) (D/F) 0.95 2.43 0.79 0.22 0.79 2.43 0.95 0.86 0.86 2.64 Empty 0.73 Empty 2.64 (D/F) (D/F) 1.37 1.37 3.03 1.7 3.03 (D/F) (D/F) 0.64 0.64 0.95 (D/F) (D/F)

Figure 2.3-14: Loading Pattern 1 for MPC-37P (All Storage cell heat loads are in kW. Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-44

0.64 0.95 0.64 3.03 3.03 1.37 1.7 1.37 (D/F) (D/F) 0.86 2.64 Empty 0.73 Empty 2.64 0.86 0.95 2.43 0.79 0.22 0.79 2.43 0.95 0.86 2.64 Empty 0.73 Empty 2.64 0.86 3.03 3.03 1.37 1.7 1.37 (D/F) (D/F) 0.64 0.95 0.64 Figure 2.3-15: Loading Pattern 2 for MPC-37P (All Storage cell heat loads are in kW. Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-45

2.3 Burnup Credit Criticality control during loading of the MPC-37 and MPC-37P is achieved through either meeting the soluble boron limits in LCO 3.3.1 OR verifying that the assemblies meet the minimum burnup requirements in Table 2.4-1.

For those spent fuel assemblies that need to meet the burnup requirements specified in Table 2.4-1, a burnup verification shall be performed in accordance with either Method A OR Method B described below.

2.3.1 Method A: Burnup Verification Through Quantitative Burnup Measurement For each assembly in the MPC-37 and MPC-37P where burnup credit is required, the minimum burnup is determined from the burnup requirement applicable to the loading configuration chosen for the cask (see Table 2.4-1). A measurement is then performed that confirms that the fuel assembly burnup exceeds this minimum burnup. The measurement technique may be calibrated to the reactor records for a representative set of assemblies. The assembly burnup value to be compared with the minimum required burnup should be the measured burnup value as adjusted by reducing the value by a combination of the uncertainties in the calibration method and the measurement itself.

2.3.2 Method B: Burnup Verification Through an Administrative Procedure and Qualitative Measurements Depending on the location in the basket, assemblies loaded into a specific MPC-37 and MPC-37P can either be fresh, or have to meet a single minimum burnup value. The assembly burnup value to be compared with the minimum required burnup should be the reactor record burnup value as adjusted by reducing the value by the uncertainties in the reactor record value. An administrative procedure shall be established that prescribes the following steps, which shall be performed for each cask loading:

a. Based on a review of the reactor records, all assemblies in the spent fuel pool that have a burnup that is below the minimum required burnup of the loading curve for the cask to be loaded are identified.

b. After the cask loading, but before the release for shipment of the cask, the presence and location of all those identified assemblies is verified, except for those assemblies that have been loaded as fresh assemblies into the cask.

c. An independent, third-party verification of the loading process, including the fuel selection process and generation of the fuel move instructions Additionally, for all assemblies to be loaded that are required to meet a minimum burnup, a qualitative verification shall be performed that verifies that the assembly is not a fresh assembly.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-46

Table 2.4-1: Polynomial Functions for the Minimum Burnup as a Function of Initial Enrichment Minimum Burnup (GWd/mtU)

Assembly Configuration Cooling as a Function of the Classes (Note 1) Time, years Initial Enrichment (wt% 235U) 3.0 and f(x) = -7.9224e-02

x^3 -7.6419e-01

x^2

<7.0 +2.2411e+01

x^1 -4.1183e+01 15x15B, C, Uniform f(x) = +1.3212e-02

x^3 -1.6850e+00

x^2 D, E, F, H, I 7.0

+2.4595e+01

x^1 -4.2603e+01 and 3.0 and f(x) = +3.6976e-01

x^3 -5.8233e+00

x^2 17x17A, B,

<7.0 +4.0599e+01

x^1 -5.8346e+01 C, D, E Regionalized f(x) = +3.3423e-01

x^3 -5.1647e+00

x^2 7.0

+3.6549e+01

x^1 -5.2348e+01 3.0 and f(x) = -1.0361e+00

x^3 +1.1386e+01 *

<7.0 x^2 -2.9174e+01

x^1 +2.0850e+01 Uniform f(x) = -9.6572e-01

x^3 +1.0484e+01

x^2 7.0

-2.5982e+01

x^1 +1.7515e+01 3.0 and f(x) = -2.1456e-01

x^3 +2.4668e+00

x^2 16x16A, B,

<7.0 +2.1381e+00

x^1 -1.2560e+01 C

f(x) = -5.9154e-01

x^3 +5.8403e+00

x^2 7.0 Regionalized -6.9339e+00

x^1 -4.7951e+00 Combined f(x) = -4.9680e-01

x^3 +4.9471e+00

x^2 (Note 2)

-4.2373e+00

x^1 -7.3936e+00

(>3.0)

Notes:

1. Uniform configuration refers to Configuration 1 in Table 2.4-2. Regionalized configuration refers to Configuration 2, 3, or 4 in Table 2.4-2.

2. The combined cooling time loading curve is applicable for fuel with above 3 years cooling time.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-47

Table 2.4-2: Burnup Credit Configurations Configuration Description Configuration 1 Spent UNDAMAGED fuel assemblies are placed in all positions of the basket Configuration 2 Fresh UNDAMAGED fuel assemblies are placed in locations 3-4, 3-5, 3-12, and 3-13 (see Figure 2.1-1); spent UNDAMAGED fuel assemblies are placed in the remaining positions Configuration 3 Damaged Fuel Containers (DFCs) and/or Damaged Fuel Isolators (DFIs) with spent DAMAGED fuel assemblies are placed in locations 3-1, 3-3, 3-4, 3-5, 3-6, 3-7, 3-10, 3-11, 3-12, 3-13, 3-14, and 3-16 (see Figure 2.1-1); spent UNDAMAGED fuel assemblies are placed in the remaining positions Configuration 4 DFCs with Damaged Fuel and/or fresh FUEL DEBRIS are placed in locations 3-1, 3-7, 3-10, and 3-16 with locations 2-1, 2-5, 2-8, and 2-12 (see Figure 2.1-1) empty; spent UNDAMAGED fuel assemblies are placed in the remaining positions Table 2.4-3: In-Core Operating Requirements Specific Moderator Fuel Assembly Soluble Boron Power Temperature Temperature Type (ppm)

(MW/mtU) (K) (K)

Bounding Values (for Design Basis Calculations) 15x15D, E, F, 47.36 604 1169 1000 H

15x15B, C 52.33 620 1219 1000 (Note 1) 16x16A, B 51.90 608 1113 1000 17x17A, B, C, 61.61 620 1181 1000 D, E Note:

1. The same core operating parameters are assumed for the 15x15I and 16x16C fuel assembly types.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-48

2.4 Burnup and Cooling Time Qualification Requirements 2.4.1 Burnup and Cooling Time for MPC-32ML Burnup and cooling time limits for fuel assemblies authorized for loading into the MPC-32ML are provided in Table 2.5-1. Burnup and cooling time limits for fuel assemblies authorized for loading according to only the alternative loading patterns shown in Figures 2.3-1 through 2.3-9 (MPC-37) and Figures 2.3-10 through 2.3-13 (MPC-89) are provided in Table 2.5-2.

The burnup and cooling time for every fuel loaded into the MPC-32 ML must satisfy the following equation:

Ct = A Bu3 + BBu2 + C Bu + D where, Ct = Minimum cooling time (years)

Bu = Assembly-average burnup (MWd/mtU)

A,B,C,D =Polynomial coefficients listed in the below tTables 2.5-1 and 2.5-2 Minimum cooling time must also meet limits specified in Table 2.1-1. If the calculated Ct is less than the cooling time limit in Table 2.1-1, the minimum cooling time in Table 2.1-1 is used.

2.4.2 Burnup and Cooling Time for MPC-37P and MPC-44 Burnup and cooling time limits for fuel assemblies authorized for loading into the MPC-37P and MPC-44 are provided in Table 2.5-3.

The burnup and cooling time for every fuel loaded into the MPC-37P and MPC-44 must satisfy the following equation:

Ct = A Bu4 + BBu3 + C Bu2 + D Bu + E where, Ct = Minimum cooling time (years)

Bu = Assembly-average burnup (MWd/mtU)

A,B,C,D,E =Polynomial coefficients listed in Tables 2.5-3 Table 2.5-1: Burnup and Cooling Time Fuel Qualification Requirements for MPC-32ML A B C D 6.7667E-14 -36736E-09 8.1319E-05 2.7951E+00 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-49

Table 2.5-2: Burnup and Cooling Time Fuel Qualification Requirements for MPC-37 and MPC-89 Cell Decay Heat Load Polynomial Coefficients Limit (kW)

A B C D (Note 1)

MPC-37 0.85 1.68353E-13 -9.65193E-09 2.69692E-04 2.95915E-01 0.85 < decay heat 3.5 1.19409E-14 -1.53990E-09 9.56825E-05 -3.98326E-01 MPC-89 0.32 1.65723E-13 -9.28339E-09 2.57533E-04 3.25897E-01 0.32 < decay heat 0.5 3.97779E-14 -2.80193E-09 1.36784E-04 3.04895E-01 0.5 < decay heat 0.75 1.44353E-14 -1.21525E-09 8.14851E-05 3.31914E-01 0.75 < decay heat 1.1 -7.45921E-15 1.09091E-09 -1.14219E-05 9.76224E-01 1.1 < decay heat 1.45 3.10800E-15 -7.92541E-11 1.56566E-05 6.47040E-01 1.45 < decay heat 1.6 -8.08081E-15 1.23810E-09 -3.48196E-05 1.11818E+00 Note:

1. For BLEU fuel, coefficient D is increased by 1.

Table 2.5-3: Burnup and Cooling Time Fuel Qualification Requirements for MPC-37P and MPC-44 Cell Decay Heat Polynomial Coefficients Load Limit (kW)

A B C D E MPC-37P 0.79 -7.95196E-18 1.45069E-12 -7.94501E-08 1.81131E-03 -1.09897E+01 0.79 < decay heat

-1.25365E-19 2.60073E-13 -2.20748E-08 7.29884E-04 -4.89153E+00 0.95 0.95 < decay heat

-5.32045E-18 1.07046E-12 -7.62281E-08 2.40535E-03 -2.51659E+01 1.37 1.37 < decay heat

-1.78154E-21 1.30015E-15 1.74063E-10 1.65882E-05 1.36110E+00 2.64 2.64 < decay heat 3.36123E-20 2.18480E-15 1.42012E-10 9.23077E-06 6.00000E-01 3.03 MPC-44 1.0 2.30737E-18 -1.72421E-13 3.59688E-09 9.41169E-05 6.41653E-01 Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-50

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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-1

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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-2

SR 3.0.3 When the Surveillance is performed within the delay period and the (continued) Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

SR 3.0.4 Entry into a specified condition in the Applicability of an LCO shall not be made unless the 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-3

3.1 SFSC INTEGRITY 3.1.1 Multi-Purpose Canister (MPC)

LCO 3.1.1 The MPC shall be dry and helium filled.

Table 3.3-1 provides decay heat and burnup limits for forced helium dehydration (FHD) and vacuum drying.

APPLICABILITY: Prior to TRANSPORT OPERATIONS.

ACTIONS

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

Separate Condition entry is allowed for each MPC.

COMPLETION CONDITION REQUIRED ACTION TIME A. MPC cavity vacuum A.1 Perform an engineering 7 days drying pressure or evaluation to determine the demoisturizer exit gas quantity of moisture left in the temperature limit not met. MPC.

AND A.2 Develop and initiate corrective 30 days actions necessary to return the MPC to compliance with Table 3.3-1.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-4

ACTIONS (continued)

B. MPC helium backfill limit B.1 Perform an engineering 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months not met. evaluation to determine the impact of helium differential.

AND B.2.1 Develop and initiate 14 days corrective actions necessary to return the MPC to an analyzed condition by adding helium to or removing helium from the MPC.

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

C. MPC helium leak rate limit C.1 Perform an engineering 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for vent and drain port evaluation to determine the cover plate welds or cover impact of increased helium plate base metal not met. leak rate on heat removal capability and offsite dose.

AND C.2 Develop and initiate corrective 7 days actions necessary to return the MPC to compliance with SR 3.1.1.3.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-5

D. Required Actions and D.1 Remove all fuel assemblies 30 days associated Completion from the SFSC.

Times not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify that the MPC cavity has been dried in Once, prior to accordance with the applicable limits in Table TRANSPORT 3.3-1. OPERATIONS SR 3.1.1.2 Verify MPC helium backfill quantity is within the limit Once, prior to specified in Table 3.3-2 for the applicable MPC TRANSPORT model. Re-performance of this surveillance is not OPERATIONS required upon successful completion of Action B.2.2.

SR 3.1.1.3 Verify that the helium leak rate through the MPC vent Once, prior to port confinement weld meets the leaktight criteria of TRANSPORT ANSI N14.5-1997 and verify that the helium leak rate OPERATIONS through the MPC drain port confinement weld 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-6

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 each 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.

COMPLETION CONDITION REQUIRED ACTION TIME A. SFSC Heat Removal A.1 Remove blockage. N/A System operable, but partially (<50%) blocked.

B. SFSC Heat Removal B.1 Restore SFSC Heat Removal 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months System inoperable. System to operable status.

(continued)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-7

ACTIONS (continued)

C. Required Action B.1 and C.1 Measure SFSC dose rates in Immediately and associated Completion accordance with the once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Time not met. Radiation Protection thereafter Program.

AND C.2.1 Restore SFSC Heat Removal 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months System to operable status.

OR C.2.2 Transfer the MPC into a 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TRANSFER CASK.

OR C.2.3 Perform an engineering 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months evaluation to demonstrate through analysis, using the models and methods from the HI-STORM FW FSAR, that all components and contents remain below allowable temperature limits.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-8

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2 Verify all OVERPACK inlets and outlets are free of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months blockage from solid debris or floodwater.

OR For OVERPACKS with installed temperature 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months monitoring equipment, verify that the difference between the average OVERPACK air outlet temperature and ISFSI ambient temperature is:

137oF for OVERPACKS containing MPC-37s,

152oF for OVERPACKS containing BWR MPCs,

130 oF for OVERPACKS containing MPC-32MLs

116 oF for OVERPACKS containing MPC-37Ps

144 oF for OVERPACKS containing MPC-44s Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-9

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.

COMPLETION CONDITION REQUIRED ACTION TIME A. MPC cavity pressure not A.1 Stop re-flooding operations Immediately within limit.

until MPC cavity pressure is within limit.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Ensure via analysis or direct measurement that MPC Once, prior to MPC cavity pressure is within limit. 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-10

3.1.4 TRANSFER CASK Heat Removal System LCO 3.1.4 The HI-TRAC VW Version V or V2 Heat Removal System shall be operable

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

The HI-TRAC Version V or V2 Heat Removal System is operable when 100% of the inlet and outlet vent areas are unblocked and available for flow. If surveillance shows partial blockage (

100%) of the duct areas, the blockage shall be removed.

APPLICABILITY: This LCO is applicable when a loaded MPC is in the HI-TRAC VW Version V or V2 TRANSFER CASK AND completion of MPC drying operations in accordance with LCO 3.1.1.

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. HI-TRAC VW Version V or A.1 Restore HI-TRAC VW 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months V2 Heat Removal System Version V or V2 Heat inoperable. Removal System to operable status B. Required Action A.1 and B.1 Continue to restore HI-TRAC 64 hours7.407407e-4 days 0.0178 hours 1.058201e-4 weeks 2.4352e-5 months for associated Completion Time VW Version V or V2 Heat Version V not met Removal System to operable status 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for Version V2 C. Required Action B.1 and C.1 Provide supplemental cooling Immediately associated Completion Time not met. OR C.2 Remove MPC from HI-TRAC Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-11

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4 Verify all HI-TRAC VW Version V or V2 inlets and Immediately and outlets are free of blockage from debris. once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-12

3.2 SFSC RADIATION PROTECTION.

3.2.1 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.

COMPLETION CONDITION REQUIRED ACTION TIME A. TRANSFER CASK or MPC A.1 Restore removable surface 7 days removable surface contamination to within limits.

contamination limits not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify that the removable contamination on the Once, prior to exterior surfaces of the TRANSFER CASK and TRANSPORT accessible portions of the MPC containing fuel is OPERATIONS within limits.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-13

3.3 SFSC CRITICALITY CONTROL 3.3.1 Boron Concentration LCO 3.3.1 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 to be stored in the MPC:

MPC-37, MPC-32ML, MPC-37P, or MPC-4432ML: Minimum soluble boron concentration as required by the table below.

One or more Damaged Fuel All Undamaged Fuel Assemblies Assemblies or Fuel Debris Maximum Initial Maximum Initial Maximum Initial Maximum Initial MPC Array/Class Enrichment Enrichment 5.0 Enrichment Enrichment 5.0 4.0 wt% 235U wt% 235U 4.0 wt% 235U wt% 235U (ppmb) (ppmb) (ppmb) (ppmb)

All 14x14 and 1000 1600 1300 1800 16x16A, B, C MPC-37 All 15x15 and 1500 2000 1800 2300 17x17 MPC-16x16D 1500 2000 1600 2100 32ML MPC-37P 15x15I 1500 2000 1800 2300 MPC-44 14x14A, B 1400 1900 1500 2000 For maximum initial enrichments between 4.0 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.0 wt% and 5.0 wt%.

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

This LCO does not apply if burnup credit as described in Section 2.3 is utilized in selecting assemblies prior to loading.

14x14 classes must use soluble boron as described in this LCO.

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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-14

ACTIONS

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

Separate Condition entry is allowed for each MPC.

COMPLETION CONDITION REQUIRED ACTION TIME A. Boron concentration not A.1 Suspend LOADING Immediately within limit. OPERATIONS or UNLOADING OPERATIONS.

AND A.2 Suspend positive reactivity Immediately additions.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

NOTE------------------------------------ Once, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to This surveillance is only required to be performed if the MPC is entering the submerged in water or if water is to be added to, or recirculated through Applicability of this the MPC.

LCO.

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

Once per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months thereafter.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-15

Table 3.3-1: MPC Cavity Drying Limits Method of Fuel Burnup Moisture MPC Type MPC Heat Load (kW)

(MWD/MTU) Removal (Notes 1 and 2) 29 (Table 2.3-9A or pattern developed in accordance with Table 2.3-9B) 44.09 (Pattern A in Tables 2.3-1A, 2.3-1B, and 2.3-1C)

MPC-37 45.00 (Pattern B in Table 2.3-1A) 37.4 (Figures 2.3-1 through 2.3-3) 39.95 (Figures 2.3-4 through 2.3-6) 44.85 (Figures 2.3-7 through 2.3-9)

MPC-32ML 44.16 (Pattern A in Table 2.3-5)

All VDS (Notes 3 and Assemblies 44.09 (Pattern A in Tables 2.3-1A)

4) or FHD (Note 4) 45,000 MPC-37P 45.00 (Pattern B in Table 2.3-1A) 45.00 (Table 2.3-7A) 28 (Table 2.3-13)

MPC-44 44 (Table 2.3-8A) 29 (Table 2.3-10A or pattern developed in accordance with Table 2.3-10B)

MPC-89 46.36 (Table 2.3-2A) 46.2 (Figures 2.3-10 and 2.3-11) 46.14 (Figures 2.3-12 and 2.3-13) 29 (Table 2.3-9A or pattern developed MPC-37 in accordance with Table 2.3-9B) 29.6 (Table 2.3-3)

MPC-32ML 28.70 (Pattern B in Table 2.3-5)

One or more MPC-37P 33.3 (Table 2.3-7B) VDS (Notes 3 and assemblies

4) or FHD (Note 4)

> 45,000 28 (Table 2.3-13)

MPC-44 30 (Table 2.3-8B) 29 (Table 2.3-10A or pattern developed MPC-89 in accordance with Table 2.3-10B 30.0 (Table 2.3-4)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-16

Method of Fuel Burnup Moisture MPC Type MPC Heat Load (kW)

(MWD/MTU) Removal (Notes 1 and 2) 44.09 (Pattern A in Tables 2.3-1A, 2.3-1B, and 2.3-1C) 45.00 (Pattern B in Table 2.3-1A)

MPC-37 37.4 (Figures 2.3-1 through 2.3-3) 39.95 (Figures 2.3-4 through 2.3-6) 44.85 (Figures 2.3-7 through 2.3-9)

MPC-32ML 44.16 (Pattern A in Table 2.3-5)

One or more VDS (Notes 3, 4, 44.09 (Pattern A in Tables 2.3-1A, 2.3-assemblies and 5) or FHD 1B, and 2.3-1C)

> 45,000 (Note 4)

MPC-37P 45.00 (Pattern B in Table 2.3-1A) 45.00 (Table 2.3-7A)

MPC-44 44 (Table 2.3-8A) 46.36 (Table 2.3-2A)

MPC-89 46.2 (Figures 2.3-10 and 2.3-11) 46.14 (Figures 2.3-12 and 2.3-13)

Notes:

1. VDS means a vacuum drying system. The acceptance criterion when using a VDS is the MPC cavity pressure shall be 3 torr for 30 minutes while the MPC is isolated from the vacuum pump.

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 MPC must be performed with the annular gap between the MPC and the TRANSFER CASK filled with water.

4. Heat load limits are set for each cell; see Section 2.2.

5. 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-17

Table 3.3-1: MPC Helium Backfill Limits (Note 1)

Decay Heat Limits Applied (per MPC Model Pressure range (psig)

Section 2.2)

Table 2.3-1C 42.0 and 50.0 Table 2.3-3 Table 2.3-1B 42.0 and 47.8 Table 2.3-1A, Pattern A 42.0 and 45.5 Table 2.3-1A, Pattern B 41.0 and 46.0 Figure 2.3-1 MPC-37 Figure 2.3-2 45.5 and 49.0 Figure 2.3-3 Figure 2.3-4 Figure 2.3-5 44.0 and 47.5 Figure 2.3-6 Figure 2.3-7 Figure 2.3-8 44.5 and 48.0 Figure 2.3-9 Table 2.3-9A 41.0 and 44.0 Table 2.3-9B Table 2.3-2B 42.0 and 50.0 Table 2.3-4 Table 2.3-2A 42.5 and 47.5 MPC-89 Figure 2.3-10 Figure 2.3-11 42.0 and 47.0 Figure 2.3-12 Figure 2.3-13 Table 2.3-10A 42.5 and 45.5 Table 2.3-10B MPC-32ML Table 2.3-5, All Patterns 41.5 and 45.5 Table 2.3-1A, Pattern A 42.0 and 45.5 Table 2.3-1A, Pattern B 41.0 and 46.0 MPC-37P Table 2.3-7A 44.0 and 47.0 Table 2.3-7B Table 2.3-8A MPC-44 Table 2.3-8B 41.0 and 44.0 Table 2.3-13 Note:

1. Helium used for backfill of MPC shall have a purity of 99.995%. Pressure range is at a reference temperature of 70ºF.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-18

4 ADMINISTRATIVE CONTROLS 4.1 Radioactive Effluent Control Program

a. The HI-STORM FW MPC Storage System does not create any radioactive materials or have any radioactive waste treatment systems. Therefore, specific operating procedures for the control of radioactive effluents and annual reporting in accordance with 10 CFR 72.44(d)(3) are not required.

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.

4.2 Transport Evaluation Program

a. For lifting of the loaded MPC, TRANSFER CASK, or OVERPACK using equipment which is integral to a structure governed by 10 CFR Part 50 regulations, 10 CFR 50 requirements apply.

b. This program is not applicable when the TRANSFER CASK or OVERPACK is in the FUEL BUILDING or is being handled by equipment providing support from underneath (i.e., on a rail car, heavy haul trailer, air pads, etc...).

c. The TRANSFER CASK or OVERPACK, when loaded with spent fuel, may be lifted to and carried at any height necessary during TRANSPORT OPERATIONS and MPC TRANSFER, provided the lifting equipment is designed in accordance with items 1, 2, and 3 below.

1. The metal body and any vertical columns of the lifting equipment shall be designed to comply with stress limits of ASME Section III, Subsection NF, Class 3 for linear structures. All vertical compression loaded primary members shall satisfy the buckling criteria of ASME Section III, Subsection NF.

2. The horizontal cross beam and any lifting attachments used to connect the load to the lifting equipment shall be designed, fabricated, operated, tested, inspected, and maintained in accordance with applicable sections and guidance of NUREG-0612, Section 5.1. For lifting attachments, Tthis includes applicable stress limits from ANSI N14.6.

3. The lifting equipment shall have redundant drop protection features which prevent uncontrolled lowering of the load.

4. For existing handling equipment which does not meet the above criteria, a site-specific drop analysis shall be performed as part of the 10 CFR 72.212 report to demonstrate that the acceptance criteria set forth in the HI-STORM FW FSAR are met. The analysis shall be performed using methodologies consistent with those described in the HI-STORM FW FSAR.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 4-1

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 OVERPACK.

b. The side OVERPACK

c. The side of the TRANSFER CASK

d. The inlet and outlet ducts on the OVERPACK (applicable only for VENTILATED OVERPACK) 4.3.1.3 Notwithstanding the limits established in Section 4.3.1.2, the measured dose rates on a loaded OVERPACK or TRANSFER CASK shall not exceed the following values:

a. 15 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. 3500 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 4-2

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 OVERPACK shall not be moved to the ISFSI or, in the case of the OVERPACK loaded at the ISFSI, the MPC shall be removed from the ISFSI 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 dose rate measurement shall be taken on the top of the OVERPACK at approximately the center of the lid.

b. 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.

c. 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. For a TRANSFER CASK with a neutron shield cylinder, dose rates shall be measured between the radial ribs of the neutron shield cylinder.

d. 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).

4.4 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.

4.5 Heavy Loads Requirements Each lift of an MPC, a HI-TRAC VW transfer cask, or any HI-STORM FW 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 of the heavy load handling procedures (under 10 CFR 50.59 or 10 CFR 72.48, as 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 4-3

4.6 Combustible Gas Monitoring During MPC Lid Welding and Cutting During MPC lid-to-shell welding and cutting operations, combustible gas monitoring of the space under the MPC lid is required, to ensure that there is no combustible mixture present.

4.7 Pre-Operational Testing and Training 4.7.1 Dry Run Training Exercise A dry run training exercise of the loading, closure, handling, unloading, and transfer of the HI-STORM FW MPC Storage System shall be conducted by the licensee prior to the first use of the system to load spent fuel assemblies. The training exercise shall not be conducted with spent fuel in the MPC. The dry run may be performed in an alternate step sequence from the actual procedures, but all steps must be performed. The dry run shall include, but is not limited to the following:

a. Moving the MPC and the transfer cask into the spent fuel pool or cask loading pool.

b. Preparation of the HI-STORM FW MPC Storage System for fuel loading.

c. Selection and verification of specific fuel assemblies to ensure type conformance.

d. Loading specific assemblies and placing assemblies into the MPC (using a dummy fuel assembly), including appropriate independent verification.

e. Remote installation of the MPC lid and removal of the MPC and transfer cask from the spent fuel pool or cask loading pool.

f. MPC welding, NDE inspections, pressure testing, draining, moisture removal (by vacuum drying or forced helium dehydration, as applicable), and helium backfilling. (A mockup may be used for this dry-run exercise.)

g. Transfer of the MPC from the transfer cask to the overpack.

h. Placement of the HI-STORM FW MPC Storage System at the ISFSI.

i. HI-STORM FW MPC Storage System unloading, including flooding MPC cavity and removing MPC lid welds. (A mockup may be used for this dry-run exercise.)

Any of the above steps can be omitted if they have already been successfully carried out at a site to load a HI-STORM 100 System (USNRC Docket 72-1014).

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 4-4

v t e Letter Sequence Other
CAC:001028, (Approved, Closed) EPID:L2021, International - Transmittal of Final Safety Analysis Report Update for the FW MPC Storage System Per 10 CFR 72.248(c)(6) (Open)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, ... further results\|Request]] Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting Questions 25 August 2021 20 February 2020 6 March 2020 31 March 2020 31 March 2020 10 April 2020 28 May 2020 28 May 2020 4 August 2020 31 August 2020 30 September 2020 28 September 2020 6 October 2020 20 November 2020 10 December 2020 16 December 2020 14 January 2021 14 January 2021 22 January 2021 23 March 2021 23 March 2021 3 March 2021 20 May 2021 15 June 2021 30 August 2021 28 October 2021 28 October 2021 18 October 2021 3 November 2021 21 December 2021 21 December 2021 21 December 2021 8 December 2021 8 December 2021 20 January 2022 20 January 2022 6 May 2022 23 March 2022 31 March 2022 1 July 2022 8 December 2022 4 January 2023 16 March 2023 6 March 2023 6 March 2023 25 July 2023 25 July 2023 20 June 2023 4 October 2023 4 October 2023 28 August 2023 ... further results Answers 31 March 2020 5 June 2020 10 July 2020 11 September 2020 11 November 2020 27 January 2021 9 February 2021 19 November 2021 30 November 2021 25 February 2022 7 June 2022 11 July 2022 13 July 2022 29 July 2022 31 August 2022 31 August 2022 9 September 2022 3 October 2022 3 October 2022 1 December 2022 21 December 2022 6 January 2023 27 January 2023 17 March 2023 8 May 2023 30 June 2023 22 April 2024 14 May 2024 Results Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, ... further results\|Approval]] Other: L-23-005, Independent Spent Fuel Storage Installation License Renewal Application, Revision 1 (Cac/Epid No. 001028/L-2022-RNW-0007), ML19276D398, ML20014E677, ML20049A082, ML20065N277, ML20065N278, ML20065N280, ML20065N281, ML20065N285, ML20071F156, ML20076D696, ML20094G482, ML20099A180, ML20104C015, ML20104C016, ML20104C018, ML20104C019, ML20105A135, ML20105A136, ML20105A137, ML20105A138, ML20105A139, ML20105A173, ML20111A240, ML20115E377, ML20121A272, ML20136A049, ML20136A050, ML20136A051, ML20150A300, ML20150A335, ML20150A421, ML20155K741, ML20155K742, ML20155K743, ML20155K744, ML20160A040, ML20161A088, ML20163A702, ML20163A703, ML20163A704, ML20181A211, ML20181A212, ML20192A328, ML20192A329, ML20212L768, ML20212L769, ML20212L878, ML20223A036, ML20224A287... further results
MONTHYEAR2020-03-05 [Table View]

ML21288A536

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