ML17362A111

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Attachment 1: Proposed Changes to CoC 1014 Amendment 11
ML17362A111
Person / Time
Site: Holtec
Issue date: 12/21/2017
From:
Holtec
To:
Office of Nuclear Material Safety and Safeguards
References
5014833, LAR 1014-11
Download: ML17362A111 (73)
v • d • e


Text

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Page 1

of 5

The U.S. Nuclear Regulatory Commission is issuing this Certificate of Compliance pursuant to Title 10 of the Code of Federal Regulations, Part 72, "Licensing Requirements for Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste" (10 CFR Part 72). This certificate is issued in accordance with 10 CFR 72.238, certifying that the storage design and contents described below meet the applicable safety standards set forth in 10 CFR Part 72, Subpart L, and on the basis of the Final Safety Analysis Report (FSAR) of the cask design. This certificate is conditional upon fulfilling the requirements of 10 CFR Part 72, as applicable, and the conditions specified below.

Certificate No.

Effective Date Expiration Date Docket No.

Amendment No.

Amendment Effective Date Package Identification No.

1014 05/31/00 05/31/20 72-1014 101 TBD USA/72-1014 Issued To: (Name/Address)

Holtec International Holtec Center 555 LincolnOne Holtec Drive West Marlton, NJ 08053 Safety Analysis Report Title Holtec International Inc.,

Final Safety Analysis Report for the HI-STORM 100 Cask System CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 72, as applicable, the attached Appendix A (Technical Specifications) and Appendix B (Approved Contents and Design Features) for aboveground systems or the attached Appendix A-100U (Technical Specifications) and Appendix B-100U (Approved Contents and Design Features) for underground systems, and the conditions specified below:

1. CASK
a. Model No.: HI-STORM 100 Cask System The HI-STORM 100 Cask System (the cask) consists of the following components: (1) interchangeable multi-purpose canisters (MPCs), which contain the fuel; (2) a storage overpack (HI-STORM), which contains the MPC during storage; and (3) a transfer cask (HI-TRAC), which contains the MPC during loading, unloading and transfer operations. The cask stores up to 32 pressurized water reactor fuel assemblies or 68 boiling water reactor fuel assemblies.
b. Description The HI-STORM 100 Cask System is certified as described in the Final Safety Analysis Report (FSAR) and in the U.S. Nuclear Regulatory Commissions (NRC) Safety Evaluation Report (SER) accompanying the Certificate of Compliance (CoC). The cask comprises three discrete components: the MPC, the HI-TRAC transfer cask, and the HI-STORM storage overpack.

The MPC is the confinement system for the stored fuel. It is a welded, cylindrical canister with a honeycombed fuel basket, a baseplate, a lid, a closure ring, and the canister shell. All MPC components that may come into contact with spent fuel pool water or the ambient environment are made entirely of stainless steel or passivated aluminum/aluminum alloys such as the neutron absorbers. The canister shell, baseplate, lid, vent and drain port cover plates, and closure ring are the main confinement boundary components. All confinement boundary components are made entirely of stainless steel. The honeycombed basket, which contains neutron absorbing material, provides criticality control.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 1 of 73

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (3-1999) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Supplemental Sheet Certificate No.

1014 Amendment No.

110 Page 2

of 5

1.
b. Description (continued)

There are nine types of MPCs: the MPC-24, MPC-24E, MPC-24EF, MPC-32, MPC-32F, MPC-68, MPC-68F, MPC-68FF, and MPC-68M. The number suffix indicates the maximum number of fuel assemblies permitted to be loaded in the MPC. All nine MPC models have the same external diameter.

The HI-TRAC transfer cask provides shielding and structural protection of the MPC during loading, unloading, and movement of the MPC from the spent fuel pool to the storage overpack. The transfer cask is a multi-walled (carbon steel/lead/carbon steel) cylindrical vessel with a neutron shield jacket attached to the exterior.

Two sizes of HI-TRAC transfer casks are available: the 125 ton HI-TRAC and the 100 ton HI-TRAC. The weight designation indicates the approximate weight of a loaded transfer cask during any loading, unloading, or transfer operation. Both transfer cask sizes have identical cavity diameters. The 125 ton HI-TRAC transfer cask has thicker shielding and larger outer dimensions than the 100 ton HI-TRAC transfer cask.

Above Ground Systems The HI-STORM 100 or 100S storage overpack provides shielding and structural protection of the MPC during storage. The HI-STORM 100S is a variation of the HI-STORM 100 overpack design that includes a modified lid which incorporates the air outlet ducts into the lid, allowing the overpack body to be shortened. The overpack is a heavy-walled steel and concrete, cylindrical vessel. Its side wall consists of plain (un-reinforced) concrete that is enclosed between inner and outer carbon steel shells. The overpack has four air inlets at the bottom and four air outlets at the top to allow air to circulate naturally through the cavity to cool the MPC inside. The inner shell has supports attached to its interior surface to guide the MPC during insertion and removal, provide a medium to absorb impact loads, and allow cooling air to circulate through the overpack. A loaded MPC is stored within the HI-STORM 100 or 100S storage overpack in a vertical orientation. The HI-STORM 100A and 100SA are variants of the HI-STORM 100 family and are outfitted with an extended baseplate and gussets to enable the overpack to be anchored to the concrete storage pad in high seismic applications.

Underground Systems The HI-STORM 100U System is an underground storage system identified with the HI-STORM 100 Cask System. The HI-STORM 100U storage Vertical Ventilated Module (VVM) utilizes a storage design identified as an air-cooled vault or caisson. The HI-STORM 100U storage VVM relies on vertical ventilation instead of conduction through the soil, as it is essentially a below-grade storage cavity. Air inlets and outlets allow air to circulate naturally through the cavity to cool the MPC inside. The subterranean steel structure is seal welded to prevent ingress of any groundwater from the surrounding subgrade, and it is mounted on a stiff foundation.

The surrounding subgrade and a top surface pad provide significant radiation shielding. A loaded MPC is stored within the HI-STORM 100U storage VVM in the vertical orientation.

2. OPERATING PROCEDURES Written operating procedures shall be prepared for cask handling, loading, movement, surveillance, and maintenance. The users site-specific written operating procedures shall be consistent with the technical basis described in Chapter 8 of the FSAR.
3. ACCEPTANCE TESTS AND MAINTENANCE PROGRAM Written cask acceptance tests and maintenance program shall be prepared consistent with the technical basis described in Chapter 9 of the FSAR. At completion of welding the MPC shell to baseplate, an MPC confinement weld helium leak test shall be performed using a helium mass spectrometer. This test shall include the base metals of the MPC shell and baseplate. A helium leak test shall also be performed on the base metal of the fabricated MPC lid. In the field, a helium leak test shall be performed on the vent and drain port confinement welds and cover plate base metal. The confinement boundary leakage rate tests shall be performed in accordance with ANSI N14.5 to leaktight criteria. If a leakage rate exceeding the acceptance criteria is detected, then the area of leakage shall be determined and the area repaired per ASME Code Section III, Subsection NB requirements. Re-testing shall be performed until the leakage rate acceptance criterion is met.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 2 of 73

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (3-1999) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Supplemental Sheet Certificate No.

1014 Amendment No.

110 Page 3

of 5

4. QUALITY ASSURANCE Activities in the areas of design, purchase, fabrication, assembly, inspection, testing, operation, maintenance, repair, modification of structures, systems and components, and decommissioning that are important to safety shall be conducted in accordance with a Commission-approved quality assurance program which satisfies the applicable requirements of 10 CFR Part 72, Subpart G, and which is established, maintained, and executed with regard to the cask system.
5. HEAVY LOADS REQUIREMENTS Each lift of an MPC, a HI-TRAC transfer cask, or any HI-STORM overpack must be made in accordance to the existing heavy loads requirements and procedures of the licensed facility at which the lift is made. A plant-specific review (under 10 CFR 50.59 or 10 CFR 72.48, if applicable) is required to show operational compliance with existing plant specific heavy loads requirements. Lifting operations outside of structures governed by 10 CFR Part 50 must be in accordance with Section 5.5 of Appendix A and Sections 3.4.6 and 3.5 (if applicable) of Appendix B, for above ground systems, section 5.5 of Appendix A-100U for the underground systems.
6. APPROVED CONTENTS Contents of the HI-STORM 100 Cask System must meet the fuel specifications given in Appendices B for aboveground systems or B-100U for underground systems to this certificate.
7. DESIGN FEATURES Features or characteristics for the site, cask or ancillary equipment must be in accordance with Appendices B for aboveground systems or B-100U for underground systems to this certificate.
8. CHANGES TO THE CERTIFICATE OF COMPLIANCE The holder of this certificate who desires to make changes to the certificate, which includes Appendices A and A-100U (Technical Specifications) and Appendices B and B-100U (Approved Contents and Design Features),

shall submit an application for amendment of the certificate.

9. SPECIAL REQUIREMENTS FOR FIRST SYSTEMS IN PLACE
a. For the storage configuration, each user of a HI-STORM 100 Cask and HI-STORM 100U Cask with a heat load equal to or greater than 20 kW shall perform a thermal validation test in which the user measures the total air mass flow rate through the cask system using direct measurements of air velocity in the inlet vents. The user shall then perform an analysis of the cask with the taken measurements to demonstrate that the measurements validate the analytic methods described in Chapter 4 of the FSAR. The thermal validation test and analysis results shall be submitted in a letter report to the NRC pursuant to 10 CFR 72.4 within 180 days of the users loading of the first cask with heat load equal to or greater than 20 kW. To satisfy condition 9(a) for casks of the same system type (i.e., HI-STORM 100 casks, HI-STORM 100U casks), in lieu of additional submittals pursuant to 10 CFR 72.4, users may document in their 72.212 report a previously performed test and analysis submitted by letter report to the NRC that demonstrates validation of the analytic methods described in Chapter 4 of the FSAR.
b. For transfer configuration, each user of the HI-STORM 100 Cask and HI-STORM 100U Cask shall procure, if necessary, a Supplemental Cooling System (SCS) capable of providing the thermal-hydraulic characteristics (coolant temperature at the annulus inlet, coolant temperature located at the annulus outlet, and coolant flow rate) that will ensure that thermal limits (described in Appendix 2.C of the FSAR) are not exceeded during transfer operations. The thermal-hydraulic characteristics of the SCS shall be determined using the analytical methods described in Chapter 4 for the transfer configuration. For the transfer configuration, each first time user shall measure the SCS thermal-hydraulic characteristics to validate the performance of the SCS. The SCS analysis and validation shall be documented in an update to the 72.212 report within 180 days of the users first transfer operation with the SCS. Condition 9(b) does not apply to the MPC-68M.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 3 of 73

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (3-1999) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Supplemental Sheet Certificate No.

1014 Amendment No.

110 Page 4

of 5

10. PRE-OPERATIONAL TESTING AND TRAINING EXERCISE A dry run training exercise of the loading, closure, handling, unloading, and transfer of the HI-STORM 100 Cask 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 100 Cask 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. Operation of the HI-STORM 100 SCS or equivalent system, if applicable.
h. Transfer cask upending/downending on the horizontal transfer trailer or other transfer device, as applicable to the sites cask handling arrangement.
i.

Transfer of the MPC from the transfer cask to the overpack/VVM.

j.

Placement of the HI-STORM 100 Cask System at the ISFSI, for aboveground systems only.

k. HI-STORM 100 Cask System unloading, including flooding MPC cavity, removing MPC lid welds. (A mockup may be used for this dry-run exercise.)
11. The NRC has approved an exemption request by the CoC applicant from the requirements of 10 CFR 72.236(f), to allow a Supplemental Cooling System to provide for decay heat removal in accordance with Section 3.1.4 of Appendices A and A-100U.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 4 of 73

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (3-1999) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Supplemental Sheet Certificate No.

1014 Amendment No.

110 Page 5

of 5

12.

AUTHORIZATION The HI-STORM 100 Cask System, which is authorized by this certificate, is hereby approved for general use by holders of 10 CFR Part 50 licenses for nuclear reactors at reactor sites under the general license issued pursuant to 10 CFR 72.210, subject to the conditions specified by 10 CFR 72.212, this certificate, and the attached Appendices A, B, A-100U, and B-100U, as applicable. The HI-STORM 100 Cask System may be fabricated and used in accordance with any approved amendment to CoC No. 1014 listed in 10 CFR 72.214. Each of the licensed HI-STORM 100 System components (i.e., the MPC, overpack, and transfer cask), if fabricated in accordance with any of the approved CoC Amendments, may be used with one another provided an assessment is performed by the CoC holder that demonstrates design compatibility.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION TBD, Chief Licensing Branch Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards Washington, DC 20555 Dated TBD Attachments:

1. Appendix A
2. Appendix B
3. Appendix A-100U
4. Appendix B-100U ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 5 of 73

Certificate of Compliance No. 1014 Amendment No. 11 Appendix A i

TABLE OF CONTENTS 1.0 USE AND APPLICATION............................................................................... 1.1-1 1.1 Definitions............................................................................................ 1.1-1 1.2 Logical Connectors.............................................................................. 1.2-1 1.3 Completion Times................................................................................ 1.3-1 1.4 Frequency............................................................................................ 1.4-1 2.0 NOT USED..................................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY............... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY............................. 3.0-2 3.1 SFSC INTEGRITY............................................................................ 3.1.1-1 3.1.1 Multi-Purpose Canister (MPC)............................................... 3.1.1-1 3.1.2 SFSC Heat Removal System................................................. 3.1.2-1 3.1.3 MPC Cavity Reflooding.......................................................... 3.1.3-1 3.1.4 Supplemental Cooling System............................................... 3.1.4-1 3.2 SFSC RADIATION PROTECTION................................................... 3.2.1-1 3.2.1 Deleted................................................................................... 3.2.1-1 3.2.2 TRANSFER CASK Surface Contamination............................ 3.2.2-2 3.2.3 Deleted................................................................................... 3.2.3-1 3.3 SFSC CRITICALITY CONTROL....................................................... 3.3.1-1 3.3.1 Boron Concentration.............................................................. 3.3.1-1 Table 3-1 MPC Cavity Drying Limits.................................................................... 3.4-1 Table 3-2 MPC Helium Backfill Limits.................................................................. 3.4-2 Table 3-3 Regionalized Storage Cell Heat Load Limits.........................3.4-3 Table 3-4 Uniform Storage Cell Heat Load Limits................................................ 3.4-3 Table 3-5 Completion Time for Actions to Restore SFSC Heat Removal System to Operable.........3.4-4 4.0 NOT USED..................................................................................................... 4.0-1 5.0 ADMINISTRATIVE CONTROLS.................................................................... 5.0-1 5.1 Deleted................................................................................................ 5.0-1 5.2 Deleted................................................................................................ 5.0-1 5.3 Deleted................................................................................................ 5.0-1 5.4 Radioactive Effluent Control Program.................................................. 5.0-1 5.5 Cask Transport Evaluation Program.................................................... 5.0-2 5.6 Deleted................................................................................................ 5.0-4 5.7 Radiation Protection Program.............................................................. 5.0-5 Table 5-1 TRANSFER CASK and Free Standing OVERPACK Lifting Requirements............................................................................ 5.0-4 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 6 of 73

Definitions 1.1 Certificate of Compliance No. 1014 Amendment No. 11 Appendix A 1.1-4 1.1 Definitions (continued)

LOADING OPERATIONS LOADING OPERATIONS include all licensed activities on an OVERPACK or TRANSFER CASK while it is being loaded with fuel assemblies.

LOADING OPERATIONS begin when the first fuel assembly is placed in the MPC and end when the OVERPACK or TRANSFER CASK is suspended from or secured on the transporter. LOADING OPERATIONS does not include MPC TRANSFER.

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

MULTI-PURPOSE CANISTER (MPC)

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

MPC TRANSFER MPC TRANSFER begins when the MPC is lifted off the TRANSFER CASK bottom lid and ends when the MPC is supported from beneath by the OVERPACK or VVM (or the reverse).

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

Axial Power Shaping Rods (APSRs), Wet Annular Burnable Absorbers (WABAs), Rod Cluster Control Assemblies (RCCAs), Control Element Assemblies (CEAs), Neutron Source Assemblies (NSAs), water displacement guide tube plugs, orifice rod assemblies, instrument tube tie rods (ITTRs),

vibration suppressor inserts, and components of these devices such as individual rods.

(continued)

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 7 of 73

Definitions 1.1 Certificate of Compliance No. 1014 Amendment No. 11 Appendix A 1.1-5 1.1 Definitions (continued)

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 provide for ventilated air flow to promote heat transfer from the MPC to the environs. The term OVERPACK does not include the TRANSFER CASK.

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

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

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

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

TRANSFER CASK TRANSFER CASKs are containers designed to contain the MPC during and after loading of spent fuel assemblies and to transfer the MPC to or from the OVERPACK/VVM. The HI-STORM 100 System employs either the 125-Ton or the 100-Ton HI-TRAC TRANSFER CASK.

(continued)

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 8 of 73

SFSC Heat Removal System 3.1.2 Certificate of Compliance No. 1014 Amendment No. 11 Appendix A 3.1.2-1 3.1 SFSC INTEGRITY 3.1.2 SFSC Heat Removal System LCO 3.1.2 The SFSC Heat Removal System shall be operable

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

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

APPLICABILITY: During STORAGE OPERATIONS.

ACTIONS

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

Separate Condition entry is allowed for each SFSC.

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

A.1 Remove blockage.

N/A B. SFSC Heat Removal System inoperable.

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

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

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

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

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

Table 3-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 9 of 73

SFSC Heat Removal System 3.1.2 Certificate of Compliance No. 1014 Amendment No. 11 Appendix A 3.1.2-2 SR 3.1.2 Verify all OVERPACK inlets and outlets are free of blockage from solid debris or floodwater.

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

< 155oF for OVERPACKS containing PWR MPCs, < 137oF for OVERPACKS containing BWR MPCs.

Table 3-5 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 10 of 73

Boron Concentration 3.3.1 Certificate of Compliance No. 1014 Amendment No.11 Appendix A 3.3.1-1 3.3 SFSC CRITICALITY CONTROL 3.3.1 Boron Concentration LCO 3.3.1 As required by CoC Appendix B, Table 2.1-2, the concentration of boron in the water in the MPC shall meet the following limits for the applicable MPC model and the most limiting fuel assembly array/class and classification to be stored in the MPC:

a. MPC-24 with one or more fuel assemblies having an initial enrichment greater than the value in Table 2.1-2 for no soluble boron credit and < 5.0 wt% 235U: > 400 ppmb
b. MPC-24E or MPC-24EF (all INTACT FUEL ASSEMBLIES) with one or more fuel assemblies having an initial enrichment greater than the value in Table 2.1-2 for no soluble boron credit and < 5.0 wt% 235U: > 300 ppmb
c.

Deleted.

d. Deleted.
e. MPC-24E or MPC-24EF (one or more DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS) with one or more fuel assemblies having an initial enrichment > 4.0 wt% 235U and

< 5.0 wt% 235U: > 600 ppmb

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

Array/Class All INTACT FUEL ASSEMBLIES One or more DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS Maximum Initial Enrichment

< 4.1 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb)

Maximum Initial Enrichment

< 4.1 wt% 235U (ppmb)

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

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 11 of 73

MPC Cavity Drying Limits Table 3-1 Certificate of Compliance No. 1014 Amendment No. 11 Appendix A 3.4-1 Table 3-1 MPC Cavity Drying Limits for all MPC Types Fuel Burnup (MWD/MTU)

MPC Heat Load (kW)

Method of Moisture Removal (Notes 1 and 2)

All Assemblies < 45,000 30 (MPC-24/24E/24EF, MPC-32/32F, MPC-68/68F/68FF) 36.9 (MPC-68M)

VDSNote 5 or FHDNote 6 All Assemblies < 45,000

> 30 (MPC-24/24E/24EF, MPC-32/32F, MPC-68/68F/68FF)

FHDNote 6 One or more assemblies

> 45,000 29 (MPC-68M)

VDSNote 4 or FHDNote 6 One or more assemblies

> 45,000 36.9 (MPC-24/24E/24EF/MPC-32/32F/MPC-68/68F/68FF/MPC-68M FHDNote 6 Notes:

1.

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

2.

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

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

3.

Deleted

4.

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

5.

Maximum allowable storage cell heat load is 1.25 kW (MPC-24/24E/24EF), 0.937 kW (MPC-32/32F) and 0.441 kW (MPC-68/68F/68FF).

6.

Maximum per assembly allowable heat loads under uniform or regionalized storage defined in Appendix B, Section 2.4.1 or 2.4.2.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 12 of 73

LCO Completion Time Table 3-5 Certificate of Compliance No. 1014 Amendment No. 11 Appendix A 3.4-4 Table 3-5: Completion Time for Actions to Restore SFSC Heat Removal System to Operable MPC Type Decay Heat Limits per Storage Location Condition B Completion Time Condition C Completion Time Surveillance Frequency MPC-24/24E/24EF Appendix B, Section 2.4 8 hrs 24 hrs 24 hrs MPC-32/32F MPC-68/68F/68FF/68M MPC-24/24E/24EF Appendix A, Table 3-3 (Regionalized)

OR Appendix A, Table 3-4 (Uniform) 8 hrs 64 hrs 24 hrs MPC-32/32F MPC-68/68F/68FF/68M MPC-24/24E/24EF 0.75 kW 24 hrs 64 hrs 30 days MPC-32/32F 0.5 kW MPC-68/68F/68FF/68M 0.264 kW ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 13 of 73

Programs 5.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix A 5.0-3 ADMINISTRATIVE CONTROLS AND PROGRAMS 5.5 Cask Transport Evaluation Program (continued)

3.

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

4.

The TRANSFER CASK and MPC, when loaded with spent fuel, may be lifted to those heights necessary to perform cask handling operations, including MPC TRANSFER, provided the lifts are made with structures and components designed in accordance with the criteria specified in Section 3.5 of Appendix B to Certificate of Compliance No. 1014, as applicable.

b.

For the transport of OVERPACKS to be anchored to the ISFSI pad, the following requirements apply:

1.

Except as provided in 5.5.b.2, user shall determine allowable OVERPACK lift height limit(s) above the transport route surface(s) based on site-specific transport route conditions. The lift heights shall be determined by evaluation or analysis, based on limiting the design basis cask deceleration during a postulated drop event to

< 45 gs at the top of the MPC fuel basket. Evaluations and/or analyses shall be performed using methodologies consistent with those in the HI-STORM 100 FSAR.

2.

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

(continued)

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 14 of 73

Certificate of Compliance No. 1014 Amendment No. 11 Appendix B i

TABLE OF CONTENTS 1.0 DEFINITIONS........................................................................................................ 1-1 2.0 APPROVED CONTENTS...................................................................................... 2-1 2.1 Fuel Specification and Loading Conditions........................................................ 2-1 2.2 Violations........................................................................................................... 2-2 2.3 Not Used............................................................................................................ 2-2 2.4 Decay Heat, Burnup & Cooling Time Limits for ZR Clad Fuel......................... 2-47 Figure 2.1-1 Fuel Loading Regions - MPC-24........................................................ 2-3 Figure 2.1-2 Fuel Loading Regions - MPC-24E/24EF............................................ 2-4 Figure 2.1-3 Fuel Loading Regions - MPC-32/32F................................................. 2-5 Figure 2.1-4 Fuel Loading Regions - MPC-68/68FF/68M....................................... 2-6 Table 2.1-1 Fuel Assembly Limits.......................................................................... 2-7 Table 2.1-2 PWR Fuel Assembly Characteristics................................................ 2-36 Table 2.1-3 BWR Fuel Assembly Characteristics................................................ 2-41 Table 2.1-4 Table Deleted................................................................................... 2-42 Table 2.1-5 Table Deleted................................................................................... 2-43 Table 2.1-6 Table Deleted................................................................................... 2-44 Table 2.1-7 Table Deleted................................................................................... 2-45 Table 2.1-8 Non-Fuel Hardware Cooling and Average Burnup............................ 2-45 Table 2.4-1 Maximum Allowable Decay Heat per Fuel Storage Location............ 2-46 Table 2.4-2 Fuel Storage Locations per MPC...................................................... 2-47 Table 2.4-3 PWR Fuel Assembly Cooling Time-Dependent Coefficients 2-53 Table 2.4-4 BWR Fuel Assembly Cooling Time-Dependent Coefficients.2-61 Table 2.4-3 PWR Fuel Assembly Cooling Time-Dependent Coefficients............. 2-50 Table 2.4-4 BWR Fuel Assembly Cooling Time-Dependent Coefficients............. 2-58 3.0 DESIGN FEATURES............................................................................................. 3-1 3.1 Site.................................................................................................................... 3-1 3.2 Design Features Important for Criticality Control............................................... 3-1 3.3 Codes and Standards........................................................................................ 3-2 3.4 Site Specific Parameters and Analyses........................................................... 3-14 3.5 Cask Transfer Facility (CTF)............................................................................ 3-18 3.6 Forced Helium Dehydration System................................................................ 3-21 3.7 Supplemental Cooling System......................................................................... 3-23 3.8 Combustible Gas Monitoring During MPC Lid Welding and Cutting................ 3-26 3.9 Environmental Temperature Requirements..................................................... 3-26 Table 3-1 List of ASME Code Alternatives for HI-STORM 100 Cask System......... 3-4 Table 3-2 Load Combinations and Service Condition Definitions for the CTF Structure....................................................................................... 3-20 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 15 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-2 2.0 Approved Contents 2.1 Fuel Specifications and Loading Conditions (contd) 2.1.3 Regionalized Fuel Loading Users may choose to store fuel using regionalized loading in lieu of uniform loading to allow higher heat emitting fuel assemblies to be stored than would otherwise be able to be stored using uniform loading.

Regionalized loading is limited to INTACT FUEL ASSEMBLIES or UNDAMAGED FUEL ASSEMBLIES with ZR cladding. Figures 2.1-1 through 2.1-4 define the regions for the MPC-24, MPC-24E, MPC-24EF, MPC-32, MPC-32F, MPC-68, MPC-68FF, and MPC-68M models, respectively1. Fuel assembly burnup, decay heat, and cooling time limits for regionalized loading are specified in Section 2.4.2. Fuel assemblies used in regionalized loading shall meet all other applicable limits specified in Tables 2.1-1 through 2.1-3.

2.2 Violations If any Fuel Specifications or Loading Conditions of 2.1 are violated, the following actions shall be completed:

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

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

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

2.3 Not Used 1

These figures are only intended to distinguish the fuel loading regions. Other details of the basket design are illustrative and may not reflect the actual basket design details.

The design drawings should be consulted for basket design details.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 16 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-7 Table 2.1-1 (page 1 of 2930)

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

1. Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):
a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class.

b. Initial Enrichment:

As specified in Table 2.1-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Classes 14x14D,14x14E, and 15x15G Cooling time 8 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes Cooling time 3 years and average burnup 68,200 as specified in Section 2.4.MWD/MTUas specified in Section 2.4.

ii. NON-FUEL HARDWARE As specified in Table 2.1-8.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 17 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-8 Table 2.1-1 (page 2 of 2930)

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

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:
i. Array/Classes 14x14D, 14x14E, and 15x15G 710 Watts ii. All Other Array/Classes As specified in Section 2.4.
e. Fuel Assembly Length:

176.8 inches (nominal design)

f. Fuel Assembly Width:

8.54 inches (nominal design)

g. Fuel Assembly Weight:

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

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

C. Deleted.

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

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

Note 1:

Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing APSRs or NSAs may only be loaded in fuel storage locations 9, 10, 15, and/or 16. Fuel assemblies containing CRAs, RCCAs, CEAs may only be stored in fuel storage locations 4, 5, 8 - 11, 14 - 17, 20 and/or 21 (see Figure 2.1-1). These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 18 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-9 Table 2.1-1 (page 3 of 2930)

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

1. Uranium oxide, BWR INTACT FUEL ASSEMBLIES, with or without ZR channels. Uranium oxide BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array class 6x6A, 6x6C, 7x7A or 8x8A, and meet the following specifications:
a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment:

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

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

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

e. Decay Heat Per Assembly 115 Watts
f. Fuel Assembly Length:

135.0 inches (nominal design)

g. Fuel Assembly Width:

4.70 inches (nominal design)

h. Fuel Assembly Weight:

400 lbs, including channels ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 19 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-10 Table 2.1-1 (page 4 of 2930)

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

A. Allowable Contents (continued)

2. Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6A, 6x6C, 7x7A, or 8x8A, and meet the following specifications:
a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment:

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

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

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

e. Decay Heat Per Assembly:

115 Watts

f. Fuel Assembly Length:

135.0 inches (nominal design)

g. Fuel Assembly Width:

4.70 inches (nominal design)

h. Fuel Assembly Weight:

550 lbs, including channels and DFC ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 20 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-11 Table 2.1-1 (page 5 of 2930)

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

A. Allowable Contents (continued)

3. Uranium oxide, BWR FUEL DEBRIS, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the uranium oxide BWR FUEL DEBRIS shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6A, 6x6C, 7x7A, or 8x8A, and meet the following specifications:
a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2.1-3 for the applicable original fuel assembly array/class.

c. Initial Maximum Rod Enrichment:

As specified in Table 2.1-3 for the applicable original fuel assembly array/class.

d. Post-irradiation Cooling Time and Average Burnup Per Assembly Cooling time 18 years and an average burnup 30,000 MWD/MTU for the original fuel assembly.
e. Decay Heat Per Assembly 115 Watts
f. Original Fuel Assembly Length 135.0 inches (nominal design)
g. Original Fuel Assembly Width 4.70 inches (nominal design)
h. Fuel Debris Weight 550 lbs, including channels and DFC ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 21 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-12 Table 2.1-1 (page 6 of 2930)

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

A. Allowable Contents (continued)

4. Mixed oxide (MOX), BWR INTACT FUEL ASSEMBLIES, with or without ZR channels. MOX BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

c. Initial Maximum Rod Enrichment:

As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

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

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

e. Decay Heat Per Assembly 115 Watts
f. Fuel Assembly Length:

135.0 inches (nominal design)

g. Fuel Assembly Width:

4.70 inches (nominal design)

h. Fuel Assembly Weight:

400 lbs, including channels ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 22 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-13 Table 2.1-1 (page 7 of 2930)

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

A. Allowable Contents (continued)

5. Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. MOX BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

c. Initial Maximum Rod Enrichment:

As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

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

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

e. Decay Heat Per Assembly 115 Watts
f. Fuel Assembly Length:

135.0 inches (nominal design)

g. Fuel Assembly Width:

4.70 inches (nominal design)

h. Fuel Assembly Weight:

550 lbs, including channels and DFC ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 23 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-14 Table 2.1-1 (page 8 of 2930)

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

A. Allowable Contents (continued)

6. Mixed Oxide (MOX), BWR FUEL DEBRIS, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the MOX BWR FUEL DEBRIS shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2.1-3 for original fuel assembly array/class 6x6B.

c. Initial Maximum Rod Enrichment:

As specified in Table 2.1-3 for original fuel assembly array/class 6x6B.

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

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

e. Decay Heat Per Assembly 115 Watts
f. Original Fuel Assembly Length:

135.0 inches (nominal design)

g. Original Fuel Assembly Width:

4.70 inches (nominal design)

h. Fuel Debris Weight:

550 lbs, including channels and DFC ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 24 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-15 Table 2.1-1 (page 9 of 2930)

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

A. Allowable Contents (continued)

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

ZR

b. Composition:

98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U OR 98.5 wt.% ThO2, 1.5 wt.% UO2 with an enrichment of 93.5 wt.% 235U.

c. Number of Rods Per Thoria Rod Canister:

18

d. Decay Heat Per Thoria Rod Canister:

115 Watts

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

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

f. Initial Heavy Metal Weight:

27 kg/canister

g. Fuel Cladding O.D.:

0.412 inches

h. Fuel Cladding I.D.:

0.362 inches

i. Fuel Pellet O.D.:

0.358 inches

j. Active Fuel Length:

111 inches

k. Canister Weight:

550 lbs, including fuel ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 25 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-16 Table 2.1-1 (page 10 of 2930)

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

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

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

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

1. Uranium oxide BWR INTACT FUEL ASSEMBLIES;
2. MOX BWR INTACT FUEL ASSEMBLIES;
3. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES placed in DFCs;
4. MOX BWR DAMAGED FUEL ASSEMBLIES placed in DFCs; or
5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.

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

D. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC-68F. The Antimony-Beryllium source material shall be in a water rod location.

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Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-17 Table 2.1-1 (page 11 of 2930)

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

1. Uranium oxide or MOX BWR INTACT FUEL ASSEMBLIES listed in Table 2.1-3, with or without channels and meeting the following specifications:
a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array/class

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment As specified in Table 2.1-3 for the applicable fuel assembly array/class.
d. Post-irradiation Cooling Time and Average Burnup Per Assembly
i. Array/Classes 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A Cooling time 18 years and an average burnup 30,000 MWD/MTU (or MWD/MTIHM).

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

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

iv. All Other Array/Classes Cooling time 3As specified in Section 2.4. years and an average burnup 65,000 MWD/MTUAs specified in Section 2.4.

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Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-18 Table 2.1-1 (page 12 of 2930)

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

A. Allowable Contents (continued)

e. Decay Heat Per Assembly
i. Array/Classes 6x6A, 6X6B, 6x6C, 7x7A, and 8x8A 115 Watts ii. Array/Class 8x8F 183.5 Watts iii. Array/Classes 10x10D and 10x10E 95 Watts iv. All Other Array/Classes As specified in Section 2.4.
f. Fuel Assembly Length
i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 135.0 inches (nominal design) ii. All Other Array/Classes 176.5 inches (nominal design)
g. Fuel Assembly Width
i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 4.70 inches (nominal design) ii. All Other Array/Classes 5.85 inches (nominal design)
h. Fuel Assembly Weight
i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 400 lbs, including channels ii. All Other Array/Classes 730 lbs, including channels ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 28 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-19 Table 2.1-1 (page 13 of 2930)

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

A. Allowable Contents (continued)

2. Uranium oxide or MOX BWR DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, with or without channels, placed in DAMAGED FUEL CONTAINERS.

Uranium oxide and MOX BWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2.1-3, and meet the following specifications:

a. Cladding Type:

ZR or Stainless Steel (SS) in accordance with Table 2.1-3 for the applicable fuel assembly array/class.

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
i. Array/Classes 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A.

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

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

c. Initial Maximum Rod Enrichment As specified in Table 2.1-3 for the applicable fuel assembly array/class.
d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A Cooling time 18 years and an average burnup 30,000 MWD/MTU (or MWD/MTIHM).

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

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

iv. All Other Array/Classes CooliAs specified in Section 2.4.ng time 3 years and an average burnup 65,000 MWD/MTUAs specified in Section 2.4.

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Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-20 Table 2.1-1 (page 14 of 2930)

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

A. Allowable Contents (continued)

e. Decay Heat Per Assembly
i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 115 Watts ii. Array/Class 8x8F 183.5 Watts iii. Array/Classes 10x10D and 10x10E 95 Watts iv. All Other Array/Classes As specified in Section 2.4.
f. Fuel Assembly Length
i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 135.0 inches (nominal design) ii. All Other Array/Classes 176.5 inches (nominal design)
g. Fuel Assembly Width
i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 4.70 inches (nominal design) ii. All Other Array/Classes 5.85 inches (nominal design)
h. Fuel Assembly Weight
i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 550 lbs, including channels and DFC ii. All Other Array/Classes 7830 lbs, including channels and DFC ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 30 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-21 Table 2.1-1 (page 15 of 2930)

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

A. Allowable Contents (continued)

3. Thoria rods (ThO2 and UO2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:
a. Cladding type ZR
b. Composition 98.2 wt.% ThO2, 1.8 wt.% UO2 with an enrichment of 93.5 wt.% 235U OR 98.5 wt.% ThO2, 1.5 wt.% UO2 with an enrichment of 93.5% wt.% 235U.
c. Number of Rods per Thoria Rod Canister:

18

d. Decay Heat Per Thoria Rod Canister:

115 Watts

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

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

f. Initial Heavy Metal Weight:

27 kg/canister

g. Fuel Cladding O.D.:

0.412 inches

h. Fuel Cladding I.D.:

0.362 inches

i. Fuel Pellet O.D.:

0.358 inches

j. Active Fuel Length:

111 inches

k. Canister Weight:

550 lbs, including fuel ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 31 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-22 Table 2.1-1 (page 16 of 2930)

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

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

1. For fuel assembly array/classes 6x6A, 6X6B, 6x6C, 7x7A, or 8x8A, up to 68 BWR INTACT FUEL ASSEMBLIES and/or DAMAGED FUEL ASSEMBLIES.

Up to eight (8) DFCs containing FUEL DEBRIS from these array/classes may be stored.

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

Uranium Oxide BWR INTACT FUEL ASSEMBLIES; or ii.

MOX BWR INTACT FUEL ASSEMBLIES.

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

D. Array/Class 10x10D and 10x10E fuel assemblies in stainless steel channels must be stored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 -

50 (see Figure 2.1-4).

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 32 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-23 Table 2.1-1 (page 17 of 2930)

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

1.

Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):

a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class

b. Initial Enrichment:

As specified in Table 2.1-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Classes 14x14D, 14x14E, and 15x15G Cooling time 8 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes Cooling time 3 years and an average As specified burnupin section 2.4.

68,200 MWD/MTUAs specified in Section 2.4.

iii. NON-FUEL HARDWARE As specified in Table 2.1-8.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 33 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-24 Table 2.1-1 (page 18 of 2930)

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

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:
i. Array/Classes 14x14D, 14x14E, and 15x15G 710 Watts.

ii. All other Array/Classes As specified in Section 2.4.

e. Fuel Assembly Length:

176.8 inches (nominal design)

f. Fuel Assembly Width:

8.54 inches (nominal design)

g. Fuel Assembly Weight:

1,720 lbs (including NON-FUEL HARDWARE) for assemblies that do not require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE)

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 34 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-25 Table 2.1-1 (page 19 of 2930)

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

A. Allowable Contents (continued)

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

Uranium oxide PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2.1-2 and meet the following specifications (Note 1):

a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class

b. Initial Enrichment:

As specified in Table 2.1-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Classes 14x14D, 14x14E, and 15x15G Cooling time 8 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes As specified in Section 2.4.Cooling time 3 years and an average burnup 68,200 MWD/MTUAs specified in Section 2.4.

iii. NON-FUEL HARDWARE As specified in Table 2.1-8.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 35 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-26 Table 2.1-1 (page 20 of 2930)

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

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:
i. Array/Classes 14x14D, 14x14E, and 15x15G 710 Watts.

ii. All Other Array/Classes As specified in Section 2.4.

e. Fuel Assembly Length 176.8 inches (nominal design)
f. Fuel Assembly Width 8.54 inches (nominal design)
g. Fuel Assembly Weight 1,720 lbs (including NON-FUEL HARDWARE and DFC) for assemblies that do not require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE and DFC)

B. Quantity per MPC: Up to four (4) DAMAGED FUEL ASSEMBLIES and/or FUEL DEBRIS in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 3, 6, 19 and/or 22. The remaining fuel storage locations may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.

C. One NSA is permitted for loading.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing APSRs or NSAs may only be loaded in fuel storage locations 9, 10, 15, and/or 16 (see Figure 2.1-2). Fuel assemblies containing CRAs, RCCAs, or CEAs may only be stored in fuel storage locations 4, 5, 8 - 11, 14 - 17, 20 and/or 21 (see Figure 2.1-2). These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 36 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-27 Table 2.1-1 (page 21 of 2930)

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

1.

Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):

a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class

b. Initial Enrichment:

As specified in Table 2.1-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Classes 14x14D, 14x14E, and 15x15G Cooling time 9 years and an average burnup 30,000 MWD/MTU or cooling time 20 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes CAs specified in Section 2.4.ooling time 3 years and an average burnup 68,200 MWD/MTUAs specified in Section 2.4.

iii. NON-FUEL HARDWARE As specified in Table 2.1-8.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 37 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-28 Table 2.1-1 (page 22 of 2930)

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

A. Allowable Contents (contd)

d. Decay Heat Per Fuel Storage Location:
i. Array/Classes 14x14D, 14x14E, and 15x15G 500 Watts.

ii. All Other Array/Classes As specified in Section 2.4.

e. Fuel Assembly Length 176.8 inches (nominal design)
f. Fuel Assembly Width 8.54 inches (nominal design)
g. Fuel Assembly Weight 1,720 lbs (including NON-FUEL HARDWARE) for assemblies that do not require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE)

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 38 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-29 Table 2.1-1 (page 23 of 2930)

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

A. Allowable Contents (contd)

2.

Uranium oxide, PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS, with or without NON-FUEL HARDWARE, placed in DAMAGED FUEL CONTAINERS. Uranium oxide PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2.1-2 and meet the following specifications (Note 1):

a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class

b. Initial Enrichment:

As specified in Table 2.1-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Classes 14x14D, 14x14E, and 15x15G Cooling time 9 years and an average burnup 30,000 MWD/MTU or cooling time 20 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes CooAs specified in Section 2.4.ling time 3 years and an average burnup 68,200 MWD/MTUAs specified in Section 2.4.

iii. NON-FUEL HARDWARE As specified in Table 2.1-8.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 39 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-30 Table 2.1-1 (page 24 of 2930)

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

A. Allowable Contents (contd)

d. Decay Heat Per Fuel Storage Location:
i. Array/Classes 14x14D, 14x14E, and 15x15G 500 Watts.

ii. All Other Array/Classes As specified in Section 2.4.

e. Fuel Assembly Length 176.8 inches (nominal design)
f. Fuel Assembly Width 8.54 inches (nominal design)
g. Fuel Assembly Weight 1,720 lbs (including NON-FUEL HARDWARE and DFC) for assemblies that do not require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE and DFC)

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

C.

One NSA is permitted for loading.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing NSAs may only be loaded in fuel storage locations 13, 14, 19 and/or 20 (see Figure 2.1-3). Fuel assemblies containing CRAs, RCCAs, CEAs or APSRs may only be loaded in fuel storage locations 7, 8, 12-15, 18-21, 25 and/or 26 (see Figure 2.1-3). These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 40 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-31 Table 2.1-1 (page 25 of 2930)

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

1. Uranium oxide BWR UNDAMAGED FUEL ASSEMBLIES listed in Table 2.1-3, with or without channels and meeting the following specifications:
a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment As specified in Table 2.1-3 for the applicable fuel assembly array/class.
d. Post-irradiation Cooling Time and Average Burnup Per Assembly
i. Array/Class 8x8F Cooling time 10 years and an average burnup 27,500 MWD/MTU.

ii. All Other Array/Classes CooliAs specified in Section 2.4.ng time 3 years and an average burnup 65,000 MWD/MTUAs specified in Section 2.4.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 41 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-32 Table 2.1-1 (page 26 of 2930)

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

A. Allowable Contents (continued)

e. Decay Heat Per Assembly
i. Array/Class 8x8F 183.5 Watts ii. All Other Array/Classes As specified in Section 2.4.
f. Fuel Assembly Length 176.5 inches (nominal design)
g. Fuel Assembly Width 5.85 inches (nominal design)
h. Fuel Assembly Weight 730 lbs, including channels ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 42 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-33 Table 2.1-1 (page 27 of 2930)

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

A. Allowable Contents (continued)

2. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, with or without channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2.1-3, and meet the following specifications:
a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment As specified in Table 2.1-3 for the applicable fuel assembly array/class.
d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Class 8x8F Cooling time 10 years and an average burnup 27,500 MWD/MTU.

ii. All Other Array/Classes ACooling times specified in Section 2.4.

3 years and an average burnup 65,000 MWD/MTUAs specified in Section 2.4.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 43 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-34 Table 2.1-1 (page 28 of 2930)

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

A. Allowable Contents (continued)

e. Decay Heat Per Assembly
i. Array/Class 8x8F 183.5 Watts ii. All Other Array/Classes As specified in Section 2.4.
f. Fuel Assembly Length 176.5 inches (nominal design)
g. Fuel Assembly Width 5.85 inches (nominal design)
h. Fuel Assembly Weight 7830 lbs, including channels and DFC ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 44 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-35 Table 2.1-1 (page 29 of 2930)

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

A. Allowable Contents (continued)

3. Thoria rods (ThO2 and UO2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:
a. Cladding type ZR
b. Composition 98.2 wt.% ThO2, 1.8 wt.% UO2 with an enrichment of 93.5 wt.% 235U OR 98.5 wt.% ThO2, 1.5 wt.% UO2 with an enrichment of 93.5% wt.% 235U
c. Number of Rods per Thoria Rod Canister:

18

d. Decay Heat Per Thoria Rod Canister:

115 Watts

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

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

f. Initial Heavy Metal Weight:

27 kg/canister

g. Fuel Cladding O.D.:

0.412 inches

h. Fuel Cladding I.D.:

0.362 inches

i. Fuel Pellet O.D.:

0.358 inches

j. Active Fuel Length:

111 inches

k. Canister Weight:

550 lbs, including fuel ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 45 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-36 Table 2.1-1 (page 30 of 30)

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

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

1. Up to sixteen (16) DFCs containing BWR DAMAGED FUEL ASSEMBLIES and/or up to eight (8) DFCs containing FUEL DEBRIS. DFCs shall be located only in fuel storage locations 1, 2, 3, 8, 9, 16, 25, 34, 35, 44, 53, 60, 61, 66, 67, and/or 68. The remaining fuel storage locations may be filled with Uranium Oxide BWR UNDAMAGED FUEL ASSEMBLIES.
2. Up to one (1) Dresden Unit 1 Thoria Rod Canister ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 46 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-45 Table 2.1-3 (page 4 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

(Note 3)

< 188

< 188

< 179

< 125

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

(wt.% 235U) (Note 14)

< 4.2

< 4.2

< 4.2

< 4.0

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

(wt.% 235U)

(Note 16, 19) 4.8 4.8 4.8 Note 18 Note 18 4.7 (Note 15) 4.675 (Note 15)

Initial Maximum Rod Enrichment (wt.% 235U)

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0 No. of Fuel Rod Locations 92/78 (Note 8) 91/83 (Note 9) 96 100 96 92/78 (Note 8) 96/84 Fuel Rod Clad O.D.

(in.)

> 0.4040

> 0.3957

> 0.3780

> 0.3960

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

< 0.3520

< 0.3480

< 0.3294

< 0.3560

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

< 0.3455

< 0.3420

< 0.3224

< 0.3500

< 0.3430 0.3500 0.334 Fuel Rod Pitch (in.)

< 0.510

< 0.510

< 0.488

< 0.565

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

< 150

< 150

< 150

< 83

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

(Note 6) 5 (Note 10) 0 4

2 5

(Note 10)

Water Rod Thickness (in.)

> 0.030

> 0.00

> 0.031 N/A

> 0.022 0.030 0.031 Channel Thickness (in.)

< 0.120

< 0.120

< 0.055

< 0.080

< 0.080 0.120 0.060 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 47 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-46 Table 2.1-3 (page 5 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS Notes:

1. All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
2. Deleted.
3. Design initial uranium weight is the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each BWR fuel assembly, the total uranium weight limit specified in this table may be increased up to 1.5 percent for comparison with users fuel records to account for manufacturer tolerances.
4. 0.635 wt. % 235U and 1.578 wt. % total fissile plutonium (239Pu and 241Pu),

(wt. % of total fuel weight, i.e., UO2 plus PuO2).

5. This assembly class contains 74 total rods; 66 full length rods and 8 partial length rods.
6. Square, replacing nine fuel rods.
7. Variable.
8. This assembly contains 92 total fuel rods; 78 full length rods and 14 partial length rods.
9. This assembly class contains 91 total fuel rods; 83 full length rods and 8 partial length rods.
10. One diamond-shaped water rod replacing the four center fuel rods and four rectangular water rods dividing the assembly into four quadrants.
11. These rods may also be sealed at both ends and contain Zr material in lieu of water.
12. This assembly is known as QUAD+. It has four rectangular water cross segments dividing the assembly into four quadrants.
13. For the SPC 9x9-5 fuel assembly, each fuel rod must meet either the 9x9E or the 9x9F set of limits for clad O.D., clad I.D., and pellet diameter.
14. For MPC-68, 68F, and 68FF loaded with both INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, the maximum PLANAR AVERAGE INITIAL ENRICHMENT for the INTACT FUEL ASSEMBLIES is limited to 3.7 wt.% 235U, as applicable.
15. Fuel assemblies classified as damaged fuel assemblies are limited to 4.6 wt.%

235U for the 10x10F and 10x10G arrays/classes and 4.0 wt.% 235U for the 8x8F, 9x9E, and 9x9F and 10x10G arrays/classes.

16. For MPC-68M loaded with both UNDAMAGED FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, the maximum PLANAR AVERAGE INITIAL ENRICHMENT for the UNDAMAGED FUEL ASSEMBLIES is limited to the enrichment limit of the damaged assembly.
17. This fuel assembly array/class is not allowable contents in MPC-68, 68F, or 68FF.
18. This fuel assembly array/class is not allowable contents in MPC-68M.
19. In accordance with the definition of UNDAMAGED FUEL ASSEMBLY, certain assemblies may be limited to up to 3.3 wt.% U-235. When loading these fuel ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 48 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-47 assemblies, all other undamaged fuel assemblies in the MPC are limited to 3.3 wt% U-235enrichments as specified in this table.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 49 of 73

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 2-48 Table 2.1-8 NON-FUEL HARDWARE COOLING AND AVERAGE BURNUP (Notes 1, 2, 3, and 7)

Notes: 1. Burnups for NON-FUEL HARDWARE are to be determined based on the burnup and uranium mass of the fuel assemblies in which the component was inserted during reactor operation.

2. Linear interpolation between points is permitted, except that APSR burnups > 180,000 MWD/MTU and < 630,000 MWD/MTU must be cooled > 11 years.
3. Applicable to uniform loading and regionalized loading.
4. Includes Burnable Poison Rod Assemblies (BPRAs), Wet Annular Burnable Absorbers (WABAs), and vibration suppressor inserts and Neutron Source Assemblies (NSAs) in combination with other control components (i.e. BPRAs, TPDs, and/or RCCAs).
5. Includes Thimble Plug Devices (TPDs), water displacement guide tube plugs, orifice rod assemblies, Control Rod Assemblies (CRAs), Control Element Assemblies (CEAs), and Rod Cluster Control Assemblies (RCCAs). and NSAs without other forms of control components.
6. NA means not authorized for loading at this cooling time.
7. Non-fuel hardware burnup and cooling times are not applicable to ITTRs since they are installed post irradiation.

Post-irradiation Cooling Time (years)

NSA with NFH INSERTS (Note 4)

BURNUP (MWD/MTU)

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

BURNUP (MWD/MTU)

APSR BURNUP (MWD/MTU)

> 3

< 24,635 NA (Note 6)

NA

> 4

< 30,000 NA NA

> 5

< 36,748

< 630,000

< 45,000

> 6

< 44,102

< 54,500

> 7

< 52,900

< 68,000

> 8

< 60,000

< 83,000

> 9

< 79,784-

< 111,000

> 10

< 101,826-

< 180,000

> 11

< 141,982-

< 630,000

> 12

< 360,000 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 50 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-49 2.4 Decay Heat Limits for ZR-Clad Fuel This section provides the limits on ZR-clad fuel assembly decay heat for storage in the HI-STORM 100 System. The method to calculate the limits and verify compliance, including examples, is provided in Chapter 12 of the HI-STORM 100 FASR.

2.4.1 Uniform Fuel Loading Decay Heat Limits for ZR-clad fuel Table 2.4-1 provides the maximum allowable decay heat per fuel storage location for ZR-clad fuel in uniform fuel loading for each MPC model.

Table 2.4-1 Maximum Allowable Decay Heat per Fuel Storage Location (Uniform Loading, ZR-Clad)

MPC Model Decay Heat per Fuel Storage Location (kW)

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

< 1.416 Not Permitted MPC-24E/24EF

< 1.416

< 1.114 MPC-32/32F

< 1.062

< 0.718 MPC-68/68FF/68M

< 0.500

< 0.393 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 51 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-51 2.4.3 Burmup Limits as a Function of Cooling Time The maximum allowable fuel assembly average burnup varies with the following parameters:

Minimum fuel assembly cooling time Maximum fuel assembly decay heat Minimum fuel assembly average enrichment The maximum allowable ZR-clad fuel assembly average burnup for a given MINIMUM ENRICHMENT is calculated as described below for minimum cooling times between 3 and 20 years using the maximum permissible decay heat determined in Section 2.4.1 or 2.4.2. Different fuel assembly average burnup limits may be calculated for different minimum enrichments (by individual fuel assembly) for use in choosing the fuel assemblies to be loaded into a given MPC.

2.4.3.1 Choose a fuel assembly minimum enrichment, E235.

2.4.3.2 Calculate the maximum allowable fuel assembly average burnup for a minimum cooling time between 3 and 20 years using the equation below.

Bu = (A x q) + (B x q2) + (C X q3) + [D x (E235)2] + (E x q x E235) + (F x q2 x E235) + G Where:

Bu = Maximum allowable average burnup per fuel assembly (MWD/MTU) q = Maximum allowable decay heat per fuel storage location determined in Section 2.4.1 or 2.4.2 (kW)

E235 =Minimum fuel assembly average enrichment (wt. %

235U)

(e.g., for 4.05 wt.%, use 4.05)

A through G = Coefficients from Tables 2.4-3 and 2.4-4 for the applicable fuel assembly array/class and minimum cooling time 2.4.3.3 Calculated burnup limits shall be rounded down to the nearest integer.

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

2.4.3.5 Linear interpolation of calculated burnups between cooling times for a given fuel assembly maximum decay heat and minimum enrichment is permitted. For example, the allowable burnup for a cooling time of 4.5 years may be in.terpolated between those burnups calculated for 4 year and 5 years.

2.4.3.6 Each ZR-clad fuel assembly to be stored must have a ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 52 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-52 MINIMUM ENRICHMENT greater than or equal to the value used in Step 2.4.3.2 2.4.4 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.

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 53 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-53 Table 2.4.3 PWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 14x14A A

B C

D E

F G

> 3 19311.5 275.367

-59.0252

-139.41 2851.12

-451.845

-615.413

> 4 33865.9

-5473.03 851.121

-132.739 3408.58

-656.479

-609.523

> 5 46686.2

-13226.9 2588.39

-150.149 3871.87

-806.533

-90.2065

> 6 56328.9

-20443.2 4547.38

-176.815 4299.19

-927.358 603.192

> 7 64136

-27137.5 6628.18

-200.933 4669.22

-1018.94 797.162

> 8 71744.1

-34290.3 9036.9

-214.249 4886.95

-1037.59 508.703

> 9 77262

-39724.2 11061

-228.2 5141.35

-1102.05 338.294

> 10 82939.8

-45575.6 13320.2

-233.691 5266.25

-1095.94

-73.3159

> 11 86541

-49289.6 14921.7

-242.092 5444.54

-1141.6

-83.0603

> 12 91383

-54456.7 17107

-242.881 5528.7

-1149.2

-547.579

> 13 95877.6

-59404.7 19268

-240.36 5524.35

-1094.72

-933.64

> 14 97648.3

-61091.6 20261.7

-244.234 5654.56

-1151.47

-749.836

> 15 102533

-66651.5 22799.7

-240.858 5647.05

-1120.32

-1293.34

> 16 106216

-70753.8 24830.1

-237.04 5647.63

-1099.12

-1583.89

> 17 109863

-75005 27038

-234.299 5652.45

-1080.98

-1862.07

> 18 111460

-76482.3 28076.5

-234.426 5703.52

-1104.39

-1695.77

> 19 114916

-80339.6 30126.5

-229.73 5663.21

-1065.48

-1941.83

> 20 119592

-86161.5 33258.2

-227.256 5700.49

-1100.21

-2474.01 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 54 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-54 Table 2.4-3 (contd)

PWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 14x14B A

B C

D E

F G

> 3 18036.1 63.7639

-24.7251

-130.732 2449.87

-347.748

-858.192

> 4 30303.4

-4304.2 598.79

-118.757 2853.18

-486.453

-459.902

> 5 40779.6

-9922.93 1722.83

-138.174 3255.69

-608.267 245.251

> 6 48806.7

-15248.9 3021.47

-158.69 3570.24

-689.876 833.917

> 7 55070.5

-19934.6 4325.62

-179.964 3870.33

-765.849 1203.89

> 8 60619.6

-24346 5649.29

-189.701 4042.23

-795.324 1158.12

> 9 64605.7

-27677.1 6778.12

-205.459 4292.35

-877.966 1169.88

> 10 69083.8

-31509.4 8072.42

-206.157 4358.01

-875.041 856.449

> 11 72663.2

-34663.9 9228.96

-209.199 4442.68

-889.512 671.567

> 12 74808.9

-36367 9948.88

-214.344 4571.29

-942.418 765.261

> 13 78340.3

-39541.1 11173.8

-212.8 4615.06

-957.833 410.807

> 14 81274.8

-42172.3 12259.9

-209.758 4626.13

-958.016 190.59

> 15 83961.4

-44624.5 13329.1

-207.697 4632.16

-952.876 20.8575

> 16 84968.5

-44982.1 13615.8

-207.171 4683.41

-992.162 247.54

> 17 87721.6

-47543.1 14781.4

-203.373 4674.3

-988.577 37.9689

> 18 90562.9

-50100.4 15940.4

-198.649 4651.64

-982.459

-247.421

> 19 93011.6

-52316.6 17049.9

-194.964 4644.76

-994.63

-413.021

> 20 95567.8

-54566.6 18124

-190.22 4593.92

-963.412

-551.983 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 55 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-55 Table 2.4-3 (contd)

PWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 14x14C A

B C

D E

F G

> 3 18263.7 174.161

-57.6694

-138.112 2539.74

-369.764

-1372.33

> 4 30514.5

-4291.52 562.37

-124.944 2869.17

-481.139

-889.883

> 5 41338

-10325.7 1752.96

-141.247 3146.48

-535.709

-248.078

> 6 48969.7

-15421.3 2966.33

-163.574 3429.74

-587.225 429.331

> 7 55384.6

-20228.9 4261.47

-180.846 3654.55

-617.255 599.251

> 8 60240.2

-24093.2 5418.86

-199.974 3893.72

-663.995 693.934

> 9 64729

-27745.7 6545.45

-205.385 3986.06

-650.124 512.528

> 10 68413.7

-30942.2 7651.29

-216.408 4174.71

-702.931 380.431

> 11 71870.6

-33906.7 8692.81

-218.813 4248.28

-704.458 160.645

> 12 74918.4

-36522 9660.01

-218.248 4283.68

-696.498

-29.0682

> 13 77348.3

-38613.7 10501.8

-220.644 4348.23

-702.266

-118.646

> 14 79817.1

-40661.8 11331.2

-218.711 4382.32

-710.578

-236.123

> 15 82354.2

-42858.3 12257.3

-215.835 4405.89

-718.805

-431.051

> 16 84787.2

-44994.5 13185.9

-213.386 4410.99

-711.437

-572.104

> 17 87084.6

-46866.1 14004.8

-206.788 4360.3

-679.542

-724.721

> 18 88083.1

-47387.1 14393.4

-208.681 4420.85

-709.311

-534.454

> 19 90783.6

-49760.6 15462.7

-203.649 4403.3

-705.741

-773.066

> 20 93212

-51753.3 16401.5

-197.232 4361.65

-692.925

-964.628 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 56 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-56 Table 2.4-3 (contd)

PWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 15x15A/B/C A

B C

D E

F G

> 3 15037.3 108.689

-18.8378

-127.422 2050.02

-242.828

-580.66

> 4 25506.6

-2994.03 356.834

-116.45 2430.25

-350.901

-356.378

> 5 34788.8

-7173.07 1065.9

-124.785 2712.23

-424.681 267.705

> 6 41948.6

-11225.3 1912.12

-145.727 3003.29

-489.538 852.112

> 7 47524.9

-14770.9 2755.16

-165.889 3253.9

-542.7 1146.96

> 8 52596.9

-18348.8 3699.72

-177.17 3415.69

-567.012 1021.41

> 9 56055.4

-20837.1 4430.93

-192.168 3625.93

-623.325 1058.61

> 10 59611.3

-23402.1 5179.52

-195.105 3699.18

-626.448 868.517

> 11 62765.3

-25766.5 5924.71

-195.57 3749.91

-627.139 667.124

> 12 65664.4

-28004.8 6670.75

-195.08 3788.33

-628.904 410.783

> 13 67281.7

-29116.7 7120.59

-202.817 3929.38

-688.738 492.309

> 14 69961.4

-31158.6 7834.02

-197.988 3917.29

-677.565 266.561

> 15 72146

-32795.7 8453.67

-195.083 3931.47

-681.037 99.0606

> 16 74142.6

-34244.8 9023.57

-190.645 3905.54

-663.682 10.8885

> 17 76411.4

-36026.3 9729.98

-188.874 3911.21

-663.449

-151.805

> 18 77091

-36088 9884.09

-188.554 3965.08

-708.55 59.3839

> 19 79194.5

-37566.4 10477.5

-181.656 3906.93

-682.4

-117.952

> 20 81600.4

-39464.5 11281.9

-175.182 3869.49

-677.179

-367.705 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 57 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-57 Table 2.4-3 (contd)

PWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 15x15D/E/F/H/I A

B C

D E

F G

> 3 14376.7 102.205

-20.6279

-126.017 1903.36

-210.883

-493.065

> 4 24351.4

-2686.57 297.975

-110.819 2233.78

-301.615

-152.713

> 5 33518.4

-6711.35 958.544

-122.85 2522.7

-371.286 392.608

> 6 40377

-10472.4 1718.53

-144.535 2793.29

-426.436 951.528

> 7 46105.8

-13996.2 2515.32

-157.827 2962.46

-445.314 1100.56

> 8 50219.7

-16677.7 3198.3

-175.057 3176.74

-492.727 1223.62

> 9 54281.2

-19555.6 3983.47

-181.703 3279.03

-499.997 1034.55

> 10 56761.6

-21287.3 4525.98

-195.045 3470.41

-559.074 1103.3

> 11 59820

-23445.2 5165.43

-194.997 3518.23

-561.422 862.68

> 12 62287.2

-25164.6 5709.9

-194.771 3552.69

-561.466 680.488

> 13 64799

-27023.7 6335.16

-192.121 3570.41

-561.326 469.583

> 14 66938.7

-28593.1 6892.63

-194.226 3632.92

-583.997 319.867

> 15 68116.5

-29148.6 7140.09

-192.545 3670.39

-607.278 395.344

> 16 70154.9

-30570.1 7662.91

-187.366 3649.14

-597.205 232.318

> 17 72042.5

-31867.6 8169.01

-183.453 3646.92

-603.907 96.0388

> 18 73719.8

-32926.1 8596.12

-177.896 3614.57

-592.868 46.6774

> 19 75183.1

-33727.4 8949.64

-172.386 3581.13

-586.347 3.57256

> 20 77306.1

-35449 9690.02

-173.784 3636.87

-626.321

-205.513 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 58 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-58 Table 2.4-3 (contd)

PWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 16x16A A

B C

D E

F G

> 3 16226.8 143.714

-32.4809

-136.707 2255.33

-291.683

-699.947

> 4 27844.2

-3590.69 444.838

-124.301 2644.09

-411.598

-381.106

> 5 38191.5

-8678.48 1361.58

-132.855 2910.45

-473.183 224.473

> 6 46382.2

-13819.6 2511.32

-158.262 3216.92

-532.337 706.656

> 7 52692.3

-18289 3657.18

-179.765 3488.3

-583.133 908.839

> 8 57758.7

-22133.7 4736.88

-199.014 3717.42

-618.83 944.903

> 9 62363.3

-25798.7 5841.18

-207.025 3844.38

-625.741 734.928

> 10 66659.1

-29416.3 6993.31

-216.458 3981.97

-642.641 389.366

> 11 69262.7

-31452.7 7724.66

-220.836 4107.55

-681.043 407.121

> 12 72631.5

-34291.9 8704.8

-219.929 4131.5

-662.513 100.093

> 13 75375.3

-36589.3 9555.88

-217.994 4143.15

-644.014

-62.3294

> 14 78178.7

-39097.1 10532

-221.923 4226.28

-667.012

-317.743

> 15 79706.3

-40104 10993.3

-218.751 4242.12

-670.665

-205.579

> 16 82392.6

-42418.9 11940.7

-216.278 4274.09

-689.236

-479.752

> 17 84521.8

-44150.5 12683.3

-212.056 4245.99

-665.418

-558.901

> 18 86777.1

-45984.8 13479

-204.867 4180.8

-621.805

-716.366

> 19 89179.7

-48109.8 14434.5

-206.484 4230.03

-648.557

-902.1

> 20 90141.7

-48401.4 14702.6

-203.284 4245.54

-670.655

-734.604 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 59 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-59 Table 2.4-3 (contd)

PWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 17x17A/16x16B/C A

B C

D E

F G

> 3 15985.1 3.53963

-9.04955

-128.835 2149.5

-260.415

-262.997

> 4 27532.9

-3494.41 428.199

-119.504 2603.01

-390.91

-140.319

> 5 38481.2

-8870.98 1411.03

-139.279 3008.46

-492.881 388.377

> 6 47410.9

-14479.6 2679.08

-162.13 3335.48

-557.777 702.164

> 7 54596.8

-19703.2 4043.46

-181.339 3586.06

-587.634 804.05

> 8 60146.1

-24003.4 5271.54

-201.262 3830.32

-621.706 848.454

> 9 65006.3

-27951 6479.04

-210.753 3977.69

-627.805 615.84

> 10 69216

-31614.7 7712.58

-222.423 4173.4

-672.33 387.879

> 11 73001.3

-34871.1 8824.44

-225.128 4238.28

-657.259 101.654

> 12 76326.1

-37795.9 9887.35

-226.731 4298.11

-647.55

-122.236

> 13 78859.9

-40058.9 10797.1

-231.798 4402.14

-669.982

-203.383

> 14 82201.3

-43032.5 11934.1

-228.162 4417.99

-661.61

-561.969

> 15 84950

-45544.6 12972.4

-225.369 4417.84

-637.422

-771.254

> 16 87511.8

-47720 13857.7

-219.255 4365.24

-585.655

-907.775

> 17 90496.4

-50728.9 15186

-223.019 4446.51

-613.378

-1200.94

> 18 91392.5

-51002.4 15461.4

-220.272 4475.28

-636.398

-1003.81

> 19 94343.9

-53670.8 16631.6

-214.045 4441.31

-616.201

-1310.01

> 20 96562.9

-55591.2 17553.4

-209.917 4397.67

-573.199

-1380.64 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 60 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-60 Table 2.4-3 (contd)

PWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 17x17B/C A

B C

D E

F G

> 3 14738 47.5402

-13.8187

-127.895 1946.58

-219.289

-389.029

> 4 25285.2

-3011.92 350.116

-115.75 2316.89

-319.23

-220.413

> 5 34589.6

-7130.34 1037.26

-128.673 2627.27

-394.58 459.642

> 6 42056.2

-11353.7 1908.68

-150.234 2897.38

-444.316 923.971

> 7 47977.6

-15204.8 2827.4

-173.349 3178.25

-504.16 1138.82

> 8 52924

-18547.6 3671.08

-183.025 3298.64

-501.278 1064.68

> 9 56465.5

-21139.4 4435.67

-200.386 3538

-569.712 1078.78

> 10 60190.9

-23872.7 5224.31

-203.233 3602.88

-562.312 805.336

> 11 63482.1

-26431.1 6035.79

-205.096 3668.84

-566.889 536.011

> 12 66095

-28311.8 6637.72

-204.367 3692.68

-555.305 372.223

> 13 67757.4

-29474.4 7094.08

-211.649 3826.42

-606.886 437.412

> 14 70403.7

-31517.4 7807.15

-207.668 3828.69

-601.081 183.09

> 15 72506.5

-33036.1 8372.59

-203.428 3823.38

-594.995 47.5175

> 16 74625.2

-34620.5 8974.32

-199.003 3798.57

-573.098

-95.0221

> 17 76549

-35952.6 9498.14

-193.459 3766.52

-556.928

-190.662

> 18 77871.9

-36785.5 9916.91

-195.592 3837.65

-599.45

-152.261

> 19 79834.8

-38191.6 10501.9

-190.83 3812.46

-589.635

-286.847

> 20 81975.5

-39777.2 11174.5

-185.767 3795.78

-595.664

-475.978 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 61 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-61 Table 2.4-4 BWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 7x7B & 10x10F A

B C

D E

F G

> 3 26409.1 28347.5

-16858

-147.076 5636.32

-1606.75 1177.88

> 4 61967.8

-6618.31

-4131.96

-113.949 6122.77

-2042.85

-96.7439

> 5 91601.1

-49298.3 17826.5

-132.045 6823.14

-2418.49

-185.189

> 6 111369

-80890.1 35713.8

-150.262 7288.51

-2471.1 86.6363

> 7 126904

-108669 53338.1

-167.764 7650.57

-2340.78 150.403

> 8 139181

-132294 69852.5

-187.317 8098.66

-2336.13 97.5285

> 9 150334

-154490 86148.1

-193.899 8232.84

-2040.37

-123.029

> 10 159897

-173614 100819

-194.156 8254.99

-1708.32

-373.605

> 11 166931

-186860 111502

-193.776 8251.55

-1393.91

-543.677

> 12 173691

-201687 125166

-202.578 8626.84

-1642.3

-650.814

> 13 180312

-215406 137518

-201.041 8642.19

-1469.45

-810.024

> 14 185927

-227005 148721

-197.938 8607.6

-1225.95

-892.876

> 15 191151

-236120 156781

-191.625 8451.86

-846.27

-1019.4

> 16 195761

-244598 165372

-187.043 8359.19

-572.561

-1068.19

> 17 200791

-256573 179816

-197.26 8914.28

-1393.37

-1218.63

> 18 206068

-266136 188841

-187.191 8569.56

-730.898

-1363.79

> 19 210187

-273609 197794

-182.151 8488.23

-584.727

-1335.59

> 20 213731

-278120 203074

-175.864 8395.63

-457.304

-1364.38 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 62 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-62 Table 2.4-4 (contd)

BWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 8x8B A

B C

D E

F G

> 3 28219.6 28963.7

-17616.2

-147.68 5887.41

-1730.96 1048.21

> 4 66061.8

-10742.4

-1961.82

-123.066 6565.54

-2356.05

-298.005

> 5 95790.7

-53401.7 19836.7

-134.584 7145.41

-2637.09

-298.858

> 6 117477

-90055.9 41383.9

-154.758 7613.43

-2612.69

-64.9921

> 7 134090

-120643 60983

-168.675 7809

-2183.3

-40.8885

> 8 148186

-149181 81418.7

-185.726 8190.07

-2040.31

-260.773

> 9 159082

-172081 99175.2

-197.185 8450.86

-1792.04

-381.705

> 10 168816

-191389 113810

-195.613 8359.87

-1244.22

-613.594

> 11 177221

-210599 131099

-208.3 8810

-1466.49

-819.773

> 12 183929

-224384 143405

-207.497 8841.33

-1227.71

-929.708

> 13 191093

-240384 158327

-204.95 8760.17

-811.708

-1154.76

> 14 196787

-252211 169664

-204.574 8810.95

-610.928

-1208.97

> 15 203345

-267656 186057

-208.962 9078.41

-828.954

-1383.76

> 16 207973

-276838 196071

-204.592 9024.17

-640.808

-1436.43

> 17 213891

-290411 211145

-202.169 9024.19

-482.1

-1595.28

> 18 217483

-294066 214600

-194.243 8859.35

-244.684

-1529.61

> 19 220504

-297897 219704

-190.161 8794.97

-10.9863

-1433.86

> 20 227821

-318395 245322

-194.682 9060.96

-350.308

-1741.16 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 63 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-63 Table 2.4-4 (contd)

BWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 8x8C/D/E A

B C

D E

F G

> 3 28592.7 28691.5

-17773.6

-149.418 5969.45

-1746.07 1063.62

> 4 66720.8

-12115.7

-1154

-128.444 6787.16

-2529.99

-302.155

> 5 96929.1

-55827.5 21140.3

-136.228 7259.19

-2685.06

-334.328

> 6 118190

-92000.2 42602.5

-162.204 7907.46

-2853.42

-47.5465

> 7 135120

-123437 62827.1

-172.397 8059.72

-2385.81

-75.0053

> 8 149162

-152986 84543.1

-195.458 8559.11

-2306.54

-183.595

> 9 161041

-177511 103020

-200.087 8632.84

-1864.4

-433.081

> 10 171754

-201468 122929

-209.799 8952.06

-1802.86

-755.742

> 11 179364

-217723 137000

-215.803 9142.37

-1664.82

-847.268

> 12 186090

-232150 150255

-216.033 9218.36

-1441.92

-975.817

> 13 193571

-249160 165997

-213.204 9146.99

-1011.13

-1119.47

> 14 200034

-263671 180359

-210.559 9107.54

-694.626

-1312.55

> 15 205581

-275904 193585

-216.242 9446.57

-1040.65

-1428.13

> 16 212015

-290101 207594

-210.036 9212.93

-428.321

-1590.7

> 17 216775

-299399 218278

-204.611 9187.86

-398.353

-1657.6

> 18 220653

-306719 227133

-202.498 9186.34

-181.672

-1611.86

> 19 224859

-314004 235956

-193.902 8990.14 145.151

-1604.71

> 20 228541

-320787 245449

-200.727 9310.87

-230.252

-1570.18 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 64 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-64 Table 2.4-4 (contd)

BWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 9x9A A

B C

D E

F G

> 3 30538.7 28463.2

-18105.5

-150.039 6226.92

-1876.69 1034.06

> 4 71040.1

-16692.2 1164.15

-128.241 7105.27

-2728.58

-414.09

> 5 100888

-60277.7 24150.1

-142.541 7896.11

-3272.86

-232.197

> 6 124846

-102954 50350.8

-161.849 8350.16

-3163.44

-91.1396

> 7 143516

-140615 76456.5

-185.538 8833.04

-2949.38

-104.802

> 8 158218

-171718 99788.2

-196.315 9048.88

-2529.26

-259.929

> 9 172226

-204312 126620

-214.214 9511.56

-2459.19

-624.954

> 10 182700

-227938 146736

-215.793 9555.41

-1959.92

-830.943

> 11 190734

-246174 163557

-218.071 9649.43

-1647.5

-935.021

> 12 199997

-269577 186406

-223.975 9884.92

-1534.34

-1235.27

> 13 207414

-287446 204723

-228.808 10131.7

-1614.49

-1358.61

> 14 215263

-306131 223440

-220.919 9928.27

-988.276

-1638.05

> 15 221920

-321612 239503

-217.949 9839.02

-554.709

-1784.04

> 16 226532

-331778 252234

-216.189 9893.43

-442.149

-1754.72

> 17 232959

-348593 272609

-219.907 10126.3

-663.84

-1915.3

> 18 240810

-369085 296809

-219.729 10294.6

-859.302

-2218.87

> 19 244637

-375057 304456

-210.997 10077.8

-425.446

-2127.83

> 20 248112

-379262 309391

-204.191 9863.67 100.27

-2059.39 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 65 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-65 Table 2.4-4 (contd)

BWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 9x9B A

B C

D E

F G

> 3 30613.2 28985.3

-18371

-151.117 6321.55

-1881.28 988.92

> 4 71346.6

-15922.9 631.132

-128.876 7232.47

-2810.64

-471.737

> 5 102131

-60654.1 23762.7

-140.748 7881.6

-3156.38

-417.979

> 6 127187

-105842 51525.2

-162.228 8307.4

-2913.08

-342.13

> 7 146853

-145834 79146.5

-185.192 8718.74

-2529.57

-484.885

> 8 162013

-178244 103205

-197.825 8896.39

-1921.58

-584.013

> 9 176764

-212856 131577

-215.41 9328.18

-1737.12

-1041.11

> 10 186900

-235819 151238

-218.98 9388.08

-1179.87

-1202.83

> 11 196178

-257688 171031

-220.323 9408.47

-638.53

-1385.16

> 12 205366

-280266 192775

-223.715 9592.12

-472.261

-1661.6

> 13 215012

-306103 218866

-231.821 9853.37

-361.449

-1985.56

> 14 222368

-324558 238655

-228.062 9834.57 3.47358

-2178.84

> 15 226705

-332738 247316

-224.659 9696.59 632.172

-2090.75

> 16 233846

-349835 265676

-221.533 9649.93 913.747

-2243.34

> 17 243979

-379622 300077

-222.351 9792.17 1011.04

-2753.36

> 18 247774

-386203 308873

-220.306 9791.37 1164.58

-2612.25

> 19 254041

-401906 327901

-213.96 9645.47 1664.94

-2786.2

> 20 256003

-402034 330566

-215.242 9850.42 1359.46

-2550.06 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 66 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-66 Table 2.4-4 (contd)

BWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 9x9C/D A

B C

D E

F G

> 3 30051.6 29548.7

-18614.2

-148.276 6148.44

-1810.34 1006

> 4 70472.7

-14696.6

-233.567

-127.728 7008.69

-2634.22

-444.373

> 5 101298

-59638.9 23065.2

-138.523 7627.57

-2958.03

-377.965

> 6 125546

-102740 49217.4

-160.811 8096.34

-2798.88

-259.767

> 7 143887

-139261 74100.4

-184.302 8550.86

-2517.19

-275.151

> 8 159633

-172741 98641.4

-194.351 8636.89

-1838.81

-486.731

> 9 173517

-204709 124803

-212.604 9151.98

-1853.27

-887.137

> 10 182895

-225481 142362

-218.251 9262.59

-1408.25

-978.356

> 11 192530

-247839 162173

-217.381 9213.58

-818.676

-1222.12

> 12 201127

-268201 181030

-215.552 9147.44

-232.221

-1481.55

> 13 209538

-289761 203291

-225.092 9588.12

-574.227

-1749.35

> 14 216798

-306958 220468

-222.578 9518.22

-69.9307

-1919.71

> 15 223515

-323254 237933

-217.398 9366.52 475.506

-2012.93

> 16 228796

-334529 250541

-215.004 9369.33 662.325

-2122.75

> 17 237256

-356311 273419

-206.483 9029.55 1551.3

-2367.96

> 18 242778

-369493 290354

-215.557 9600.71 659.297

-2589.32

> 19 246704

-377971 302630

-210.768 9509.41 1025.34

-2476.06

> 20 249944

-382059 308281

-205.495 9362.63 1389.71

-2350.49 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 67 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-67 Table 2.4-4 (contd)

BWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 9x9E/F A

B C

D E

F G

> 3 30284.3 26949.5

-16926.4

-147.914 6017.02

-1854.81 1026.15

> 4 69727.4

-17117.2 1982.33

-127.983 6874.68

-2673.01

-359.962

> 5 98438.9

-58492 23382.2

-138.712 7513.55

-3038.23

-112.641

> 6 119765

-95024.1 45261

-159.669 8074.25

-3129.49 221.182

> 7 136740

-128219 67940.1

-182.439 8595.68

-3098.17 315.544

> 8 150745

-156607 88691.5

-193.941 8908.73

-2947.64 142.072

> 9 162915

-182667 109134

-198.37 8999.11

-2531

-93.4908

> 10 174000

-208668 131543

-210.777 9365.52

-2511.74

-445.876

> 11 181524

-224252 145280

-212.407 9489.67

-2387.49

-544.123

> 12 188946

-240952 160787

-210.65 9478.1

-2029.94

-652.339

> 13 193762

-250900 171363

-215.798 9742.31

-2179.24

-608.636

> 14 203288

-275191 196115

-218.113 9992.5

-2437.71

-1065.92

> 15 208108

-284395 205221

-213.956 9857.25

-1970.65

-1082.94

> 16 215093

-301828 224757

-209.736 9789.58

-1718.37

-1303.35

> 17 220056

-310906 234180

-201.494 9541.73

-1230.42

-1284.15

> 18 224545

-320969 247724

-206.807 9892.97

-1790.61

-1381.9

> 19 226901

-322168 250395

-204.073 9902.14

-1748.78

-1253.22

> 20 235561

-345414 276856

-198.306 9720.78

-1284.14

-1569.18 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 68 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-68 Table 2.4-4 (contd)

BWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 9x9G A

B C

D E

F G

> 3 35158.5 26918.5

-17976.7

-149.915 6787.19

-2154.29 836.894

> 4 77137.2

-19760.1 2371.28

-130.934 8015.43

-3512.38

-455.424

> 5 113405

-77931.2 35511.2

-150.637 8932.55

-4099.48

-629.806

> 6 139938

-128700 68698.3

-173.799 9451.22

-3847.83

-455.905

> 7 164267

-183309 109526

-193.952 9737.91

-3046.84

-737.992

> 8 182646

-227630 146275

-210.936 10092.3

-2489.3

-1066.96

> 9 199309

-270496 184230

-218.617 10124.3

-1453.81

-1381.41

> 10 213186

-308612 221699

-235.828 10703.2

-1483.31

-1821.73

> 11 225587

-342892 256242

-236.112 10658.5

-612.076

-2134.65

> 12 235725

-370471 285195

-234.378 10604.9 118.591

-2417.89

> 13 247043

-404028 323049

-245.79 11158.2

-281.813

-2869.82

> 14 253649

-421134 342682

-243.142 11082.3 400.019

-2903.88

> 15 262750

-448593 376340

-245.435 11241.2 581.355

-3125.07

> 16 270816

-470846 402249

-236.294 10845.4 1791.46

-3293.07

> 17 279840

-500272 441964

-241.324 11222.6 1455.84

-3528.25

> 18 284533

-511287 458538

-240.905 11367.2 1459.68

-3520.94

> 19 295787

-545885 501824

-235.685 11188.2 2082.21

-3954.2

> 20 300209

-556936 519174

-229.539 10956 2942.09

-3872.87 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 69 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-69 Table 2.4-4 (contd)

BWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 10x10A/B/G A

B C

D E

F G

> 3 29285.4 27562.2

-16985

-148.415 5960.56

-1810.79 1001.45

> 4 67844.9

-14383 395.619

-127.723 6754.56

-2547.96

-369.267

> 5 96660.5

-55383.8 21180.4

-137.17 7296.6

-2793.58

-192.85

> 6 118098

-91995 42958

-162.985 7931.44

-2940.84 60.9197

> 7 135115

-123721 63588.9

-171.747 8060.23

-2485.59 73.6219

> 8 148721

-151690 84143.9

-190.26 8515.81

-2444.25

-63.4649

> 9 160770

-177397 104069

-197.534 8673.6

-2101.25

-331.046

> 10 170331

-198419 121817

-213.692 9178.33

-2351.54

-472.844

> 11 179130

-217799 138652

-209.75 9095.43

-1842.88

-705.254

> 12 186070

-232389 151792

-208.946 9104.52

-1565.11

-822.73

> 13 192407

-246005 164928

-209.696 9234.7

-1541.54

-979.245

> 14 200493

-265596 183851

-207.639 9159.83

-1095.72

-1240.61

> 15 205594

-276161 195760

-213.491 9564.23

-1672.22

-1333.64

> 16 209386

-282942 204110

-209.322 9515.83

-1506.86

-1286.82

> 17 214972

-295149 217095

-202.445 9292.34

-893.6

-1364.97

> 18 219312

-302748 225826

-198.667 9272.27

-878.536

-1379.58

> 19 223481

-310663 235908

-194.825 9252.9

-785.066

-1379.62

> 20 227628

-319115 247597

-199.194 9509.02

-1135.23

-1386.19 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 70 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-70 Table 2.4-4 (contd)

BWR FUEL ASSEMBLY COOLING TIME-DEPENDENT COEFFICIENTS (ZR-CLAD FUEL)

Cooling Time (years)

Array/Class 10x10C A

B C

D E

F G

> 3 31425.3 27358.9

-17413.3

-152.096 6367.53

-1967.91 925.763

> 4 71804

-16964.1 1000.4

-129.299 7227.18

-2806.44

-416.92

> 5 102685

-62383.3 24971.2

-142.316 7961

-3290.98

-354.784

> 6 126962

-105802 51444.6

-164.283 8421.44

-3104.21

-186.615

> 7 146284

-145608 79275.5

-188.967 8927.23

-2859.08

-251.163

> 8 162748

-181259 105859

-199.122 9052.91

-2206.31

-554.124

> 9 176612

-214183 133261

-217.56 9492.17

-1999.28

-860.669

> 10 187756

-239944 155315

-219.56 9532.45

-1470.9

-1113.42

> 11 196580

-260941 174536

-222.457 9591.64

-944.473

-1225.79

> 12 208017

-291492 204805

-233.488 10058.3

-1217.01

-1749.84

> 13 214920

-307772 221158

-234.747 10137.1

-897.23

-1868.04

> 14 222562

-326471 240234

-228.569 9929.34

-183.47

-2016.12

> 15 228844

-342382 258347

-226.944 9936.76 117.061

-2106.05

> 16 233907

-353008 270390

-223.179 9910.72 360.39

-2105.23

> 17 244153

-383017 304819

-227.266 10103.2 380.393

-2633.23

> 18 249240

-395456 321452

-226.989 10284.1 169.947

-2623.67

> 19 254343

-406555 335240

-220.569 10070.5 764.689

-2640.2

> 20 260202

-421069 354249

-216.255 10069.9 854.497

-2732.77 ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 71 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-74 DESIGN FEATURES 3.3.1 Alternatives to Codes, Standards, and Criteria Table 3-1 lists approved alternatives to the ASME Code for the design of the MPCs, OVERPACKs, and TRANSFER CASKs of the HI-STORM 100 Cask System.

3.3.2 Construction/Fabrication Alternatives to Codes, Standards, and Criteria Proposed alternatives to the ASME Code, Sections II and III, 1995 Edition with Addenda through 1997 including modifications to the alternatives allowed by Specification 3.3.1 may be used on a case-specific basis when authorized by the Director of the Office of Nuclear Material Safety and Safeguards or designee. The request for such alternative should demonstrate that:

1.

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

2.

Compliance with the specified requirements of the ASME Code,Section III, 1995 Edition with Addenda through 1997, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

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

(continued)

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 72 of 73

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 11 Appendix B 3-87 DESIGN FEATURES (continued) 3.4 Site-Specific Parameters and Analyses (continued)

NOTE:

The above anchorage specifications are required for the seismic spectra defined in item 3.4.3.c.i. Users may use fewer studs or those of different diameter to account for site-specific seismic spectra less severe than those specified above. The embedment design shall comply with Appendix B of ACI-349-97. A later edition of this Code may be used, provided a written reconciliation is performed.

iii. Embedment Concrete Compressive Strength: 4,000 psi at 28 days

4.

The analyzed flood condition of 15 fps water velocity and a height of 125 feet of water (full submergence of the loaded cask) are not exceeded.

5.

The potential for fire and explosion while handling a loaded OVERPACK or TRANSFER CASK shall be addressed, based on site-specific considerations. The user shall demonstrate that the site-specific potential for fire is bounded by the fire conditions analyzed by the Certificate Holder, or an analysis of the site-specific fire considerations shall be performed.

6.
a.

For freestanding casks, the ISFSI pad shall be verified by analysis to limit cask deceleration during design basis drop and non-mechanistic tip-over events to 45 gs at the top of the MPC fuel basket. Analyses shall be performed using methodologies consistent with those described in the HI-STORM 100 FSAR. A restriction on the lift and/or drop height is not required if the cask is lifted with a device designed in accordance with applicable stress limits from ANSI N14.6, and/or NUREG-0612, and has redundant drop protection features.

b.

For anchored casks, the ISFSI pad shall be designed to meet the embedment requirements of the anchorage design. A cask tip-over event for an anchored cask is not credible. The ISFSI pad shall be verified by analysis to limit cask deceleration during a design basis drop event to 45 gs at the top of the MPC fuel basket, except as provided for in this paragraph below. Analyses shall be performed using methodologies consistent with those described in the HI-STORM 100 FSAR. A restriction on the lift and/or drop height is not required to be established if the cask is lifted with a device designed in accordance with applicable stress limits from ANSI N14.6, and/or NUREG-0612, and has redundant drop protection features.

(continued)

ATTACHMENT 1 TO HOLTEC LETTER 5014833 Page 73 of 73

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