Text

Enclosure 3 - Certificate of Compliance No. 1032, Amendment 7, Appendix B
	ML24199A240
Person / Time
Site:	07201032
Issue date:	08/13/2024
From:	; Storage and Transportation Licensing Branch
To:	; Holtec
Shared Package
ML24199A236	List: ML24199A237; ML24199A238; ML24199A239; ML24199A240; ML24199A241;
References
	CAC 001028, EPID L-2021-LLA-0053
	Download: ML24199A240 (1)
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CERTIFICATE OF COMPLIANCE NO. 1032

APPENDIX B

APPROVED CONTENTS AND DESIGN FEATURES

FOR THE HI-STORM FW MPC STORAGE SYSTEM

TABLE OF CONTENTS

Page 1.0 Definitions...................................................................................................................... 1-1 2.0 APPROVED CONTENTS.............................................................................................. 2-1 2.1 Fuel Specifications and Loading Conditions...................................................... 2-1 2.1.1 Fuel to Be Stored in the HI-STORM FW MPC Storage System............. 2-1 2.1.2 Fuel Loading........................................................................................... 2-1 2.2 Violations............................................................................................................ 2-1 2.3 Decay Heat Limits............................................................................................ 2-26 2.3.1 Fuel Loading Decay Heat Limits for VENTILATED OVERPACK......... 2-26 2.3.2 Fuel Loading Decay Heat Limits for UNVENTILATED OVERPACK.... 2-26 2.3.3 Variable Fuel Height for MPC-37 and MPC-44..................................... 2-27 2.3.4 Variable Fuel Height for MPC-89.......................................................... 2-27 2.3.5 Maximum fuel storage location decay heat limits................................. 2-27 2.4 Burnup Credit................................................................................................... 2-52 2.5 Burn up and Cooling Time Qualification Requirements.................................... 2-56 3.0 DESIGN FEATURES..................................................................................................... 3-1 3.1 Site..................................................................................................................... 3-1 3.1.1 Site Location........................................................................................... 3-1 3.2 Design Features Important for Criticality Control................................................ 3-1 3.2.1 MPC-37................................................................................................... 3-1 3.2.2 MPC-89................................................................................................... 3-1 3.2.3 Neutron Absorber Tests.......................................................................... 3-1 3.2.4 MPC-32 ML.............................................................................................. 3-1 3.2.5 MPC-37P................................................................................................ 3-2 3.2.6 MPC-44..................................................................................................... 3-2 3.3 Codes and Standards......................................................................................... 3-2 3.3.1 Alternatives to Codes, Standards, and Criteria....................................... 3-2 3.3.2 Construction/Fabrication Alternatives to Codes, Standards, and Criteria............................................................................................. 3-2 3.4 Site-Specific Parameters and Analyses............................................................. 3-9 3.5 Combustible Gas Monitoring During MPC Lid Welding and Cutting................ 3-12

List of Tables

Table 2.1-1 Fuel Assembly Limits......................................................................................... 2-7 Table 2.1-2 PWR FUEL ASSEMBLY CHARACTERISTICS................................................ 2-17 Table 2.1-3 BWR FUEL ASSEMBLY CHARACTERISTICS................................................ 2-21 Table 2.3-1A MPC-37 AND MPC-37P HEAT LOAD DATA (See Figure 2.1-1)..................... 2-28 Table 2.3-1B MPC-37 HEAT LOAD DATA (See Figure 2.1-1).............................................. 2-28 Table 2.3-1C MPC-37 HEAT LOAD DATA (See Figure 2.1-1).............................................. 2-28 Table 2.3-2A MPC-89 HEAT LOAD DATA (See Figure 2.1-2).............................................. 2-29 Table 2.3-2B MPC-89 HEAT LOAD DATA (See Figure 2.1-2).............................................. 2-29 Table 2.3-3 MPC-37 HEAT LOAD DATA (See Figure 2.1-1).............................................. 2-29 Table 2.3-4 MPC-89 HEAT LOAD DATA (See Figure 2.1-2).............................................. 2-30 Table 2.3-5 MPC-32ML HEAT LOAD DATA....................................................................... 2-30 Table 2.3-6 PWR FUEL LENGTH CATEGORIES............................................................... 2-30 Table 2.3-7A MPC-37P HEAT LOAD DATA for VENTILATED OVERPACK (see Figure 2.1-4).................................................................................................... 2-31

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B i Table 2.3-7B MPC-37P HEAT LOAD DATA for VENTILATED OVERPACK (See Figure 2.1-4)................................................................................................. 2-31 Table 2.3-8A MPC-44 HEAT LOAD DATA for VENTILATED OVERPACK (See Figure 2.1-5)................................................................................................. 2-32 Table 2.3-8B MPC-44 HEAT LOAD DATA for VENTILATED OVERPACK (See Figure 2.1-5)................................................................................................. 2-32 Table 2.3-9B MPC-37 REQUIREMENTS ON DEVELOPING REGIONALIZED HEAT LOAD PATTERNS for UNVENTILATED OVERPACK (See Figure 2.1-1)............................. 2-33 Table 2.3-10A MPC-89 HEAT LOAD DATA for UNVENTILATED OVERPACK...................... 2-34 Table 2.3-10B MPC-89 REQUIREMENTS ON DEVELOPING REGIONALIZED HEAT LOAD PATTERNS for UNVENTILATED OVERPACK (See Figure 2.1-2)............................. 2-34 Table 2.3-11 SECTION HEAT LOAD CALCULATIONS FOR MPC-37................................. 2-35 Table 2.3-12 SECTION HEAT LOAD CALCULATIONS FOR MPC-89................................. 2-36 Table 2.3-13 MPC-44 HEAT LOAD DATA for UNVENTILATED OVERPACK...................... 2-36 Table 2.4-1 POLYNOMIAL FUNCTIONS FOR THE MINIMUM BURNUP AS A FUNCTION OF INITIAL ENRICHMENT......................................................................................... 2-53 Table 2.4-2 BURNUP CREDIT CONFIGURATIONS.......................................................... 2-54 Table 2.4-3 IN-CORE OPERATING REQUIREMENTS...................................................... 2-55 Table 2.5-1 BURNUP AND COOLING TIME FUEL QUALIFICATION REQUIREMENTS FOR MPC-32ML.......................................................................................................... 2-57 Table 2.5-2 BURNUP AND COOLING TIME FUEL QUALIFICATION REQUIREMENTS FOR MPC-37 AND MPC-89......................................................................................... 2-57 Table 2.5-3 BURNUP AND COOLING TIME FUEL QUALIFICATION REQUIREMENTS FOR MPC-37P AND MPC-44...................................................................................... 2-58 Table 2.5-4 ALTERNATIVE BURNUP AND CO OLING TIME FUEL QUALIFICATION REQUIREMENTS FOR THE MPC-37P....................................................................... 2-59 Table 2.5-5 ALTERNATIVE BURNUP AND CO OLING TIME FUEL QUALIFICATION REQUIREMENTS FOR THE MPC-37......................................................................... 2-60 Table 2.5-6 BURNUP AND COOLING TIME FUEL QUALIFICATION REQUIREMENTS.. 2-61 Table 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)................ 3-3 Table 3-2 REFERENCE ASME CODE PARA GRAPHS FOR HI-STORM FW OVERPACK and HI-TRAC VW TRANSFER CASK, PRIMARY LOAD BEARING PARTS................ 3-8

List of Figures

Figure 2.1-1 MPC-37 Region-Cell Identification..................................................................... 2-2 Figure 2.1-2 MPC-89 Region-Cell Identification..................................................................... 2-3 Figure 2.1-3 MPC-32ML Cell Identification............................................................................. 2-4 Figure 2.1-4 MPC-37P Cell Identification............................................................................... 2-5 Figure 2.1-5 MPC-44 Cell Identification.................................................................................. 2-6 Figure 2.3-1 Loading Pattern 37C1 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC Short Fuel per Cell Heat Load Limits..................................................................................................................... 2-37 Figure 2.3-2 Loading Pattern 37C2 for MPC-37 Containing Undamaged and Damaged Fuel in DFC/DFI/, Short Fuel per Cell Heat Load Limits............................................ 2-38 Figure 2.3-3 Loading Pattern 37C3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Short Fuel per Cell Heat Load Limits..................................................................................................................... 2-39

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B ii Figure 2.3-4 Loading Pattern 37D1 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, Standard Fuel per Cell Heat Load Limits............................................................................................................ 2-40 Figure 2.3-5 Loading Pattern 37D2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs Standard Fuel per Cell Heat Load Limits.................................... 2-41 Figure 2.3-6 Loading Pattern 37D3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Standard Fuel per Cell Heat Load Limits................................................................................................................. 2-4 2 Figure 2.3-7 Loading Pattern 37E1 for MPC-37 Loading Pattern for MPCs Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, Long Fuel per Cell Heat Load Limits..................................................................................... 2-43 Figure 2.3-8 Loading Pattern 37E2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, Long Fuel per Cell Heat Load Limits...................................................... 2-44 Figure 2.3-9 Loading Pattern 37E3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Long Fuel per Cell Heat Load Limits..................................................................................................................... 2-45 Figure 2.3-10 Loading Pattern 89A1 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per Cell Heat Load Limits.................. 2-46 Figure 2.3-11 Loading Pattern 89A2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, per Cell Heat Load Limits................ 2-47 Figure 2.3-12 Loading Pattern 89B1 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per cell Heat Load Limits.................. 2-48 Figure 2.3-13 Loading Pattern 89B2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per Cell Heat Load Limits.................. 2-49 Figure 2.3-14 Loading Pattern 1 for MPC-37P....................................................................... 2-50 Figure 2.3-15 Loading Pattern 2 for MPC-37P....................................................................... 2-51

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B iii Definitions 1.0

This page is intended to be BLANK.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1.0 DEFINITIONS

Refer to Appendix A for Definitions.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 1-1 Approved Contents 2.0

2.0 APPROVED CONTENTS

2.1 Fuel Specifications and Loading Conditions

2.1.1 Fuel to Be Stored in the HI-STORM FW MPC Storage System

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

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

2.1.2 Fuel Loading

Figures 2.1-1 and 2.1-2 define the regions for the MPC-37 and MPC-89 models, respectively. Figure 2.1-3 defines the cell identifications for the MPC-32ML.

Figures 2.1-4 and 2.1-5 define the cell identifications for the MPC-37P and MPC-44 models, respectively. Fuel assembly decay heat limits are specified in section 2.3.1. Fuel assemblies 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 />, notif y 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.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-1 Approved Contents 2.0

3-1 3-2 3-3

3-4 2-1 2-2 2-3 3-5

3-6 2-4 1-1 1-2 1-3 2-5 3-7

3-8 2-6 1-4 1-5 1-6 2-7 3-9

3-10 2-8 1-7 1-8 1-9 2-9 3-11

3-12 2-10 2-11 2-12 3-13

3-14 3-15 3-16

Legend

Region-Cell ID

Figure 2.1-1. MPC-37 Region-Cell Identification

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-2 Approved Contents 2.0

3-1 3-2 3-3

3-4 3-5 3-6 2-1 3-7 3-8 3-9

3-10 3-11 2-2 2-3 2-4 2-5 2-6 3-12 3-13

3-14 2-7 2-8 2-9 2-10 2-11 2-12 2-13 3-15

3-16 3-17 2-14 2-15 1-1 1-2 1-3 2-16 2-17 3-18 3-19

3-20 2-18 2-19 2-20 1-4 1-5 1-6 2-21 2-22 2-23 3-21

3-22 3-23 2-24 2-25 1-7 1-8 1-9 2-26 2-27 3-24 3-25

3-26 2-28 2-29 2-30 2-31 2-32 2-33 2-34 3-27

3-28 3-29 2-35 2-36 2-37 2-38 2-39 3-30 3-31

3-32 3-33 3-34 Legend 2-40 3-35 3-36 3-37

Region-Cell ID 3-38 3-39 3-40

Figure 2.1-2. MPC-89 Region-Cell Identification

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-3 Approved Contents 2.0

1-1 1-2 1-3 1-4

1-5 1-6 1-7 1-8 1-9 1-10

1-11 1-12 1-13 1-14 1-15 1-16

1-17 1-18 1-19 1-20 1-21 1-22

1-23 1-24 1-25 1-26 1-27 1-28

1-29 1-30 1-31 1-32

Figure 2.1-3. MPC-32ML Cell Identification

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-4 Approved Contents 2.0

Quadrant 4 Quadrant 1 3-1 3-2 3-3

3-4 2-1 2-2 2-3 3-5

3-6 2-4 1-1 1-2 1-3 2-5 3-7

3-8 2-6 1-4 1-5 1-6 2-7 3-9

3-10 2-8 1-7 1-8 1-9 2-9 3-11

3-12 2-10 2-11 2-12 3-13

3-14 3-15 3-16 Quadrant 3 Quadrant 2

Figure 2.1-4. MPC-37P Cell Identification

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-5 Approved Contents 2.0

3-1 3-2

3-3 3-4 2-1 2-2 3-5 3-6

3-7 2-3 2-4 2-5 2-6 3-8

3-9 2-7 2-8 1-1 1-2 2-9 2-10 3-10

3-11 2-11 2-12 1-3 1-4 2-13 2-14 3-12

3-13 2-15 2-16 2-17 2-18 3-14

3-15 3-16 2-19 2-20 3-17 3-18

3-19 3-20

Figure 2.1-5. MPC-44 Cell Identification

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-6 Approved Contents 2.0

Table 2.1-1. Fuel Assembly Limits (page 1 of 10)

I. MPC MODEL: MPC-37

A. Allowable Contents

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

a. Cladding Type: ZR

b. Maximum Initial Enrichment: 5.0 weight percent (wt. %)

Uranium-235 (235U) with soluble boron credit per LCO 3.3.1 OR burnup credit per section 2.4

c. Post-irradiation Cooling Time Cooling Time 1 years and and Average Burnup Per meeting the equation in section 2.5 Assembly: Assembly Average Burnup 68.2 GWD/MTU.

d. Decay Heat Per Fuel Storage As specified in section 2.3 Location:

e. Fuel Assembly Length: 199.2 inches (in.) (nominal design including NON-FUEL HARDWARE and DFC)

f. Fuel Assembly Width: 8.54 in. (nominal design)

g. Fuel Assembly Weight: 2050 pounds (lb.) (including NON-FUEL HARDWARE and DFC)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-7 Approved Contents 2.0

Table 2.1-1. Fuel Assembly Limits (Page 2 of 10)

I. MPC MODEL: MPC-37 (continued)

B. Quantity per MPC: 37 FUEL ASSEMBLIES with up to twelve (12) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 3-1, 3-3 through 3-7, 3-10 through 3-14, and 3-16 (see figure 2.1-1) OR in fuel storage locations 2-1, 2-3, 2-4, 2-5, 2-8, 2-9, 2-10, and 2-12 (see figure 2.1-1), depending on heat load pattern, see section 2.3.1. The remaining fuel storage locations may be filled with PWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications.

For MPCs utilizing burnup credit, the MPC and DFC loading configuration must also meet the additional requirements of section 2.4.

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

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

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing APSRs, RCCAs, CEAs, CRAs (including, but not limited to those with hafnium), or NSAs may only be loaded in fuel storage Regions 1 and 2 (see figure 2.1-1).

Note 2: DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected, may be stored in storage locations designated for DFCs using DFIs or DFCs. Damaged fuel stored in DFIs may contain missing or partial fuel rods and/or fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-8 Approved Contents 2.0

Table 2.1-1. Fuel Assembly Limits (Page 3 of 10)

II. MPC MODEL: MPC-89

A. Allowable Contents

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

a. Cladding Type: ZR

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

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

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

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

ii. All Other Array Classes Cooling Time 1 year and meeting the equation in section 2.5 and an assembly average burnup 65 GWD/MTU

e. Decay Heat Per Assembly

i. Array/Class 8x8F 183.5 Watts

ii. All Other Array Classes As specified in section 2.3

f. Fuel Assembly Length 176.5 in. (nominal design)

g. Fuel Assembly Width 5.95 in. (nominal design)

h. Fuel Assembly Weight 850 lb. including a DFC as well as a channel

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-9 Approved Contents 2.0

Table 2.1-1. Fuel Assembly Limits (Page 4 of 10)

II. MPC MODEL: MPC-89 (continued)

B. Quantity per MPC: 89 FUEL ASSEMBLIES with up to sixteen (16) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 3-1, 3-3, 3-4, 3-9, 3-10, 3-13, 3-16, 3-19, 3-22, 3-25, 3-28, 3-31, 3-32, 3-37, 3-38, and 3-40 (see figure 2.1-2), OR in fuel storage locations 2-1, 2-2, 2-6, 2-7, 2-13, 2-18, 2-23, 2-28, 2-34, 2-35, 2-39, and 2-40 (see figure 2.1-2), depending on heat load pattern, see section 2.3.1. The remaining fuel storage locations may be filled with BWR UNDAMAGED FUEL ASSEMBLIES meeti ng the applicable specifications.

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

Note 2: DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected, may be stored in storage locations designated for DFCs using DFIs or DFCs. Damaged fuel stored in DFIs may contain missing or partial fuel rods and/or fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-10 Approved Contents 2.0

Table 2.1-1. Fuel Assembly Limits (Page 5 of 10)

III. MPC MODEL: MPC-32ML

A. Allowable Contents

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

a. Cladding Type: ZR

b. Maximum initial enrichment: 5.0 wt. % 235U with soluble boron credit per LCO 3.3.1

c. Post-irradiation Cooling Time Cooling Time 3 years and meeting and Average Burnup Per the equation in section 2.5 Assembly Assembly Average Burnup 68.2 GWD/MTU More limitation specified in section 2.5

d. Decay Heat Per Fuel Storage As specified in section 2.3 Location:

e. Fuel Assembly Length: 196.122 in. (nominal design including NON-FUEL HARDWARE and DFC)

f. Fuel Assembly Width: 9.04 in. (nominal design)

g. Fuel Assembly Weight: 2200 lb. (including NON-FUEL HARDWARE and DFC). Average fuel weight not to exceed 2140 lb.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-11 Approved Contents 2.0

Table 2.1-1. Fuel Assembly Limits (Page 6 of 10)

III. MPC MODEL: MPC-32ML (continued)

B. Quantity per MPC: 32 FUEL ASSEMBLIES with up to eight (8) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs).

DFCs may be stored in fuel storage locations 1-1, 1-4, 1-5, 1-10, 1-23, 1-28, 1-29, and 1-32 (see figure 2.1-3). The remaining fuel storage locations may be filled with PWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications.

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

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

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing APSRs, RCCAs, CEAs, CRAs, or NSAs may only be loaded in fuel cells 1-6 through 1-9, 1-12 through 1-15, 1-18 through 1-21, and 1-24 through 1-27.

Note 2: DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected, may be stored in storage locations designated for DFCs using DFIs or DFCs. Damaged fuel stored in DFIs may contain missing or partial fuel rods and/or fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-12 Approved Contents 2.0

Table 2.1-1. Fuel Assembly Limits (Page 7 of 10)

IV. MPC MODEL: MPC-37P

A. Allowable Contents

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

a. Cladding Type: ZR

b. Maximum initial enrichment: 5.0 wt. % 235U with soluble boron credit per LCO 3.3.1

c. Post-irradiation Cooling Time Cooling Time 1.6 years and and Average Burnup Per meeting the equation in section 2.5 Assembly Assembly Average Burnup 68.2 GWD/MTU

d. Decay Heat Per Fuel Storage As specified in section 2.3 Location:

e. Fuel Assembly Length: 160.5 in. (nominal design including NON-FUEL HARDWARE and DFC)

f. Fuel Assembly Width: 8.52 in. (nominal design)

g. Fuel Assembly Weight: 1610 lb. (including NON-FUEL HARDWARE and DFC)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-13 Approved Contents 2.0

Table 2.1-1. Fuel Assembly Limits (Page 8 of 10)

IV. MPC MODEL: MPC-37P (continued)

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

Note 1: Fuel assemblies containing TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing APSRs, RCCAs, CEAs, CRAs (including, but not limited to those with hafnium), or NSAs may only be loaded in fuel storage Regions 1 and 2 (see Figure 2.1-4).

Note 2: DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected, may be stored in storage locations designated for DFCs using DFIs or DFCs. Damaged fuel stored in DFIs may contain missing or partial fuel rods and/or fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-14 Approved Contents 2.0

Table 2.1-1. Fuel Assembly Limits (Page 9 of 10)

V. MPC MODEL: MPC-44

A. Allowable Contents

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

a. Cladding Type: ZR

b. Maximum initial enrichment: 5.0 wt. % 235U

c. Post-irradiation Cooling Time Cooling Time 3 years and meeting and Average Burnup Per the equation in section 2.5 Assembly Assembly Average Burnup 60.0 GWD/MTU

d. Decay Heat Per Fuel Storage As specified in section 2.3 Location:

e. Fuel Assembly Length: 170.5 in. (nominal design including DFC)

f. Fuel Assembly Width: 7.81 in. (nominal design)

g. Fuel Assembly Weight: 1250 lb. (including DFC)

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

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

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-15 Approved Contents 2.0

Table 2.1-1. Fuel Assembly Limits (Page 10 of 10)

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location.

Note 2: DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected, may be stored in storage locations designated for DFCs using DFIs or DFCs. Damaged fuel stored in DFIs may contain missing or partial fuel rods and/or fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-16 Approved Contents 2.0

Table 2.1-2. PWR FUEL ASSEMBLY CHARACTERISTICS (page 1 of 4)

(Notes 1, 7)

Fuel Assembly Array/ Class 14x14 A 14x14 B 14x14 C 15x15 B 15x15 C No. of Fuel Rod Locations (Note 6) 179 179 176 204 204 Fuel Clad O.D.

(inches (in.)) 0.400 0.417 0.440 0.420 0.417 Fuel Clad I.D. (in.) 0.3514 0.374 0.3880 0.3736 0.3640 Fuel Pellet Dia. (in.)

(Note 3) 0.3444 0.367 0.3805 0.3671 0.3570 Fuel Rod Pitch (in.) 0.556 0.566 0.580 0.563 0.563 Active Fuel Length (in.) 150 150 150 150 150 No. of Guide and/or Instrument Tubes 17 17 5 (Note 2) 21 21 Guide/Instrument Tube Thickness (in.) 0.017 0.017 0.038 0.015 0.0165

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-17 Approved Contents 2.0

Table 2.1-2. PWR FUEL ASSEMBLY CHARACTERISTICS (page 2 of 4)

(Notes 1, 7)

Fuel Assembly Array/Class 15x15 D 15x15 E 15x15 F 15x15 H 15x15 I No. of Fuel Rod (Note 4)

Locations (Note 6) 208 208 208 208 216 Fuel Clad O.D. (in.) 0.430 0.428 0.428 0.414 0.413 Fuel Clad I.D. (in.) 0.3800 0.3790 0.3820 0.3700 0.3670 Fuel Pellet Dia. (in.)

(Note 3) 0.3735 0.3707 0.3742 0.3622 0.3600 Fuel Rod Pitch (in.) 0.568 0.568 0.568 0.568 0.550 Active Fuel Length (in.) 150 150 150 150 150 No. of Guide and/or (Note 4)

Instrument Tubes 17 17 17 17 9 Guide/Instrument Tube Thickness (in.) 0.0150 0.0140 0.0140 0.0140 0.0140

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-18 Approved Contents 2.0

Table 2.1-2. PWR FUEL ASSEMBLY CHARACTERISTICS (page 3 of 4)

(Notes 1, 7)

Fuel Assembly Array and Class 16x16 A 16x16B 16x16C 16x16D (Note 5) 16x16E No. of Fuel Rod Locations (Note 6) 236 236 235 236 235 Fuel Clad O.D. (in.) 0.382 0.374 0.374 0.423 0.359 Fuel Clad I.D. (in.) 0.3350 0.3290 0.3290 0.373 0.3326 Fuel Pellet Dia. (in.)

(Note 3) 0.3255 0.3225 0.3225 0.359 0.3225 Fuel Rod Pitch (in.) 0.506 0.506 0.485 0.563 0.485 Active Fuel length (in.) 150 150 150 154.5 150 No. of Guide and/or 5 5 Instrument Tubes (Note 2) (Note 2) 21 20 21 Guide/Instrument Tube Thickness (in.) 0.0350 0.04 0.0157 0.015 0.0157

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-19 Approved Contents 2.0

Table 2.1-2. PWR FUEL ASSEMBLY CHARACTERISTICS (page 4 of 4)

(Notes 1, 7)

Fuel Assembly Array and Class 17x17A 17x17 B 17x17 C 17x17 D 17x17 E No. of Fuel Rod Locations (Note 6) 264 264 264 264 265 Fuel Clad O.D. (in.) 0.360 0.372 0.377 0.372 0.372 Fuel Clad I.D. (in.) 0.3150 0.3310 0.3330 0.3310 0.3310 Fuel Pellet Dia. (in.)

(Note 3) 0.3088 0.3232 0.3252 0.3232 0.3232 Fuel Rod Pitch (in.) 0.496 0.496 0.502 0.496 0.496 Active Fuel length (in.) 150 150 150 170 170 No. of Guide and/or Instrument Tubes 25 25 25 25 24 Guide/Instrument Tube Thickness (in.) 0.016 0.014 0.020 0.014 0.014

Notes:

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

2. Each guide tube replaces four fuel rods.

3. Annular fuel pellets are allowed in the top and bottom 12 of the active fuel length, except as noted below.

4. Assemblies have one Instrument Tube and eight Guide Bars (Solid ZR). Some assemblies have up to 8 fuel rods removed or replaced by Guide Tubes.

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

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

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

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-20 Approved Contents 2.0

Table 2.1-3. BWR FUEL ASSEMBLY CHARACTERISTICS (page 1 of 5)

(Notes 1, 17)

Fuel Assembly Array and Class 7x7 B 7x7 C 8x8 B 8x8 C 8x8 D 8x8 E Maximum Planar-Average Initial 4.8 4.8 4.8 4.8 4.8 4.8 Enrichment (wt.%

235U) (Note 14)

No. of Fuel Rod Locations (Full Length 49 48 63 or 64 62 60 or 61 59 or Total/Full Length)

(Note 16)

Fuel Clad O.D. (in.) 0.5630 0.5630 0.4840 0.4830 0.4830 0.4930 Fuel Clad I.D. (in.) 0.4990 0.4990 0.4295 0.4250 0.4230 0.4250 Fuel Pellet Dia. (in.) 0.4910 0.4910 0.4195 0.4160 0.4140 0.4160 Fuel Rod Pitch (in.) 0.738 0.738 0.642 0.641 0.640 0.640 Design Active Fuel Length (in.) 150 150 150 150 150 150 No. of Water Rods (Note 10) 0 1 (Note 15) 1 or 0 2 1 - 4 (Note 6) 5 Water Rod Thickness 0.034 > 0.00 > 0.00 0.034 (in.) N/A N/A Channel Thickness (in.) 0.120 0.120 0.120 0.120 0.120 0.100

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-21 Approved Contents 2.0

Table 2.1-3. BWR FUEL ASSEMBLY CHARACTERISTICS (2 of 5)

(Notes 1, 17)

Fuel Assembly Array and Class 8x8F 8x8G 9x9 A 9x9 B 9x9 C 9x9 D Maximum Planar-Average Initial 4.5 Enrichment (wt.% 235U) (Note 12) 4.8 4.8 4.8 4.8 4.8 (Note 14)

No. of Fuel Rod 74/66 Locations (Note 16) 64 60 (Note 4) 72 80 79 Fuel Clad O.D. (in.) 0.4576 0.5015 0.4400 0.4330 0.4230 0.4240 Fuel Clad I.D. (in.) 0.3996 0.4295 0.3840 0.3810 0.3640 0.3640 Fuel Pellet Dia. (in.) 0.3913 0.4195 0.3760 0.3740 0.3565 0.3565 Fuel Rod Pitch (in.) 0.609 0.642 0.566 0.572 0.572 0.572 Design Active Fuel Length (in.) 150 150 150 150 150 150 No. of Water Rods N/A 4 (Note 10) (Note 2) (Note 15) 2 1 (Note 5) 1 2 Water Rod Thickness (in.) 0.025 N/A > 0.00 > 0.00 0.020 0.0300 Channel Thickness (in.) 0.055 0.120 0.120 0.120 0.100 0.100

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-22 Approved Contents 2.0

Table 2.1-3. BWR FUEL ASSEMBLY CHARACTERISTICS (page 3 of 5)

(Notes 1, 17)

Fuel Assembly Array and Class 9x9 E 9x9 F (Note 2) (Note 2) 9x9 G 10x10 A 10x10 B Maximum Planar-Average Initial 4.5 4.5 Enrichment (wt.% 235U) (Note 14) (Note 12) (Note 12) 4.8 4.8 4.8 No. of Fuel Rod Locations (Note 16) 76 76 72 92/78 91/83 (Note 7) (Note 8)

Fuel Clad O.D. (in.) 0.4170 0.4430 0.4240 0.4040 0.3957 Fuel Clad I.D. (in.) 0.3640 0.3860 0.3640 0.3520 0.3480 Fuel Pellet Dia. (in.) 0.3530 0.3745 0.3565 0.3455 0.3420 Fuel Rod Pitch (in.) 0.572 0.572 0.572 0.510 0.510 Design Active Fuel Length (in.) 150 150 150 150 150 No. of Water Rods (Note 10) 5 5 1 (Note 5) 2 1 (Note 5)

Water Rod Thickness (in.) 0.0120 0.0120 0.0320 0.0300 > 0.00 Channel Thickness (in.) 0.120 0.120 0.120 0.120 0.120

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-23 Approved Contents 2.0

Table 2.1-3. BWR FUEL ASSEMBLY CHARACTERISTICS (page 4 of 5)

(Notes 1, 17)

Fuel Assembly Array and Class 10x10 C 10x10 F 10x10 G 10x10 I 10x10 J 11x11 A Maximum Planar-Average Initial 4.8 4.7 4.6 (Note Enrichment (wt.% (Note 13) 12) 4.8 4.8 4.8 235U) (Note 14)

No. of Fuel Rod 96/80 112/92 Locations 96 92/78 (Note 7) 96/84 91/79 (Note 18) (Note 19) (Note 20)

(Note 16)

Fuel Clad O.D. (in.) 0.3780 0.4035 0.387 0.4047 0.3999 0.3701 Fuel Clad I.D. (in.) 0.3294 0.3570 0.340 0.3559 0.3603 0.3252 Fuel Pellet Dia. (in.) 0.3224 0.3500 0.334 0.3492 0.3531 0.3193 Fuel Rod Pitch (in.) 0.488 0.510 0.512 0.5100 0.5149 0.4705 (Note 21)

Design Active Fuel Length (in.) 150 150 150 150 150 150 No. of Water Rods 5 1 (Note 10) (Note 9) 2 5 (Note 9) (Note 5) 1 1 (Note 5)

Water Rod Thickness (in.) 0.031 0.030 0.031 0.0315 0.0297 0.0320 Channel Thickness (in.) 0.055 0.120 0.060 0.100 0.0938 0.100

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-24 Approved Contents 2.0

Table 2.1-3. BWR FUEL ASSEMBLY CHARACTERISTICS (page 5 of 5)

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

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

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

5. Square, replacing nine fuel rods.

6. Variable.

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

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

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

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

11. Not used.

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

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

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

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

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

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

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

19. Contains in total 96 fuel rods; 80 full length rods, 8 long partial length rods, 8 short partial length rods and one water rod replacing 4 or 12 fuel rods.

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

21. This is the maximum fixed rod pitch. The assembly may have areas of variable pitch that exceed this value and remains acceptable for storage.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-25 Approved Contents 2.0

2.3 Decay Heat Limits

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

2.3.1 Fuel Loading Decay Heat Limits for VENTILATED OVERPACK

Tables 2.3-1A, 2.3-1B, and 2.3-1C provide the maximum allowable decay heat per fuel storage location for MPC-37. Tables 2.3-2A and 2.3-2B provide the maximum allowable decay heat per fuel storage location for MPC-89. Tables 2.3-1A and 2.3-7A provides the maximum allowable decay heat per fuel storage location for MPC-37P. Table 2.3-8A provide the maximum allowable decay heat per fuel storage location for MPC-44. No drying time limits are required for decay heat values meeting the limits in these tables are applicable when using FHD to dry moderate or high burnup fuel and when using VDS to dry moderate burnup fuel. Drying time limits apply when using VDS to dry high burnup fuel with decay heat values meeting the limits in these tables. Tables 2.3-3 and 2.3-4 provide the maximum allowable decay heat per fuel storage location for MPC-37 and MPC-89, respectively, with no drying time limits imposed, when using VDS to dry high burnup fuel. Table 2.3-5 provides the maximum allowable decay heat per fuel storage location for the MPC-32ML for both FHD and VDS drying. Tables 2.3-7B and 2.3-8B provide the maximum allowable decay heat per fuel storage location for the MPC-37P and MPC-44, respectively, with no drying time limits imposed, when using VDS to dry high burnup fuel. The per cell limits in these tables apply to cells containing undamaged fuel or damaged fuel in DFCs/DFIs or fuel debris in DFCs.

Figures 2.3-1 through 2.3-14 provide alternative loading patterns for the MPC-37 and MPC-89, with undamaged fuel and a combination of undamaged fuel and damaged fuel in DFCs/DFIs and fuel debris in DFCs. The per cell limits in these figures are applicable when using vacuum drying or FHD to dry moderate or high burnup fuel in accordance with table 3-1 of Appendix A of the CoC. The MPC-37 patterns are based on the fuel length to be stored in the MPC, see table 2.3-6.

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

2.3.2 Fuel Loading Decay Heat Limits for UNVENTILATED OVERPACK

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

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-26 Approved Contents 2.0

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

2.3.3 Variable Fuel Height for MPC-37 and MPC-44

2.3.3.1 For fuel with a longer active fuel length than the reference fuel (144 inches), the maximum total heat load, maximum quadrant heat load limits and specific heat load limits in each cell, may be increased by the ratio SQRT(L/144), where L is the active length of the fuel in inches.

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

2.3.4 Variable Fuel Height for MPC-89

2.3.4.1 For fuel with a longer active fuel length than the reference fuel (150 inches), the maximum total heat load, maximum quadrant heat load limits and specific heat load limits in each cell, may be increased by the ratio SQRT(L/150), where L is the active length of the fuel in inches.

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

2.3.5 Maximum fuel storage location decay heat limits

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

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-27 Approved Contents 2.0

Table 2.3-1A. MPC-37 AND MPC-37P HEAT LOAD DATA (See Figure 2.1-1)

Number of Regions: 3

Number of Storage Cells: 37

Maximum Design Basis Heat Load (kilowatt (kW)): 44.09 (Pattern A); 45.0 (Pattern B)

Decay Heat Limit per Cell, Decay Heat Limit per Region No. kW Number of Cells per Region Region, kW Pattern A Pattern B Pattern A Pattern B 1 1.05 1.0 9 9.45 9.0 2 1.70 1.2 12 20.4 14.4 3 0.89 1.35 16 14.24 21.6

Table 2.3-1B. MPC-37 HEAT LOAD DATA (See Figure 2.1-1)

Number of Regions: 3

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

Table 2.3-1C. MPC-37 HEAT LOAD DATA (See Figure 2.1-1)

Number of Regions: 3 Number of Storage Cells: 37

80% of Pattern A - Sub-design Heat Load (kW): 35.27 Region No. Decay Heat Limit per Cell, Number of Cells Decay Heat Limit per kW per Region Region, kW 1 0.84 9 7.56 2 1.36 12 16.32 3 0.712 16 11.392

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-28 Approved Contents 2.0

Table 2.3-2A. MPC-89 HEAT LOAD DATA (See Figure 2.1-2)

Number of Regions: 3

Number of Storage Cells: 89

Maximum Design Basis Heat Load: 46.36 kW Region No. Decay Heat Limit per Number of Cells Decay Heat Limit per Cell, kW per Region Region, kW 1 0.44 9 3.96 2 0.62 40 24.80 3 0.44 40 17.60

Table 2.3-2B. MPC-89 HEAT LOAD DATA (See Figure 2.1-2)

Number of Regions: 3

Number of Storage Cells: 89

80% Sub-design Heat Load (kW): 37.1 Region No. Decay Heat Limit per Cell, Number of Cells Decay Heat Limit per kW per Region Region, kW 1 0.352 9 3.168 2 0.496 40 19.84 3 0.352 40 14.08

Table 2.3-3. MPC-37 HEAT LOAD DATA (See Figure 2.1-1)

Number of Regions: 3

Number of Storage Cells: 37

Maximum Heat Load: 29.6 Region No. Decay Heat Limit per Number of Cells Decay Heat Limit per Cell, W per Region Region, kW 1 800 9 7.2 2 800 12 9.6 3 800 16 12.8

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-29 Approved Contents 2.0

Table 2.3-4. MPC-89 HEAT LOAD DATA (See Figure 2.1-2)

Number of Regions: 3

Number of Storage Cells: 89

Maximum Heat Load: 30.0kW Region No. Decay Heat Limit per Number of Cells Decay Heat Limit per Cell, W per Region Region, kW 1 337 9 3.03 2 337 40 13.48 3 337 40 13.48

Table 2.3-5. MPC-32ML HEAT LOAD DATA Number of Regions: 1

Number of Storage Cells: 32 Pattern* Maximum Heat Load, kW Decay Heat Limit per Cell, kW Pattern A 44.16 1.380 Pattern B 28.70 0.897

See Appendix A, Table 3-1, MPC Cavity Drying Limits

Table 2.3-6. PWR FUEL LENGTH CATEGORIES Category Length Range

Short Fuel 128 inches L < 144 inches

Standard Fuel 144 inches L < 168 inches

Long Fuel L 168 inches Note:

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

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-30 Approved Contents 2.0

TABLE 2.3-7A. MPC-37P HEAT LOAD DATA for VENTILATED OVERPACK (see Figure 2.1-4)

Number of Storage Cells: 37

Maximum Design Basis Heat Load (kW): 45

Maximum Quadrant Heat Load (kW): 11.25

Decay Heat Limit per Cell (kW): See Figures 2.3-14 and 2.3-15 Notes:

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

TABLE 2.3-7B. MPC-37P HEAT LOAD DATA for VENTILATED OVERPACK (See Figure 2.1-4)

Number of Regions: 3

Number of Storage Cells: 37

Maximum Heat Load: 33.3 Region No. Decay Heat Limit Number of Cells Decay Heat Limit per Cell, W per Region per Region, kW 1 900 9 8.1 2 900 12 10.8 3 900 16 14.4

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-31 Approved Contents 2.0

TABLE 2.3-8A. MPC-44 HEAT LOAD DATA for VENTILATED OVERPACK (See Figure 2.1-5)

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

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

TABLE 2.3-8B. MPC-44 HEAT LOAD DATA for VENTILATED OVERPACK (See Figure 2.1-5)

Number of Regions: 1 Number of Storage Cells: 44 Maximum Total Heat Load (kW): 30 Maximum Decay Heat Limit per Cell (kW): 0.682

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-32 Approved Contents 2.0

TABLE 2.3-9A. MPC-37 HEAT LOAD DATA for UNVENTILATED OVERPACK (See Figure 2.1-1)

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

Region No. Decay Heat Limit per Number of Cells per Decay Heat Limit per Cell, kW (Note 2) Region Region, kW 1 0.784 9 7.054 2 0.784 12 9.405 3 0.784 16 12.541 Note 1: Figure 2.1-1 identifies the cell locations, and Table 2.3-11 identifies the cells included in the heat load for each section.

Note 2: Maximum total heat load, maximum section heat load and specific cell heat load limits may need to be adjusted in accordance with Section 2.3.3.

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

TABLE 2.3-9B. MPC-37 REQUIREMENTS ON DEVELOPING REGIONALIZED HEAT LOAD PATTERNS for UNVENTILATED OVERPACK (See Figure 2.1-1)

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

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

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

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

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

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

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

8. Pattern-specific decay heat for any storage cell in Region 2 may be determined by reducing the allowable in Region 2 of Table 2.3-9A by and pattern-specific decay heat for any storage cell in Region 3 may be determined by increasing the allowable in Region 3 of Table 2.3-9A by the same. This may not be added to other cells in Region 2.

9. Items 1 through 8 need to be scaled in accordance with Section 2.3.4 for non-standard active fuel lengths.

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

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-33 Approved Contents 2.0

TABLE 2.3-10A. MPC-89 HEAT LOAD DATA for UNVENTILATED OVERPACK (See Figure 2.1-2)

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

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

Note 2: Maximum total heat load, maximum section heat load and specific cell heat load limits may need to be adjusted in accordance with Section 2.3.4.

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

TABLE 2.3-10B. MPC-89 REQUIREMENTS ON DEVELOPING REGIONALIZED HEAT LOAD PATTERNS for UNVENTILATED OVERPACK (See Figure 2.1-2)

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

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

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

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

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

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

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

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

9. Items 1 through 8 need to be scaled in accordance with Section 2.3.4 for non-standard active fuel lengths.

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

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-34 Approved Contents 2.0

TABLE 2.3-11. SECTION HEAT LOAD CALCULATIONS FOR MPC-37 Section Equation for Section Heat Load 1 Section 1 Q3-1 + Q2-1 + 1/2Q3-2 + 1/2Q3-4 + 1/2Q2-2 + 1/2Q1-1 + 1/2Q1-2 + 1/8Q1-5 Section 2 Q3-3 + Q2-3 + 1/2Q3-2 + 1/2Q3-5 + 1/2Q2-2 + 1/2Q1-3 + 1/2Q1-2 + 1/8Q1-5 Section 3 Q2-5 + Q3-7 + 1/2Q1-6 + 1/2Q3-5 + 1/2Q2-7 + 1/2Q1-3 + 1/2Q3-9 + 1/8Q1-5 Section 4 Q2-9 + Q3-11 + 1/2Q1-6 + 1/2Q1-9 + 1/2Q2-7 + 1/2Q3-13 + 1/2Q3-9 + 1/8Q1-5 Section 5 Q2-12 + Q3-16 + 1/2Q1-8 + 1/2Q1-9 + 1/2Q2-11 + 1/2Q3-13 + 1/2Q3-15 + 1/8Q1-5 Section 6 Q2-10 + Q3-14 + 1/2Q1-8 + 1/2Q1-7 + 1/2Q2-11 + 1/2Q3-12 + 1/2Q3-15 + 1/8Q1-5 Section 7 Q2-8 + Q3-10 + 1/2Q1-4 + 1/2Q1-7 + 1/2Q2-6 + 1/2Q3-12 + 1/2Q3-8 + 1/8Q1-5 Section 8 Q2-4 + Q3-6 + 1/2Q1-4 + 1/2Q1-1 + 1/2Q2-6 + 1/2Q3-4 + 1/2Q3-8 + 1/8Q1-5 Notes:

1. QX-Y is the heat load in kW in cell ID (X-Y), identified in Figure 2.1-1.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-35 Approved Contents 2.0

TABLE 2.3-12. SECTION HEAT LOAD CALCULATIONS FOR MPC-89 Section Equation for Section Heat Load 1 Section 1 Q3-1 + Q3-4 +Q3-5 + Q3-6 +Q2-2 + Q2-3 + Q2-9 + 1/2Q3-2 + 1/2Q2-1 + 1/2Q2-4 + 1/2Q2-10 + 1/2Q1-2 + 1/2Q1-1 + 1/2Q2-8 + 1/2Q2-11 + 1/8Q1-5

Section 2 Q3-3 + Q3-7 +Q3-8 + Q3-9 +Q2-5 + Q2-6 + Q2-11 + 1/2Q3-2 + 1/2Q2-1 + 1/2Q2-4 + 1/2Q2-10 + 1/2Q1-2 + 1/2Q1-3 + 1/2Q2-12 + 1/2Q3-12 + 1/8Q1-5

Section 3 Q3-13 + Q2-13 +Q3-15 + Q2-16 +Q2-17 + Q3-18 + Q3-19 + 1/2Q1-6 + 1/2Q2-21 + 1/2Q2-22 + 1/2Q2-23 + 1/2Q3-21 + 1/2Q1-3 + 1/2Q2-12 + 1/2Q3-12 + 1/8Q1-5

Section 4 Q2-26 + Q2-27 +Q3-24 + Q3-25 +Q2-34 + Q3-27 + Q3-31 + 1/2Q1-6 + 1/2Q2-21 + 1/2Q2-22 + 1/2Q2-23 + 1/2Q3-21 + 1/2Q1-9 + 1/2Q2-33 + 1/2Q3-30 + 1/8Q1-5

Section 5 Q2-32 + Q2-38 +Q2-39 + Q3-35 +Q2-36 + Q3-37 + Q3-40 + 1/2Q1-8 + 1/2Q2-31 + 1/2Q2-37 + 1/2Q2-40 + 1/2Q3-39 + 1/2Q1-9 + 1/2Q2-33 + 1/2Q3-30 + 1/8Q1-5

Section 6 Q2-30 + Q2-35 +Q2-36 + Q3-32 +Q2-33 + Q3-34 + Q3-38 + 1/2Q1-8 + 1/2Q2-31 + 1/2Q2-37 + 1/2Q2-40 + 1/2Q3-39 + 1/2Q1-7 + 1/2Q2-29 + 1/2Q3-29 + 1/8Q1-5

Section 7 Q2-25 + Q2-24 +Q3-23 + Q3-22 +Q2-28 + Q3-26 + Q3-28 + 1/2Q1-4 + 1/2Q2-20 + 1/2Q2-19 + 1/2Q2-18 + 1/2Q3-20 + 1/2Q1-7 + 1/2Q2-29 + 1/2Q3-29 + 1/8Q1-5

Section 8 Q2-15 + Q2-14 +Q3-17 + Q3-16 +Q2-7 + Q3-14 + Q3-10 + 1/2Q1-4 + 1/2Q2-20 + 1/2Q2-19 + 1/2Q2-18 + 1/2Q3-20 + 1/2Q1-1 + 1/2Q2-8 + 1/2Q3-11 + 1/8Q1-5 Notes:

1. QX-Y is the heat load in kW in cell ID (X-Y), identified in Figure 2.1-2.

TABLE 2.3-13. MPC-44 HEAT LOAD DATA for UNVENTILATED OVERPACK (See Figure 2.1-5)

Number of Regions: 1 Number of Storage Cells: 44 Maximum Total Heat Load (kW): 28 Maximum Decay Heat Limit per Cell (kW): 0.636 Notes:

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

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-36 Approved Contents 2.0

0.45 (D/F) 0.45 0.45 (D/F)

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

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

0.6 0.5 0.6 0.5 0.6 0.5 0.6

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

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

0.45 (D/F) 0.45 0.45 (D/F)

Figure 2.3-1. Loading Pattern 37C1 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC Short Fuel per Cell Heat Load Limits

(All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-37 Approved Contents 2.0

0.45 0.45 0.45

3.2 3.2 0.45 (D) Empty (D) 0.45

0.6 2.4 Empty 0.6 Empty 2.4 (D) (D) 0.6

0.6 0.5 0.6 0.5 0.6 0.5 0.6

0.6 2.4 Empty 0.6 Empty 2.4 (D) (D) 0.6

3.2 3.2 0.45 (D) Empty (D) 0.45

0.45 0.45 0.45

Figure 2.3-2. Loading Pattern 37C2 for MPC-37 Containing Undamaged and Damaged Fuel in DFC/DFI/, Short Fuel per Cell Heat Load Limits

(All storage cell heat loads are in kW, Undamaged Fuel or Damaged Fuel in a DFC and/or using DFIs may be stored in cells denoted by D. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-38 Approved Contents 2.0

0.45 0.45 0.45

3.2 3.2 0.45 (D/F) Empty (D/F) 0.45

0.6 2.4 Empty 0.6 Empty 2.4 0.6

0.6 0.5 0.6 0.5 0.6 0.5 0.6

0.6 2.4 Empty 0.6 Empty 2.4 0.6

3.2 3.2 0.45 (D/F) Empty (D/F) 0.45

0.45 0.45 0.45

Figure 2.3-3. Loading Pattern 37C3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Short Fuel per Cell Heat Load Limits

(All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-39 Approved Contents 2.0

0.55 (D/F) 0.55 0.55 (D/F)

0.55 (D/F) 3.2 0.55 3.2 0.55 (D/F)

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

0.75 0.55 0.65 0.55 0.65 0.55 0.75

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

0.55 (D/F) 3.2 0.55 3.2 0.55 (D/F)

0.55 (D/F) 0.55 0.55 (D/F)

Figure 2.3-4. Loading Pattern 37D1 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, Standard Fuel per Cell Heat Load Limits

(All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-40 Approved Contents 2.0

0.55 0.55 0.55

3.2 3.2 0.55 (D) Empty (D) 0.55

0.75 2.4 Empty 0.65 Empty 2.4 (D) (D) 0.75

0.75 0.55 0.65 0.55 0.65 0.55 0.75

0.75 2.4 Empty 0.65 Empty 2.4 (D) (D) 0.75

3.2 3.2 0.55 (D) Empty (D) 0.55

0.55 0.55 0.55

Figure 2.3-5. Loading Pattern 37D2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs Standard Fuel per Cell Heat Load Limits

(All storage cell heat loads are in kW, D Undamaged Fuel or Damaged Fuel in a DFC and/or using DFIs may be stored in cells denoted by D. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-41 Approved Contents 2.0

0.55 0.55 0.55

3.2 3.2 0.55 (D/F) Empty (D/F) 0.55

0.75 2.4 Empty 0.65 Empty 2.4 0.75

0.75 0.55 0.65 0.55 0.65 0.55 0.75

0.75 2.4 Empty 0.65 Empty 2.4 0.75

3.2 3.2 0.55 (D/F) Empty (D/F) 0.55

0.55 0.55 0.55

Figure 2.3-6. Loading Pattern 37D3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Standard Fuel per Cell Heat Load Limits

(All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-42 Approved Contents 2.0

0.65 (D/F) 0.65 0.65 (D/F)

0.65 (D/F) 3.5 0.65 3.5 0.65 (D/F)

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

0.85 0.65 0.75 0.65 0.75 0.65 0.85

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

0.65 (D/F) 3.5 0.65 3.5 0.65 (D/F)

0.65 (D/F) 0.65 0.65 (D/F)

Figure 2.3-7. Loading Pattern 37E1 for MPC-37 Loading Pattern for MPCs Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, Long Fuel per Cell Heat Load Limits

(All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-43 Approved Contents 2.0

0.65 0.65 0.65

3.5 3.5 0.65 (D) Empty (D) 0.65

0.85 2.6 Empty 0.75 Empty 2.6 (D) (D) 0.85

0.85 0.65 0.75 0.65 0.75 0.65 0.85

0.85 2.6 Empty 0.75 Empty 2.6 (D) (D) 0.85

3.5 3.5 0.65 (D) Empty (D) 0.65

0.65 0.65 0.65

Figure 2.3-8. Loading Pattern 37E2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, Long Fuel per Cell Heat Load Limits

(All storage cell heat loads are in kW, D means Undamaged Fuel or Damaged Fuel in a DFC and/or using DFIs may be stored in cells denoted by D. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-44 Approved Contents 2.0

0.65 0.65 0.65

3.5 3.5 0.65 (D/F) Empty (D/F) 0.65

0.85 2.6 Empty 0.75 Empty 2.6 0.85

0.85 0.65 0.75 0.65 0.75 0.65 0.85

0.85 2.6 Empty 0.75 Empty 2.6 0.85

3.5 3.5 0.65 (D/F) Empty (D/F) 0.65

0.65 0.65 0.65

Figure 2.3-9. Loading Pattern 37E3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Long Fuel per Cell Heat Load Limits

(All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-45 Approved Contents 2.0

0.25 0.25 (D/F) 0.25 (D/F)

0.25 0.25 (D/F) 0.25 0.25 1.45 0.25 0.25 (D/F)

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

0.25 1.45 0.32 0.32 0.32 0.32 0.32 1.45 0.25

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

0.25 1.45 0.9 0.32 0.32 0.32 0.32 0.32 0.9 1.45 0.25

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

0.25 1.45 0.32 0.32 0.32 0.32 0.32 1.45 0.25

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

0.25 0.25 (D/F) 0.25 0.25 1.45 0.25 0.25 (D/F)

0.25 0.25 (D/F) 0.25 (D/F)

Figure 2.3-10. Loading Pattern 89A1 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per Cell Heat Load Limits

(All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-46 Approved Contents 2.0

0.25 0.25 0.25

0.25 0.25 0.25 1.45 (D/F) 0.25 0.25 0.25

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

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

0.25 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 0.25

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

0.25 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 0.25

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

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

0.25 0.25 0.25 1.45 (D/F) 0.25 0.25 0.25

0.25 0.25 0.25

Figure 2.3-11. Loading Pattern 89A2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, per Cell Heat Load Limits

(All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as empty must remain empty regardless of contents in adjacent cells)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-47 Approved Contents 2.0

0.11 0.11 (D/F) 0.47 (D/F)

0.19 0.19 (D/F) 0.23 0.68 1.46 0.68 0.23 (D/F)

0.25 0.25 (D/F) 0.27 1.42 1.05 0.40 1.05 1.42 0.27 (D/F)

0.23 1.44 0.29 0.31 0.33 0.31 0.29 1.44 0.23

0.10 0.10 (D/F) 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 (D/F)

0.40 1.46 0.47 0.33 0.21 0.10 0.21 0.33 0.47 1.46 0.40

0.10 0.10 (D/F) 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 (D/F)

0.23 1.44 0.29 0.31 0.33 0.31 0.29 1.44 0.23

0.25 0.25 (D/F) 0.27 1.42 1.05 0.40 1.05 1.42 0.27 (D/F)

0.19 0.19 (D/F) 0.23 0.68 1.46 0.68 0.23 (D/F)

0.11 0.11 (D/F) 0.47 (D/F)

Figure 2.3-12. Loading Pattern 89B1 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per cell Heat Load Limits

(All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-48 Approved Contents 2.0

0.11 0.47 0.11

0.19 0.23 0.68 1.46 (D/F) 0.68 0.23 0.19

0.25 0.27 1.42 1.42 (D/F) 1.05 0.40 1.05 (D/F) 0.27 0.25

0.23 1.44 Empty 0.31 0.33 0.31 Empty 1.44 (D/F) (D/F) 0.23

0.10 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 0.10

0.40 1.46 1.46 (D/F) 0.47 0.33 0.21 0.10 0.21 0.33 0.47 (D/F) 0.40

0.10 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 0.10

0.23 1.44 1.44 (D/F) Empty 0.31 0.33 0.31 Empty (D/F) 0.23

0.25 0.27 1.42 1.42 (D/F) 1.05 0.40 1.05 (D/F) 0.27 0.25

0.19 0.23 0.68 1.46 (D/F) 0.68 0.23 0.19

0.11 0.47 0.11

Figure 2.3-13. Loading Pattern 89B2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per Cell Heat Load Limits

(All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as empty must remain empty regardless of contents in adjacent cells)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-49 Approved Contents 2.0

0.64 0.64 (D/F) 0.95 (D/F)

1.37 1.37 (D/F) 3.03 1.7 3.03 (D/F)

0.86 Empty 0.73 Empty 2.64 0.86 (D/F) 2.64 (D/F)

0.95 2.43 0.79 0.22 0.79 2.43 0.95

0.86 Empty 0.73 Empty 2.64 0.86 (D/F) 2.64 (D/F)

1.37 1.37 (D/F) 3.03 1.7 3.03 (D/F)

0.64 0.64 (D/F) 0.95 (D/F)

Figure 2.3-14. Loading Pattern 1 for MPC-37P

(All Storage cell heat loads are in kW. Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell. Total MPC heat load shall not exceed 45 kW. Total heat load in every quadrant defined in appendix B figure 2.1-4 shall not exceed 11.25 kW.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-50 Approved Contents 2.0

0.64 0.95 0.64

3.03 3.03 1.37 (D/F) 1.7 (D/F) 1.37

0.86 2.64 Empty 0.73 Empty 2.64 0.86

0.95 2.43 0.79 0.22 0.79 2.43 0.95

0.86 2.64 Empty 0.73 Empty 2.64 0.86

3.03 3.03 1.37 (D/F) 1.7 (D/F) 1.37

0.64 0.95 0.64

Figure 2.3-15. Loading Pattern 2 for MPC-37P

(All Storage cell heat loads are in kW. Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell. Total MPC heat load shall not exceed 45 kW. Total heat load in every quadrant defined in appendix B figure 2.1-4 shall not exceed 11.25 kW.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-51 Approved Contents 2.0

2.4 Burnup Credit

Criticality control during loading of the MPC-37 and MPC-37P is achieved through either meeting the soluble boron limits in LCO 3.3.1 OR verifying that the assemblies meet the minimum burnup requirements in table 2.4-1 and the in-core operating requirements in table 2.4-3.

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

Method A: Burnup Verification Through Quantitative Burnup Measurement

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

Method B: Burnup Verification Through an Administrative Procedure and Qualitative Measurements

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

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

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

An independent, third-party verification of the loading process, including the fuel selection process and generation of the fuel move instructions.

Additionally, for all assemblies to be loaded that are required to meet a minimum burnup, a qualitative verification shall be performed that verifies that the assembly is not a fresh assembly.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-52 Approved Contents 2.0

Table 2.4-1. POLYNOMIAL FUNCTIONS FOR THE MINIMUM BURNUP AS A FUNCTION OF INITIAL ENRICHMENT

Cooling Minimum Burnup (GWd/mtU)

Assembly 1 Time, as a Function of the Initial Classes Configuration years Enrichment (wt.% 235U)

3.0 and f(x) = -7.9224E-02

x^3 -7.6419E-01

x^2 15x15B, C, Uniform <7.0 +2.2411E+01

x^1 -4.1183E+01 D, E, F, H, I 7.0 f(x) = +1.3212E-02

x^3 -1.6850E+00

x^2

+2.4595E+01

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

x^3 -5.8233E+00

x^2 17x17A, B, Regionalized <7.0 +4.0599E+01

x^1 -5.8346E+01 C, D, E 7.0 f(x) = +3.3423E-01

x^3 -5.1647E+00

x^2

+3.6549E+01

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

x^3 +1.1386E+01

x^2 Uniform <7.0 -2.9174E+01

x^1 +2.0850E+01 16x16A, B, 7.0 f(x) = -9.6572E-01

x^3 +1.0484E+01

x^2 C -2.5982E+01

x^1 +1.7515E+01 Regionalized Combined2 f(x) = -4.9680E-01

x^3 +4.9471E+00

x^2

(>3.0) -4.2373E+00

x^1 -7.3936E+00

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

2 The combined cooling time loading curve bounds the loading curves at 3 and 7 years cooling times and it is applicable for fuel with above 3 years cooling time.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-53 Approved Contents 2.0

Table 2.4-2. BURNUP CREDIT CONFIGURATIONS

Configuration Description

Configuration 1 Spent UNDAMAGED fuel assemblies are placed in all positions of the basket

Fresh UNDAMAGED fuel assemblies are placed in locations 3-4, Configuration 2 3-5, 3-12, and 3-13 (see figure 2.1-1); spent UNDAMAGED fuel assemblies are placed in the remaining positions Damaged Fuel Containers (DFCs) and/or Damaged Fuel Isolators (DFIs) with spent DAMAGED fuel assemblies are placed in Configuration 3 locations 3-1, 3-3, 3-4, 3-5, 3-6, 3-7, 3-10, 3-11, 3-12, 3-13, 3-14, and 3-16 (see figure 2.1-1); spent UNDAMAGED fuel assemblies are placed in the remaining positions DFCs with Damaged Fuel and/or with fresh FUEL DEBRIS are Configuration 4 placed in locations 3-1, 3-7, 3-10, and 3-16 with locations 2-1, 2-5, 2-8, and 2-12 (see figure 2.1-1) empty; spent UNDAMAGED fuel assemblies are placed in the remaining positions

1 PWR assemblies that have been located under a control rod bank that was permitted to be inserted more than 8 inches from the top of the active length during full power operation are restricted for storage in the Configuration 1, but permitted for storage in the Configuration 2, specifically in the basket cells qualified for the fresh fuel assemblies.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-54 Approved Contents 2.0

Table 2.4-3. IN-CORE OPERATING REQUIREMENTS

Assembly Specific Moderator Fuel Soluble Boron Type Power Temperature Temperature (ppm)

(MW/mtU) (K) (K)

Bounding Values (for Design Basis Calculations)

15x15D, E, F, 47.36 604 1169 1000 H

15x15B, C 52.33 620 1219 1000 (Note 1)

16x16A, B 51.90 608 1113 1000

17x17A, B, C, 61.61 620 1181 1000 D, E

Note:

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

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-55 Approved Contents 2.0

2.5 Burn up and Cooling Time Qualification Requirements

2.5.1 Burnup and cooling time limits for fuel assemblies authorized for loading into the MPC-32ML are provided in table 2.5-1. Burnup and cooling time limits for fuel assemblies authorized for loading according to only the alternative loading patterns shown in figures 2.3-1 through 2.3-9 (MPC-37) and figures 2.3-10 through 2.3-13 (MPC-89) are provided in table 2.5-2.

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

Ct = A

Bu3 + B

Bu2 + C

Bu + D

where,

Ct = Minimum cooling time (years)

Bu = Assembly-average burnup (MWd/mtU)

A, B, C, D = Polynomial coefficients listed in Tables 2.5-1 and 2.5-2

Minimum cooling time must also meet limits specified in table 2.1-1. If the calculated Ct is less than the cooling time limit in table 2.1-1, the minimum cooling time in table 2.1-1 is used.

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

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

Ct = A

Bu4 + B

Bu3 + C

Bu2 + D

Bu + E

Where,

Ct = Minimum cooling time (years)

Bu = Assembly-average burnup (MWd/mtU)

A, B, C, D, E = Polynomial coefficients listed in Table 2.5-3

2.5.3 Alternative burnup and cooling time limits for fuel assemblies authorized for loading into the MPC-37P and MPC-37 are provided in Tables 2.5-4 and Table 2.5-5, respectively.

2.5.4 Burnup and cooling time limits for Assembly Class 10x10J loaded according to Tables 2.3-2A, 2.3-2B, and 2.3-4 are provided in Table 2.5-6.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-56 Approved Contents 2.0

Table 2.5-1. BURNUP AND COOLIN G TIME FUEL QUALIFICATION REQUIREMENTSFOR MPC-32ML

A B C D

6.7667E-14 -3.6726E-09 8.1319E-05 2.7951E+00

Table 2.5-2. BURNUP AND COOLING TIME FUEL QUALIFICATION REQUIREMENTSFOR MPC-37 AND MPC-89

Cell Decay Heat Load Polynomial Coefficients Limit (kW) A B C D (Note 1)

MPC-37

0.85 1.68353E-13 -9.65193E-09 2.69692E-04 2.95915E-01

0.85 < decay heat 3.5 1.19409E-14 -1.53990E-09 9.56825E-05 -3.98326E-01

MPC-89 (Note 2)

0.32 1.65723E-13 -9.28339E-09 2.57533E-04 3.25897E-01

0.32 < decay heat 0.5 3.97779E-14 -2.80193E-09 1.36784E-04 3.04895E-01

0.5 < decay heat 0.75 1.44353E-14 -1.21525E-09 8.14851E-05 3.31914E-01

0.75 < decay heat 1.1 -7.45921E-15 1.09091E-09 -1.14219E-05 9.76224E-01

1.1 < decay heat 1.45 3.10800E-15 -7.92541E-11 1.56566E-05 6.47040E-01

1.45 < decay heat 1.6 -8.08081E-15 1.23810E-09 -3.48196E-05 1.11818E+00

Notes:

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

2. For calculation of the minimum cooling time for 10x10J fuel that is loaded in accordance with Figures 2.3-10 through 2.3-13, the assembly-average burnup must be increased by 5,000 MWd/mtU.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-57 Approved Contents 2.0

TABLE 2.5-3. BURNUP AND COOLING TIME FUEL QUALIFICATION REQUIREMENTS FOR MPC-37P AND MPC-44

Cell Decay Heat Load Polynomial Coefficients Limit (kW) A B C D E

MPC-37P

0.79 -7.95196E-18 1.45069E-12 -7.94501E-08 1.81131E-03 -1.09897E+01

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

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

1.37 < decay heat 2.64 -1.78154E-21 1.30015E-15 1.74063E-10 1.65882E-05 1.36110E+00

2.64 < decay heat 3.03 3.36123E-20 2.18480E-15 1.42012E-10 9.23077E-06 6.00000E-01

MPC-44

1.0 2.30737E-18 -1.72421E-13 3.59688E-09 9.41169E-05 6.41653E-01

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-58 Approved Contents 2.0

TABLE 2.5-4. ALTERNATIVE BURNUP A ND COOLING TIME FUEL QUALIFICATION REQUIREMENTS FOR THE MPC-37P Cell Location (see Figure 2.1-4) Maximum Burnup Minimum Cooling Time MWd/mtU Years

2-2, 2-4 through 2-9, 2-11 55000 1.6 60000 3.5

2-1, 2-3, 2-10, 2-12 55000 1.8 60000 3.5

3-4, 3-5, 3-12, 3-13 55000 2 60000 6

45000 3.5 3-2, 3-6 through 3-11, 3-15 50000 5 55000 6 60000 10 3-1, 3-3, 3-14, 3-16 50000 11 15000 3.5 1-2, 1-4, 1-5, 1-6, 1-8 50000 5 55000 10 60000 13 Note: Cell locations 1-1, 1-3, 1-7, and 1-9 need to remain empty.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-59 Approved Contents 2.0

TABLE 2.5-5. ALTERNATIVE BURNUP A ND COOLING TIME FUEL QUALIFICATION REQUIREMENTS FOR THE MPC-37 Cell Location Maximum Burnup Minimum Cooling Time (see Figure 2.1-1) MWd/mtU Years 50000 5 1-1 through 1-9 55000 6 60000 10

2-1 through 2-12 55000 5 60000 6

50000 3.5 3-1 through 3-16 55000 5 60000 6

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-60 Approved Contents 2.0

TABLE 2.5-6. BURNUP AND COOLING TIME FUEL QUALIFICATION REQUIREMENTS FOR ASSEMBLY CLASS 10X10J LOADED ACCORDING TO TABLE 2.3-2A

Region Maximum Burnup Minimum Cooling Time MWd/mtU Years 5000 1.2 10000 1.4 20000 2.0 2 30000 2.4 40000 3.0 50000 3.5 60000 5.0 70000 6.0 5000 1.8 10000 2.2 20000 2.8 1, 3 30000 3.5 40000 5.0 50000 7.0 60000 9.0 70000 13.0

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 2-61 Design Features 3.0

3.0 DESIGN FEATURES

3.1 Site

3.1.1 Site Location

The HI-STORM FW Cask System is authorized for general use by 10 CFR Part 50 license holders at various site locations under the provisions of 10 CFR 72, Subpart K.

3.2 Design Features Important for Criticality Control

3.2.1 MPC-37

1. Minimum basket cell ID: 8.92 in. (nominal)

2. Minimum basket cell wall thickness: 0.57 in. (nominal)

3. B4C in the Metamic-HT: 10.0 wt. % (min.)

3.2.2 MPC-89

1. Minimum basket cell ID: 5.99 in. (nominal)

2. Minimum basket cell wall thickness: 0.38 in. (nominal)

3. B4C in the Metamic-HT: 10.0 wt. % (min.)

3.2.3 Neutron Absorber Tests

1. The weight percentage of the boron carbide must be confirmed to be greater than or equal to 10% in each lot of Al/B4C powder.

2. The areal density of the B-10 isotope corresponding to the 10% min. weight density in the manufactured Metamic HT panels shall be independently confirmed by the neutron attenuation test method by testing at least one coupon from a randomly selected panel in each lot.

3. If the B-10 areal density criterion in the tested panels fails to meet the specific minimum, then the manufacturer has the option to reject the entire lot or to test a statistically significant number of panels and perform statistical analysis for acceptance.

4. All test procedures used in demonstrating compliance with the above requirements shall conform to the cask designers QA program which has been approved by the USNRC under docket number 71-0784.

3.2.4 MPC-32ML

1. Minimum basket cell ID: 9.53 (nominal)

2. Minimum basket cell wall thickness: 0.57 in (nominal)

3. B4C in the Metamic-HT: 10.0 wt. % (min.)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-1 Design Features 3.0

3.2.5 MPC-37P

1. Minimum basket cell ID: 8.70 (nominal)

2. Minimum basket cell wall thickness: 0.77 in (nominal)

3. B4C in the Metamic-HT: 10.0wt% (min.)

3.2.6 MPC-44

1. Minimum basket cell ID: 8.00 (nominal)

2. Minimum basket cell wall thickness: 0.49 in (nominal)

3. B4C in the Metamic-HT: 10.0wt% (min.)

3.3 Codes and Standards

The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2007 Edition, is the governing Code for the HI-STORM FW System MPC as clarified in Specification 3.3.1 below, except for Code sections V and IX. The ASME Code paragraphs applicable to the HI-STORM FW OVERPACK and TRANSFER CASK are listed in table 3-2. The latest effective editions of ASME Code sections V and IX, including addenda, may be used for activities governed by those sections, provided a written reconciliation of the later edition against the 2007 Edition, including any addenda, is performed by the certificate holder. American Concrete Institute (ACI) 349-85 is the governing Code for plain concrete as clarified in Appendix 1.D of the Final Safety Analysis Report for the HI-STORM 100 Cask System.

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 of the HI-STORM FW Cask System.

3.3.2 Construction/Fabrication Alternatives to Codes, Standards, and Criteria

Proposed alternatives to the ASME Code, section III, 2007 Edition, 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, 2007 Edition, 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)

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-2 Design Features 3.0

Table 3-1. List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC Subsection General Requirements. Because the MPC is not an ASME Enclosure NCA Requires preparation of a Code stamped vessel, none of the Vessel Design Specification, Design specifications, reports, certificates, or Report, Overpressure other general requirements specified by Protection Report, NCA are required. In lieu of a Design Certification of Construction Specification and Design Report, the Report, Data Report, and HI-STORM FSAR includes the design other administrative controls criteria, service conditions, and load for an ASME Code stamped combinations for the design and vessel. operation of the MPCs as well as the results of the stress analyses to demonstrate that applicable Code stress limits are met. Additionally, the fabricator is not required to have an ASME-certified QA program. All important-to-safety activities are governed by the NRC-approved Holtec QA program.

Because the cask components are not certified to the Code, the terms Certificate Holder and Inspector are not germane to the manufacturing of NRC-certified cask components. To eliminate ambiguity, the responsibilities assigned to the Certificate Holder in the Code, as applicable, shall be interpreted to apply to the NRC Certificate of Compliance (CoC) holder (and by extension, to the component fabricator) if the requirement must be fulfilled. The Code term Inspector means the QA/QC personnel of the CoC holder and its vendors assigned to oversee and inspect the manufacturing process.

MPC NB-1100 Statement of requirements MPC Enclosure Vessel is designed and Enclosure for Code stamping of will be fabricated in accordance with Vessel components. ASME Code, section III, subsection NB to the maximum practical extent, but Code stamping is not required.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-3 Design Features 3.0

Table 3-1. List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs) (continued)

MPC basket NB-1130 NB-1132.2(d) requires that The lugs that are used exclusively for supports the first connecting weld of a lifting an empty MPC are welded to the and lift lugs non-pressure retaining inside of the pressure-retaining MPC structural attachment to a shell, but are not designed in component shall be accordance with subsection NB. The considered part of the lug-to-Enclosure Vessel Weld is component unless the weld required to meet the stress limits of is more than 2t from the Reg. Guide 3.61 in lieu of subsection pressure retaining portion of NB of the Code.

the component, where t is the nominal thickness of the pressure retaining material.

NB-1132.2(e) requires that the first connecting weld of a welded nonstructural attachment to a component shall conform to NB-4430 if the connecting weld is within 2t from the pressure retaining portion of the component.

MPC NB-2000 Requires materials to be Materials will be supplied by Holtec Enclosure supplied by ASME-approved approved suppliers with Certified Vessel material supplier. Material Test Reports (CMTRs) in accordance with NB-2000 requirements.

MPC NB-2121 Provides permitted material Certain duplex stainless steels are not Enclosure specification for pressure-included in section II, Part D, tables 2A Vessel retaining material, which and 2B. These stainless steel alloys are must conform to section II, evaluated in the HI-STORM FW FSAR Part D, tables 2A and 2B and meet the required design criteria for use in the HI-STORM FW system.

MPC NB-3100 Provides requirements for These requirements are subsumed by Enclosure NF-3100 determining design loading the HI-STORM FW FSAR, serving as Vessel conditions, such as the Design Specification, which pressure, temperature, and establishes the service conditions and mechanical loads. load combinations for the storage system.

MPC NB-4120 NB-4121.2 and NF-4121.2 In-shop operations of short duration that Enclosure provide requirements for apply heat to a component, such as Vessel repetition of tensile or plasma cutting of plate stock, welding, impact tests for material machining, and coating are not, unless subjected to heat treatment explicitly stated by the Code, defined as during fabrication or heat treatment operations.

installation.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-4 Design Features 3.0

Table 3-1. List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs) (continued)

MPC NB-4220 Requires certain forming The cylindricity measurements on the Enclosure tolerances to be met for rolled shells are not specifically Vessel cylindrical, conical, or recorded in the shop travelers, as would spherical shells of a vessel. be the case for a Code-stamped pressure vessel. Rather, the requirements on inter-component clearances (such as the MPC-to-transfer cask) are guaranteed through fixture-controlled manufacturing. The fabrication specification and shop procedures ensure that all dimensional design objectives, including inter-component annular clearances are satisfied. The dimensions required to be met in fabrication are chosen to meet the functional requirements of the dry storage components. Thus, although the post-forming Code cylindricity requirements are not evaluated for compliance directly, they are indirectly satisfied (actually exceeded) in the final manufactured components.

MPC NB-4122 Implies that with the MPCs are built in lots. Material Enclosure exception of studs, bolts, traceability on raw materials to a heat Vessel nuts and heat exchanger number and corresponding CMTR is tubes, CMTRs must be maintained by Holtec through markings traceable to a specific piece on the raw material. Where material is of material in a component. cut or processed, markings are transferred accordingly to assure traceability. As materials are assembled into the lot of MPCs being manufactured, documentation is maintained to identify the heat numbers of materials being used for that item in the multiple MPCs being manufactured under that lot. A specific item within a specific MPC will have a number of heat numbers identified as possibly being used for the item in that particular MPC of which one or more of those heat numbers (and corresponding CMTRS) will have actually been used.

All of the heat numbers identified will comply with the requirements for the particular item.

MPC Lid NB-4243 Full penetration welds MPC lid and closure ring are not full and Closure required for Category C penetration welds. They are welded Ring Welds Joints (flat head to main independently to provide a redundant shell per NB-3352.3) seal.

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Table 3-1. List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs) (continued)

MPC NB-5230 Radiographic (RT) or Root (if more than one weld pass is Closure ultrasonic (UT) examination required) and final liquid penetrant Ring, Vent required. examination to be performed in and Drain accordance with NB-5245. The closure Cover Plate ring provides independent redundant Welds closure for vent and drain cover plates.

Vent and drain port cover plate welds are helium leakage tested.

MPC Lid to NB-5230 Radiographic (RT) or Only progressive liquid penetrant (PT)

Shell Weld ultrasonic (UT) examination examination is permitted. PT required. examination will include the root and final weld layers and each approx. 3/8" of weld depth.

MPC NB-6111 All completed pressure The MPC vessel is welded in the field Enclosure retaining systems shall be following fuel assembly loading. After Vessel and pressure tested. the lid to shell weld is completed, the Lid MPC shall then be pressure tested as defined in Chapter 10. Accessibility for leakage inspections preclude a Code compliant pressure test. All MPC enclosure vessel welds (except closure ring and vent/drain cover plate) are inspected by volumetric examination.

The MPC lid-to-shell weld shall be verified by progressive PT examination.

PT must include the root and final layers and each approximately 3/8 inch of weld depth.

The inspection results, including relevant findings (indications) shall be made a permanent part of the users records by video, photographic, of other means which provide an equivalent record of weld integrity. The video or photographic records should be taken during the final interpretation period described in ASME section V, Article 6, T-676. The vent/drain cover plate and the closure ring welds are confirmed by liquid penetrant examination. The inspection of the weld must be performed by qualified personnel and shall meet the acceptance requirements of ASME Code section III, NB-5350.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-6 Design Features 3.0

Table 3-1. List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs) (continued)

MPC NB-7000 Vessels are required to have No overpressure protection is provided.

Enclosure overpressure protection. Function of MPC enclosure vessel is to Vessel contain radioactive contents under normal, off-normal, and accident conditions of storage. MPC vessel is designed to withstand maximum internal pressure considering 100% fuel rod failure and maximum accident temperatures.

MPC NB-8000 States requirements for The HI-STORM FW system is to be Enclosure nameplates, stamping and marked and identified in accordance Vessel reports per NCA-8000. with 10 CFR 71 and 10 CFR 72 requirements. Code stamping is not required. QA data package to be in accordance with Holtec approved QA program.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-7 Design Features 3.0

Table 3-2. REFERENCE ASME CODE PARAGRAPHS FOR HI-STORM FW OVERPACK and HI-TRAC VW TRANSFER CASK, PRIMARY LOAD BEARING PARTS Item Code Paragraph Notes, Explanation and Applicability

1. Definition of primary and secondary members NF-1215 -

2. Jurisdictional boundary NF-1133 The intervening elements are termed interfacing SSCs in this FSAR.

Materials for ITS components shall be

3. Certification of material NF-2130 certified to the applicable section II of the (b) and (c) ASME Code or equivalent ASTM Specification.

4. Heat treatment of material NF-2170 and NF-2180 -

5. Storage of welding material NF-2440, NF-4411 -

6. Welding procedure specification Section IX Acceptance Criteria per Subsection NF

7. Welding material Section II -

8. Definition of Loading conditions NF-3111 -

9. Allowable stress values NF-3112.3 -

10. Rolling and sliding supports NF-3124 -

11. Differential thermal expansion NF-3127 -

NF-3143 Provisions for stress analysis for Class 3

12. Stress analysis NF-3380 linear structures is applicable for overpack NF-3522 top lid and the overpack and transfer cask NF-3523 shells.

13. Cutting of plate stock NF-4211 NF-4211.1 -

14. Forming NF-4212 -

15. Forming tolerance NF-4221 All cylindrical parts.

16. Fitting and Aligning Tack NF-4231 Welds NF-4231.1 -

17. Alignment NF-4232 -

18. Cleanliness of Weld Surfaces NF-4412 Applies to structural and non-structural welds

19. Backing Strips, Peening NF-4421 Applies to structural and non-structural NF-4422 welds NF-4611 Applies to structural and non-structural

20. Pre-heating and Interpass Temperature NF-4612 welds NF-4613

21. Non-Destructive Examination NF-5360 Invokes section V, Applies to Code welds only NF-5522

22. NDE Personnel Certification NF-5523 Applies to Code welds only NF-5530 All references to the ASME Code refer to applicable sections of the 2007 edition.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-8 Design Features 3.0

3.4 Site-Specific Parameters and Analyses

Site-specific parameters and analyses that w ill require verification by the system user are, as a minimum, as follows:

1. The temperature of 80o F is the maximum average yearly temperature for the VENTILATED OVERPACK. The temperature of 70°F is the maximum average yearly temperature for the UNVENTILATED OVERPACK. A Sites yearly average ambient temperature may be used for site-specific analysis.

2. The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40o F and less than 125o F.

3. a. For a storage cask in a free standing OVERPACK, the resultant horizontal acceleration (vectorial sum of two horizontal Zero Period Accelerations (ZPAs) at a three-dimensional seismic site), a H, and vertical ZPA, aV, on the top surface of the ISFSI pad, expressed as fractions of a, shall satisfy the following inequalities:

aH f (1 - aV); and aH r (1 - aV) / h

where f is the Coulomb friction coefficient for the cask/ISFSI pad interface, r is the radius of the cask, and h is the height of the cask center-of-gravity above the ISFSI pad surface. Unless demonstrated by appropriate testing that a higher coefficient of friction value is appropriate for a specific ISFSI, the value used shall be 0.53. If acceleration time-histories on the ISFSI pad surface are available, a H and aV may be the coincident values of the instantaneous net horizontal and vertical accelerations. If instantaneous accelerations are used, the inequalities shall be evaluated at each time step in the acceleration time history over the total duration of the seismic event.

If this static equilibrium based inequality cannot be met, a dynamic analysis of the cask/ISFSI pad assemblage with appropriate recognition of soil/structure interaction effects shall be performed to ensure that the casks will not tip over or undergo excessive sliding under the sites Design Basis Earthquake.

b. For a free standing OVERPACK under environmental conditions that may degrade the pad/cask interface friction (such as due to icing) the response of the casks under the sites Design Basis Earthquake shall be established using the best estimate of the friction coefficient in an appropriate analysis model. The analysis should demonstrate that the earthquake will not result in cask tipover or cause excessive sliding such that impact between casks could oc cur. Any impact between casks should be considered an accident for which the maximum total deflection, d, in the active fuel region of the basket panels shall be limited by the following inequality: d 0.005 l, where l is the basket cell inside dimension.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-9 Design Features 3.0

c. For those ISFSI sites with design basis seismic acceleration values that may overturn or cause excessive sliding of free-standing casks, the anchored OVERPACK shall be utilized. Each OVERPACK shall be anchored with studs and nuts fabricated with material(s) compatible with the environment of the expected location of the ISFSI. 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.

4. The maximum permitted depth of submergence under water shall not exceed 125 feet.

5. The maximum permissible velocity of floodwater, V, for a flood of height, h, shall be the lesser of V1 or V2, where:

V 1 = (1.876 W*)1/2 / h V 2 = (1.876 f W*/ D h)1/2

and W* is the apparent (buoyant weight) of the loaded overpack (in pounds force), D is the diameter of the overpack (in feet), and f is the interface coefficient of friction between the ISFSI pad and the overpack, as used in step 3.a above.

Use the height of the overpack, H, if h>H.

6. 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.

7. a. For a storage cask in a freestanding OVERPACK, the user shall demonstrate that the ISFSI pad parameters used in the non-mechanistic tipover and drop analyses are bounding for the site or a site specific non-mechanistic tipover and drop analyses to demonstrate that the acceptance criteria set forth in the HI-STORM FW FSAR are met shall be performed using the dynamic model described in FSAR section 3.4. The maximum total deflection, d, in the active fuel region of the basket panels shall be limited by the following inequality: d 0.005 l, where l is basket cell inside dimension. The site-speci fic analyses shall be performed using methodologies consistent with those described in the HI-STORM FW FSAR.

b. For storage in an anchored OVERPACK, a tipover event is not credible.

However, the ISFSI pad shall be designed to meet requirements of the anchored design. In addition, the user shall demonstrate that the ISFSI pad parameters used in the drop analysis are bounding for the site or a site-specific drop analysis to demonstrat e that the acceptance criteria set forth in the HI-STORM FW FSAR are met shall be performed using the dynamic model described in FSAR section 3.4. The maximum total deflection, d, in the active fuel region of the basket panels shall be limited by the following inequality: d 0.005 l, where l is basket cell inside

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-10 Design Features 3.0

dimension. The site-specific drop analysis shall be performed using methodologies consistent with those described in the HI-STORM FW FSAR.

8. In cases where engineered features (i.e., berms and shield walls) are used to ensure that the requirements of 10CFR72.104(a) are met, such features are to be considered important-to-safety and must be evaluated to determine the applicable quality assurance category.

9. LOADING OPERATIONS, TRANSPORT OPERATIONS, and UNLOADING OPERATIONS shall only be conducted with working area ambient temperatures 0o F.

10. For those users whose site-specific design basis includes an event or events (e.g., flood) that result in the blockage of any OVERPACK inlet or outlet air ducts for an extended period of time (i.e, longer than the total Completion Time of LCO 3.1.2), an analysis or evaluation may be performed to demonstrate adequate heat removal is available for the duration of the event. Adequate heat removal is defined as fuel cladding temperatures remaining below the short-term temperature limit. If the analysis or evaluati on is not performed, or if fuel cladding temperature limits are unable to be demonstrated by analysis or evaluation to remain below the short-term temperature limit for the duration of the event, provisions shall be established to provide alternate means of cooling to accomplish this objective.

11. Users shall establish procedural and/or mechanical barriers to ensure that during LOADING OPERATIONS and UNLOADING OPERATIONS, either the fuel cladding is covered by water, or the MPC is filled with an inert gas.

12. The entire haul route shall be evaluated to ensure that the route can support the weight of the loaded system and its conveyance.

13. The loaded system and its conveyance shall be evaluated to ensure under the site-specific Design Basis Earthquake the system does not tipover or slide off the haul route.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-11 Design Features 3.0

14. The HI-STORM FW/HI-TRAC VW stack which occurs during MPC TRANSFER shall be evaluated to ensure under the site-specific Design Basis Earthquake the system does not tipover. A probabilistic risk assessment cannot be used to rule out the occurrence of the earthquake during MPC TRANSFER.

3.5 Combustible Gas Monitoring During MPC Lid Welding and Cutting

During MPC lid-to-shell welding and cutting operations, combustible gas monitoring of the space under the MPC lid is required, to ensure that there is no combustible mixture present.

Certificate of Compliance No. 1032 Amendment No. 7 Appendix B 3-12

v t e Letter Sequence Other
CAC:001028, (Approved, Closed) EPID:L-2021-LLA-0053, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, ... further results\|Request]] Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting Questions 25 August 2021 20 February 2020 6 March 2020 31 March 2020 31 March 2020 10 April 2020 28 May 2020 28 May 2020 4 August 2020 31 August 2020 30 September 2020 28 September 2020 6 October 2020 20 November 2020 10 December 2020 16 December 2020 14 January 2021 14 January 2021 22 January 2021 23 March 2021 23 March 2021 3 March 2021 20 May 2021 15 June 2021 30 August 2021 28 October 2021 28 October 2021 18 October 2021 3 November 2021 21 December 2021 21 December 2021 8 December 2021 8 December 2021 20 January 2022 20 January 2022 6 May 2022 23 March 2022 31 March 2022 25 May 2022 1 July 2022 8 December 2022 4 January 2023 6 March 2023 6 March 2023 25 July 2023 25 July 2023 20 June 2023 4 October 2023 4 October 2023 28 August 2023 2 November 2023 ... further results Answers 21 September 2023 31 March 2020 5 June 2020 10 July 2020 11 September 2020 11 November 2020 27 January 2021 9 February 2021 19 November 2021 30 November 2021 25 February 2022 7 June 2022 11 July 2022 13 July 2022 29 July 2022 31 August 2022 31 August 2022 9 September 2022 3 October 2022 3 October 2022 1 December 2022 21 December 2022 6 January 2023 27 January 2023 17 March 2023 8 May 2023 30 June 2023 22 April 2024 14 May 2024 4 November 2024 Results Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, ... further results\|Approval]] Other: L-23-005, Independent Spent Fuel Storage Installation License Renewal Application, Revision 1 (Cac/Epid No. 001028/L-2022-RNW-0007), ML19276D398, ML20014E677, ML20065N277, ML20065N278, ML20065N280, ML20065N281, ML20065N285, ML20071F156, ML20076D696, ML20094G482, ML20099A180, ML20104C015, ML20104C016, ML20104C018, ML20104C019, ML20105A135, ML20105A136, ML20105A137, ML20105A138, ML20105A139, ML20105A173, ML20111A240, ML20115E377, ML20136A049, ML20136A050, ML20136A051, ML20150A300, ML20150A335, ML20150A421, ML20155K741, ML20155K742, ML20155K743, ML20155K744, ML20160A040, ML20161A088, ML20163A702, ML20163A703, ML20163A704, ML20181A211, ML20181A212, ML20192A328, ML20192A329, ML20212L768, ML20212L769, ML20212L878, ML20223A036, ML20224A287, ML20260H376, ML20261H420... further results
MONTHYEAR2020-03-06 [Table View]

ML24199A240

Text

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