ML22019A240

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Proposed Amendment 8 TS, Appendix B
ML22019A240
Person / Time
Site: 07201032
Issue date: 04/25/2022
From:
Storage and Transportation Licensing Branch
To:
C ALLEN NRC/NMSS/DFM/STLB 3014156877
Shared Package
ML22019A111 List:
References
CAC 001028, EPID L-2021-LLA-0139
Download: ML22019A240 (60)
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Text

CERTIFICATE OF COMPLIANCE NO. 1032 APPENDIX B APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STORM FW MPC STORAGE SYSTEM

TABLE OF CONTENTS 1.0 DEFINITIONS ........................................................................................................ 1-1 2.0 APPROVED CONTENTS ...................................................................................... 2-1 2.1 Fuel Specifications and Loading Conditions ...................................................... 2-1 2.2 Violations ........................................................................................................... 2-1 2.3 Decay Heat Limits ........................................................................................... 2-21 2.4 Burnup Credit .................................................................................................. 2-39 2.5 Burn up and Cooling Time Fuel Qualification Requirements ........................... 2-43 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 Table 2.1-1 Fuel Assembly Limits .......................................................................... 2-5 Table 2.1-2 PWR Fuel Assembly Characteristics ................................................ 2-11 Table 2.1-3 BWR Fuel Assembly Characteristics ................................................ 2-16 Table 2.3-1A MPC-37 Heat Load Data................................................................... 2-22 Table 2.3-1B MPC-37 Heat Load Data................................................................... 2-22 Table 2.3-1C MPC-37 Heat Load Data................................................................... 2-22 Table 2.3-2A MPC-89 Heat Load Data................................................................... 2-23 Table 2.3-2B MPC-89 Heat Load Data................................................................... 2-23 Table 2.3-3 MPC-37 Heat Load Data................................................................... 2-23 Table 2.3-4 MPC-89 Heat Load Data................................................................... 2-24 Table 2.3-5 MPC-32ML Heat Load Data.............................................................. 2-24 Table 2.3-6 PWR Fuel Length Categories ........................................................... 2-24 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.................................................................. 2-26 Figure 2.3-2 Loading Pattern 37C2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, Short Fuel per Cell Heat Load Limits

.......................................................................................................... 2-27 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.................................................................. 2-28 Figure 2.3-4 Loading Pattern 37D1 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Standard Fuel per Cell Heat Load ................................................................... 2-29 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 ...................................................................................... 2-30 Certificate of Compliance No. 1032 Amendment No. 8 Appendix B i

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 ......................................................... 2-31 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 DFC, Long Fuel per Cell Heat Load Limits ..................... 2-32 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 ...................................................................................... 2-33 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.................................................................. 2-34 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 ...................................................................................... 2-35 Figure 2.3-11 Loading Pattern 89A2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per Cell Heat Load Limits ...................................................................................... 2-36 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 ....................................................................................... 2-37 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 ....................................................................................... 2-38 Table 2.4-1 Polynomial Functions for the Minimum Burnup as a Function of Initial Enrichment........................................................................................ 2-40 Table 2.4-2 Burnup Credit Configurations............................................................ 2-41 Table 2.4-3 In-Core Operating Requirements ...................................................... 2-42 Table 2.5-1 Burnup and Cooling Time Fuel Qualification Requirements for MPC-32ML........................................................................................ 2-43 Table 2.5-2 Burnup and Cooling Time Fuel Qualification Requirements for MPC-37 And MPC-89 .................................................................................... 2-44 3.0 DESIGN FEATURES............................................................................................. 3-1 3.1 Site .................................................................................................................... 3-1 3.2 Design Features Important for Criticality Control ............................................... 3-1 3.3 Codes and Standards ........................................................................................ 3-2 3.4 Site Specific Parameters and Analyses ............................................................. 3-9 3.5 Combustible Gas Monitoring During MPC Lid Welding and Cutting ................ 3-12 Table 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)..... 3-3 Table 3-2 Reference ASME Code Paragraphs for HI-STORM FW Overpack and HI-TRAC VW Transfer Cask, Primary Load Bearing Parts ..................... 3-8 Certificate of Compliance No. 1032 Amendment No. 8 Appendix B ii

Definitions 1.0 This page is intended to be BLANK.

1.0 Definitions Refer to Appendix A for Definitions.

Certificate of Compliance No. 1032 Amendment No. 8 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 HARDWARE meeting the limits specified in Table 2.1-1 and other referenced tables may be stored in the HI-STORM FW MPC Storage System.
b. All BWR fuel assemblies may be stored with or without ZR channels.

2.1.2 Fuel Loading Figures 2.1-1 and 2.1-2 define the regions for the MPC-37 and MPC-89 models, respectively. Figure 2.1-3 defines the cell identifications for the MPC-32ML. 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 />, notify the NRC Operations Center.

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

Certificate of Compliance No.1032 Amendment No. 8 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. 8 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 2-40 3-35 3-36 3-37 Legend Region-Cell ID 3-38 3-39 3-40 Figure 2.1-2 MPC-89 Region-Cell Identification Certificate of Compliance No.1032 Amendment No. 8 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. 8 Appendix B 2-4

Approved Contents 2.0 Table 2.1-1 (page 1 of 6)

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

1. Uranium oxide PWR UNDAMAGED FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, and/or FUEL DEBRIS meeting the criteria in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):
a. Cladding Type: ZR
b. Maximum Initial Enrichment: 5.0 wt. % U-235 with soluble boron credit per LCO 3.3.1 OR burnup credit per Section 2.4
c. Post-irradiation Cooling Time Cooling Time 1 years and meeting the and Average Burnup Per 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 (nominal design including NON-FUEL HARDWARE and DFC)
f. Fuel Assembly Width: 8.54 inches (nominal design)
g. Fuel Assembly Weight: 2050 lbs (including NON-FUEL HARDWARE and DFC)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-5

Approved Contents 2.0 Table 2.1-1 (page 2 of 6)

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

B. Quantity per MPC: 37 FUEL ASSEMBLIES with up to twelve (12) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 3-1, 3-3 through 3-7, 3-10 through 3-14, and 3-16 (see Figure 2.1-1) OR in fuel storage locations 2-1, 2-3, 2-4, 2-5, 2-8, 2-9, 2-10, and 2-12 (see Figure 2.1-1), depending on heat load pattern, see Section 2.3.1. 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) BRPAs 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. 8 Appendix B 2-6

Approved Contents 2.0 Table 2.1-1 (page 3 of 6)

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

1. Uranium oxide BWR UNDAMAGED FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, and/or FUEL DEBRIS meeting the criteria in Table 2.1-3, 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. % U-235
d. Post-irradiation Cooling Time and Average Burnup Per Assembly
i. Array/Class 8x8F Cooling time 10 years and an assembly average burnup 27.5 GWD/MTU.

ii. All Other Array Classes Cooling Time 1 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 inches (nominal design)
g. Fuel Assembly Width 5.95 inches (nominal design)
h. Fuel Assembly Weight 850 lbs, including a DFC as well as a channel Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-7

Approved Contents 2.0 Table 2.1-1 (page 4 of 6)

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

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

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

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

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

Approved Contents 2.0 Table 2.1-1 (page 5 of 6)

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

1. Uranium oxide PWR UNDAMAGED FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, and/or FUEL DEBRIS meeting the criteria for array/class 16x16D in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):
a. Cladding Type: ZR
b. Maximum initial enrichment: 5.0 wt. % U-235 with soluble boron credit per LCO 3.3.1
c. Post-irradiation Cooling Time Cooling Time 3 years and meeting the and Average Burnup Per 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 inches (nominal design including NON-FUEL HARDWARE and DFC)
f. Fuel Assembly Width: 9.04 inches (nominal design)
g. Fuel Assembly Weight: 2200 lbs (including NON-FUEL HARDWARE and DFC). Average fuel weight not to exceed 2140 lbs.

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-9

Approved Contents 2.0 Table 2.1-1 (page 6 of 6)

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

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

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

D. Up to thirty-two (32) BRPAs 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. 8 Appendix B 2-10

Approved Contents 2.0 Table 2.1-2 (page 1 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Notes 1, 7)

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

Fuel Clad O.D. (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.)

0.3444 0.367 0.3805 0.3671 0.3570 (Note 3)

Fuel Rod Pitch (in.) 0.556 0.566 0.580 0.563 0.563 Active Fuel Length 150 150 150 150 150 (in.)

No. of Guide and/or 5 17 17 21 21 Instrument Tubes (Note 2)

Guide/Instrument 0.017 0.017 0.038 0.015 0.0165 Tube Thickness (in.)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-11

Approved Contents 2.0 Table 2.1-2 (page 2 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Notes 1, 7)

Fuel Assembly 15x15 D 15x15 E 15x15 F 15x15 H 15x15 I Array/Class No. of Fuel Rod 216 208 208 208 208 Locations (Note 6) (Note 4)

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.)

0.3735 0.3707 0.3742 0.3622 0.3600 (Note 3)

Fuel Rod Pitch (in.) 0.568 0.568 0.568 0.568 0.550 Active Fuel Length 150 150 150 150 150 (in.)

No. of Guide and/or 17 17 17 17 9 (Note 4)

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

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-12

Approved Contents 2.0 Table 2.1-2 (page 3 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Notes 1, 7)

Fuel Assembly 16x16D 16x16 A 16x16B 16x16C 16x16E Array and Class (Note 5)

No. of Fuel Rod 236 236 235 236 235 Locations (Note 6)

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.)

0.3255 0.3225 0.3225 0.359 0.3225 (Note 3)

Fuel Rod Pitch (in.) 0.506 0.506 0.485 0.563 0.485 Active Fuel length 150 150 150 154.5 150 (in.)

No. of Guide and/or 5 5 21 20 21 Instrument Tubes (Note 2) (Note 2)

Guide/Instrument Tube Thickness 0.0350 0.04 0.0157 0.015 0.0157 (in.)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-13

Approved Contents 2.0 Table 2.1-2 (page 4 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Notes 1, 7)

Fuel Assembly Array 17x17A 17x17 B 17x17 C 17x17 D 17x17 E and Class No. of Fuel Rod 264 264 264 264 265 Locations (Note 6)

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.)

0.3088 0.3232 0.3252 0.3232 0.3232 (Note 3)

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 25 25 25 25 24 Instrument Tubes Guide/Instrument 0.016 0.014 0.020 0.014 0.014 Tube Thickness (in.)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-14

Approved Contents 2.0 Table 2.1-2 (page 5 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS Notes:

1. All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
2. 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. 8 Appendix B 2-15

Approved Contents 2.0 Table 2.1-3 (page 1 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Notes 1, 17)

Fuel Assembly Array 7x7 B 7x7 C 8x8 B 8x8 C 8x8 D 8x8 E and Class 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

< 150 < 150 < 150 < 150 < 150 < 150 Length (in.)

No. of Water Rods 1 1-4 0 1 or 0 2 5 (Note 10) (Note 15) (Note 6)

Water Rod Thickness N/A N/A > 0.034 > 0.00 > 0.00 > 0.034 (in.)

Channel Thickness

< 0.120 < 0.120 < 0.120 < 0.120 < 0.120 < 0.100 (in.)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-16

Approved Contents 2.0 Table 2.1-3 (2 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Notes 1, 17)

Fuel Assembly 8x8F 8x8G 9x9 A 9x9 B 9x9 C 9x9 D Array and Class Maximum Planar-Average Initial < 4.5

< 4.8 < 4.8 < 4.8 < 4.8 < 4.8 Enrichment (wt.% (Note 12) 235U) (Note 14)

No. of Fuel Rod 74/66 64 60 72 80 79 Locations (Note 16) (Note 4)

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

< 150 < 150 < 150 < 150 < 150 < 150 Length (in.)

No. of Water Rods N/A 4 1 2 1 2 (Note 10) (Note 2) (Note 15) (Note 5)

Water Rod

> 0.0315 N/A > 0.00 > 0.00 > 0.020 > 0.0300 Thickness (in.)

Channel Thickness

< 0.055 < 0.120 < 0.120 < 0.120 < 0.100 < 0.100 (in.)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-17

Approved Contents 2.0 Table 2.1-3 (page 3 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Notes 1, 17)

Fuel Assembly 9x9 E 9x9 F 9x9 G 10x10 A 10x10 B Array and Class (Note 2) (Note 2)

Maximum Planar-

< 4.5 < 4.5 Average Initial (Note (Note < 4.8 < 4.8 < 4.8 Enrichment (wt.%

235U) (Note 14) 12) 12)

No. of Fuel Rod 92/78 91/83 76 76 72 Locations (Note 16) (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

< 150 < 150 < 150 < 150 < 150 Length (in.)

No. of Water Rods 1 1 5 5 2 (Note 10) (Note 5) (Note 5)

Water Rod Thickness

>0.0120 >0.0120 >0.0320 >0.0300 > 0.00 (in.)

Channel Thickness

< 0.120 < 0.120 < 0.120 < 0.120 < 0.120 (in.)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-18

Approved Contents 2.0 Table 2.1-3 (page 4 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Notes 1, 17)

Fuel Assembly Array and 10x10 C 10x10 F 10x10 G 10x10 I 11x11 A Class Maximum Planar-Average

< 4.7 < 4.6 Initial Enrichment (wt.% 235U) < 4.8 < 4.8 < 4.8 (Note 13) (Note 12)

(Note 14)

No. of Fuel Rod Locations 92/78 96 96/84 91/79 112/92 (Note 16) (Note 7)

Fuel Clad O.D. (in.) > 0.3780 > 0.4035 > 0.387 > 0.4047 > 0.3701 Fuel Clad I.D. (in.) < 0.3294 < 0.3570 < 0.340 < 0.3559 < 0.3252 Fuel Pellet Dia. (in.) < 0.3224 < 0.3500 < 0.334 < 0.3492 < 0.3193 Fuel Rod Pitch (in.) < 0.488 < 0.510 < 0.512 < 0.5100 < 0.4705 Design Active Fuel Length (in.) < 150 < 150 < 150 < 150 < 150 No. of Water Rods (Note 10) 5 5 1 1 2

(Note 9) (Note 9) (Note 5) (Note 5)

Water Rod Thickness (in.) > 0.031 > 0.030 > 0.031 > 0.0315 > 0.0340 Channel Thickness (in.) < 0.055 < 0.120 < 0.060 < 0.100 < 0.100 Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-19

Approved Contents 2.0 Table 2.1-3 (page 5 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS NOTES:

1. All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
2. 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.% U-235.
13. When loading fuel assemblies classified as DAMAGED FUEL, all assemblies in the MPC are limited to 4.6 wt.% U-235.
14. In accordance with the definition of UNDAMAGED FUEL, certain assemblies may be limited to 3.3 wt.% U-235. When loading these fuel assemblies, all assemblies in the MPC are limited to 3.3 wt.% U-235.
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.

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-20

Approved Contents 2.0 2.3 Decay Heat Limits (Changes in blue are due to RAI response)

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 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. 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. 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.

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-21

Approved Contents 2.0 TABLE 2.3-1A MPC-37 HEAT LOAD DATA (See Figure 2.1-1)

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

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

Number of Regions: 3 Number of Storage Cells: 37 90% of Pattern A - Sub-design Heat Load (kW): 39.68 Region No. Decay Heat Limit per Number of Cells Decay Heat Limit per Cell, 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 Number of Cells Decay Heat Limit per Cell, 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. 8 Appendix B 2-22

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 Number of Cells Decay Heat Limit per 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 Number of Cells Decay Heat Limit per Cell, 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 Number of Cells Decay Heat Limit per 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. 8 Appendix B 2-23

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 Number of Cells Decay Heat Limit per 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 Notes:
1. L means "nominal active fuel length". The nominal, unirradiated active fuel length of the PWR fuel assembly is used to designate it as short, standard and long.

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-24

Approved Contents 2.0 2.3.2 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. 8 Appendix B 2-25

Approved Contents 2.0 0.45 0.45 0.45 (D/F) (D/F) 0.45 0.45 3.2 0.5 3.2 (D/F) (D/F) 0.6 0.6 2.4 0.5 0.6 0.5 2.4 (D/F) (D/F) 0.6 0.5 0.6 0.5 0.6 0.5 0.6 0.6 0.6 2.4 0.5 0.6 0.5 2.4 (D/F) (D/F) 0.45 0.45 3.2 0.5 3.2 (D/F) (D/F) 0.45 0.45 0.45 (D/F) (D/F)

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

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-26

Approved Contents 2.0 0.45 0.45 0.45 3.2 3.2 0.45 Empty 0.45 (D) (D) 2.4 2.4 0.6 Empty 0.6 Empty 0.6 (D) (D) 0.6 0.5 0.6 0.5 0.6 0.5 0.6 2.4 2.4 0.6 Empty 0.6 Empty 0.6 (D) (D) 3.2 3.2 0.45 Empty 0.45 (D) (D) 0.45 0.45 0.45 Figure 2.3-2 Loading Pattern 37C2 for MPC-37 Containing Undamaged and Damaged Fuel in DFC/DFI/, Short Fuel per Cell Heat Load Limits (All storage cell heat loads are in kW, Undamaged Fuel or Damaged Fuel in a DFC and/or using DFIs may be stored in cells denoted by D. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-27

Approved Contents 2.0 0.45 0.45 0.45 3.2 3.2 0.45 Empty 0.45 (D/F) (D/F) 0.6 2.4 Empty 0.6 Empty 2.4 0.6 0.6 0.5 0.6 0.5 0.6 0.5 0.6 0.6 2.4 Empty 0.6 Empty 2.4 0.6 3.2 3.2 0.45 Empty 0.45 (D/F) (D/F) 0.45 0.45 0.45 Figure 2.3-3 Loading Pattern 37C3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Short Fuel per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.

Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-28

Approved Contents 2.0 0.55 0.55 0.55 (D/F) (D/F) 0.55 0.55 3.2 0.55 3.2 (D/F) (D/F) 0.75 0.75 2.4 0.55 0.65 0.55 2.4 (D/F) (D/F) 0.75 0.55 0.65 0.55 0.65 0.55 0.75 0.75 0.75 2.4 0.55 0.65 0.55 2.4 (D/F) (D/F) 0.55 0.55 3.2 0.55 3.2 (D/F) (D/F) 0.55 0.55 0.55 (D/F) (D/F)

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

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-29

Approved Contents 2.0 0.55 0.55 0.55 3.2 3.2 0.55 Empty 0.55 (D) (D) 2.4 2.4 0.75 Empty 0.65 Empty 0.75 (D) (D) 0.75 0.55 0.65 0.55 0.65 0.55 0.75 2.4 2.4 0.75 Empty 0.65 Empty 0.75 (D) (D) 3.2 3.2 0.55 Empty 0.55 (D) (D) 0.55 0.55 0.55 Figure 2.3-5 Loading Pattern 37D2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs Standard Fuel per Cell Heat Load Limits (All storage cell heat loads are in kW, D Undamaged Fuel or Damaged Fuel in a DFC and/or using DFIs may be stored in cells denoted by D. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-30

Approved Contents 2.0 0.55 0.55 0.55 3.2 3.2 0.55 Empty 0.55 (D/F) (D/F) 0.75 2.4 Empty 0.65 Empty 2.4 0.75 0.75 0.55 0.65 0.55 0.65 0.55 0.75 0.75 2.4 Empty 0.65 Empty 2.4 0.75 3.2 3.2 0.55 Empty 0.55 (D/F) (D/F) 0.55 0.55 0.55 Figure 2.3-6 Loading Pattern 37D3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Standard Fuel per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.

Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell.)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-31

Approved Contents 2.0 0.65 0.65 0.65 (D/F) (D/F) 0.65 0.65 3.5 0.65 3.5 (D/F) (D/F) 0.85 0.85 2.6 0.65 0.75 0.65 2.6 (D/F) (D/F) 0.85 0.65 0.75 0.65 0.75 0.65 0.85 0.85 0.85 2.6 0.65 0.75 0.65 2.6 (D/F) (D/F) 0.65 0.65 3.5 0.65 3.5 (D/F) (D/F) 0.65 0.65 0.65 (D/F) (D/F)

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

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-32

Approved Contents 2.0 0.65 0.65 0.65 3.5 3.5 0.65 Empty 0.65 (D) (D) 2.6 2.6 0.85 Empty 0.75 Empty 0.85 (D) (D) 0.85 0.65 0.75 0.65 0.75 0.65 0.85 2.6 2.6 0.85 Empty 0.75 Empty 0.85 (D) (D) 3.5 3.5 0.65 Empty 0.65 (D) (D) 0.65 0.65 0.65 Figure 2.3-8 Loading Pattern 37E2 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, Long Fuel per Cell Heat Load Limits (All storage cell heat loads are in kW, D means Undamaged Fuel or Damaged Fuel in a DFC and/or using DFIs may be stored in cells denoted by D. Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-33

Approved Contents 2.0 0.65 0.65 0.65 3.5 3.5 0.65 Empty 0.65 (D/F) (D/F) 0.85 2.6 Empty 0.75 Empty 2.6 0.85 0.85 0.65 0.75 0.65 0.75 0.65 0.85 0.85 2.6 Empty 0.75 Empty 2.6 0.85 3.5 3.5 0.65 Empty 0.65 (D/F) (D/F) 0.65 0.65 0.65 Figure 2.3-9 Loading Pattern 37E3 for MPC-37 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, Long Fuel per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.

Cells denoted as Empty must remain empty regardless of the contents of the adjacent cell)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-34

Approved Contents 2.0 0.25 0.25 0.25 (D/F) (D/F) 0.25 0.25 0.25 0.25 1.45 0.25 0.25 (D/F) (D/F) 0.25 0.25 0.25 1.45 0.9 0.9 0.9 1.45 0.25 (D/F) (D/F) 0.25 1.45 0.32 0.32 0.32 0.32 0.32 1.45 0.25 0.25 0.25 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 (D/F) (D/F) 0.25 1.45 0.9 0.32 0.32 0.32 0.32 0.32 0.9 1.45 0.25 0.25 0.25 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 (D/F) (D/F) 0.25 1.45 0.32 0.32 0.32 0.32 0.32 1.45 0.25 0.25 0.25 0.25 1.45 0.9 0.9 0.9 1.45 0.25 (D/F) (D/F) 0.25 0.25 0.25 0.25 1.45 0.25 0.25 (D/F) (D/F) 0.25 0.25 0.25 (D/F) (D/F)

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

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-35

Approved Contents 2.0 0.25 0.25 0.25 1.45 0.25 0.25 0.25 0.25 0.25 0.25 (D/F) 1.45 1.45 0.25 0.25 0.9 0.9 0.9 0.25 0.25 (D/F) (D/F) 1.45 1.45 0.25 Empty 0.32 0.32 0.32 Empty 0.25 (D/F) (D/F) 0.25 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 0.25 1.45 1.45 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 (D/F) (D/F) 0.25 0.25 0.9 0.32 0.32 0.32 0.32 0.32 0.9 0.25 0.25 1.45 1.45 0.25 Empty 0.32 0.32 0.32 Empty 0.25 (D/F) (D/F) 1.45 1.45 0.25 0.25 0.9 0.9 0.9 0.25 0.25 (D/F) (D/F) 1.45 0.25 0.25 0.25 0.25 0.25 0.25 (D/F) 0.25 0.25 0.25 Figure 2.3-11 Loading Pattern 89A2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFCs, per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.

Cells denoted as empty must remain empty regardless of contents in adjacent cells)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-36

Approved Contents 2.0 0.11 0.11 0.47 (D/F) (D/F) 0.19 0.19 0.23 0.68 1.46 0.68 0.23 (D/F) (D/F) 0.25 0.25 0.27 1.42 1.05 0.40 1.05 1.42 0.27 (D/F) (D/F) 0.23 1.44 0.29 0.31 0.33 0.31 0.29 1.44 0.23 0.10 0.10 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 (D/F) (D/F) 0.40 1.46 0.47 0.33 0.21 0.10 0.21 0.33 0.47 1.46 0.40 0.10 0.10 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 (D/F) (D/F) 0.23 1.44 0.29 0.31 0.33 0.31 0.29 1.44 0.23 0.25 0.25 0.27 1.42 1.05 0.40 1.05 1.42 0.27 (D/F) (D/F) 0.19 0.19 0.23 0.68 1.46 0.68 0.23 (D/F) (D/F) 0.11 0.11 0.47 (D/F) (D/F)

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

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-37

Approved Contents 2.0 0.11 0.47 0.11 1.46 0.19 0.23 0.68 0.68 0.23 0.19 (D/F) 1.42 1.42 0.25 0.27 1.05 0.40 1.05 0.27 0.25 (D/F) (D/F) 1.44 1.44 0.23 Empty 0.31 0.33 0.31 Empty 0.23 (D/F) (D/F) 0.10 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 0.10 1.46 1.46 0.40 0.47 0.33 0.21 0.10 0.21 0.33 0.47 0.40 (D/F) (D/F) 0.10 0.71 0.72 0.36 0.28 0.21 0.28 0.36 0.72 0.71 0.10 1.44 1.44 0.23 Empty 0.31 0.33 0.31 Empty 0.23 (D/F) (D/F) 1.42 1.42 0.25 0.27 1.05 0.40 1.05 0.27 0.25 (D/F) (D/F) 1.46 0.19 0.23 0.68 0.68 0.23 0.19 (D/F) 0.11 0.47 0.11 Figure 2.3-13 Loading Pattern 89B2 for MPC-89 Containing Undamaged and Damaged Fuel in DFCs/DFIs, and/or Fuel Debris in DFC, per Cell Heat Load Limits (All Storage cell heat loads are in kW, Undamaged Fuel, or Damaged Fuel in DFCs and/or using DFIs, and/or Fuel Debris in a DFC may be stored in cells denoted by D/F.

Cells denoted as empty must remain empty regardless of contents in adjacent cells)

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-38

Approved Contents 2.0 2.4 Burnup Credit Criticality control during loading of the MPC-37 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 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 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. 8 Appendix B 2-39

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 Time, as a Function of the Initial Classes Configuration1 years Enrichment (wt% 235U) 3.0 and f(x) = -7.9224e-02

  • x^3 -7.6419e-01
  • x^2 15x15B, C, <7.0 +2.2411e+01
  • x^1 -4.1183e+01 D, E, F, H, I Uniform f(x) = +1.3212e-02
  • x^3 -1.6850e+00
  • x^2 7.0

+2.4595e+01

  • x^1 -4.2603e+01 and 3.0 and f(x) = +3.6976e-01
  • x^3 -5.8233e+00
  • x^2 17x17A, B, <7.0 +4.0599e+01
  • x^1 -5.8346e+01 C, D, E Regionalized f(x) = +3.3423e-01
  • x^3 -5.1647e+00
  • x^2 7.0

+3.6549e+01

  • x^1 -5.2348e+01 3.0 and f(x) = -1.0361e+00
  • x^3 +1.1386e+01
  • x^2

<7.0 -2.9174e+01

  • x^1 +2.0850e+01 Uniform f(x) = -9.6572e-01
  • x^3 +1.0484e+01
  • x^2 16x16A, B, 7.0 C -2.5982e+01
  • x^1 +1.7515e+01 Combined2 f(x) = -4.9680e-01
  • x^3 +4.9471e+00
  • x^2 Regionalized

(>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. 8 Appendix B 2-40

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 Configuration 2 Fresh UNDAMAGED fuel assemblies are placed in locations 3-4, 3-5, 3-12, and 3-13 (see Figure 2.1-1); spent UNDAMAGED fuel assemblies are placed in the remaining positions Configuration 3 Damaged Fuel Containers (DFCs) and/or Damaged Fuel Isolators (DFIs) with spent DAMAGED fuel assemblies are placed in locations 3-1, 3-3, 3-4, 3-5, 3-6, 3-7, 3-10, 3-11, 3-12, 3-13, 3-14, and 3-16 (see Figure 2.1-1); spent UNDAMAGED fuel assemblies are placed in the remaining positions Configuration 4 DFCs with Damaged Fuel and/or with fresh FUEL DEBRIS are placed in locations 3-1, 3-7, 3-10, and 3-16 with locations 2-1, 2-5, 2-8, and 2-12 (see Figure 2.1-1) empty; spent UNDAMAGED fuel assemblies are placed in the remaining positions 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. 8 Appendix B 2-41

Approved Contents 2.0 TABLE 2.4-3 IN-CORE OPERATING REQUIREMENTS Specific Moderator Fuel Assembly Soluble Boron Power Temperature Temperature Type (ppm)

(MW/mtU) (K) (K)

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

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

1. The same core operating parameters are assumed for the 15x15I and 16x16C fuel assembly types Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-42

Approved Contents 2.0 2.5 Burn up and Cooling Time Qualification Requirements 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 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 the above table 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.

TABLE 2.5-1 BURNUP AND COOLING TIME FUEL QUALIFICATION REQUIREMENTS FOR MPC-32ML A B C D 6.7667E-14 -3.6726E-09 8.1319E-05 2.7951E+00 Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-43

Approved Contents 2.0 TABLE 2.5-2 BURNUP AND COOLING TIME FUEL QUALIFICATION REQUIREMENTS FOR MPC-37 AND MPC-89 Cell Decay Heat Load Polynomial Coefficients Limit (kW) A B C D (Note 1)

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

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

Certificate of Compliance No.1032 Amendment No. 8 Appendix B 2-44

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. Basket cell ID: 8.92 in. (min.)
2. Basket cell wall thickness: 0.57 in. (min.)
3. B4C in the Metamic-HT: 10.0 wt % (min.)

3.2.2 MPC-89

1. Basket cell ID: 5.99 in. (min.)
2. Basket cell wall thickness: 0.38 in. (min.)
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.

Certificate of Compliance No. 1032 Amendment No. 8 Appendix B 3-1

Design Features 3.0 3.2.4 MPC-32ML

1. Basket cell ID: 9.53 (min.)
2. Basket cell wall thickness: 0.57 in (min.)
3. B4C in the Metamic-HT: 10.0 wt. % (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. 8 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, specifications, reports, certificates, or Design Report, other general requirements specified by Overpressure Protection NCA are required. In lieu of a Design Report, Certification of Specification and Design Report, the Construction Report, Data HI-STORM FSAR includes the design Report, and other criteria, service conditions, and load administrative controls for combinations for the design and an ASME Code stamped operation of the MPCs as well as the vessel. 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. 8 Appendix B 3-3

Design Features 3.0 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC basket NB-1130 NB-1132.2(d) requires that The lugs that are used exclusively for supports the first connecting weld of lifting an empty MPC are welded to the and lift lugs a 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 NB of the Code.

of 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 suppliers with Certified Vessel approved 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. 8 Appendix B 3-4

Design Features 3.0 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

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 on the raw material. Where material is piece of material in a cut or processed, markings are component. 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 and NB-4243 Full penetration welds MPC lid and closure ring are not full Closure Ring required for Category C penetration welds. They are welded Welds Joints (flat head to main independently to provide a redundant shell per NB-3352.3) seal.

Certificate of Compliance No. 1032 Amendment No. 8 Appendix B 3-5

Design Features 3.0 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC Closure NB-5230 Radiographic (RT) or Root (if more than one weld pass is Ring, Vent and ultrasonic (UT) required) and final liquid penetrant Drain Cover examination required. examination to be performed in Plate Welds accordance with NB-5245. The closure ring provides independent redundant 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 is permitted. PT examination 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 Lid pressure tested. the lid to shell weld is completed, the 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. 8 Appendix B 3-6

Design Features 3.0 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

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

Enclosure have overpressure Function of MPC enclosure vessel is to Vessel protection. 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 10CFR71 and 10CFR72 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. 8 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 Notes, Explanation and Applicability Paragraph

1. Definition of primary and NF-1215 -

secondary members

2. Jurisdictional boundary NF-1133 The intervening elements are termed interfacing SSCs in this FSAR.
3. Certification of material NF-2130 Materials for ITS components shall be (b) and (c) certified to the applicable Section II of the 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 Section IX Acceptance Criteria per Subsection NF specification
7. Welding material Section II -
8. Definition of Loading NF-3111 -

conditions

9. Allowable stress values NF-3112.3 -
10. Rolling and sliding supports NF-3124 -
11. Differential thermal expansion NF-3127 -
12. Stress analysis NF-3143 Provisions for stress analysis for Class 3 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
20. Pre-heating and Interpass NF-4611 Applies to structural and non-structural Temperature NF-4612 welds NF-4613
21. Non-Destructive Examination NF-5360 InvokesSection V, Applies to Code welds only
22. NDE Personnel Certification NF-5522 Applies to Code welds only NF-5523 NF-5530 All references to the ASME Code refer to applicable sections of the 2007 edition.

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

Design Features 3.0 3.0 DESIGN FEATURES (continued) 3.4 Site-Specific Parameters and Analyses Site-specific parameters and analyses that will require verification by the system user are, as a minimum, as follows:

1. The temperature of 80o F is the maximum average yearly temperature. 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. The resultant horizontal acceleration (vectorial sum of two horizontal Zero Period Accelerations (ZPAs) at a three-dimensional seismic site), aH, 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, aH 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.

Certificate of Compliance No. 1032 Amendment No. 8 Appendix B 3-9

Design Features 3.0

b. 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 occur. 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 I is the basket cell inside dimension.
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:

V1 = (1.876 W*)1/2 / h V2 = (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. The user shall demonstrate that the ISFSI pad parameters used in the non-mechanistic tipover analysis are bounding for the site or a site specific non-mechanistic tipover analysis 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.
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 Certificate of Compliance No. 1032 Amendment No. 8 Appendix B 3-10

Design Features 3.0 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 evaluation 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.
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.

(continued)

Certificate of Compliance No. 1032 Amendment No. 8 Appendix B 3-11

Design Features 3.0 3.0 DESIGN FEATURES (continued) 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. 8 Appendix B 3-12

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