ML20161A091

Proposed TS - CoC 1040 A4 App B

ML20161A091
Person / Time
Site:	HI-STORM 100
Issue date:	10/26/2020
From:	Office of Nuclear Material Safety and Safeguards
To:	Holtec
CJJacobs NMSS/DFM/STL 415.6825
Shared Package
ML20161A087	List: ML20161A088 ML20161A089 ML20161A090 ML20161A091 ML20161A092
References
Download: ML20161A091 (56)

Text

CERTIFICATE OF COMPLIANCE NO. 1040 APPENDIX B APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STORM UMAX CANISTER STORAGE SYSTEM

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B i

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........................................................................................... 2-15 Table 2.1-1 Fuel Assembly Limits.......................................................................... 2-2 Table 2.1-2 PWR Fuel Assembly Characteristics.................................................. 2-6 Table 2.1-3 BWR Fuel Assembly Characteristics.................................................. 2-9 Table 2.1-4 Classification of Fuel Assembly for MPC-37 in the HI-STORM UMAX System...................................................................................................... 2-14 Table 2.3-1 Permissible Heat Load for long term storage.................................... 2-16 Table 2.3-2 HI-STORM UMAX MPC-37 Type 1 Permissible Heat Loads............ 2-19 Figure 2.3-1 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 1 for Long-term Storage for Short and Standard Fuel........................................ 2-21 Figure 2.3-2 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 2 for Long-Term Storage for Short and Standard Fuel....................................... 2-22 Figure 2.3-3 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Short Fuel.............................................................. 2-23 Figure 2.3-4 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Standard Fuel........................................................ 2-24 Figure 2.3-5 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 1 for Long-term Storage for Long Fuel............................................................... 2-25 Figure 2.3-6 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 2 for Long-term Storage for Long Fuel............................................................... 2-26 Figure 2.3-7 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Long Fuel............................................................... 2-27 Figure 2.3-8 HI-STORM UMAX MPC-37 Permissible Heat Load for Short and Standard Fuel for Helium Backfill Option3 in Table 3-2 of Appendix A....................................................................................... 2-28 Figure 2.3-9 HI-STORM UMAX MPC-37 Permissible Heat Load for Long Fuel for Helium Backfill Option 3 in Table 3-2 of Appendix A......................... 2-29 Figure 2.3-10 HI-STORM UMAX MPC-89 Permissible Heat Load for Long-Term Storage............................................................................................ 2-30 Figure 2.3-11 HI-STORM UMAX MPC-89 Permissible Heat Load for Helium Backfill Option 2 in Table 3-2 of Appendix A................................................ 2-31 Figure 2.3-12 HI-STORM UMAX MPC-37 Permissible Threshold Heat Load for VDS High Burnup Fuel in Table 3-1 of Appendix A and Helium Backfill Option

Certificate of Compliance No. 1040 Amendment No. 4 Appendix B ii 3 in Table 3-2 of Appendix A............................................................. 2-32 Figure 2.3-13 HI-STORM UMAX MPC-89 Permissible Threshold Heat Load for VDS High Burnup Fuel in Table 3-1 of Appendix A and Helium Backfill Option 2 in Table 3-2 of Appendix A............................................................. 2-33 Figure 2.3-14 HI-STORM UMAX MPC-37 Permissible Heat Load for 16x16A Undamaged Fuel with up to Thirty-seven DFCs............................... 2-34 Figure 2.3-15: HI-STORM UMAX MPC-37 Type 1 Heat Permissible Heat Loads...... 2-35 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........................................................... 3-10 3.5 Combustible Gas Monitoring During MPC Lid Welding and Cutting................ 3-16 3.6 Periodic Corrosion Inspections for Underground Systems.............................. 3-16 Figure 3-1 SUBGRADE AND UNDERGRADE SPACE NOMENCLATURE....3-15 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 UMAX OVERPACK and HI-TRAC VW TRANSFER CASK, PRIMARY LOAD BEARING PARTS.................................................................................. 3-8 Table 3-3 LOAD COMBINATIONS FOR THE TOP SURFACE PAD, ISFSI PAD, AND SUPPORT FOUNDATION PAD PER ACI-318 (2005)................. 3-12 Table 3-4 Values of Principal Design Parameters for the Underground ISFSI...... 3-13

Definitions 1.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 1-1 1.0 Definitions Refer to Appendix A for Definitions.

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-1 2.0 APPROVED CONTENTS 2.1 Fuel Specifications and Loading Conditions 2.1.1 Fuel to Be Stored in the HI-STORM UMAX Canister 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 UMAX Canister Storage System.

b.

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

2.1.2 Fuel Loading Figures 2.3-1 through 2.3-7 and 2.3-10 define the unique cell numbers for the MPC-37 and MPC-89 models, respectively, and the maximum allowable heat load per fuel assembly for each cell under multiple loading conditions. 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.

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-2 Table 2.1-1 (page 1 of 4)

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

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

Cooling Time 3 years Assembly Average Burnup 68.2 GWD/MTU

d. Decay Heat Per Fuel Storage Location:

As specified in Section 2.3

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)

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-3 Table 2.1-1 (page 2 of 4)

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 1, 3, 4, 8, 9, 15, 23, 29, 30, 34, 35, and 37 (see Figures 2.3-1 through 2.3-7). The remaining fuel storage locations may be filled with PWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications.

OR 37 class 16x16A UNDAMAGED FUEL ASSEMBLIES, with up to thirty-seven (37) of these stored in DAMAGED FUEL CONTAINERS, with up to twelve (12)

DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS stored in DAMAGED FUEL CONTAINERS (DFCs). DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS may be stored in fuel storage locations to 1, 3, 4, 8, 9, 15, 23, 29, 30, 34, 35, and 37 (see Figure 2.3-14). UNDAMAGED FUEL ASSEMBLIES, class 16x16A may be stored in DFCs only under loading pattern shown in Figure 2.3.14 OR For MPC-37 Type 1 only, up to 37 PWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications under loading pattern shown in Figure 2.3.15 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, or NSAs may only be loaded in fuel storage locations 5 through 7, 10 through 14, 17 through 21, 24 through 28, and 31 through 33 (see Figures 2.3-1 through 2.3-7).

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-4 Table 2.1-1 (page 3 of 4)

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 INITIAL ENRICHMENT(Note 1):

As specified in Table 2.1-3 for the 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 3 years 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

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-5 Table 2.1-1 (page 4 of 4)

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 1, 3, 4, 10, 11, 19, 29, 39, 51, 61, 71, 79, 80, 86, 87, and 89 (see Figure 2.3-10). 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.

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-6 Table 2.1-2 (page 1 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

0.400 0.417 0.440 0.420 0.417 Fuel Clad I.D. (in.)

0.3514 0.3734 0.3880 0.3736 0.3640 Fuel Pellet Dia. (in.)

(Note 3) 0.3444 0.3659 0.3805 0.3671 0.3570 Fuel Rod Pitch (in.)

0.556 0.556 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

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-7 Table 2.1-2 (page 2 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

(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 Instrument Tubes 17 17 17 17 9 (Note 4)

Guide/Instrument Tube Thickness (in.)

0.0150 0.0140 0.0140 0.0140 0.0140

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-8 Table 2.1-2 (page 3 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array and Class 16x16 A 16x16B 16x16C No. of Fuel Rod Locations 236 236 236 Fuel Clad O.D. (in.)

0.382 0.374 0.374 Fuel Clad I.D. (in.)

0.3350 0.3290 0.3290 Fuel Pellet Dia. (in.)

(Note 3) 0.3255 0.3225 0.3225 Fuel Rod Pitch (in.)

0.506 0.506 0.485 Active Fuel length (in.)

150 150 150 No. of Guide and/or Instrument Tubes 5

(Note 2) 5 (Note 2) 21 Guide/Instrument Tube Thickness (in.)

0.0350 0.04 0.0157

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-9 Table 2.1-2 (page 4 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array and Class 17x17A 17x17 B 17x17 C 17x17 D 17x17 E No. of Fuel Rod Locations 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 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.

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.

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-10 Table 2.1-3 (page 1 of 4)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

235U) (Note 14)

< 4.8

< 4.8

< 4.8

< 4.8

< 4.8 No. of Fuel Rod Locations (Full Length or Total/Full Length) 49 63 or 64 62 60 or 61 59 Fuel Clad O.D. (in.)

> 0.5630

> 0.4840

> 0.4830

> 0.4830

> 0.4930 Fuel Clad I.D. (in.)

< 0.4990

< 0.4295

< 0.4250

< 0.4230

< 0.4250 Fuel Pellet Dia. (in.)

< 0.4910

< 0.4195

< 0.4160

< 0.4140

< 0.4160 Fuel Rod Pitch (in.)

< 0.738

< 0.642

< 0.641

< 0.640

< 0.640 Design Active Fuel Length (in.)

< 150

< 150

< 150

< 150

< 150 No. of Water Rods (Note 10) 0 1 or 0 2

1 - 4 (Note 6) 5 Water Rod Thickness (in.)

N/A

> 0.034

> 0.00

> 0.00

> 0.034 Channel Thickness (in.)

< 0.120

< 0.120

< 0.120

< 0.120

< 0.100

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-11 Table 2.1-3 (2 of 4)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array and Class 8x8F 9x9 A 9x9 B 9x9 C 9x9 D Maximum Planar-Average Initial Enrichment (wt.%

235U) (Note 14)

< 4.5 (Note 12)

< 4.8

< 4.8

< 4.8

< 4.8 No. of Fuel Rod Locations 64 74/66 (Note 4) 72 80 79 Fuel Clad O.D. (in.)

> 0.4576

> 0.4400

> 0.4330

> 0.4230

> 0.4240 Fuel Clad I.D. (in.)

< 0.3996

< 0.3840

< 0.3810

< 0.3640

< 0.3640 Fuel Pellet Dia. (in.)

< 0.3913

< 0.3760

< 0.3740

< 0.3565

< 0.3565 Fuel Rod Pitch (in.)

< 0.609

< 0.566

< 0.572

< 0.572

< 0.572 Design Active Fuel Length (in.)

< 150

< 150

< 150

< 150

< 150 No. of Water Rods (Note 10)

N/A (Note 2) 2 1

(Note 5) 1 2

Water Rod Thickness (in.)

> 0.0315

> 0.00

> 0.00

> 0.020

> 0.0300 Channel Thickness (in.)

< 0.055

< 0.120

< 0.120

< 0.100

< 0.100

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-12 Table 2.1-3 (page 3 of 4)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array and Class 9x9 E (Note 2) 9x9 F (Note 2) 9x9 G 10x10 A 10x10 B Maximum Planar-Average Initial Enrichment (wt.%

235U) (Note 14)

< 4.5 (Note

12)

< 4.5 (Note

12)

< 4.8

< 4.8

< 4.8 No. of Fuel Rod Locations 76 76 72 92/78 (Note 7) 91/83 (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

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-13 Table 2.1-3 (page 4 of 4)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array and Class 10x10 C 10x10 F 10x10 G Maximum Planar-Average Initial Enrichment (wt.% 235U)

(Note 14)

< 4.8

< 4.7 (Note 13)

< 4.6 (Note 12)

No. of Fuel Rod Locations 96 92/78 (Note 7) 96/84 Fuel Clad O.D. (in.)

> 0.3780

> 0.4035

> 0.387 Fuel Clad I.D. (in.)

< 0.3294

< 0.3570

< 0.340 Fuel Pellet Dia. (in.)

< 0.3224

< 0.3500

< 0.334 Fuel Rod Pitch (in.)

< 0.488

< 0.510

< 0.512 Design Active Fuel Length (in.)

< 150

< 150

< 150 No. of Water Rods (Note 10) 5 (Note 9) 2 5

(Note 9)

Water Rod Thickness (in.)

> 0.031

> 0.030

> 0.031 Channel Thickness (in.)

< 0.055

< 0.120

< 0.060

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-14 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.

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-15 Table 2.1-4 CLASSIFICATION OF FUEL ASSEMBLY FOR MPC-37 IN THE HI-STORM UMAX ISFSI MPC Type Classification Nominal Active Fuel Length MPC-37 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".

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-16 2.3 Decay Heat Limits This section provides the limits on fuel assembly decay heat for storage in the HI-STORM UMAX Canister Storage System. The method to verify compliance, including examples, is provided in Chapter 13 of the HI-STORM UMAX FSAR.

2.3.1 Fuel Loading Decay Heat Limits Table 2.3-1 provides the maximum permissible decay heat under long-term storage for MPC-37 and MPC-89. Table 2.3-1 also lists the applicable figures providing the permissible decay heat per fuel storage location, including MPCs using the optional helium backfill pressure ranges permitted in Table 3-2 of Appendix A.

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-17 TABLE 2.3-1 PERMISSIBLE HEAT LOAD FOR LONG-TERM STORAGE MPC Type Heat Load Chart Helium Backfill Pressure Option (Notes 1,2)

Permissible Heat Load Per Storage Cell Permissible Aggregate Heat Load, kW (Note 4)

MPC-37 Short Fuel (Note 3) 1 1

Figure 2.3-1 33.88 2

2 Figure 2.3-2 33.70 3

1 Figure 2.3-3 33.53 Standard Fuel (Note 3 and

7) 1 1

Figure 2.3-1 33.88 2

2 Figure 2.3-2 33.70 3

1 Figure 2.3-4 35.30 Long Fuel (Note 3) 1 1

Figure 2.3-5 35.76 2

2 Figure 2.3-6 35.57 3

1 Figure 2.3-7 37.06 Short Fuel (Note 3) 3 Figure 2.3-8 34.28 3

Figure 2.3-12 33.46 Standard Fuel (Note 3) 3 Figure 2.3-8 34.28 3

Figure 2.3-12 33.46 Long Fuel (Note 3) 3 Figure 2.3-9 36.19 3

Figure 2.3-12 33.46 16x16A Fuel with up to 37 DFCs (Note 6) 3 Figure 2.3-14 32.3 (Note 5)

MPC-89 1

Figure 2.3-10 36.32 2

Figure 2.3-11 36.72 2

Figure 2.3-13 34.75 Notes:

1. For helium backfill pressure option pressure ranges see Appendix A, Table 3-2

2. For the details on the use of VDS to dry High Burnup Fuel see Appendix A, Table 3-1

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-18

3. See Table 2.1-4 for fuel length data

4. Aggregate heat load is defined as the sum of heat loads of all stored fuel assemblies. The permissible aggregate heat load is set to 80% of the design basis heat load.

5. This aggregate heat load has been calculated with significant margin to fuel cladding limits, and is therefore not subject to the 80% penalty.

6. As stated in Table 2.1-1 Item I.B, this can include undamaged fuel both in DFCs and not, and damaged fuel in DFCs. These heat load limits apply with one or more undamaged fuel assemblies stored in DFCs.

7. For MPC-37 Type 1, the permissible Aggregate Heat Load is given in Table 2.3-2

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-19 TABLE 2.3-2 HI-STORM UMAX MPC-37 TYPE 1 PERMISSIBLE HEAT LOADS Fuel Type (Note 1)

Helium Backfill Pressure Option (Note 2)

Heat Load per Storage Cell Permissible Aggregate Heat Load (Note 3), kW Standard Fuel 1

Figure 2.3-15 32.3 Note 1: See Table 2.1-4 for fuel length data Note 2: For helium backfill pressure option pressure ranges see Appendix A, Table 3-2 Note 3: The aggregate heat load is defined as a sum of all stored fuel assemblies.

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-20 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.

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-21 1

0.873 2

0.873 3

0.873 4

0.873 5

1.602 6

1.602 7

1.602 8

0.873 9

0.873 10 1.602 11 1.017 12 1.017 13 1.017 14 1.602 15 0.873 16 0.873 17 1.602 18 1.017 19 1.017 20 1.017 21 1.602 22 0.873 23 0.873 24 1.602 25 1.017 26 1.017 27 1.017 28 1.602 29 0.873 30 0.873 31 1.602 32 1.602 33 1.602 34 0.873 35 0.873 36 0.873 37 0.873 Figure 2.3-1 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 1 for Long-term Storage for Short and Standard Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-22 1

1.215 2

1.215 3

1.215 4

1.215 5

1.080 6

1.080 7

1.080 8

1.215 9

1.215 10 1.080 11 1.080 12 1.080 13 1.080 14 1.080 15 1.215 16 1.215 17 1.080 18 1.080 19 1.080 20 1.080 21 1.080 22 1.215 23 1.215 24 1.080 25 1.080 26 1.080 27 1.080 28 1.080 29 1.215 30 1.215 31 1.080 32 1.080 33 1.080 34 1.215 35 1.215 36 1.215 37 1.215 Figure 2.3-2 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 2 for Long-term Storage for Short and Standard Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-23 1

0.922 2

0.922 3

0.922 4

0.922 5

1.520 6

1.520 7

1.520 8

0.922 9

0.922 10 1.710 11 0.950 12 0.950 13 0.950 14 1.710 15 0.922 16 0.922 17 1.520 18 0.950 19 0.570 20 0.950 21 1.520 22 0.922 23 0.922 24 1.710 25 0.950 26 0.950 27 0.950 28 1.710 29 0.922 30 0.922 31 1.520 32 1.520 33 1.520 34 0.922 35 0.922 36 0.922 37 0.922 Figure 2.3-3 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Short Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-24 1

0.970 2

0.970 3

0.970 4

0.970 5

1.600 6

1.600 7

1.600 8

0.970 9

0.970 10 1.800 11 1.000 12 1.000 13 1.000 14 1.800 15 0.970 16 0.970 17 1.600 18 1.000 19 0.600 20 1.000 21 1.600 22 0.970 23 0.970 24 1.800 25 1.000 26 1.000 27 1.000 28 1.800 29 0.970 30 0.970 31 1.600 32 1.600 33 1.600 34 0.970 35 0.970 36 0.970 37 0.970 Figure 2.3-4 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Standard Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-25 1

0.922 2

0.922 3

0.922 4

0.922 5

1.691 6

1.691 7

1.691 8

0.922 9

0.922 10 1.691 11 1.074 12 1.074 13 1.074 14 1.691 15 0.922 16 0.922 17 1.691 18 1.074 19 1.074 20 1.074 21 1.691 22 0.922 23 0.922 24 1.691 25 1.074 26 1.074 27 1.074 28 1.691 29 0.922 30 0.922 31 1.691 32 1.691 33 1.691 34 0.922 35 0.922 36 0.922 37 0.922 Figure 2.3-5 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 1 for Long-term Storage for Long Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-26 1

1.283 2

1.283 3

1.283 4

1.283 5

1.140 6

1.140 7

1.140 8

1.283 9

1.283 10 1.140 11 1.140 12 1.140 13 1.140 14 1.140 15 1.283 16 1.283 17 1.140 18 1.140 19 1.140 20 1.140 21 1.140 22 1.283 23 1.283 24 1.140 25 1.140 26 1.140 27 1.140 28 1.140 29 1.283 30 1.283 31 1.140 32 1.140 33 1.140 34 1.283 35 1.283 36 1.283 37 1.283 Figure 2.3-6 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 2 for Long-term Storage for Long Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-27 1

1.019 2

1.019 3

1.019 4

1.019 5

1.680 6

1.680 7

1.680 8

1.019 9

1.019 10 1.890 11 1.050 12 1.050 13 1.050 14 1.890 15 1.019 16 1.019 17 1.680 18 1.050 19 0.630 20 1.050 21 1.680 22 1.019 23 1.019 24 1.890 25 1.050 26 1.050 27 1.050 28 1.890 29 1.019 30 1.019 31 1.680 32 1.680 33 1.680 34 1.019 35 1.019 36 1.019 37 1.019 Figure 2.3-7 HI-STORM UMAX MPC-37 Permissible Heat Load Chart 3 for Long-term Storage for Long Fuel Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-28 1

0.785 2

0.785 3

0.785 4

0.785 5

1.441 6

1.441 7

1.441 8

0.785 9

0.785 10 1.441 11 0.915 12 0.915 13 0.915 14 1.441 15 0.785 16 0.785 17 1.441 18 0.915 19 0.915 20 0.915 21 1.441 22 0.785 23 0.785 24 1.441 25 0.915 26 0.915 27 0.915 28 1.441 29 0.785 30 0.785 31 1.441 32 1.441 33 1.441 34 0.785 35 0.785 36 0.785 37 0.785 Figure 2.3-8 HI-STORM UMAX MPC-37 Permissible Heat Load for Short and Standard Fuel for Helium Backfill Option 3 in Table 3-2 of Appendix A Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-29 1

0.829 2

0.829 3

0.829 4

0.829 5

1.521 6

1.521 7

1.521 8

0.829 9

0.829 10 1.521 11 0.966 12 0.966 13 0.966 14 1.521 15 0.829 16 0.829 17 1.521 18 0.966 19 0.966 20 0.966 21 1.521 22 0.829 23 0.829 24 1.521 25 0.966 26 0.966 27 0.966 28 1.521 29 0.829 30 0.829 31 1.521 32 1.521 33 1.521 34 0.829 35 0.829 36 0.829 37 0.829 Figure 2.3-9 HI-STORM UMAX MPC-37 Permissible Heat Load for Long Fuel for Helium Backfill Option 3 in Table 3-2 of Appendix A Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-30 1

0.431 2

0.431 3

0.431 4

0.431 5

0.431 6

0.431 7

0.607 8

0.431 9

0.431 10 0.431 11 0.431 12 0.431 13 0.607 14 0.607 15 0.607 16 0.607 17 0.607 18 0.431 19 0.431 20 0.431 21 0.607 22 0.607 23 0.607 24 0.607 25 0.607 26 0.607 27 0.607 28 0.431 29 0.431 30 0.431 31 0.607 32 0.607 33 0.431 34 0.431 35 0.431 36 0.607 37 0.607 38 0.431 39 0.431 40 0.431 41 0.607 42 0.607 43 0.607 44 0.431 45 0.431 46 0.431 47 0.607 48 0.607 49 0.607 50 0.431 51 0.431 52 0.431 53 0.607 54 0.607 55 0.431 56 0.431 57 0.431 58 0.607 59 0.607 60 0.431 61 0.431 62 0.431 63 0.607 64 0.607 65 0.607 66 0.607 67 0.607 68 0.607 69 0.607 70 0.431 71 0.431 72 0.431 73 0.607 74 0.607 75 0.607 76 0.607 77 0.607 78 0.431 79 0.431 80 0.431 81 0.431 82 0.431 83 0.607 84 0.431 85 0.431 86 0.431 87 0.431 88 0.431 89 0.431 Figure 2.3-10 HI-STORM UMAX MPC-89 Permissible Heat Load for Long-Term Storage Note that this figure shows the per cell heat load limit for storage.

The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-31 1

0.387 2

0.387 3

0.387 4

0.387 5

0.387 6

0.387 7

0.546 8

0.387 9

0.387 10 0.387 11 0.387 12 0.387 13 0.546 14 0.546 15 0.546 16 0.546 17 0.546 18 0.387 19 0.387 20 0.387 21 0.546 22 0.546 23 0.546 24 0.546 25 0.546 26 0.546 27 0.546 28 0.387 29 0.387 30 0.387 31 0.546 32 0.546 33 0.387 34 0.387 35 0.387 36 0.546 37 0.546 38 0.387 39 0.387 40 0.387 41 0.546 42 0.546 43 0.546 44 0.387 45 0.387 46 0.387 47 0.546 48 0.546 49 0.546 50 0.387 51 0.387 52 0.387 53 0.546 54 0.546 55 0.387 56 0.387 57 0.387 58 0.546 59 0.546 60 0.387 61 0.387 62 0.387 63 0.546 64 0.546 65 0.546 66 0.546 67 0.546 68 0.546 69 0.546 70 0.387 71 0.387 72 0.387 73 0.546 74 0.546 75 0.546 76 0.546 77 0.546 78 0.387 79 0.387 80 0.387 81 0.387 82 0.387 83 0.546 84 0.387 85 0.387 86 0.387 87 0.387 88 0.387 89 0.387 Figure 2.3-11 HI-STORM UMAX MPC-89 Permissible Heat Load for Helium Backfill Option 2 in Table 3-2 of Appendix A Note that this figure shows the per cell heat load limit for storage.

The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-32 1

0.97 2

0.97 3

0.97 4

0.97 5

0.97 6

0.97 7

0.97 8

0.97 9

0.97 10 0.97 11 0.7 12 0.7 13 0.7 14 0.97 15 0.97 16 0.97 17 0.97 18 0.7 19 0.7 20 0.7 21 0.97 22 0.97 23 0.97 24 0.97 25 0.7 26 0.7 27 0.7 28 0.97 29 0.97 30 0.97 31 0.97 32 0.97 33 0.97 34 0.97 35 0.97 36 0.97 37 0.97 Figure 2.3-12 HI-STORM UMAX MPC-37 Permissible Threshold Heat Load for VDS High Burnup Fuel in Table 3-1 of Appendix A and Helium Backfill Option 3 in Table 3-2 of Appendix A Note that this figure shows the per cell heat load limit for storage. The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-33 1

0.44 2

0.44 3

0.44 4

0.44 5

0.44 6

0.44 7

0.35 8

0.44 9

0.44 10 0.44 11 0.44 12 0.44 13 0.35 14 0.35 15 0.35 16 0.35 17 0.35 18 0.44 19 0.44 20 0.44 21 0.35 22 0.35 23 0.35 24 0.35 25 0.35 26 0.35 27 0.35 28 0.44 29 0.44 30 0.44 31 0.35 32 0.35 33 0.35 34 0.35 35 0.35 36 0.35 37 0.35 38 0.44 39 0.44 40 0.44 41 0.35 42 0.35 43 0.35 44 0.35 45 0.35 46 0.35 47 0.35 48 0.35 49 0.35 50 0.44 51 0.44 52 0.44 53 0.35 54 0.35 55 0.35 56 0.35 57 0.35 58 0.35 59 0.35 60 0.44 61 0.44 62 0.44 63 0.35 64 0.35 65 0.35 66 0.35 67 0.35 68 0.35 69 0.35 70 0.44 71 0.44 72 0.44 73 0.35 74 0.35 75 0.35 76 0.35 77 0.35 78 0.44 79 0.44 80 0.44 81 0.44 82 0.44 83 0.35 84 0.44 85 0.44 86 0.44 87 0.44 88 0.44 89 0.44 Figure 2.3-13 HI-STORM UMAX MPC-89 Permissible Threshold Heat Load for VDS High Burnup Fuel in Table 3-1 of Appendix A and Helium Backfill Option 2 in Table 3-2 of Appendix A Note that this figure shows the per cell heat load limit for storage.

The total permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-1 for corresponding permissible aggregate heat load.

Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-34 1

0.80 2

0.80 3

0.80 4

1.00 5

1.00 6

1.40 7

1.00 8

1.00 9

0.80 10 1.00 11 0.60 12 0.60 13 0.60 14 1.00 15 0.80 16 0.80 17 1.40 18 0.60 19 0.30 20 0.60 21 1.40 22 0.80 23 0.80 24 1.00 25 0.60 26 0.60 27 0.60 28 1.00 29 0.80 30 1.00 31 1.00 32 1.40 33 1.00 34 1.00 35 0.80 36 0.80 37 0.80 Figure 2.3-14 HI-STORM UMAX MPC-37 Permissible Heat Load for 16x16A Undamaged Fuel with up to Thirty-seven DFCs Legend Cell ID Heat Load, kW

Approved Contents 2.0 Certificate of Compliance No.1040 Amendment No. 4 Appendix B 2-35 0.725 0.865 0.725 0.66 1.075 1.24 1.075 0.66 0.725 1.075 0.775 0.865 0.775 1.075 0.725 0.865 1.24 0.865 0.285 0.865 1.24 0.865 0.725 1.075 0.775 0.865 0.775 1.075 0.725 0.66 1.075 1.24 1.075 0.66 0.725 0.865 0.725 Figure 2.3-15: HI-STORM UMAX MPC-37 Type 1 Heat Permissible Heat Loads (All storage cell heat loads are in kW)

Note that this figure shows the per cell heat load limit for storage. The permissible aggregate heat load may be less than the sum of each individual cell heat load. See Table 2.3-2 for corresponding permissible aggregate heat load and the helium backfill option.

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-1 3.0 DESIGN FEATURES 3.1 Site 3.1.1 Site Location The HI-STORM UMAX Canister Storage 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. nominal)

2.

Basket cell wall thickness: 0.57 in. (min.nominal )

3.

B4C in the Metamic-HT: 10.0 wt % (min. nominal) 3.2.2 MPC-89

1.

Basket cell ID: 5.99 in. (min.nominal)

2.

Basket cell wall thickness: 0.38 in. (min.nominal)

3.

B4C in the Metamic-HT: 10.0 wt % (min. nominal) 3.2.3 Metamic-HT Test Requirements

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 panel fails to meet the specified 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 to show that the minimum areal density in the panels (that comprise the lot) is satisfied with 95% confidence.

4.

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

3.3 Codes and Standards The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2007, is the governing Code for the HI-STORM UMAX system MPC as clarified in

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-2 Specification 3.3.1 below, except for Code Sections V and IX. However, the HI-STORM UMAX VVM is structurally qualified per the newer 2010 ASME code. The ASME Code paragraphs applicable to the manufacturing of HI-STORM UMAX VVM 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 applicable edition (including addenda) specified above, is performed by the certificate holder. American Concrete Institute ACI-318 (2005) is the governing Code for both plain concrete and reinforced concrete as clarified in Chapter 3 of the Final Safety Analysis Report for the HI-STORM 100 UMAX 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 UMAX Canister Storage 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)

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-3 3.0 DESIGN FEATURES (continued)

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

MPC Enclosure Vessel Subsection NCA General Requirements.

Requires preparation of a Design Specification, Design Report, Overpressure Protection Report, Certification of Construction Report, Data Report, and other administrative controls for an ASME Code stamped vessel.

Because the MPC is not an ASME Code stamped vessel, none of the specifications, reports, certificates, or other general requirements specified by NCA are required. In lieu of a Design Specification and Design Report, the HI-STORM FSAR includes the design criteria, service conditions, and load combinations for the design and 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 Enclosure Vessel NB-1100 Statement of requirements for Code stamping of components.

MPC Enclosure Vessel is designed and will be fabricated in accordance with ASME Code,Section III, Subsection NB to the maximum practical extent, but Code stamping is not required.

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-4 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC basket supports and lift lugs NB-1130 NB-1132.2(d) requires that the first connecting weld of a non-pressure retaining structural attachment to a component shall be considered part of the component unless the weld is more than 2t from the pressure retaining portion 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.

The lugs that are used exclusively for lifting an empty MPC are welded to the inside of the pressure-retaining MPC shell, but are not designed in accordance with Subsection NB. The lug-to-Enclosure Vessel Weld is required to meet the stress limits of Reg. Guide 3.61 in lieu of Subsection NB of the Code.

MPC Enclosure Vessel NB-2000 Requires materials to be supplied by ASME-approved material supplier.

Materials will be supplied by Holtec approved suppliers with Certified Material Test Reports (CMTRs) in accordance with NB-2000 requirements.

MPC Enclosure Vessel NB-3100 NF-3100 Provides requirements for determining design loading conditions, such as pressure, temperature, and mechanical loads.

These requirements are subsumed by the HI-STORM FW FSAR, serving as the Design Specification, which establishes the service conditions and load combinations for the storage system.

MPC Enclosure Vessel NB-4120 NB-4121.2 and NF-4121.2 provide requirements for repetition of tensile or impact tests for material subjected to heat treatment during fabrication or installation.

In-shop operations of short duration that apply heat to a component, such as plasma cutting of plate stock, welding, machining, and coating are not, unless explicitly stated by the Code, defined as heat treatment operations.

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-5 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC Enclosure Vessel NB-4220 Requires certain forming tolerances to be met for cylindrical, conical, or spherical shells of a vessel.

The cylindricity measurements on the rolled shells are not specifically recorded in the shop travelers, as would 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 Enclosure Vessel NB-4122 Implies that with the exception of studs, bolts, nuts and heat exchanger tubes, CMTRs must be traceable to a specific piece of material in a component.

MPCs are built in lots. Material traceability on raw materials to a heat number and corresponding CMTR is maintained by Holtec through markings on the raw material. Where material is 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 and Closure Ring Welds NB-4243 Full penetration welds required for Category C Joints (flat head to main shell per NB-3352.3)

MPC lid and closure ring are not full penetration welds. They are welded independently to provide a redundant seal.

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-6 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC Closure Ring, Vent and Drain Cover Plate Welds NB-5230 Radiographic (RT) or ultrasonic (UT) examination required.

Root (if more than one weld pass is required) and final liquid penetrant examination to be performed in 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 Shell Weld NB-5230 Radiographic (RT) or ultrasonic (UT) examination required.

Only progressive liquid penetrant (PT) examination is permitted. PT examination will include the root and final weld layers and each approx. 3/8" of weld depth.

MPC Enclosure Vessel and Lid NB-6111 All completed pressure retaining systems shall be pressure tested.

The MPC vessel is welded in the field following fuel assembly loading. After the lid to shell weld is completed, the MPC shall then be pressure tested as defined in Chapter 10. Accessibility for leakage inspections precludes a Code compliant pressure test. Since the shell welds of the MPC cannot be checked for leakage during this pressure test, the shop leakage test to 10-7 ref cc/sec provides reasonable assurance as to its leak tightness. 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.

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-7 TABLE 3-1 List of ASME Code Alternatives for Multi-Purpose Canisters (MPCs)

MPC Enclosure Vessel NB-7000 Vessels are required to have overpressure protection.

No overpressure protection is provided.

Function of MPC enclosure vessel is to 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 Enclosure Vessel NB-8000 States requirements for nameplates, stamping and reports per NCA-8000.

The HI-STORM UMAX system is to be marked and identified in accordance with 10CFR71 and 10CFR72 requirements. Code stamping is not required. QA data package to be in accordance with Holtec approved QA program.

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-8 Table 3-2 REFERENCE ASME CODE PARAGRAPHS FOR VVM PRIMARY LOAD BEARING PARTS Item Code Paragraph

[2.6.1]

Explanation and Applicability

1.

Definition of primary and secondary members NF-1215

2.

Jurisdictional boundary NF-1133 The VVMs jurisdictional boundary is defined by the bottom surface of the SFP, the top surface of the ISFSI pad and the SES side surfaces.

3.

Certification of material(structural)

NF-2130(b) and (c)

Materials shall be 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-2400

6.

Welding procedure Section IX

7.

Welding material Section II

8.

Loading conditions NF-3111

9.

Allowable stress values NF-3112.3

10.

Rolling and sliding supports NF-3424

11.

Differential thermal expansion NF-3127

12.

Stress analysis NF-3143 NF-3380 NF-3522 NF-3523 Provisions for stress analysis for Class 3 plate and shell supports and for linear supports are applicable for Closure Lid and Container Shell, respectively.

13.

Cutting of plate stock NF-4211 NF-4211.1

14.

Forming NF-4212

15.

Forming tolerance NF-4221 Applies to the Container Shell

16.

Fitting and Aligning Tack Welds NF-4231 NF-4231.1

17.

Alignment NF-4232

18.

Storage of Welding Materials NF-4411

19.

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

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-9 Table 3-2 REFERENCE ASME CODE PARAGRAPHS FOR VVM PRIMARY LOAD BEARING PARTS Item Code Paragraph

[2.6.1]

Explanation and Applicability

20.

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

21.

Pre-heating and Interpass Temperature NF-4611 NF-4612 NF-4613 Applies to structural and non-structural welds

22.

Non-Destructive Examination NF-5360 InvokesSection V

23.

NDE Personnel Certification NF-5522 NF-5523 NF-5530

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-10 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.

2.

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

3.

The resultant zero period acceleration at the top of the grade and at the elevation of the Support Foundation Pad (SFP) at the host site (computed by the Newmarks rule as the sum of A+0.4*B+0.4*C, where A, B, C denote the free field ZPAs in the three orthogonal directions in decreasing magnitude, i.e., A B C) shall be less than or equal to 1.3 and 1.214, respectively.

For HI-STORM UMAX Version MSE, the corresponding Newmark sum of the ZPAs at the top of the Support Foundation Pad is limited to 2.121 Gs and the vertical ZPA is limited to 1.0G.

4.

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

5.

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

6.

The moment and shear capacities of the ISFSI Structures shall meet the structural requirements under the load combinations in Table 3-3.

7.

Radiation Protection Space (RPS) as defined in Subsection 5.3.9 of Appendix A, is intended to ensure that the subgrade material in and around the lateral space occupied by the VVMs remains essentially intact under all service conditions including during an excavation activity adjacent to the RPS.

8.

The SFP for a VVM array established in any one construction campaign shall be of monolithic construction, to the extent practicable, to maximize the physical stability of the underground installation.

9.

Excavation activities contiguous to a loaded UMAX ISFSI on the side facing the excavation can occur down to the depth of the bottom surface of the SFP of the loaded ISFSI (i.e. within the area labeled Space B in Figure 3-

1) considering that there may be minor variations in the depth due to normal construction practices. For excavation activities which are contiguous to the loaded ISFSI (within a distance W, see Figure 3-1) and below the depth of the bottom surface of the SFP (i.e. within the area labeled Space D in Figure 3-1), asite-specific seismic analysis will be performed to demonstrate the stability of the RPS boundary and structural integrity of the ISFSI structure. This analysis shall be submitted to Holtec International to be incorporated in an amendment request for NRC review and approval

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-11 prior to any excavation taking place.

10.

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.

11.

LOADING OPERATIONS, TRANSPORT OPERATIONS, and UNLOADING OPERATIONS shall only be conducted with working area Ambient Temperature 0o F.

12.

For those users whose site-specific design basis includes an event or events (e.g., flood) that result in the blockage of any VVM 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.

13.

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.

14.

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

15.

The loaded transfer cask and its conveyance shall be evaluated to ensure, under the site specific Design Basis Earthquake, that the cask and its conveyance does not tipover or slide off the haul route.

(continued)

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-12 DESIGN FEATURES (continued)

Table 3-3 LOAD COMBINATIONS FOR THE TOP SURFACE PAD, ISFSI PAD, AND SUPPORT FOUNDATION PAD PER ACI-318 (2005)

Load Combination Case Load Combination LC-1 1.4D LC-2 1.2D + 1.6L LC-3 1.2D + E + L where:

D:

Dead Load including long-term differential settlement effects.

L:

Live Load E:

DBE for the Site

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-13 DESIGN FEATURES (continued)

Table 3-4 Values of Principal Design Parameters for the Underground ISFSI Thickness of the Support Foundation Pad, inch (nominal) 33 Thickness of the ISFSI Pad and curb, inch (nominal) 34 Thickness of the ISFSI Pad, inch (nominal) 30 Rebar Size* and Layout* (nominal)

1. 11 @ 9" each face, each direction Rebar Concrete Cover (top and bottom)*, inch per 7.7.1 of ACI-318 (2005)

Compressive Strength of Concrete at 28 days*, psi 4500 Compressive Strength of Self-hardening Engineered Subgrade (SES), psi For Version MSE only, the Compressive Strength of plain concrete, psi 1,000 3000 Lower Bound Shear Wave Velocity in the Subgrade lateral to the VVM (Figure 3-1 Space A), fps**

1,300 Depth Averaged Density of subgrade in Space A. (Figure 3-1)1 (lb/ft3) 120 Depth Averaged Density of subgrade in Space B. (Figure 3-1)1 (lb/ft3) 110 Depth Averaged Density of subgrade in Space C. (Figure 3-1)2 (lb/ft3) 120 Depth Averaged Density of subgrade in Space D. (Figure 3-1)3 (lb/ft3) 120 Lower Bound Shear Wave Velocity in the Subgrade below the Support Foundation Pad (Figure 3-1 Space C & D), fps**

485

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-14 Lower Bound Shear Wave Velocity in the Subgrade laterally surrounding the ISFSI (Figure 3-1 Space B), fps**

For Version MSE only, Nominal Strain compatible Shear wave Velocity in Space B, fps 450 344

• Applies to Support Foundation Pad and ISFSI Pad.

• • Strain compatible effective shear wave velocities shall be computed using the guidance provided in Section 16 of the International Building Code, 2009 Edition.

Users must account for potential variability in the subgrade shear wave velocity in accordance with Section 3.7.2 of NUREG-0800.

Notes:

1. A lower average density value may be used in shielding analysis per FSAR Chapter 5 for conservatism.

2. Not required for shielding, not credited in Version MSE model.

3. This space will typically contain native soil. Not required for shielding, not credited in Version MSE model.

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-15 Figure 3 SUBGRADE AND UNDERGRADE SPACE NOMENCLATURE Note: W is a representative dimension of the ISFSI determined by site-specific layouts

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-16 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.

3.6 Periodic Corrosion Inspections for Underground Systems HI-STORM UMAX VVM ISFSIs not employing an impressed current cathodic protection system shall be subject to visual and UT inspection of at least one representative VVM to check for significant corrosion of the CEC Container Shell and Bottom Plate at an interval not to exceed 20 years. The VVM chosen for inspection is not required to be in use or to have previously contained a loaded MPC. The VVM considered to be most vulnerable to corrosion degradation shall be selected for inspection. If significant corrosion is identified, either an evaluation to demonstrate sufficient continued structural integrity (sufficient for at least the remainder of the licensing period) shall be performed or the affected VVM shall be promptly scheduled for repair or decommissioning. Through wall corrosion shall not be permitted without promptly scheduling for repair or decommissioning.

Promptness of repair or decommissioning shall be commensurate with the extent of degradation of the VVM but shall not exceed 3 years from the date of inspection.

If the representative VVM is determined to require repair or decommissioning, the next most vulnerable VVM shall be selected for inspection. This inspection process shall conclude when a VVM is found that does not require repair or decommissioning. Since the last VVM inspected is considered more prone to corrosion than the remaining un-inspected VVMs, the last VVM inspected becomes the representative VVM for the remaining VVMs.

Inspections Visual Inspection: Visual inspection of the inner surfaces of the CEC Container Shell and Bottom Plate for indications of significant or through wall corrosion (i.e.,

holes).

UT Inspection: The UT inspection or an equivalent method shall be used to measure CEC shell wall thickness to determine the extent of metal loss from corrosion. A minimum of 16 data points shall be obtained, 4 near the top, 4 near the mid-height and 4 near the bottom of the CEC Container Shell all approximately 0, 90, 180, and 270 degrees apart; and 4 on the CEC Bottom Plate near the CEC Container Shell approximately 0, 90, 180, and 270 degrees apart. Locations where visual inspection has identified potentially significant corrosion shall also receive UT inspection. Locations suspected of significant corrosion may receive further UT inspection to determine the extent of corrosion.

Design Features 3.0 Certificate of Compliance No. 1040 Amendment No. 4 Appendix B 3-17 Inspection Criteria General wall thinning exceeding 1/8 in depth and local pitting exceeding 1/4" in depth are conditions of significant corrosion.