Text

3 Proposed TS, Appendix B, Certificate of Compliance No. 1014, Renewed Amendment 18
	ML24095A043
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Site:	Holtec
Issue date:	08/22/2024
From:	; Storage and Transportation Licensing Branch
To:	; Holtec
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ML24095A039	List: ML24095A040; ML24095A041; ML24095A042; ML24095A043; ML24095A044; ML24095A045; ML24095A046; ML24095A047; ML24095A048;
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PROPOSED RENEWED CERTIFICATE OF COMPLIANCE NO. 1014

APPENDIX B

APPROVED CONTENTS AND DESIGN FEATURES

FOR THE HI-STORM 100 CASK SYSTEM

AMENDMENT NO. 18

TABLE OF CONTENTS

1.0 DEFINITIONS..................................................................................................................... 1-1

2.0 APPROVED CONTENTS................................................................................................... 2-1 2.1 Fuel Specification and Loading Conditions.................................................................... 2-1 2.2 Violations........................................................................................................................ 2-2 2.3 Not Used......................................................................................................................... 2-2 2.4 Decay Heat, Burnup & Cooling Time Limits for ZR Clad Fuel...................................... 2-50

Figure 2.1-1 Fuel Loading Regions - MPC-24................................................................... 2-3 Figure 2.1-2 Fuel Loading Regions - MPC-24E/24EF....................................................... 2-4 Figure 2.1-3 Fuel Loading Regions - MPC-32/32F............................................................ 2-5 Figure 2.1-4 Fuel Loading Regions - MPC-68/68FF/68M.................................................. 2-6 Figure 2.4-1 QSHL-2 Pattern, Per Cell Allowable Heat Loads (kW) - MPC-68M..2-60 Figure 2.4-2 QSHL-2 Pattern, Per Cell Allowable Heat Loads (kW) - MPC-68M..2-61 Figure 2.4-3 QSHL-3 Pattern, Per Cell Allowable Heat Loads (kW) - MPC-68M..2-62 Figure 2.4-4 QSHL-4 Pattern, Per Cell Allowable Heat Loads (kW) - MPC-68M..2-63

Table 2.1-1 Fuel Assembly Limits..................................................................................... 2-7 Table 2.1-2 PWR Fuel Assembly Characteristics........................................................... 2-37 Table 2.1-3 BWR Fuel Assembly Characteristics........................................................... 2-42 Table 2.1-4 Table Deleted Table 2.1-5 Table Deleted Table 2.1-6 Table Deleted Table 2.1-7 Table Deleted Table 2.1-8 Non-Fuel Hardware Cooling and Average Burnup....................................... 2-48 Table 2.1-9 Restrictions for Partial Gadolinium Credit in MPC-68M............................... 2-49 Table 2.4-1 Maximum Allowable Decay Heat per Fuel Storage Location....................... 2-50 Table 2.4-2 Fuel Storage Locations per MPC................................................................. 2-52 Table 2.4-3 PWR Fuel Assembly Burnup and Cooling Time Limits for VENTILATED OVERPACK.......................................................................... 2-55 Table 2.4-4 BWR Fuel Assembly Burnup and Cooling Time Limits for VENTILATED OVERPACK.......................................................................... 2-56 Table 2.4-5 Heat Load for Damaged Fuel Assemblies and Fuel Debris under Regionalized Loading..................................................................................2-52 Table 2.4-6a MPC-68M Heat Load Data for UNVENTILATED OVERPACK.................... 2-56 Table 2.4-6b MPC-68M Requirements on Developing Regionalized Heat Load Patterns for UNVENTILATED OVERPACK.....................................................................2-57 Table 2.4-7 Section Heat Load Calculations for MPC-68M for UNVENTILATED OVERPACK................................................................................................. 2-58 Table 2.4-8 DFC and DFI Storage Locations with Heat Load penalties for MPC-68M for UNVENTILATED OVERPACK..................................................................... 2-58 Table 2.4-9 Burnup and Cooling Time Fuel Qualification Requirements for MPC-68M for UNVENTILATED OVERPACK............................................................... 2-59

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B i 3.4 Site Specific Parameters and Analyses....................................................................... 3-13 3.5 Cask Transfer Facility (CTF)........................................................................................ 3-17 3.6 Forced Helium Dehydration System............................................................................ 3-20 3.7 Supplemental Cooling System..................................................................................... 3-22 3.8 Combustible Gas Monitoring During MPC Lid Welding and Cutting............................ 3-25 3.9 Environmental Temperature Requirements................................................................. 3-25

Table 3-1 List of ASME Code Alternatives for HI-STORM 100 Cask System.................... 3-4 Table 3-2 Load Combinations and Service Condition Definitions for the CTF Structure................................................................................................... 3-19 Table 3-3 Requirements for Supplemental Cooling System............................................. 3-24

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B ii Definitions 1.0

1.0 Definitions

Refer to Appendix A for Definitions.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 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 100 SFSC System

a. INTACT FUEL ASSEMBLIES, 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 100 SFSC System.

b. For MPCs partially loaded with stainless steel clad fuel assemblies, all remaining fuel assemblies in the MPC shall meet the decay heat generation limit for the stainless steel clad fuel assemblies.

c. For MPCs partially loaded with array/class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A fuel assemblies, all remaining ZR clad INTACT FUEL ASSEMBLIES in the MPC shall meet the decay heat generation limits for the 6x6A, 6x6B, 6x6C, 7x7A and 8x8A fuel assemblies.

d. All BWR fuel assemblies may be stored with or without ZR channels with the exception of array/class 10x10D and 10x10E fuel assemblies, which may be stored with or without ZR or stainless steel channels.

2.1.2 Uniform Fuel Loading Any authorized fuel assembly may be stored in any fuel storage location, subject to other restrictions related to DAMAGED FUEL, FUEL DEBRIS, and NON-FUEL HARDWARE specified in the CoC.

(continued)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-1 Approved Contents 2.0 2.0 Approved Contents 2.1 Fuel Specifications and Loading Conditions (contd) 2.1.3 Regionalized Fuel Loading Users may choose to store fuel using regionalized loading in lieu of uniform loading to allow higher heat emitting fuel assemblies to be stored than would otherwise be able to be stored using uniform loading. Figures 2.1-1 through 2.1-4 define the regions for the MPC-24, MPC-24E, MPC-24EF, MPC-32, MPC-32F, MPC-68, MPC-68FF, and MPC-68M models, respectively1. Fuel assemblydecay heat limits for regionalized loading are specified in Section 2.4.2 for VENTILATED OVERPACK, and Section 2.4.5 for UNVENTILATED OVERPACK. Fuel assemblies used in regionalized loading shall meet all other applicable limits specified in Tables 2.1-1 through 2.1-3.

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

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

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

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

2.3 Not Used

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

The design drawings should be consulted for basket design details.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-2 Approved Contents 2.0

Figure 2.1-1 Fuel Loading Regions - MPC-24

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-3 Approved Contents 2.0

Figure 2.1-2 Fuel Loading Regions - MPC-24E/24EF

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-4 Approved Contents 2.0

Figure 2.1-3 Fuel Loading Regions - MPC-32/32F

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-5 Approved Contents 2.0

Figure 2.1-4 Fuel Loading Regions - MPC-68/68FF/68M

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-6 Approved Contents 2.0 Table 2.1-1 (page 1 of 30)

Fuel Assembly Limits

I. MPC MODEL: MPC-24 A. Allowable Contents

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

a. Cladding Type: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel

assembly array/class.

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

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

i. Array/Classes Cooling time 8 years and an average 14x14D,14x14E, and burnup 40,000 MWD/MTU.

15x15G

ii. All Other Array/Classes Cooling time and average burnup as specified in Section 2.4.

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-7 Approved Contents 2.0 Table 2.1-1 (page 2 of 30)

Fuel Assembly Limits

I. MPC MODEL: MPC-24 (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 710 Watts 14x14E, and 15x15G

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

e. Fuel Assembly Length: 176.8 inches (nominal design)

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

g. Fuel Assembly Weight: 1720 lbs (including NON-FUEL HARDWARE) for assemblies that do not

require fuel spacers, otherwise 1680 lbs (including NON-FUEL HARDWARE)

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

C. Deleted.

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

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

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-8 Approved Contents 2.0 Table 2.1-1 (page 3 of 30)

Fuel Assembly Limits

II. MPC MODEL: MPC-68F A. Allowable Contents

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

a. Cladding Type: ZR

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

c. Initial Maximum Rod Enrichment: As specified in Table 2.1-3 for the applicable fuel assembly array/class.

d. Post-irradiation Cooling Time and Cooling time 18 years and an average Average Burnup Per Assembly: burnup 30,000 MWD/MTU.

e. Decay Heat Per Assembly 115 Watts

f. Fuel Assembly Length: 135.0 inches (nominal design)

g. Fuel Assembly Width: 4.70 inches (nominal design)

h. Fuel Assembly Weight: 400 lbs, including channels

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-9 Approved Contents 2.0 Table 2.1-1 (page 4 of 30)

Fuel Assembly Limits

II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

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

a. Cladding Type: ZR

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

c. Initial Maximum Rod Enrichment: As specified in Table 2.1-3 for the applicable fuel assembly array/class.

d. Post-irradiation Cooling Time and Cooling time 18 years and an average Average Burnup Per Assembly: burnup 30,000 MWD/MTU.

e. Decay Heat Per Assembly: 115 Watts

f. Fuel Assembly Length: 135.0 inches (nominal design)

g. Fuel Assembly Width: 4.70 inches (nominal design)

h. Fuel Assembly Weight: 550 lbs, including channels and DFC

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-10 Approved Contents 2.0 Table 2.1-1 (page 5 of 30)

Fuel Assembly Limits

II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

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

a. Cladding Type: ZR

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

c. Initial Maximum Rod Enrichment: As specified in Table 2.1-3 for the applicable original fuel assembly array/class.

d. Post-irradiation Cooling Time and Cooling time 18 years and an average Average Burnup Per Assembly burnup 30,000 MWD/MTU for the original fuel assembly.

e. Decay Heat Per Assembly 115 Watts

f. Original Fuel Assembly Length 135.0 inches (nominal design)

g. Original Fuel Assembly Width 4.70 inches (nominal design)

h. Fuel Debris Weight 550 lbs, including channels and DFC

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-11 Approved Contents 2.0 Table 2.1-1 (page 6 of 30)

Fuel Assembly Limits

II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

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

a. Cladding Type: ZR

b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for fuel INITIAL ENRICHMENT: assembly array/class 6x6B.

c. Initial Maximum Rod Enrichment: As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

d. Post-irradiation Cooling Time and Cooling time 18 years and an average Average Burnup Per Assembly: burnup 30,000 MWD/MTIHM.

e. Decay Heat Per Assembly 115 Watts

f. Fuel Assembly Length: 135.0 inches (nominal design)

g. Fuel Assembly Width: 4.70 inches (nominal design)

h. Fuel Assembly Weight: 400 lbs, including channels

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-12 Approved Contents 2.0 Table 2.1-1 (page 7 of 30)

Fuel Assembly Limits

II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

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

a. Cladding Type: ZR

b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for fuel INITIAL ENRICHMENT: assembly array/class 6x6B.

c. Initial Maximum Rod Enrichment: As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

d. Post-irradiation Cooling Time and Cooling time 18 years and an average Average Burnup Per Assembly: burnup 30,000 MWD/MTIHM.

e. Decay Heat Per Assembly 115 Watts

f. Fuel Assembly Length: 135.0 inches (nominal design)

g. Fuel Assembly Width: 4.70 inches (nominal design)

h. Fuel Assembly Weight: 550 lbs, including channels and DFC

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-13 Approved Contents 2.0 Table 2.1-1 (page 8 of 30)

Fuel Assembly Limits

II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

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

a. Cladding Type: ZR

b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for original INITIAL ENRICHMENT: fuel assembly array/class 6x6B.

c. Initial Maximum Rod Enrichment: As specified in Table 2.1-3 for original fuel assembly array/class 6x6B.

d. Post-irradiation Cooling Time and Cooling time 18 years and an average Average Burnup Per Assembly: burnup 30,000 MWD/MTIHM for the original fuel assembly.

e. Decay Heat Per Assembly 115 Watts

f. Original Fuel Assembly Length: 135.0 inches (nominal design)

g. Original Fuel Assembly Width: 4.70 inches (nominal design)

h. Fuel Debris Weight: 550 lbs, including channels and DFC

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-14 Approved Contents 2.0 Table 2.1-1 (page 9 of 30)

Fuel Assembly Limits

II. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

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

a. Cladding Type: ZR

b. Composition: 98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U.

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

c. Number of Rods Per Thoria Rod 18 Canister:

d. Decay Heat Per Thoria Rod 115 Watts Canister:

e. Post-irradiation Fuel Cooling Time A fuel post-irradiation cooling time 18 and Average Burnup Per Thoria years and an average burnup 16,000 Rod Canister: MWD/MTIHM.

f. Initial Heavy Metal Weight: 27 kg/canister

g. Fuel Cladding O.D.: 0.412 inches

h. Fuel Cladding I.D.: 0.362 inches

i. Fuel Pellet O.D.: 0.358 inches

j. Active Fuel Length: 111 inches

k. Canister Weight: 550 lbs, including fuel

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-15 Approved Contents 2.0 Table 2.1-1 (page 10 of 30)

Fuel Assembly Limits

II. MPC MODEL: MPC-68F (continued)

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

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

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

1. Uranium oxide BWR INTACT FUEL ASSEMBLIES;

2. MOX BWR INTACT FUEL ASSEMBLIES;

3. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES placed in DFCs;

4. MOX BWR DAMAGED FUEL ASSEMBLIES placed in DFCs; or

5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.

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

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-16 Approved Contents 2.0 Table 2.1-1 (page 11 of 30)

Fuel Assembly Limits

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

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

a. Cladding Type: ZR or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel

assembly array/class

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

c. Initial Maximum Rod Enrichment As specified in Table 2.1-3 for the applicable fuel assembly array/class.

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

i. Array/Classes 6x6A, 6x6B, Cooling time 18 years and an average 6x6C, 7x7A, and 8x8A burnup 30,000 MWD/MTU (or MWD/MTIHM).

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

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

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-17 Approved Contents 2.0 Table 2.1-1 (page 12 of 30)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

e. Decay Heat Per Assembly

i. Array/Classes 6x6A, 6X6B, 115 Watts 6x6C, 7x7A, and 8x8A

ii. Array/Class 8x8F 183.5 Watts

iii. Array/Classes 10x10D 95 Watts and 10x10E

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

f. Fuel Assembly Length

i. Array/Class 6x6A, 6x6B, 135.0 inches (nominal design) 6x6C, 7x7A, or 8x8A

ii. All Other Array/Classes 176.5 inches (nominal design)

g. Fuel Assembly Width

i. Array/Class 6x6A, 6x6B, 4.70 inches (nominal design) 6x6C, 7x7A, or 8x8A ii. All Other Array/Classes 5.85 inches (nominal design)

h. Fuel Assembly Weight

i. Array/Class 6x6A, 6x6B, 400 lbs, including channels 6x6C, 7x7A, or 8x8A

ii. All Other Array/Classes 730 lbs, including channels

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-18 Approved Contents 2.0 Table 2.1-1 (page 13 of 30)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

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

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

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

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

i. Array/Classes 6x6A, 6x6B, As specified in Table 2.1-3 for the 6x6C, 7x7A, and 8x8A. applicable fuel assembly array/class.

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

c. Initial Maximum Rod Enrichment As specified in Table 2.1-3 for the applicable fuel assembly array/class.

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

i. Array/Class 6x6A, 6x6B, Cooling time 18 years and an average 6x6C, 7x7A, or 8x8A burnup 30,000 MWD/MTU (or MWD/MTIHM).

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

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

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-19 Approved Contents 2.0 Table 2.1-1 (page 14 of 30)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

e. Decay Heat Per Assembly

i. Array/Class 6x6A, 6x6B, 115 Watts 6x6C, 7x7A, or 8x8A

ii. Array/Class 8x8F 183.5 Watts

iii. Array/Classes 10x10D 95 Watts and 10x10E

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

f. Fuel Assembly Length

i. Array/Class 6x6A, 6x6B, 135.0 inches (nominal design) 6x6C, 7x7A, or 8x8A

ii. All Other Array/Classes 176.5 inches (nominal design)

g. Fuel Assembly Width

i. Array/Class 6x6A, 6x6B, 4.70 inches (nominal design) 6x6C, 7x7A, or 8x8A

ii. All Other Array/Classes 5.85 inches (nominal design)

h. Fuel Assembly Weight

i. Array/Class 6x6A, 6x6B, 550 lbs, including channels and DFC 6x6C, 7x7A, or 8x8A ii. All Other Array/Classes 830 lbs, including channels and DFC

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-20 Approved Contents 2.0 Table 2.1-1 (page 15 of 30)

Fuel Assembly limits

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

A. Allowable Contents (continued)

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

a. Cladding type ZR

b. Composition 98.2 wt.% ThO2, 1.8 wt.% UO2 with an enrichment of 93.5 wt.% 235U.

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

c. Number of Rods per Thoria Rod 18 Canister:

d. Decay Heat Per Thoria Rod 115 Watts Canister:

e. Post-irradiation Fuel Cooling Time A fuel post-irradiation cooling time 18 and Average Burnup per Thoria years and an average burnup 16,000 Rod Canister: MWD/MTIHM

f. Initial Heavy Metal Weight: 27 kg/canister

g. Fuel Cladding O.D.: 0.412 inches

h. Fuel Cladding I.D.: 0.362 inches

i. Fuel Pellet O.D.: 0.358 inches

j. Active Fuel Length: 111 inches

k. Canister Weight: 550 lbs, including fuel

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-21 Approved Contents 2.0 Table 2.1-1 (page 16 of 30)

Fuel Assembly Limits

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

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

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

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

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

i. Uranium Oxide BWR INTACT FUEL ASSEMBLIES; or ii. MOX BWR INTACT FUEL ASSEMBLIES.

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

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

50 (see Figure 2.1-4).

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-22 Approved Contents 2.0 Table 2.1-1 (page 17 of 30)

Fuel Assembly Limits

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

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

a. Cladding Type: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel

assembly array/class

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

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

i. Array/Classes 14x14D, Cooling time 8 years and an average 14x14E, and 15x15G burnup 40,000 MWD/MTU.

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

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-23 Approved Contents 2.0 Table 2.1-1 (page 18 of 30)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 710 Watts.

14x14E, and 15x15G

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

e. Fuel Assembly Length: 176.8 inches (nominal design)

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

g. Fuel Assembly Weight: 1,720 lbs (including NON-FUEL HARDWARE) for assemblies that do not

require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-24 Approved Contents 2.0 Table 2.1-1 (page 19 of 30)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

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

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

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

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

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

i. Array/Classes 14x14D, Cooling time 8 years and an average 14x14E, and 15x15G burnup 40,000 MWD/MTU.

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

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-25 Approved Contents 2.0 Table 2.1-1 (page 20 of 30)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 710 Watts.

14x14E, and 15x15G

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

e. Fuel Assembly Length 176.8 inches (nominal design)

f. Fuel Assembly Width 8.54 inches (nominal design)

g. Fuel Assembly Weight 1,720 lbs (including NON-FUEL HARDWARE and DFC) for assemblies that do not require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE and DFC)

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

C. One NSA is permitted for loading.

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-26 Approved Contents 2.0 Table 2.1-1 (page 21 of 30)

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

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

a. Cladding Type: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel

assembly array/class

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

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

i. Array/Classes 14x14D, Cooling time 9 years and an average 14x14E, and 15x15G burnup 30,000 MWD/MTU or cooling time 20 years and an average burnup 40,000 MWD/MTU.

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

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-27 Approved Contents 2.0 Table 2.1-1 (page 22 of 30)

Fuel Assembly Limits

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

A. Allowable Contents (contd)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 500 Watts.

14x14E, and 15x15G

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

e. Fuel Assembly Length 176.8 inches (nominal design)

f. Fuel Assembly Width 8.54 inches (nominal design)

g. Fuel Assembly Weight 1,720 lbs (including NON-FUEL HARDWARE) for assemblies that do not

require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-28 Approved Contents 2.0 Table 2.1-1 (page 23 of 30)

Fuel Assembly Limits

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

A. Allowable Contents (contd)

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

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

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

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

i. Array/Classes 14x14D, Cooling time 9 years and an average 14x14E, and 15x15G burnup 30,000 MWD/MTU or cooling time 20 years and an average burnup 40,000 MWD/MTU.

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

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-29 Approved Contents 2.0 Table 2.1-1 (page 24 of 30)

Fuel Assembly Limits

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

A. Allowable Contents (contd)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 500 Watts.

14x14E, and 15x15G

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

e. Fuel Assembly Length 176.8 inches (nominal design)

f. Fuel Assembly Width 8.54 inches (nominal design)

g. Fuel Assembly Weight 1,720 lbs (including NON-FUEL HARDWARE and DFC) for assemblies

that do not require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE and DFC)

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

C. One NSA is permitted for loading.

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-30 Approved Contents 2.0 Table 2.1-1 (page 25 of 30)

Fuel Assembly Limits

VI. MPC MODEL: MPC-68M A. Allowable Contents

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

a. Cladding Type: ZR

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

c. Initial Maximum Rod Enrichment As specified in Table 2.1-3 for the applicable fuel assembly array/class.

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

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

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

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-31 Approved Contents 2.0 Table 2.1-1 (page 26 of 30)

Fuel Assembly Limits

VI. MPC MODEL: MPC-68M (continued)

A. Allowable Contents (continued)

e. Decay Heat Per Assembly

i. Array/Class 8x8F 183.5 Watts

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

f. Fuel Assembly Length 176.5 inches (nominal design)

g. Fuel Assembly Width 5.85 inches (nominal design)

h. Fuel Assembly Weight 730 lbs, including channels

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-32 Approved Contents 2.0 Table 2.1-1 (page 27 of 30)

Fuel Assembly Limits

VI. MPC MODEL: MPC-68M (continued)

A. Allowable Contents (continued)

2. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, with or without channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES whose damage is limited such that the fuel assembly is able to be handled by normal means and whose structural integrity remains intact to the extent that geometric rearrangement of fuel is not expected, with or without channels, placed in basket cell locations containing top and bottom DAMAGED FUEL ISOLATORS. BWR DAMAGED FUEL ASSEMBLIES used with 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. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2.1-3, and meet the following specifications:

a. Cladding Type: ZR

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

c. Initial Maximum Rod Enrichment As specified in Table 2.1-3 for the applicable fuel assembly array/class.

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

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

ii. All Other Array/Classes Cooling time 1 year and an average burnup 65,000 MWD/MTU.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-33 Approved Contents 2.0 Table 2.1-1 (page 28 of 30)

Fuel Assembly Limits

VI. MPC MODEL: MPC-68M (continued)

A. Allowable Contents (continued)

e. Decay Heat Per Assembly

i. Array/Class 8x8F 183.5 Watts ii. All Other Array/Classes As specified in Section 2.4.

f. Fuel Assembly Length 176.5 inches (nominal design)

g. Fuel Assembly Width 5.85 inches (nominal design)

h. Fuel Assembly Weight 830 lbs, including channels and DFC/DFIs

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-34 Approved Contents 2.0 Table 2.1-1 (page 29 of 30)

Fuel Assembly Limits

VI. MPC MODEL: MPC-68M (continued)

A. Allowable Contents (continued)

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

a. Cladding Type: ZR

b. Composition 98.2 wt.% ThO2, 1.8 wt.% UO2 with an 235U enrichment of 93.5 wt.%

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

c. Number of Rods per Thoria Rod 18 Canister:

d. Decay Heat Per Thoria Rod 115 Watts Canister:

e. Post-irradiation Fuel Cooling Time A fuel post-irradiation cooling time 18 and Average Burnup per Thoria years and an average burnup 16,000 Rod Canister: MWD/MTIHM

f. Initial Heavy Metal Weight: 27 kg/canister

g. Fuel Cladding O.D.: 0.412 inches

h. Fuel Cladding I.D.: 0.362 inches

i. Fuel Pellet O.D.: 0.358 inches

j. Active Fuel Length: 111 inches

k. Canister Weight: 550 lbs, including fuel

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-35 Approved Contents 2.0 Table 2.1-1 (page 30 of 30)

Fuel Assembly Limits

VI. MPC MODEL: MPC-68M (continued)

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

1. Up to sixteen (16) DFCs or DFIs containing BWR DAMAGED FUEL ASSEMBLIES and/or up to eight (8) DFCs containing FUEL DEBRIS.

DFCs/DFIs shall be located only in fuel storage locations 1, 2, 3, 8, 9, 16, 25, 34, 35, 44, 53, 60, 61, 66, 67, and/or 68. Alternatively BWR DAMAGED FUEL ASSEMBLIES using DFCs/DFIs may be stored in inner locations when using the loading pattern in Figure 2.4-4. The remaining fuel storage locations may be filled with Uranium Oxide BWR UNDAMAGED FUEL ASSEMBLIES.

2. Up to one (1) Dresden Unit 1 Thoria Rod Canister.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-36 Approved Contents 2.0 Table 2.1-2 (page 1 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 14x14A 14x14B 14x14C 14x14D 14x14E

Clad Material ZR ZR ZR SS SS

Design Initial U (kg/assy.) (Note 3) 365 412 438 400 206

Initial Enrichment 4.6 (24) 4.6 (24) 4.6 (24) 4.0 (24) 5.0 (24)

(MPC-24, 24E and 24EF without soluble boron 5.0 5.0 5.0 5.0 5.0 credit) (wt % 235U) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF)

(Note 7)

Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F 5.0 5.0 5.0 5.0 5.0 with soluble boron credit - see Note 5)

(wt % 235U)

No. of Fuel Rod Locations 179 179 176 180 173 (Note 11)

Fuel Rod Clad O.D. (in.) 0.400 0.417 0.440 0.422 0.3415

Fuel Rod Clad I.D.

(in.) 0.3514 0.3734 0.3880 0.3890 0.3175

Fuel Pellet Dia.

(in.)(Note 8) 0.3444 0.3659 0.3805 0.3835 0.3130

Fuel Rod Pitch (in.) 0.556 0.556 0.580 0.556 Note 6

Active Fuel Length (in.) 150 150 150 144 102

No. of Guide and/or Instrument 17 17 5 (Note 4) 16 0 Tubes

Guide/Instrument Tube Thickness 0.017 0.017 0.038 0.0145 N/A (in.)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-37 Approved Contents 2.0 Table 2.1-2 (page 2 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 15x15A 15x15B 15x15C 15x15D 15x15E 15x15F

Clad Material ZR ZR ZR ZR ZR ZR

Design Initial U < 473 < 473 < 495 < 495 < 495 (kg/assy.) (Note 3) < 473

Initial Enrichment (MPC-24, 24E and < 4.1 (24) < 4.1 (24) < 4.1 (24) < 4.1 (24) < 4.1 (24) < 4.1 (24) 24EF without soluble boron credit) < 4.5 < 4.5 < 4.5 < 4.5 < 4.5 < 4.5 (wt % 235U) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF)

(Note 7)

Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 with soluble boron credit - see Note 5)(wt % 235U)

No. of Fuel Rod Locations 204 204 204 208 208 208 (Note 11)

Fuel Rod Clad > 0.420 > 0.417 > 0.430 > 0.428 > 0.428 O.D. (in.) > 0.418

Fuel Rod Clad I.D. < 0.3736 < 0.3640 < 0.3800 < 0.3790 < 0.3820 (in.) < 0.3660

Fuel Pellet Dia. < 0.3671 < 0.3570 < 0.3735 < 0.3707 < 0.3742 (in.) (Note 8) < 0.3580

Fuel Rod Pitch < 0.563 < 0.563 < 0.568 < 0.568 < 0.568 (in.) < 0.550

Active Fuel Length < 150 < 150 < 150 < 150 < 150 (in.) < 150

No. of Guide and/or Instrument 21 21 21 17 17 17 Tubes

Guide/Instrument Tube Thickness > 0.0165 > 0.015 > 0.0165 > 0.0150 > 0.0140 > 0.0140 (in.)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-38 Approved Contents 2.0 Table 2.1-2 (page 3 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/ Class 15x15G 15x15H 15x15I 16x16A 16x16B 16x16C

Clad Material SS ZR ZR ZR ZR ZR

Design Initial U < 495 495 < 448 < 448 < 448 (kg/assy.)(Note 3) < 420

Initial Enrichment < 4.0 < 3.8 (24) N/A < 4.6 (24) < 4.6 (24)

(MPC-24, 24E, (24) (Note 9) < 4.6 (24) and 24EF without soluble boron < 4.5 < 4.2 < 5.0 < 5.0 < 5.0 credit)(wt % 235U) (24E/24 (24E/24E (24E/24E (24E/24E (24E/24E (Note 7) EF) F) F) F) F)

Initial Enrichment 5.0 (MPC-24, 24E, (Note 9) 24EF, 32, or 32F with soluble < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 boron credit - see Note 5) (wt %

235U)

No. of Fuel Rod 216 Locations 204 208 236 236 235 (Note 11)

Fuel Rod Clad > 0.414 0.413 > 0.382 > 0.374 > 0.374 O.D. (in.) > 0.422

Fuel Rod Clad < 0.367 < 0.3350 < 0.3290 < 0.3290 I.D. (in.) 0.3890 < 0.3700

Fuel Pellet Dia. < 0.360 < 0.3255 < 0.3225 < 0.3225 (in.) (Note 8) 0.3825 < 0.3622

Fuel Rod Pitch < 0.568 0.550 < 0.506 < 0.506 < 0.485 (in.) < 0.563

Active Fuel < 150 150 < 150 < 150 < 150 Length (in.) < 144

No. of Guide 9 and/or Instrument 21 17 (Note 10) 5 (Note 4) 5 (Note 4) 21 Tubes

Guide/Instrument > 0.0140 Tube Thickness 0.0145 > 0.0140 > 0.0350 > 0.0400 > 0.0157 (in.)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-39 Approved Contents 2.0

Table 2.1-2 (page 4 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/ Class 17x17A 17x17B 17x17C

Clad Material ZR ZR ZR

Design Initial U (kg/assy.)(Note < 474 < 480

3) < 433

Initial Enrichment (MPC-24, < 4.0 (24) < 4.0 (24) < 4.0 (24) 24E, and 24EF without soluble boron credit)(wt % 235U) (Note < 4.4 < 4.4 < 4.4

7) (24E/24EF) (24E/24EF) (24E/24EF)

Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F with < 5.0 < 5.0 < 5.0 soluble boron credit - see Note

5) (wt % 235U)

No. of Fuel Rod Locations (Note 11) 264 264 264

Fuel Rod Clad O.D. (in.) > 0.360 > 0.372 > 0.377

Fuel Rod Clad I.D. (in.) < 0.3150 < 0.3310 < 0.3330

Fuel Pellet Dia. (in.) (Note 8) < 0.3088 < 0.3232 < 0.3252

Fuel Rod Pitch (in.) < 0.496 < 0.496 < 0.502

Active Fuel Length (in.) < 150 < 150 < 150

No. of Guide and/or Instrument Tubes 25 25 25

Guide/Instrument Tube > 0.014 > 0.020 Thickness (in.) > 0.016

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-40 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. Deleted.

3. Design initial uranium weight is the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each PWR fuel assembly, the total uranium weight limit specified in this table may be increased up to 2.0 percent for comparison with users fuel records.

4. Each guide tube replaces four fuel rods.

5. Soluble boron concentration per LCO 3.3.1.

6. This fuel assembly array/class includes only the Indian Point Unit 1 fuel assembly.

This fuel assembly has two pitches in different sectors of the assembly. These pitches are 0.441 inches and 0.453 inches.

7. For those MPCs loaded with both INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, the maximum initial enrichment of the INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS is 4.0 wt.% 235U.

8. Annular fuel pellets are allowed in the top and bottom 12" of the active fuel length.

9. This fuel assembly array/class can only be loaded in MPC-32.

10. One Instrument Tube and eight Guide Bars (Solid ZR).

11. 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.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-41 Approved Contents 2.0 Table 2.1-3 (page 1 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 6x6A 6x6B 6x6C 7x7A 7x7B 8x8A Clad Material ZR ZR ZR ZR ZR ZR Design Initial U < 110 < 110 < 100 < 198 < 120 (kg/assy.) (Note 3) < 110 Maximum PLANAR- < 2.7 for AVERAGE the UO2 INITIAL rods.

ENRICHMENT < 2.7 See Note < 2.7 < 2.7 < 4.2 < 2.7 (MPC-68, 68F, 4 for and 68FF) MOX (wt.% 235U) rods (Note 14)

Maximum PLANAR-AVERAGE INITIAL Note 18 Note 18 Note 18 Note 18 4.8 Note 18 ENRICHMENT (MPC-68M)

(wt.% 235U)

(Note 16, 19)

Initial Maximum Rod Enrichment < 4.0 < 4.0 < 4.0 < 5.5 < 5.0 < 4.0 (wt.% 235U)

No. of Fuel Rod 35 or 36 Locations (Note 20) 35 or 36 (up to 9 36 49 49 63 or 64 MOX rods)

Fuel Rod Clad O.D. > 0.5625 > 0.5630 > 0.4860 > 0.5630 > 0.4120 (in.) > 0.5550 Fuel Rod Clad I.D. < 0.4945 < 0.4990 < 0.4204 < 0.4990 < 0.3620 (in.) < 0.5105 Fuel Pellet Dia. (in.) < 0.4980 < 0.4820 < 0.4880 < 0.4110 < 0.4910 < 0.3580 Fuel Rod Pitch (in.) < 0.710 < 0.710 < 0.740 < 0.631 < 0.738 < 0.523 Active Fuel Length < 120 < 77.5 < 80 < 150 < 120 (in.) < 120 No. of Water Rods (Note 11) 1 or 0 1 or 0 0 0 0 1 or 0 Water Rod Thickness (in.) > 0 > 0 N/A N/A N/A > 0 Channel Thickness < 0.060 < 0.060 < 0.060 < 0.120 < 0.100 (in.) < 0.060

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-42 Approved Contents 2.0 Table 2.1-3 (2 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 8x8B 8x8C 8x8D 8x8E 8x8F 9x9A Clad Material ZR ZR ZR ZR ZR ZR Design Initial U < 190 < 190 < 190 < 191 < 180 (kg/assy.) (Note 3) < 192 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT < 4.2 < 4.2 < 4.2 < 4.2 < 4.0 < 4.2 (MPC-68, 68F, and 68FF)

(wt.% 235U)

(Note 14)

Maximum PLANAR-AVERAGE INITIAL 4.8 4.8 4.8 4.8 4.5 ENRICHMENT (Note 15) 4.8 (MPC-68M)

(wt.% 235U)

(Note 16, 19)

Initial Maximum Rod Enrichment < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 (wt.% 235U)

No. of Fuel Rod 74/66 Locations (Note 20) 63 or 64 62 60 or 61 59 64 (Note 5)

Fuel Rod Clad O.D. > 0.4830 > 0.4830 > 0.4930 > 0.4576 > 0.4400 (in.) > 0.4840 Fuel Rod Clad I.D. < 0.4250 < 0.4230 < 0.4250 < 0.3996 < 0.3840 (in.) < 0.4295 Fuel Pellet Dia. (in.) < 0.4195 < 0.4160 < 0.4140 < 0.4160 < 0.3913 < 0.3760 Fuel Rod Pitch (in.) < 0.642 < 0.641 < 0.640 < 0.640 < 0.609 < 0.566 Design Active Fuel < 150 < 150 < 150 < 150 < 150 Length (in.) < 150 No. of Water Rods 1 - 4 N/A (Note 11) 1 or 0 2 5 2 (Note 7) (Note 12)

Water Rod > 0.00 > 0.00 > 0.034 > 0.0315 > 0.00 Thickness (in.) > 0.034 Channel Thickness < 0.120 < 0.120 < 0.100 < 0.055 < 0.120 (in.) < 0.120

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-43 Approved Contents 2.0 Table 2.1-3 (page 3 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 9x9B 9x9C 9x9D 9x9E 9x9F 9x9G Array/Class (Note 13) (Note 13)

Clad Material ZR ZR ZR ZR ZR ZR Design Initial U < 180 < 182 < 182 < 183 < 183 < 164 (kg/assy.)(Note 3)

Maximum PLANAR-AVERAGE INITIAL ENRICHMENT < 4.2 < 4.2 < 4.2 < 4.0 < 4.0 < 4.2 (MPC-68, 68F, and 68FF)

(wt.% 235U)

(Note 14)

Maximum PLANAR-AVERAGE INITIAL 4.8 4.8 4.8 4.5 4.5 ENRICHMENT (Note 15) (Note 15) 4.8 (MPC-68M)

(wt.% 235U)

(Note 16, 19)

Initial Maximum < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 Rod Enrichment (wt.% 235U)

No. of Fuel Rod 72 80 79 76 76 72 Locations (Note 20)

Fuel Rod Clad O.D. > 0.4330 > 0.4230 > 0.4240 > 0.4170 > 0.4430 > 0.4240 (in.)

Fuel Rod Clad I.D. < 0.3810 < 0.3640 < 0.3640 < 0.3640 < 0.3860 < 0.3640 (in.)

Fuel Pellet Dia. (in.) < 0.3740 < 0.3565 < 0.3565 < 0.3530 < 0.3745 < 0.3565 Fuel Rod Pitch (in.) < 0.572 < 0.572 < 0.572 < 0.572 < 0.572 < 0.572 Design Active Fuel < 150 < 150 < 150 < 150 < 150 < 150 Length (in.)

No. of Water Rods 1 (Note 6) 1 2 5 5 1 (Note 6)

(Note 11)

Water Rod > 0.00 > 0.020 > 0.0300 > 0.0120 > 0.0120 > 0.0320 Thickness (in.)

Channel Thickness < 0.120 < 0.100 < 0.100 < 0.120 < 0.120 < 0.120 (in.)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-44 Approved Contents 2.0 Table 2.1-3 (page 4 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 10x10A 10x10B 10x10C 10x10D 10x10E 10x10F 10x10G

Clad Material ZR ZR ZR SS SS ZR ZR

Design Initial U (kg/assy.) < 188 < 188 < 179 < 125 < 125 192 188 (Note 3)

Maximum PLANAR-AVERAGE INITIAL ENRICHMENT(MPC- < 4.2 < 4.2 < 4.2 < 4.0 < 4.0 Note 17 Note 17 68, 68F, and 68FF)

(wt.% 235U) (Note 14)

Maximum PLANAR-4.7 4.75 AVERAGE INITIAL (Note 15) (Note 21)

ENRICHMENT (MPC-4.8 4.8 4.8 Note 18 Note 18 68M) 5.0 5.0 (wt.% 235U) (Note 26) (Note 26)

(Note 16, 19)

Initial Maximum Rod < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 Enrichment (wt.% 235U) < 5.0

No. of Fuel Rod 92/78 91/83 92/78 96/84 Locations (Note 20) (Note 8) (Note 9) 96 100 96 (Note 8)

Fuel Rod Clad O.D. > > > >

(in.) 0.4040 0.3957 > 0.3780 0.3960 0.3940 0.4035 0.387

Fuel Rod Clad I.D. (in.) < < < <

0.3520 0.3480 < 0.3294 0.3560 0.3500 0.3570 0.340

Fuel Pellet Dia. (in.) < < < <

0.3455 0.3420 < 0.3224 0.3500 0.3430 0.3500 0.334

Fuel Rod Pitch (in.) < 0.510 < 0.510 < 0.488 < 0.565 < 0.557 0.510 0.512

Design Active Fuel < 150 < 150 < 83 < 83 150 150 Length (in.) < 150

No. of Water Rods 5 (Note 11) 2 1 (Note 6) (Note 10) 0 4 2 5 (Note 10)

Water Rod Thickness > 0.00 > 0.031 N/A > 0.022 0.030 0.031 (in.) > 0.030

Channel Thickness < 0.120 < 0.055 < 0.080 < 0.080 0.120 0.060 (in.) < 0.120

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-45 Approved Contents 2.0 Table 2.1-3 (page 5 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array 10x10I 10x10J 11x11A and Class (Note 17, 22) (Note 17, 23) (Note 17, 24)

Clad Material Zr Zr Zr Design Initial U (kg/assy.)

(Note 3) 194 194 194 Maximum Planar-Average Initial Enrichment 4.8 4.8 4.8 (wt.% 235U) (Note 16, 19)

Maximum Planar-Average Initial Enrichment with 5.0 5.0 5.0 Partial Gadolinium Credit (wt.%235U) (Note 26)

Initial Rod Maximum Enrichment (wt.% 235U) 5.0 5.0 5.0 No. of Fuel Rod Locations (Note 20) 91/79 96/80 112/92 Fuel Clad O.D. (in.) 0.4047 0.3999 0.3701 Fuel Clad I.D. (in.) 0.3559 0.3603 0.3252 Fuel Pellet Dia. (in.) 0.3492 0.3531 0.3193 Fuel Rod Pitch (in.) 0.5100 0.5149 0.4705 Design Active Fuel Length (in.) 150 150 150 No. of Water Rods (Note 25) 1 1 1 Water Rod Thickness (in.) 0.0315 0.0297 0.0340 Channel Thickness (in.) 0.100 0.0938 0.100

Notes:

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

2. Deleted.

3. Design initial uranium weight is the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each BWR fuel assembly, the total uranium weight limit specified in this table may be increased up to 1.5 percent for comparison with users fuel records.

4. 0.635 wt. % 235U and 1.578 wt. % total fissile plutonium (239Pu and 241Pu), (wt. % of total fuel weight, i.e., UO2 plus PuO2).

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

6. Square, replacing nine fuel rods.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-46 Approved Contents 2.0

Table 2.1-3 (page 6 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS

7. Variable.

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

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

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

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

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

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

14. For MPC-68, 68F, and 68FF loaded with both INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, the maximum PLANAR AVERAGE INITIAL ENRICHMENT for the INTACT FUEL ASSEMBLIES is limited to 3.7 wt.% 235U, as applicable.

15. Fuel assemblies classified as damaged fuel assemblies are limited to 4.6 wt.% 235U for the 10x10F arrays/classes. Fuel assemblies classified as damaged fuel assemblies are limited to 4.0 wt.% 235U for the 8x8F, 9x9E and 9x9F arrays/classes except when loaded to Figure 2.4.4. Fuel assemblies classified as damaged fuel assemblies are limited to 4.5 wt.% 235U for the 8x8F, 9x9E and 9x9F when loaded to Figure 2.4.4.

16. For MPC-68M loaded with both UNDAMAGED FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, the maximum PLANAR AVERAGE INITIAL ENRICHMENT for the UNDAMAGED FUEL ASSEMBLIES is limited to the enrichment limit of the damaged assembly.

17. This fuel assembly array/class is not allowable contents in MPC-68, 68F, or 68FF.

18. This fuel assembly array/class is not allowable contents in MPC-68M.

19. In accordance with the definition of UNDAMAGED FUEL ASSEMBLY, certain assemblies may be limited to up to 3.3 wt.% U-235. When loading these fuel assemblies, all other undamaged fuel assemblies in the MPC are limited to enrichments as specified in this table.

20. 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.

21. Fuel assemblies classified as damaged fuel assemblies are limited to 4.6 wt.% 235U for the 10x10G array/class escept when loaded to Figure 2.4.4. Fuel assemblies classified as damaged fuel assemblies are limited to 4.5 wt.% 235U for the 10x10G array/class when loaded to Figure 2.4.4.

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

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

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

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

26. The restrictions in Table 2.1-9 apply.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-47 Approved Contents 2.0 Table 2.1-8 NON-FUEL HARDWARE COOLING AND AVERAGE BURNUP (Notes 1, 2, 3, and 7)

Post-NSA with NFH NSA without APSR irradiation INSERTS NFH, GUIDE BURNUP Cooling Time (Note 4) TUBE (MWD/MTU)

(years) BURNUP HARDWARE, or (MWD/MTU) CONTROL COMPONENT (Note 5)

BURNUP (MWD/MTU)

3 24,635 NA (Note 6) NA

4 30,000 NA NA

5 36,748 630,000 45,000

6 44,102 - 54,500

7 52,900 - 68,000

8 60,000 - 83,000

9 79,784 - 111,000

10 101,826 - 180,000

11 141,982 - 630,000

12 360,000 - -

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

2. Linear interpolation between points is permitted, except that APSR burnups > 180,000 MWD/MTU and < 630,000 MWD/MTU must be cooled > 11 years.

3. Applicable to uniform loading and regionalized loading.

4. Includes Burnable Poison Rod Assemblies (BPRAs), Wet Annular Burnable Absorbers (WABAs), vibration suppressor inserts and Neutron Source Assemblies (NSAs) in combination with other control components (i.e. BPRAs, TPDs, and/or RCCAs).

5. Includes Thimble Plug Devices (TPDs), water displacement guide tube plugs, orifice rod assemblies, Control Rod Assemblies (CRAs), Control Element Assemblies (CEAs), Rod Cluster Control Assemblies (RCCAs) and NSAs without other forms of control components.

6. NA means not authorized for loading at this cooling time.

7. Non-fuel hardware burnup and cooling times are not applicable to ITTRs since they are installed post irradiation.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-48 Approved Contents 2.0 Table 2.1-9 RESTRICTIONS FOR PARTIAL GADOLINIUM CREDIT IN MPC-68M

FUEL ASSEMBLY ARRAY RESTRICTION AND CLASS All 10x10 and The gadolinium rod loading is not less than 11x11 3.0 wt% Gd2O3 All 10x10 and The gadolinium rods located in the peripheral row 11x11 of the fuel lattice cannot be credited All 10x10 and 11x11 Gadolinium rods are NOT required to be present in damaged fuel in DFIs or damaged fuel/fuel debris in DFCs 10x10A, 10x10B, 10x10F, At least one gadolinium rod must be present.

10x10I, 10x10J, and 11x11A 10x10C and 10x10G At least two gadolinium rods must be present

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-49 Approved Contents 2.0 2.4 Decay Heat Limits for ZR-Clad Fuel This section provides the limits on ZR-clad fuel assembly decay heat, burnup, and cooling time for storage in the HI-STORM 100 System. The method to calculate the limits and verify compliance, including examples, is provided in Chapter 12 of the HI-STORM 100 FSAR.

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

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

Decay Heat per Fuel Storage Location MPC Model (kW)

Intact or Undamaged Damaged Fuel Assemblies Fuel Assemblies and Fuel Debris MPC-24 < 1.416 Not Permitted MPC-24E/24EF < 1.416 < 1.114 MPC-32/32F < 1.062 < 0.718 MPC-68/68FF/68M < 0.500 < 0.393

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-50 Approved Contents 2.0 2.4.2 Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel for VENTILATED OVERPACK

The maximum allowable decay heat per fuel storage location for intact or undamaged fuel assemblies in regionalized loading is determined using the following equations:

Q(X) = 2 x Q0 / (1 + Xy) y = 0.23 / X0.1 q2 = Q(X) / (n1 x X +n2) q1 = q2 x X

Where:

Q0 = Maximum uniform storage MPC decay heat (34 kW)

X = Inner region to outer region assembly decay heat ratio (0.5 X 3) n1 = Number of storage locations in inner region from Table 2.4-2.

n2 = Number of storage locations in outer region from Table 2.4-2.

Allowable heat loads for Damaged Fuel and Fuel Debris in regionalized loading are shown in Table 2.4-5.

Optional loading patterns for MPC-68M are shown in Figures 2.4-1 through 2.4-4.

Alternatively to the heat load patterns in Sections 2.4.1 and 2.4.2, per cell allowable heat loads may be determined per Topical Report HI-2200343-A.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-51 Approved Contents 2.0

Table 2.4-2 Fuel Storage Regions per MPC

MPC Model Number of Storage Locations Number of Storage in Inner Region (Region 1) Locations in Outer Region (Region 2)

MPC-24 and MPC-24E/EF 12 12 MPC-32/32F 12 20 MPC-68/68FF/68MNote1 32 36 Note 1: For an optional regionalized loading pattern for MPC-68M, see Figures 2.4-1 through 2.4-4.

Table 2.4-5 Allowable Heat Load for Damaged Fuel Assemblies and Fuel Debris under Regionalized Loading

Maximum Per Cell Allowable Heat Load for MPC Model Damaged Fuel Assemblies and Fuel Debris in DFCs Note 1,3 MPC-24E/24EF 0.75*q2

MPC-32/32F 0.65*q2

MPC-68/68FF/68MNote 2 0.75*q2

Note 1: q2 is the maximum permissible heat load in Region 2 for intact fuel assemblies.

Note 2: Optional QSHL loading patterns for MPC-68M including Damaged Fuel and Fuel Debris are shown in Figures 2.4-1 through 2.4-4.

Note 3: Damaged fuel stored with DFIs can be stored up to q 2 limits.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-52 Approved Contents 2.0 2.4.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel for VENTILATED OVERPACK

The maximum allowable ZR-clad fuel assembly average burnup varies with the minimum required fuel assembly cooling time. Tables 2.4-3 and 2.4-4 provide for each MPC the allowable maximum burnup based on the assemblys particular cooling time. These same limits apply for heat load patterns developed in accordance with the topical report, HI-2200343-A.

2.4.3.1 Linear interpolation of burnups between cooling times is permitted. For example, the allowable burnup for a cooling time of 4.5 years may be interpolated between those burnups calculated for 4 year and 5 years.

2.4.3.2 Calculated burnup limits shall be rounded down to the nearest integer.

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

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

2.4.5 Fuel Loading Decay Heat Limits for UNVENTILATED OVERPACK

Tables 2.4-6a and 2.4-6b provide the maximum allowable decay heat per fuel storage location for MPC-68M in an UNVENTILATED OVERPACK.

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. 1014 Renewed Amendment No. 18 Appendix B 2-53 Approved Contents 2.0

2.4.6 Burnup and Cooling Time Qualifications for the MPC-68M for UNVENTILATED OVERPACK

The burnup and cooling time for every fuel loaded into the MPC-68M must satisfy the following equation:

= 3 + 2 + +

where, Ct = Minimum cooling time (years),

Bu = Assembly-average burnup (MWd/mtU),

A, B, C, D = Polynomial coefficients listed in Table 2.4-9

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-54 Approved Contents 2.0 Table 2.4-3

PWR Fuel Assembly Burnup and Cooling Time Limits for VENTILATED OVERPACK (ZR-Clad Fuel)

Minimum Maximum Cooling Time Allowable Burnup, (years) MWd/mtU

MPC-24/24E/24EF 1.0 5,000 1.4 15,000 1.8 25,000 2.0 35,000 2.2 40,000 2.4 45,000 2.6 50,000 2.8 55,000 3.0 60,000 4.0 69,000 5.0 75,000 MPC-32/32F 1.0 5,000 1.4 10,000 1.8 20,000 2.0 25,000 2.2 30,000 2.4 35,000 2.6 40,000 3.0 45,000 4.0 60,000 5.0 69,000

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-55 Approved Contents 2.0 Table 2.4-4

BWR Fuel Assembly Burnup and Cooling Time Limits for VENTILATED OVERPACK (ZR-Clad Fuel)

Minimum Maximum Cooling Time Allowable Burnup, (years) MWd/mtU

MPC-68/68FF/68M 1.0 10,000 1.2 15,000 1.4 20,000 2.0 25,000 2.2 30,000 2.4 35,000 2.6 40,000 3.0 50,000 4.0 62,000 5.0 65,000 6.0 70,000

TABLE 2.4-6a MPC-68M HEAT LOAD DATA for UNVENTILATED OVERPACK Number of Regions: 2

Number of Storage Cells: 68

Maximum Total Heat Load (kW): 25 Maximum Section Heat Load (kW): 3.125 (Note 1)

Region No. Decay Heat Limit per Number of Cells per Decay Heat Limit per Cell, kW Region Region, kW 1 (Inner) 0.368 32 11.765 2 (Outer) 0.368 36 13.325 Note 1: Figure 2.1-4 identifies the MPC basket regions and cell locations, and Table 2.4-7 identifies the cells included in each Heat Load for each section.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-56 Approved Contents 2.0 TABLE 2.4-6b MPC-68M REQUIREMENTS ON DEVELOPING REGIONALIZED HEAT LOAD PATTERNS for UNVENTILATED OVERPACK (See Figure 2.1-4)

1. Total MPC aggregate Heat Load must be equal to 25 kW

2. Maximum Section Heat Load must be equal to 3.125 kW, calculated per Table 2.4-7, and pattern must be 1/8th symmetric

3. Maximum Heat Load per Cell in Region 1 is 0.368 kW

4. Maximum Heat Load per Cell in Region 2 is 0.735 kW

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

6. Pattern-specific Heat Load for storage cells may be determined by reducing the allowable heat load in any Region 1 cell in Table 2.4-6a by a certain amount ( ) and adding the same to a single cell or distributed amongst multiple cells in Region 2.

i.e. Any reduction of total allowable heat load in Region 1 must be compensated by an equivalent addition in Region 2.

General Notes -

1. Any assembly with a Heat Load less than the limits defined above can be loaded in the applicable cell, provided it meets all other CoC requirements.

2. DFCs/DFIs are permitted in locations denoted in Table 2.4-8 with the applicable Heat Load penalties identified therein.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-57 Approved Contents 2.0 TABLE 2.4-7 SECTION HEAT LOAD CALCULATIONS FOR MPC-68M for UNVENTILATED OVERPACK

Section Equation for Section Heat Load 1

Section 1 Q21 + Q13 + Q14 + Q6 + Q7 + Q8 + Q2 + 1/2Q30 + 1/2Q22 + 1/2Q15

Section 2 Q31 + Q32 + Q23 + Q33 + Q24 + Q16 + Q34 + 1/2Q30 + 1/2Q22 + 1/2Q15

Section 3 Q41 + Q42 + Q51 + Q43 + Q52 + Q60 + Q44 + 1/2Q40 + 1/2Q50 + 1/2Q59

Section 4 Q49 + Q58 + Q57 + Q64 + Q65 + Q66 + Q68 + 1/2Q40 + 1/2Q50 + 1/2Q59

Section 5 Q48 + Q56 + Q55 + Q61 + Q62 + Q63 + Q67 + 1/2Q39 + 1/2Q47 + 1/2Q54

Section 6 Q38 + Q46 + Q37 + Q36 + Q45 + Q53 + Q35 + 1/2Q39 + 1/2Q47 + 1/2Q54

Section 7 Q28 + Q27 + Q18 + Q9 + Q17 + Q26 + Q25 + 1/2Q29 + 1/2Q19 + 1/2Q10

Section 8 Q20 + Q11 + Q12 + Q3 + Q4 + Q5 + Q1 + 1/2Q29 + 1/2Q19 + 1/2Q10

Notes 1.) QX-Y is the heat load in kW in cell ID (X-Y), identified in Figure 2.1-4

Table 2.4-8 DFC and DFI Storage Locations with Heat Load penalties for MPC-68M for UNVENTILATED OVERPACK Locations/Storage Cell Heat Load Min. Soluble Boron MPC Type DFC/DFI (Note 1) Numbers Penalty Content (Note 2) (Note 3)

DFI 25%

MPC-68M DFC 25% 1, 2, 3, 8, 9, 16, 25, 34, 35, N/A DFC or DFI DFCs - 25% 44, 53, 60, 61, 66, 67, 68 DFIs - 25%

Notes 1: Damaged fuel assemblies or fuel debris can be loaded in DFCs while only damaged fuel assemblies that can be handled by normal means can be loaded in DFIs.

2: DFCs/DFIs are allowed for storage in certain basket peripheral locations as defined herein. Basket storage cell numbers are identified in Figure 2.1-4 for the MPC-68M.

3: Heat load penalties are applicable to ONLY those cells where DFCs/DFIs are located and are applied to the allowable undamaged fuel assembly decay heat limit in that storage cell location. The penalties remain the same for all regionalized patterns and discrete loading patterns.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-58 Approved Contents 2.0

TABLE 2.4-9 Burnup and Cooling Time Fuel Qualification Requirements for MPC-68M for UNVENTILATED OVERPACK

Region No. Polynomial Coefficients, see Subsection 2.4.5 (see Figure 2.1-4) A B C D

1 (Inner) 9.44656e-14 -8.01992e-09 2.79524e-04 -4.10441e-01

2 (Outer) 5.58795e-15 -5.13598e-10 5.81723e-05 4.09393e-01

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-59 Approved Contents 2.0

1 2 0.5* 0.5*

3 4 5 6 7 8 0.5* 0.5 1.2 1.2 0.5 0.5*

9 10 11 12 13 14 15 16 0.5* 0.5 1.2 0.4 0.4 1.2 0.5 0.5*

17 18 19 20 21 22 23 24 0.5 1.2 0.4 0.4 0.4 0.4 1.2 0.5

25 26 27 28 29 30 31 32 33 34 0.5* 1.2 0.4 0.4 0.4 0.4 0.4 0.4 1.2 0.5*

35 36 37 38 39 40 41 42 43 44 0.5* 1.2 0.4 0.4 0.4 0.4 0.4 0.4 1.2 0.5*

45 46 47 48 49 50 51 52 0.5 1.2 0.4 0.4 0.4 0.4 1.2 0.5

53 54 55 56 57 58 59 60 0.5* 0.5 1.2 0.4 0.4 1.2 0.5 0.5*

61 62 63 64 65 66 0.5* 0.5 1.2 1.2 0.5 0.5*

Cell ID 67 68

Heat Load (kW) 0.5* 0.5*

When DAMAGED FUEL or FUEL DEBRIS is stored in this location (in a DFC),

the allowable heat load of the cell is limited to 0.35 kW. When DFIs are utilized for DAMAGED FUEL, the value in the figure applies.

Figure 2.4-1 QSHL Pattern Per Cell Allowable Heat Loads (kW) - MPC-68M

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-60 Approved Contents 2.0

DFCs/DFIs are allowed in shaded cells. When DAMAGED FUEL or FUEL DEBRIS (in a DFC) is stored in this location, the allowable heat load of the cell is reduced by 25%. When DFIs are utilized for DAMAGED FUEL, the value in the figure applies.

Figure 2.4-2 QSHL-2 Pattern, Per Cell Allowabl e Heat Loads (kW) - MPC-68M

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-61 Approved Contents 2.0

DFCs/DFIs are allowed in shaded cells. When DAMAGED FUEL or FUEL DEBRIS (in a DFC) is stored in this location, the allowable heat load of the cell is reduced by 25%. When DFIs are utilized for DAMAGED FUEL, the value in the figure applies.

Figure 2.4-3 QSHL-3 Pattern, Per Cell Allowabl e Heat Loads (kW) - MPC-68M

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-62 Approved Contents 2.0

DFCs/DFIs are allowed in shaded cells. Cell IDs 19, 22, 47 and 50 must remain empty.

Figure 2.4-4 QSHL-4 Pattern, Per Cell Allo wable Heat Loads (kW) - MPC-68M

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 2-63 Design Features 3.0

3.0 DESIGN FEATURES 3.1 Site 3.1.1 Site Location The HI-STORM 100 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-24

1. Flux trap size: 1.09 in.

2. 10B loading in the neutron absorbers: 0.0267 g/cm2 (Boral) and 0.0223 g/cm2 (METAMIC) 3.2.2 MPC-68 and MPC-68FF

1. Fuel cell pitch: 6.43 in.

2. 10B loading in the neutron absorbers: 0.0372 g/cm2 (Boral) and 0.0310 g/cm2 (METAMIC) 3.2.3 MPC-68F

1. Fuel cell pitch: 6.43 in.

2. 10B loading in the Boral neutron absorbers: 0.01 g/cm2 3.2.4 MPC-24E and MPC-24EF

1. Flux trap size:

i. Cells 3, 6, 19, and 22: 0.776 inch ii. All Other Cells: 1.076 inches

2. 10B loading in the neutron absorbers: 0.0372 g/cm2 (Boral) and 0.0310 g/cm2 (METAMIC) 3.2.5 MPC-32 and MPC-32F

1. Fuel cell pitch: 9.158 inches

2. 10B loading in the neutron absorbers: 0.0372 g/cm2 (Boral) and 0.0310 g/cm2 (METAMIC)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-1 Design Features 3.0 DESIGN FEATURES (continued)

3.2 Design features Important for Criticality Control (contd) 3.2.6 MPC-68M

1. Basket Cell wall thickness 0.4 in. (nom.)

2. B4C content in METAMIC-HT shall be 10 wt. %

3.2.7 Fuel spacers shall be sized to ensure that the active fuel region of intact or undamaged fuel assemblies remains within the neutron poison region of the MPC basket with water in the MPC.

3.2.8 The B4C content in METAMIC shall be 33.0 wt.%.

3.2.9 Neutron Absorber Tests Boral and Metamic Classic Section 9.1.5.3 of the HI-STORM 100 FSAR is hereby incorporated by reference into the HI-STORM 100 CoC. For each MPC model specified in Sections 3.2.1 through 3.2.5 above, the neutron absorber shall meet the minimum requirements for 10B areal density or B4C content, as applicable.

Metamic-HT (Section 3.2.6 above)

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

2. The areal density of the B-10 isotope corresponding to the 10% min.

weight density in the manufactured Metamic-HT panels shall be independently confirmed by the neutron attenuation test method by testing at least one coupon from a randomly selected panel in each lot.

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

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

3.3 Codes and Standards The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 1995 Edition with Addenda through 1997, is the governing Code for the HI-STORM 100 System MPCs, OVERPACKs, and TRANSFER CASKs, as clarified in Specification 3.3.1 below, except for Code Sections V and IX. 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 1995 Edition, including 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.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-2 Design Features 3.0 DESIGN FEATURES (continued)

3.3.1 Alternatives to Codes, Standards, and Criteria Table 3-1 lists approved alternatives to the ASME Code for the design of the MPCs, OVERPACKs, and TRANSFER CASKs of the HI-STORM 100 Cask System.

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

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

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

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

(continued)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-3 Design Features 3.0 DESIGN FEATURES (continued)

Table 3-1 (page 1 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM

Component Reference Code Alternative, Justification & Compensatory ASME Code Requirement Measures Section/Article MPC, MPC Subsection General Because the MPC, OVERPACK, and basket NCA Requirements. TRANSFER CASK are not ASME Code stamped assembly, Requires vessels, none of the specifications, reports, HI-STORM preparation of a certificates, or other general requirements OVERPACK Design specified by NCA are required. In lieu of a Design steel Specification, Specification and Design Report, the HI-STORM structure, Design Report, FSAR includes the design criteria, service and HI-Overpressure conditions, and load combinations for the design TRAC Protection Report, and operation of the HI-STORM 100 System as TRANSFER Certification of well as the results of the stress analyses to CASK steel Construction demonstrate that applicable Code stress limits structure Report, Data are met. Additionally, the fabricator is not Report, and other required to have an ASME-certified QA program.

administrative All important-to-safety activities are governed by controls for an the NRC-approved Holtec QA program.

ASME Code stamped vessel. 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 various articles of Subsections NB, NG, and NF of 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 MPC enclosure vessel is designed and will be requirements for fabricated in accordance with ASME Code, Code stamping of Section III, Subsection NB to the maximum components. practical extent, but Code stamping is not required.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-4 Design Features 3.0 DESIGN FEATURES (continued)

Table 3-1 (page 2 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Alternative, Justification & Compensatory ASME Code Requirement Measures Section/Article MPC basket NB-1130 NB-1132.2(d) The MPC basket supports (nonpressure-supports requires that the retaining structural attachments)and lift lugs and lift lugs first connecting (nonstructural attachments (relative to the weld of a function of lifting a loaded MPC) that are used nonpressure-exclusively for lifting an empty MPC) are welded retaining structural to the inside of the pressure-retaining MPC attachment to a shell, but are not designed in accordance with component shall Subsection NB. The basket supports and be considered part associated attachment welds are designed to of the component satisfy the stress limits of Subsection NG and unless the weld is the lift lugs and associated attachment welds more than 2t from are designed to satisfy the stress limits of the pressure-Subsection NF, as a minimum. These retaining portion of attachments and their welds are shown by the component, analysis to meet the respective stress limits for where t is the their service conditions. Likewise, non-structural nominal thickness items, such as shield plugs, spacers, etc. if of the pressure-used, can be attached to pressure-retaining retaining material. parts in the same manner.

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

MPC NB-2121 Provides permitted Certain duplex stainless steels are not included material in Section II, Part D, Tables 2A and 2B. UNS specification for S31803 duplex stainless steel alloy is evaluated pressure-retaining in the HI-STORM 100 FSAR and meets the material, which required design criteria for use in the HI-STORM must conform to 100 system per ASME Code Case N-635-1.

Section II, Part D, Tables 2A and 2B

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-5 Design Features 3.0 DESIGN FEATURES (continued)

Table 3-1 (page 3 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM

Component Reference Code Alternative, Justification & Compensatory ASME Code Requirement Measures Section/Article MPC, MPC NB-3100 Provides These requirements are not applicable. The HI-basket NG-3100 requirements for STORM FSAR, serving as the Design assembly, NF-3100 determining Specification, establishes the service conditions HI-STORM design loading and load combinations for the storage system.

OVERPACK conditions, such and HI-as pressure, TRAC temperature, and TRANSFER mechanical loads.

CASK MPC NB-3350 NB-3352.3 Due to MPC basket-to-shell interface requires, for requirements, the MPC shell-to-baseplate weld Category C joints, joint design (designated Category C) does not that the minimum include a reinforcing fillet weld or a bevel in the dimensions of the MPC baseplate, which makes it different than any welds and throat of the representative configurations depicted in thickness shall be Figure NB-4243-1. The transverse thickness of as shown in Figure this weld is equal to the thickness of the adjoining NB-4243-1. shell (1/2 inch). The weld is designed as a full penetration weld that receives VT and RT or UT, as well as final surface PT examinations.

Because the MPC shell design thickness is considerably larger than the minimum thickness required by the Code, a reinforcing fillet weld that would intrude into the MPC cavity space is not included. Not including this fillet weld provides for a higher quality radiographic examination of the full penetration weld.

From the standpoint of stress analysis, the fillet weld serves to reduce the local bending stress (secondary stress) produced by the gross structural discontinuity defined by the flat plate/shell junction. In the MPC design, the shell and baseplate thicknesses are well beyond that required to meet their respective membrane stress intensity limits.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-6 Design Features 3.0 DESIGN FEATURES (continued)

Table 3-1 (page 4 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM

Component Reference Code Alternative, Justification & Compensatory ASME Code Requirement Measures Section/Article MPC, MPC NB-4120 NB-4121.2, NG-In-shop operations of short duration that apply Basket NG-4120 4121.2, and NF-heat to a component, such as plasma cutting of Assembly, NF-4120 4121.2 provide plate stock, welding, machining, coating, and HI-STORM requirements for pouring of lead are not, unless explicitly stated by OVERPACK repetition of tensile the Code, defined as heat treatment operations.

steel or impact tests for structure, material subjected For the steel parts in the HI-STORM 100 and HI-to heat treatment System components, the duration for which a TRAC during fabrication part exceeds the off-normal temperature limit TRANSFER or installation. defined in Chapter 2 of the FSAR shall be CASK steel limited to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a particular manufacturing structure process (such as the HI-TRAC lead pouring process).

MPC, MPC NB-4220 Requires certain The cylindricity measurements on the rolled basket NF-4220 forming tolerances shells are not specifically recorded in the shop assembly, to be met for travelers, as would be the case for a Code-HI-STORM cylindrical, conical, stamped pressure vessel. Rather, the OVERPACK or spherical shells requirements on inter-component clearances steel of a vessel. (such as the MPC-to-TRANSFER CASK) are structure, guaranteed through fixture-controlled and HI-manufacturing. The fabrication specification TRAC and shop procedures ensure that all TRANSFER dimensional design objectives, including inter-CASK steel component annular clearances are satisfied.

structure 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 Lid NB-4243 Full penetration MPC lid and closure ring are not full penetration and Closure welds required for welds. They are welded independently to Ring Welds Category C Joints provide a redundant seal. Additionally, a weld (flat head to main efficiency factor of 0.45 has been applied to the shell per NB-analyses of these welds.

3352.3).

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-7 Design Features 3.0 DESIGN FEATURES (continued)

Table 3-1 (page 5 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM

Component Reference Code Alternative, Justification & Compensatory ASME Code Requirement Measures Section/Article MPC Lid to NB-5230 Radiographic (RT) Only UT or multi-layer liquid penetrant (PT)

Shell Weld or ultrasonic (UT) examination is permitted. If PT alone is used, at examination a minimum, it will include the root and final weld required layers and each approximately 3/8 inch of weld depth.

MPC NB-5230 Radiographic (RT) Root (if more than one weld pass is required)

Closure or ultrasonic (UT) and final liquid penetrant examination to be Ring, Vent examination performed in accordance with NB-5245. The and Drain required closure ring provides independent redundant Cover Plate closure for vent and drain cover plates. Vent Welds and drain port cover plate welds are helium leakage testsed.

MPC NB-6111 All completed The MPC enclosure vessel is seal welded in the Enclosure pressure retaining field following fuel assembly loading. The MPC Vessel and systems shall be enclosure vessel shall then be pressure tested Lid pressure tested. as defined in Chapter 9. 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, except the MPC lid-to-shell weld shall be verified by volumetric or multi-layer PT examination. If PT alone is used, at a minimum, it must include the root and final layers and each approximately 3/8 inch of weld depth. For either UT or PT, the maximum undetectable flaw size must be demonstrated to be less than the critical flaw size. The critical flaw size must be determined in accordance with ASME Section XI methods.

The critical flaw size shall not cause the primary stress limits of NB-3000 to be exceeded.

The inspection results, including relevant findings (indications), shall be made a permanent part of the users records by video, photographic, or other means which provide an equivalent retrievable 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 for PT or NB-5332 for UT.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-8 Design Features 3.0 DESIGN FEATURES (continued)

Table 3-1 (page 6 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM

Component Reference Code Alternative, Justification & Compensatory ASME Code Requirement Measures Section/Article MPC NB-7000 Vessels are No overpressure protection is provided. The Enclosure required to have function of the MPC enclosure vessel is to Vessel overpressure contain the radioactive contents under normal, protection off-normal, and accident conditions. The MPC vessel is designed to withstand maximum internal pressure considering 100% fuel rod failure and maximum accident temperatures.

MPC NB-8000 States The HI-STORM100 System is to be marked and Enclosure requirements for identified in accordance with 10CFR71 and Vessel nameplates, 10CFR72 requirements. Code stamping is not stamping and required. QA data package to be in accordance reports per NCA-with Holtec approved QA program.

8000.

MPC Basket NG-2000 Requires materials Materials will be suppli ed by Holtec-approved Assembly to be supplied by supplier with CMTRs in accordance with ASME-approved NG-2000 requirements.

material supplier.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-9 Design Features 3.0 DESIGN FEATURES (continued)

Table 3-1 (page 7 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM

Component Reference Code Alternative, Justification & Compensatory ASME Code Requirement Measures Section/Article MPC basket NG-4420 NG-4427(a) allows Modify the Code requirement (intended for core assembly a fillet weld in any support structures) with the following text single continuous prepared to accord with the geometry and stress weld to be less analysis imperatives for the fuel basket: For the than the specified longitudinal MPC basket fillet welds, the following fillet weld criteria apply: 1) The specified fillet weld throat dimension by not dimension must be maintained over at least 92 more than 1/16 percent of the total weld length. All regions of inch, provided that undersized weld must be less than 3 inches long the total undersize and separated from each other by at least 9 portion of the weld inches. 2) Areas of undercuts and porosity does not exceed beyond that allowed by the applicable ASME 10 percent of the Code shall not exceed 1/2 inch in weld length.

length of the weld. The total length of undercut and porosity over any Individual 1-foot length shall not exceed 2 inches. 3) The undersize weld total weld length in which items (1) and (2) apply portions shall not shall not exceed a total of 10 percent of the exceed 2 inches in overall weld length. The limited access of the length. MPC basket panel longitudinal fillet welds makes it difficult to perform effective repairs of these welds and creates the potential for causing additional damage to the basket assembly (e.g.,

to the neutron absorber and its sheathing) if repairs are attempted. The acceptance criteria provided in the foregoing have been established to comport with the objectives of the basket design and preserve the margins demonstrated in the supporting stress analysis.

From the structural standpoint, the weld acceptance criteria are established to ensure that any departure from the ideal, continuous fillet weld seam would not alter the primary bending stresses on which the design of the fuel baskets is predicated. Stated differently, the permitted weld discontinuities are limited in size to ensure that they remain classifiable as local stress elevators (peak stress, F, in the ASME Code for which specific stress intensity limits do not apply).

MPC Basket NG-8000 States The HI-STORM100 System is to be marked and Assembly requirements for identified in accordance with 10CFR71 and nameplates, 10CFR72 requirements. Code stamping is not stamping and required. The MPC basket data package to be reports per in accordance with Holtec approved QA NCA-8000. program.

OVERPACK NF-2000 Requires materials Materials will be supplied by Holtec-approved Steel to be supplied by supplier with CMTRs in accordance with Structure ASME-approved NF-2000 requirements.

material supplier.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-10 Design Features 3.0 DESIGN FEATURES (continued)

Table 3-1 (page 8 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM

Component Reference Code Alternative, Justification & Compensatory ASME Code Requirement Measures Section/Article TRANSFER NF-2000 Requires materials Materials will be supplied by Holtec-approved CASK Steel to be supplied by supplier with CMTRs in accordance with Structure ASME-approved NF-2000 requirements.

material supplier.

OVERPACK NF-4441 Requires special The margins of safety in these welds under Baseplate examinations or loads experienced during lifting operations or and Lid Top requirements for accident conditions are quite large. The Plate welds where a OVERPACK baseplate welds to the inner shell, primary member of pedestal shell, and radial plates are only loaded thickness 1 inch or during lifting conditions and have large safety greater is loaded factors during lifting. Likewise, the top lid plate to transmit loads in to lid shell weld has a large structural margin the through under the inertia loads imposed during a non-thickness mechanistic tipover event.

direction.

OVERPACK NF-3256 Provides Welds for which no structural credit is taken are Steel NF-3266 requirements for identified as Non-NF welds in the design Structure welded joints. drawings. These non-structural welds are specified in accordance with the pre-qualified welds of AWS D1.1. These welds shall be made by welders and weld procedures qualified in accordance with AWS D1.1 or ASME Section IX.

Welds for which structural credit is taken in the safety analyses shall meet the stress limits for NF-3256.2, but are not required to meet the joint configuration requirements specified in these Code articles. The geometry of the joint designs in the cask structures are based on the fabricability and accessibility of the joint, not generally contemplated by this Code section governing supports.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-11 Design Features 3.0 DESIGN FEATURES (continued)

Table 3-1 (page 9 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM

Component Reference Code Alternative, Justification & Compensatory ASME Code Requirement Measures Section/Article HI-STORM NF-3320 NF-3324.6 and These Code requirements are applicable to linear OVERPACK NF-4720 NF-4720 provide structures wherein bolted joints carry axial, and HI-requirements for shear, as well as rotational (torsional) loads. The TRAC bolting OVERPACK and TRANSFER CASK bolted TRANSFER connections in the structural load path are CASK qualified by design based on the design loadings defined in the FSAR. Bolted joints in these components see no shear or torsional loads under normal storage conditions. Larger clearances between bolts and holes may be necessary to ensure shear interfaces located elsewhere in the structure engage prior to the bolts experiencing shear loadings (which occur only during side impact scenarios).

Bolted joints that are subject to shear loads in accident conditions are qualified by appropriate stress analysis. Larger bolt-to-hole clearances help ensure more efficient operations in making these bolted connections, thereby minimizing time spent by operations personnel in a radiation area. Additionally, larger bolt-to-hole clearances allow interchangeability of the lids from one particular fabricated cask to another.

HI-STORM Section II, SA-All SA-516 material used in the HI-STORM 100 OVERPACK 516/516A Table 1 - Chemical system is required to meet the material and HI-requirements composition described in ASME Code Section TRAC II, 2007 edition. This edition allows for a TRANSFER different manganese content from the 1995 CASK edition, but does not change the structural or thermal properties of the material.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-12 Design Features 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 for the VENTILATED OVERPACK. The temperature of 70°F is the maximum average yearly temperature for the UNVENTILATED OVERPACK.

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

3. a. For storage in freestanding OVERPACKs, the resultant horizontal acceleration (vectorial sum of two horizontal Zero Period Accelerations (ZPAs) at a three-dimensional seismic site), GH, and vertical ZPA, GV, on the top surface of the ISFSI pad, expressed as fractions of g, shall satisfy the following inequality:

GH + GV where is either the Coulomb friction coefficient for the cask/ISFSI pad interface or the ratio r/h, where r is the radius of the cask and h is the height of the cask center-of-gravity above the ISFSI pad surface. The above inequality must be met for both definitions of,

but only applies to ISFSIs where the casks are deployed in a freestanding configuration. 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, GH and GV may be the coincident values of the instantaneous net horizontal and vertical accelerations. If instantaneous accelerations are used, the inequality 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.

(continued)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-13 Design Features 3.0 DESIGN FEATURES (continued)

3.4 Site-Specific Parameters and Analyses (continued)

b. For free-standing casks, 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 a cask to fall off the pad. In addition, impact between casks should be precluded, or should be considered an accident for which the maximum g-load experienced by the stored fuel shall be limited to 45 gs.

c. For those ISFSI sites with design basis seismic acceleration values that may overturn or cause excessive sliding of free-standing casks, the HI-STORM 100 System OVERPACKs shall be anchored to the ISFSI pad. The site seismic characteristics and the anchorage system shall meet the following requirements:

i. The site acceleration response spectra at the top of the ISFSI pad shall have ZPAs that meet the following inequalities:

GH 2.12 AND GV 1.5 Where:

GH is the vectorial sum of the two horizontal ZPAs at a three-dimensional seismic site (or the horizontal ZPA at a two-dimensional site) and GV is the vertical ZPA.

ii. Each HI-STORM 100 dry storage cask shall be anchored with twenty-eight (28), 2-inch diameter studs and compatible nuts of material suitable for the expected ISFSI environment. The studs shall meet the following requirements:

Yield Strength at Ambient Temperature: 80 ksi Ultimate Strength at Ambient Temperature: 125 ksi Initial Tensile Pre-Stress: 55 ksi AND 65 ksi (continued)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-14 Design Features 3.0 DESIGN FEATURES (continued)

3.4 Site-Specific Parameters and Analyses (continued)

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

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

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

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

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

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

(continued)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-15 Design Features 3.0 DESIGN FEATURES (continued)

3.4 Site-Specific Parameters and Analyses (continued)

7. 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.

8. LOADING OPERATIONS, OVERPACK TRANSPORT OPERATIONS, and UNLOADING OPERATIONS shall only be conducted with working area ambient temperatures 0o F for all MPC heat loads, and

a. 90oF (averaged over a 3-day period) for operations subjected to direct solar heating

b. 110oF (averaged over a 3-day period) for operations not subjected to direct solar heating for all MPC heat loads.

If the reference ambient temperature exceeds the corresponding Threshold Temperature then a site specific analysis shall be performed using the actual heat load and reference ambient temperature equal to the three day average to demonstrate that the steady state peak fuel cladding temperature will remain below the 400°C limit.

9. For those users whose site-specific design basis includes an event or events (e.g., flood) that result in the blockage of any OVERPACK inlet or outlet air ducts for an extended period of time (i.e, longer than the total Completion Time of LCO 3.1.2), an analysis or evaluation may be performed to demonstrate adequate heat removal is available for the duration of the event. Adequate heat removal is defined as fuel cladding temperatures remaining below the short term temperature limit. If the analysis or 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.

10. 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.

11. Site ambient temperature under HI-TRAC TRANSPORT OPERATIONS shall be evaluated in accordance with Section 3.9 requirements.

(continued)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-16 Design Features 3.0 DESIGN FEATURES (continued)

3.5 Cask Transfer Facility (CTF) 3.5.1 TRANSFER CASK and MPC Lifters Lifting of a loaded TRANSFER CASK and MPC using devices that are not integral to structures governed by 10 CFR Part 50 shall be performed with a CTF that is designed, operated, fabricated, tested, inspected, and maintained in accordance with the guidelines of NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, as applicable, and the below clarifications. The CTF Structure requirements below do not apply to heavy loads bounded by the regulations of 10 CFR Part 50 or to the loading of an OVERPACK in a belowground restraint system which permits MPC TRANSFER near grade level and does not require an aboveground CTF.

3.5.2 CTF Structure Requirements 3.5.2.1 Cask Transfer Station and Stationary Lifting Devices

1. The metal weldment structure of the CTF structure shall be designed to comply with the stress limits of ASME Section III, Subsection NF, Class 3 for linear structures. The applicable loads, load combinations, and associated service condition definitions are provided in Table 3-2. All compression loaded members shall satisfy the buckling criteria of ASME Section III, Subsection NF.

2. If a portion of the CTF structure is constructed of reinforced concrete, then the factored load combinations set forth in ACI-318 (89) for the loads defined in Table 3-2 shall apply.

3. The TRANSFER CASK and MPC lifting device used with the CTF shall be designed, fabricated, operated, tested, inspected and maintained in accordance with NUREG-0612, Section 5.1.

4. The CTF shall be designed, constructed, and evaluated to ensure that if the MPC is dropped during inter-cask transfer operations, its confinement boundary would not be breached. This requirement applies to CTFs with either stationary or mobile lifting devices.

(continued)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-17 Design Features 3.0 DESIGN FEATURES (continued)

3.5 Cask Transfer Facility (CTF) (continued) 3.5.2.2 Mobile Lift Devices If a mobile lifting device is used as the lifting device, in lieu of a stationary lifting device, it shall meet the guidelines of NUREG-0612, Section 5.1, with the following clarifications:

1. Mobile lifting devices shall have a minimum safety factor of two over the allowable load table for the lifting device in accordance with the guidance of NUREG-0612, Section 5.1.6(1)(a) and shall be capable of stopping and holding the load during a Design Basis Earthquake (DBE) event.

2. Mobile lifting devices shall conform to meet the requirements of ANSI B30.5, Mobile and Locomotive Cranes, in lieu of the requirements of ANSI B30.2, Overhead and Gantry Cranes.

3. Mobile cranes are not required to meet the requirements of NUREG-0612, Section 5.1.6(2) for new cranes.

4. Horizontal movements of the TRANSFER CASK and MPC using a mobile crane are prohibited.

(continued)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-18 Design Features 3.0 DESIGN FEATURES (continued)

3.5 Cask Transfer Facility (CTF)(continued)

Table 3-2 Load Combinations and Service Condition Definitions for the CTF Structure (Note 1)

Load Combination ASME III Service Condition Comment for Definition of Allowable Stress D* Level A All primary load bearing members must satisfy Level A D + S stress limits D + M + W (Note 2)

D + F Level D Factor of safety against overturning shall be 1.1 D + E

D + Y

D = Dead load D* = Apparent dead load S = Snow and ice load for the CTF site M = Tornado missile load for the CTF site W = Tornado wind load for the CTF site F = Flood load for the CTF site E = Seismic load for the CTF site Y = Tsunami load for the CTF site Notes: 1. The reinforced concrete portion of the CTF structure shall also meet the factored combinations of loads set forth in ACI-318(89).

2. Tornado missile load may be reduced or eliminated based on a PRA for the CTF site.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-19 Design Features 3.0 DESIGN FEATURES (continued)

3.6 Forced Helium Dehydration System 3.6.1 System Description Use of a forced helium dehydration (FHD) system, (a closed-loop system) is an alternative to vacuum drying the MPC for moderate burnup fuel (

45,000 MWD/MTU) with lower MPC heat load and for drying MPCs containing one or more high burnup fuel assemblies or higher MPC heat loads as indicated in Appendix A Table 3-1. The FHD system shall be designed for normal operation (i.e., excluding startup and shutdown ramps) in accordance with the criteria in Section 3.6.2.

3.6.2 Design Criteria 3.6.2.1 The temperature of the helium gas in the MPC shall be at least 15oF higher than the saturation temperature at coincident pressure.

3.6.2.2 The pressure in the MPC cavity space shall be 60.3 psig (75 psia) during drying. Backfill pressures shall be as described in Appendix A.

3.6.2.3 The hourly recirculation rate of helium shall be 10 times the nominal helium mass backfilled into the MPC for fuel storage operations.

3.6.2.4 The partial pressure of the water vapor in the MPC cavity will not exceed 3 torr. The limit is met if the gas temperature at the demoisturizer outlet is verified by measurement to remain 21oF for a period of 30 minutes or if the dew point of the gas exiting the MPC is verified by measurement to remain 22.9oF for 30 minutes.

3.6.2.5 The condensing module shall be designed to de-vaporize the recirculating helium gas to a dew point 120oF.

3.6.2.6 The demoisturizing module shall be configured to be introduced into its helium conditioning function after the condensing module has been operated for the required length of time to assure that the bulk moisture vaporization in the MPC (defined as Phase 1 in FSAR Appendix 2.B) has been completed.

3.6.2.7 The helium circulator shall be sized to effect the minimum flow rate of circulation required by these design criteria.

3.6.2.8 The pre-heater module shall be engineered to ensure that the temperature of the helium gas in the MPC meets these design criteria.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-20 Design Features 3.0 DESIGN FEATURES (continued)

3.6 Forced Helium Dehydration System (continued) 3.6.3 Fuel Cladding Temperature A steady-state thermal analysis of the MPC under the forced helium flow scenario shall be performed using the methodology described in HI-STORM 100 FSAR Section 4.4, with due recognition of the forced convection process during FHD system operation. This analysis shall demonstrate that the peak temperature of the fuel cladding, under the most adverse condition of FHD system operation, is below the peak cladding temperature limit for normal conditions of storage for the applicable fuel type (PWR or BWR) and cooling time at the start of dry storage.

3.6.4 Pressure Monitoring During FHD Malfunction During an FHD malfunction event, described in HI-STORM 100 FSAR Chapter 11 as a loss of helium circulation, the system pressure must be monitored to ensure that the conditions listed therein are met.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-21 Design Features 3.0 DESIGN FEATURES (continued)

3.7 Supplemental Cooling System 3.7.1 System Description A supplemental cooling system (SCS) is an external system for cooling the MPC inside the HI-TRAC transfer cask during on-site transport. The SCS is required for transport of high burnup fuel under certain heat load conditions defined in Table 3-3. The SCS shall be designed for normal operation (i.e., excluding startup and shutdown ramps) in accordance with the criteria in Section 3.7.2.

3.7.2 Design Criteria 3.7.2.1 Not Used.

3.7.2.2 If water is used as the coolant, the system shall be sized to limit the coolant temperature to below 180ºF under steady-state conditions for the design basis heat load at an ambient air temperature of 110ºF. Any electric motors shall have a backup power supply for uninterrupted operation.

3.7.2.3 The system shall utilize a contamination-free fluid medium in contact with the external surfaces of the MPC and inside surfaces of the HI -TRAC transfer cask to minimize corrosion.

3.7.2.4 All passive components such as tubular heat exchangers, manually operated valves and fittings shall be designed to applicable standards (TEMA, ANSI).

3.7.2.5 The heat dissipation capacity of the SCS shall be equal to or greater than the minimum necessary to ensure that the peak cladding temperature is below 400ºC (752ºF). All heat transfer surfaces in heat exchangers shall be assumed to be fouled to the maximum limits specified in a widely used heat exchange equipment standard such as the Standards of Tubular Exchanger Manufacturers Association.

3.7.2.6 The coolant utilized to extract heat from the MPC shall be high purity water or air. Antifreeze may be used to prevent water from freezing if warranted by operating conditions. (continued)

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-22 Design Features 3.0 DESIGN FEATURES (continued)

3.7 Supplemental Cooling System (continued) 3.7.2.7 All pressure boundaries (as defined in the ASME Boiler and Pressure Vessel Code,Section VIII Division 1) shall have pressure ratings that are greater than the maximum system operating pressure by at least 15 psi.

3.7.2.8 All ASME Code components shall comply with Section VIII Division 1 of the ASME Boiler and Pressure Vessel Code.

3.7.2.9 All gasketed and packed joints shall have a minimum design pressure rating of the pump shut-off pressure plus 15 psi.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-23 Design Features 3.0 DESIGN FEATURES (continued)

Table 3-3 Requirements for Supplemental Cooling System

Criteria for use of SCS Requirement

MPC-68M Not required

MPC containing one or more high Burnup fuel assemblies (> 45,000 MWD/MTU) and Yes Heat loads more than 90% of maximum permissible heat loads defined in Section 2.4 under higher helium backfill limits in Table 3-2 of Appendix A

MPC containing one or more high Burnup Yes fuel assemblies (> 45,000 MWD/MTU) and Heat loads more than 90% of heat load limits in Tables 3-3 or 3-4 of Appendix A under lower helium backfill limits in Table 3-2 of Appendix A

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-24 Design Features 3.0 DESIGN FEATURES (continued)

3.8 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.

3.9 Environmental Temperature Requirements TRANSPORT OPERATIONS operations involving the HI-TRAC transfer cask can be carried out if the reference ambient temperature (three day average around the cask) is above 0°F and below the Threshold Temperature of 110 deg. F ambient temperature, applicable during HI-TRAC transfer operations inside the 10 CFR Part 50 or 10 CFR Part 52 structural boundary and 90 deg. F outside of it. The determination of the Threshold Temperature compliance shall be made based on the best available thermal data for the site.

If the reference ambient temperature exceeds the corresponding Threshold Temperature then a site specific analysis shall be performed using the actual heat load and reference ambient temperature equal to the three day average to ensure that the steady state peak fuel cladding temperature will remain below the 400°C limit. If the peak fuel cladding temperature exceeds 400°C limit then the operation of a Supplemental Cooling System (SCS) in accordance with LCO 3.1.4 is mandatory.

SCS operation is mandatory if site data is not available or if a user elects to deploy Supplemental Cooling in lieu of site ambient temperature evaluation.

Certificate of Compliance No. 1014 Renewed Amendment No. 18 Appendix B 3-25

v t e Letter Sequence Other
CAC:001208, (Approved, Closed) EPID:L-2022-LLA-0002, International, Submittal of HI-STORM 100 Request for Amendment 18 (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance, Acceptance, Acceptance, Acceptance, Acceptance Supplement Administration Questions 30 June 2022 7 December 2022 7 December 2022 6 December 2023 6 December 2023 Answers Results Approval, Approval, Approval, Approval, Approval Other: ML20295A413, ML20295A415, ML20295A416, ML20295A417, ML20295A418, ML20295A419, ML20295A420, ML20295A421, ML20329A323, ML21118A864, ML21118A865, ML21118A866, ML21118A867, ML21118A868, ML21118A869, ML21118A870, ML21168A352, ML21168A353, ML21168A354, ML21168A355, ML21168A356, ML21168A357, ML21168A358, ML21168A359, ML21168A361, ML21168A362, ML21168A363, ML21168A364, ML21237A177, ML23074A102, ML23234A135, ML23317A123, ML24010A058, ML24010A061, ML24095A040, ML24095A041, ML24095A042, ML24095A043, ML24095A044, ML24095A045, ML24095A046, ML24095A047, ML24178A113, ML24179A273
MONTHYEAR2021-12-15 [Table View]

ML24095A043

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