ML22098A237

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Proposed Renewed Certificate of Compliance No. 1014, Appendix B: Technical Specifications for the HI-STORM 100 Cask System Amendment No. 0
ML22098A237
Person / Time
Site: Holtec
Issue date: 01/31/2023
From:
Division of Fuel Management
To:
Kris Banovac NMSS/DFM/STLB 301-415-7116
Shared Package
ML22098A233 List: ... further results
References
CAC 001028, EPID L-2020-RNW-0007 NRC-2022-0109, RIN 3150-AK86
Download: ML22098A237 (1)
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Text

RENEWED CERTIFICATE OF COMPLIANCE NO. 1014

APPENDIX B

APPROVED CONTENTS AND DESIGN FEATURES

FOR THE HI-STORM 100 CASK SYSTEM

AMENDMENT NO. 0 TABLE OF CONTENTS

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

2.0 APPROVED CONTENTS.............................................................................................2-1

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.......................................................................................3-1 3.4 Site Specific Parameters and Analyses...........................................................3-8 3.5 Cask Transfer Facility (CTF)............................................................................3-11

Table 3-1 List of ASME Code Exceptions for HI-STORM 100 System............................3-3 Table 3-2 Representative DBE Acceleration Values to Prevent HI-STORM 100 Sliding (/G46= 0.53)........................................................3-8 Table 3-3 Load Combinations and Service Condition Definitions for the CTF Structure..........................................................................3-13

Certificate of Compliance No. 1014 Renewed Amendment No. 0 Appendix B i Definitions 1.0

1.0 Definitions

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

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition

CASK TRANSFER FACILITY The CASK TRANSFER FACILITY includes the (CTF) following components and equipment: (1) a Cask Transfer Structure used to stabilize the TRANSFER CASK and MPC during lifts involving spent fuel not bounded by the regulations of 10 CFR Part 50, and (2) Either a stationary lifting device or a mobile lifting device used in concert with the stationary structure to lift the OVERPACK, TRANSFER CASK and MPC

DAMAGED FUEL ASSEMBLY DAMAGED FUEL ASSEMBLIES are fuel assemblies with known or suspected cladding defects, as determined by a review of records, greater than pinhole leaks or hairline cracks, missing fuel rods that are not replaced with dummy fuel rods, or those that cannot be handled by normal means. Fuel assemblies which cannot be handled by normal means due to fuel cladding damage are considered FUEL DEBRIS.

DAMAGED FUEL CONTAINER DFCs are specially designed enclosures for (DFC) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS which permit gaseous and liquid media to escape while minimizing dispersal of gross particulates.

FUEL DEBRIS FUEL DEBRIS is ruptured fuel rods, severed rods, loose fuel pellets or fuel assemblies with known or suspected defects which cannot be handled by normal means due to fuel cladding damage.

Certificate of Compliance No. 1014 Renewed Amendment No. 0 Appendix B 1-1 Definitions 1.0 1.0 Definitions (continued)

INTACT FUEL ASSEMBLY INTACT FUEL ASSEMBLIES are fuel assemblies without known or suspected cladding defects greater than pinhole leaks or hairline cracks and which can be handled by normal means. Partial fuel assemblies, that is fuel assemblies from which fuel rods are missing, shall not be classified as INTACT FUEL ASSEMBLIES unless dummy fuel rods are used to displace an amount of water greater than or equal to that displaced by the original fuel rod(s).

LOADING OPERATIONS LOADING OPERATIONS include all licensed activities on an OVERPACK or TRANSFER CASK while it is being loaded with fuel assemblies. LOADING OPERATIONS begin when the first fuel assembly is placed in the MPC and end when the OVERPACK or TRANSFER CASK is suspended from or secured on the transporter. LOADING OPERATIONS does not include MPC transfer between the TRANSFER CASK and the OVERPACK.

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

OVERPACK OVERPACKs are the casks which receive and contain the sealed MPCs for interim storage on the ISFSI. They provide gamma and neutron shielding, and provide for ventilated air flow to promote heat transfer from the MPC to the environs. The OVERPACK does not include the TRANSFER CASK.

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

(continued)

Certificate of Compliance No. 1014 Renewed Amendment No. 0 Appendix B 1-2 Definitions 1.0

1.0 Definitions (continued)

SPENT FUEL STORAGE An SFSC is a container approved for the storage CASK (SFSC) of spent fuel assemblies at the ISFSI. The HI-STORM 100 SFSC System consists of the OVERPACK and its integral MPC

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

TRANSPORT OPERATIONS TRANSPORT OPERATIONS include all licensed activities performed on an OVERPACK or TRANSFER CASK loaded with one or more fuel assemblies when it is being moved to and from the ISFSI. TRANSPORT OPERATIONS begin when the OVERPACK or TRANSFER CASK is first suspended from or secured on the transporter and end when the OVERPACK or TRANSFER CASK is at its destination and no longer secured on or suspended from the transporter. TRANSPORT OPERATIONS includes transfer of the MPC between the OVERPACK and the TRANSFER CASK.

UNLOADING OPERATIONS UNLOADING OPERATIONS include all licensed activities on an SFSC to be unloaded of the contained fuel assemblies. UNLOADING OPERATIONS begin when the OVERPACK or TRANSFER CASK is no longer suspended from or secured on the transporter and end when the last fuel assembly is removed from the SFSC.

UNLOADING OPERATIONS does not include MPC transfer between the TRANSFER CASK and the OVERPACK.

Certificate of Compliance No. 1014 Renewed Amendment No. 0 Appendix B 1-3 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, DAMAGED FUEL ASSEMBLIES, and FUEL DEBRIS meeting the limits specified in Table 2.1-1 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 DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, all remaining Zircaloy clad INTACT FUEL ASSEMBLIES in the MPC shall meet the decay heat generation limits for the DAMAGED FUEL ASSEMBLIES.
d. For MPC-68's partially loaded with array/class 6x6A, 6x6B, 6x6C, or 8x8A fuel assemblies, all remaining Zircaloy clad INTACT FUEL ASSEMBLIES in the MPC shall meet the decay heat generation limits for the 6x6A, 6x6B, 6x6C, and 8x8A fuel assemblies.

2.1.2 Preferential Fuel Loading

Preferential fuel loading shall be used whenever fuel assemblies with significantly different post-irradiation cooling times (>1 year) are to be loaded in the same MPC. Fuel assemblies with the longest post-irradiation cooling times shall be loaded into fuel storage locations at the periphery of the basket. Fuel assemblies with shorter post-irradiation cooling times shall be placed toward the center of the basket.

(continued)

Certificate of Compliance No. 1014 Appendix B 2-1 Approved Contents 2.0

2.0 Approved Contents (continued)

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

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

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

Table 2.1-1 (page 1 of 15)

Fuel Assembly Limits

I. MPC MODEL: MPC-24

A. Allowable Contents

1. Uranium oxide, PW R INTACT FUEL ASSEMBLIES listed in Table 2.1-2 and meeting the following specifications:
a. Cladding Type: Zircaloy (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. Zr Clad: An assembly post-irradiation cooling time and average burnup as specified in Table 2.1-4.

ii. SS Clad: An assembly post-irradiation cooling time

> 8 years and an average burnup <

40,000 MW D/MTU.

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

Table 2.1-1 (page 2 of 15)

Fuel Assembly Limits

I. MPC MODEL: MPC-24 (continued)

d. Decay Heat Per Assembly
i. Zr Clad An assembly decay heat as specified in Table 2.1-5 for the applicable post-irradiation cooling time

ii. SS Clad < 710 W atts

e. Fuel Assembly Length <176.8 inches (nominal design)
f. Fuel Assembly W idth <8.54 inches (nominal design)
g. Fuel Assembly W eight <1,680 lbs

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

C. Fuel assemblies shall not contain control components.

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

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

Table 2.1-1 (page 3 of 15)

Fuel Assembly Limits

II. MPC MODEL: MPC-68

A. Allowable Contents

1. Uranium oxide, BW R INTACT FUEL ASSEMBLIES listed in Table 2.1-3, with or without Zircaloy channels, and meeting the following specifications:
a. Cladding Type: Zircaloy (Zr) or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array/class.
b. Maximum PLANAR-As specified in Table 2.1-3 for the AVERAGE INITIAL applicable fuel assembly array/class.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment: applicable fuel assembly array/class.
d. Post-irradiation Cooling Time and Average Burnup Per Assembly
i. Zr Clad: An assembly post-irradiation cooling time and average burnup as specified in Table 2.1-4, except for array/class 6x6A, 6x6C, and 8x8A fuel assemblies, which shall have a cooling time > 18 years and an average burnup < 30,000 MW D/MTU.

ii. SS Clad: An assembly cooling time after discharge

> 10 years and an average burnup <

22,500 MW D/MTU.

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

Table 2.1-1 (page 4 of 15)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

e. Decay Heat Per Assembly
i. Zr Clad An assembly decay heat as specified in Table 2.1-5 for the applicable post-irradiation cooling time, except for array/class 6x6A, 6x6C, and 8x8A fuel assemblies, which shall have a decay heat < 115 W atts.

ii. SS Clad < 95 W atts

f. Fuel Assembly Length <176.2 inches (nominal design)
g. Fuel Assembly W idth <5.85 inches (nominal design)
h. Fuel Assembly W eight <700 lbs, including channels

Certificate of Compliance No. 1014 Appendix B 2-6 Approved Contents 2.0

Table 2.1-1 (page 5 of 15)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

2. Uranium oxide, BW R DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide BW R 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: Zircaloy (Zr)
b. Maximum PLANAR-As specified in Table 2.1-3 for the AVERAGE INITIAL applicable fuel assembly array/class.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment: applicable fuel assembly array/class.
d. Post-irradiation Cooling An assembly post-irradiation cooling time Time and Average Burnup > 18 years and an average burnup <

Per Assembly: 30,000 MW D/MTU.

e. Decay Heat Per Assembly <115 W atts
f. Fuel Assembly Length: <135.0 inches (nominal design)
g. Fuel Assembly W idth: <4.70 inches (nominal design)
h. Fuel Assembly W eight: <400 lbs, including channels

Certificate of Compliance No. 1014 Appendix B 2-7 Approved Contents 2.0

Table 2.1-1 (page 6 of 15)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

3. Mixed oxide (MOX), BW R INTACT FUEL ASSEMBLIES, with or without Zircaloy channels. MOX BW R 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: Zircaloy (Zr)
b. Maximum PLANAR-As specified in Table 2.1-3 for fuel AVERAGE INITIAL assembly array/class 6x6B.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 2.1-3 for fuel Enrichment: assembly array/class 6x6B.
d. Post-irradiation Cooling An assembly post-irradiation cooling time Time and Average Burnup > 18 years and an average burnup <

Per Assembly: 30,000 MW D/MTIHM.

e. Decay Heat Per Assembly <115 W atts
f. Fuel Assembly Length: <135.0 inches (nominal design)
g. Fuel Assembly W idth: <4.70 inches (nominal design)
h. Fuel Assembly W eight: <400 lbs, including channels

Certificate of Compliance No. 1014 Appendix B 2-8 Approved Contents 2.0

Table 2.1-1 (page 7 of 15)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

4. Mixed oxide (MOX), BW R DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. MOX BW R 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: Zircaloy (Zr)
b. Maximum PLANAR-As specified in Table 2.1-3 for array/class AVERAGE INITIAL 6x6B.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 2.1-3 for array/class Enrichment: 6x6B.
d. Post-irradiation Cooling An assembly post-irradiation cooling time Time and Average Burnup > 18 years and an average burnup <

Per Assembly: 30,000 MW D/MTIHM.

e. Decay Heat Per Assembly <115 W atts
f. Fuel Assembly Length: <135.0 inches (nominal design)
g. Fuel Assembly W idth: <4.70 inches (nominal design)
h. Fuel Assembly W eight: <400 lbs, including channels

Certificate of Compliance No. 1014 Appendix B 2-9 Approved Contents 2.0

Table 2.1-1 (page 8 of 15)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

B. Quantity per MPC: Any combination of DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS and INTACT FUEL ASSEMBLIES up to a total of 68.

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

Certificate of Compliance No. 1014 Appendix B 2-10 Approved Contents 2.0

Table 2.1-1 (page 9 of 15)

Fuel Assembly Limits

III. MPC MODEL: MPC-68F

A. Allowable Contents

1. Uranium oxide, BW R INTACT FUEL ASSEMBLIES, with or without Zircaloy channels. Uranium oxide BW R INTACT FUEL ASSEMBLIES shall meet the criteria in Table 2.1-3 for fuel assembly array class 6x6A, 6x6C, 7x7A or 8x8A, and meet the following specifications:
a. Cladding Type: Zircaloy (Zr)
b. Maximum PLANAR-As specified in Table 2.1-3 for the AVERAGE INITIAL applicable fuel assembly array/class.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment: applicable fuel assembly array/class.
d. Post-irradiation Cooling An assembly post-irradiation cooling time Time and Average Burnup > 18 years and an average burnup <

Per Assembly: 30,000 MW D/MTU.

e. Decay Heat Per Assembly <115 W atts
f. Fuel Assembly Length: <176.2 inches (nominal design)
g. Fuel Assembly W idth: <5.85 inches (nominal design)
h. Fuel Assembly W eight: <700 lbs, including channels

Certificate of Compliance No. 1014 Appendix B 2-11 Approved Contents 2.0

Table 2.1-1 (page 10 of 15)

Fuel Assembly Limits

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

2. Uranium oxide, BW R DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide BW R 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: Zircaloy (Zr)
b. Maximum PLANAR-As specified in Table 2.1-3 for the AVERAGE INITIAL applicable fuel assembly array/class.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment: applicable fuel assembly array/class.
d. Post-irradiation Cooling A post-irradiation cooling time after Time and Average Burnup discharge > 18 years and an average Per Assembly: burnup < 30,000 MW D/MTU.
e. Decay Heat Per Assembly <115 W atts
f. Fuel Assembly Length: <135.0 inches (nominal design)
g. Fuel Assembly W idth: <4.70 inches (nominal design)
h. Fuel Assembly W eight: <400 lbs, including channels

Certificate of Compliance No. 1014 Appendix B 2-12 Approved Contents 2.0

Table 2.1-1 (page 11 of 15)

Fuel Assembly Limits

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

3. Uranium oxide, BW R FUEL DEBRIS, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the uranium oxide BW R 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: Zircaloy (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 As specified in Table 2.1-3 for the Enrichment: applicable original fuel assembly array/class.
d. Post-irradiation Cooling Time A post-irradiation cooling time after and Average Burnup Per discharge > 18 years and an average Assembly burnup < 30,000 MW D/MTU for the original fuel assembly.
e. Decay Heat Per Assembly <115 W atts
f. Original Fuel Assembly Length <135.0 inches (nominal design)
g. Original Fuel Assembly W idth <4.70 inches (nominal design)
h. Fuel Debris W eight <400 lbs, including channels

Certificate of Compliance No. 1014 Appendix B 2-13 Approved Contents 2.0

Table 2.1-1 (page 12 of 15)

Fuel Assembly Limits

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

4. Mixed oxide (MOX), BW R INTACT FUEL ASSEMBLIES, with or without Zircaloy channels. MOX BW R 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: Zircaloy (Zr)
b. Maximum PLANAR-As specified in Table 2.1-3 for fuel AVERAGE INITIAL assembly array/class 6x6B.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 2.1-3 for fuel Enrichment: assembly array/class 6x6B.
d. Post-irradiation Cooling An assembly post-irradiation cooling time Time and Average Burnup after discharge >18 years and an Per Assembly: average burnup < 30,000 MW D/MTIHM.
e. Decay Heat Per Assembly <115 W atts
f. Fuel Assembly Length: <135.0 inches (nominal design)
g. Fuel Assembly W idth: <4.70 inches (nominal design)
h. Fuel Assembly W eight: <400 lbs, including channels

Certificate of Compliance No. 1014 Appendix B 2-14 Approved Contents 2.0

Table 2.1-1 (page 13 of 15)

Fuel Assembly Limits

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

5. Mixed oxide (MOX), BW R DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. MOX BW R 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: Zircaloy (Zr)
b. Maximum PLANAR-As specified in Table 2.1-3 for fuel AVERAGE INITIAL assembly array/class 6x6B.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 2.1-3 for fuel Enrichment: assembly array/class 6x6B.
d. Post-irradiation Cooling A post-irradiation cooling time after Time and Average Burnup discharge > 18 years and an average Per Assembly: burnup < 30,000 MW D/MTIHM.
e. Decay Heat Per Assembly <115 W atts
f. Fuel Assembly Length: <135.0 inches (nominal design)
g. Fuel Assembly W idth: <4.70 inches (nominal design)
h. Fuel Assembly W eight: <400 lbs, including channels

Certificate of Compliance No. 1014 Appendix B 2-15 Approved Contents 2.0

Table 2.1-1 (page 14 of 15)

Fuel Assembly Limits

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

6. Mixed Oxide (MOX), BW R FUEL DEBRIS, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the MOX BW R 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: Zircaloy (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 As specified in Table 2.1-3 for original Enrichment: fuel assembly array/class 6x6B.
d. Post-irradiation Cooling Time A post-irradiation cooling time after and Average Burnup Per discharge > 18 years and an average Assembly: burnup < 30,000 MW D/MTIHM for the original fuel assembly.
e. Decay Heat Per Assembly <115 W atts
f. Original Fuel Assembly Length: <135.0 inches (nominal design)
g. Original Fuel Assembly W idth: <4.70 inches (nominal design)
h. Fuel Debris W eight: <400 lbs, including channels

Certificate of Compliance No. 1014 Appendix B 2-16 Approved Contents 2.0

Table 2.1-1 (page 15 of 15)

Fuel Assembly Limits

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

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

Up to four (4) DFCs containing uranium oxide BW R FUEL DEBRIS or MOX BW R FUEL DEBRIS. The remaining MPC-68F fuel storage locations may be filled with array/class 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A fuel assemblies of the following type, as applicable:

1. Uranium oxide BW R INTACT FUEL ASSEMBLIES;
2. MOX BW R INTACT FUEL ASSEMBLIES;
3. Uranium oxide BW R DAMAGED FUEL ASSEMBLIES placed in DFCs; or
4. MOX BW R DAMAGED FUEL ASSEMBLIES placed in DFCs.

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

Certificate of Compliance No. 1014 Appendix B 2-17 Approved Contents 2.0

Table 2.1-2 (page 1 of 4)

PW R FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 14x14A 14x14B 14x14C 14x14D 15x15A Array/Class

Clad Material (Note 2) Zr Zr Zr SS Zr

Design Initial U < 402 <402 <410 <400 <420 (kg/assy.) (Note 3)

Initial Enrichment < 4.6 <4.6 <4.6 <4.0 <4.1 (wt % 235U)

No. of Fuel Rods 179 179 176 180 204

Clad O.D. (in.) >0.400 >0.417 >0.440 >0.422 >0.418

Clad I.D. (in.) <0.3514 <0.3734 <0.3840 <0.3890 <0.3660

Pellet Dia. (in.) <0.3444 <0.3659 <0.3770 <0.3835 <0.3580

Fuel Rod Pitch (in.) <0.556 < 0.556 <0.580 <0.556 <0.550

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

No. of Guide Tubes 17 17 5 (Note 4) 16 21

Guide Tube Thickness > 0.017 >0.017 >0.040 >0.0145 >0.0165 (in.)

Certificate of Compliance No. 1014 Appendix B 2-182-18 Approved Contents 2.0

Table 2.1-2 (page 2 of 4)

PW R FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

Clad Material (Note 2) Zr Zr Zr Zr Zr

Design Initial U < 464 <464 <475 <475 <475 (kg/assy.) (Note 3)

Initial Enrichment < 4.1 <4.1 <4.1 <4.1 <4.1 (wt % 235U)

No. of Fuel Rods 204 204 208 208 208

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

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

Pellet Dia. (in.) <0.3671 <0.3570 <0.3735 <0.3707 <0.3742

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

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

No. of Guide Tubes 21 21 17 17 17

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

Certificate of Compliance No. 1014 Appendix B 2-192-19 Approved Contents 2.0

Table 2.1-2 (page 3 of 4)

PW R FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 15x15G 16x16A 17x17A 17x17B 17x17C Array/ Class

Clad Material (Note 2) SS Zr Zr Zr Zr

Design Initial U < 420 <430 <450 <464 <460 (kg/assy.) (Note 3)

Initial Enrichment < 4.0 <4.6 <4.0 <4.0 <4.0 (wt % 235U)

No. of Fuel Rods 204 236 264 264 264

Clad O.D. (in.) >0.422 >0.382 >0.360 >0.372 >0.377

Clad I.D. (in.) <0.3890 <0.3320 <0.3150 <0.3310 <0.3330

Pellet Dia. (in.) <0.3825 <0.3255 <0.3088 <0.3232 <0.3252

Fuel Rod Pitch (in.) <0.563 < 0.506 <0.496 <0.496 <0.502

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

No. of Guide Tubes 21 5 (Note 4) 25 25 25

Guide Tube Thickness > 0.0145 >0.0400 >0.016 >0.014 >0.020 (in.)

Certificate of Compliance No. 1014 Appendix B 2-20 Approved Contents 2.0

Table 2.1-2 (page 4 of 4)

PW R 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. Zr designates cladding material made of zirconium or zirconium alloys.
3. Design initial uranium weight is the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each PW R fuel assembly, the total initial uranium weight may be up to 2.0 percent higher than the design initial uranium weight due to manufacturer tolerances.
4. Each guide tube replaces four fuel rods.

Certificate of Compliance No. 1014 Appendix B 2-21 Approved Contents 2.0

Table 2.1-3 (page 1 of 5)

BW R FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 6x6A 6x6B 6x6C 7x7A 7x7B 8x8A Array/Class

Clad Material (Note 2) Zr Zr Zr Zr Zr Zr

Design Initial U < 108 <108 <108 <100 <195 <120 (kg/assy.) (Note 3)

Maximum PLANAR- < 2.7 <2.7 for the < 2.7 <2.7 <4.2 <2.7 AVERAGE INITIAL UO 2 rods.

ENRICHMENT SeeNote4 (wt.% 235U) for MOX rods

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

No. of Fuel Rods 36 36 (up to 9 36 49 49 64 MOX rods)

Clad O.D. (in.) > 0.5550 > 0.5625 >0.5630 > 0.4860 > 0.5630 > 0.4120

Clad I.D. (in.) <0.4945 <0.4945 <0.4990 <0.4200 < 0.4990 < 0.3620

Pellet Dia. (in.) <0.4940 < 0.4820 <0.4880 < 0.4110 < 0.4880 < 0.3580

Fuel Rod Pitch (in.) <0.694 < 0.694 <0.740 <0.631 <0.738 <0.523

Active Fuel Length < 110 <110 <77.5 <79 <150 <110 (in.)

No. of W ater Rods 0 0 0 0 0 0

W ater Rod Thickness N/A N/A N/A N/A N/A N/A (in.)

Channel Thickness < 0.060 <0.060 <0.060 <0.060 <0.120 <0.100 (in.)

Certificate of Compliance No. 1014 Appendix B 2-22 Approved Contents 2.0

Table 2.1-3 (2 of 5)

BW R FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 8x8B 8x8C 8x8D 8x8E 9x9A 9x9B Array/Class

Clad Material (Note 2) Zr Zr Zr Zr Zr Zr

Design Initial U < 185 <185 <185 <180 <173 <173 (kg/assy.) (Note 3)

Maximum PLANAR- < 4.2 <4.2 <4.2 <4.2 <4.2 <4.2 AVERAGE INITIAL ENRICHMENT (wt.% 235U)

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

No. of Fuel Rods 63 62 60 59 74/6672 (Note 5)

Clad O.D. (in.) >0.4840 >0.4830 >0.4830 >0.4930 >0.4400 >0.4330

Clad I.D. (in.) <0.4250 <0.4250 <0.4190 <0.4250 <0.3840 <0.3810

Pellet Dia. (in.) <0.4160 <0.4160 <0.4110 <0.4160 <0.3760 <0.3740

Fuel Rod Pitch (in.) <0.641 < 0.641 <0.640 <0.640 <0.566 <0.569

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

No. of W ater Rods 1 2 1 - 4521(Note7)

(Note 6)

W ater Rod Thickness > 0.034 > 0.00 > 0.00 >0.034 > 0.00 > 0.00 (in.)

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

Certificate of Compliance No. 1014 Appendix B 2-23 Approved Contents 2.0

Table 2.1-3 (page 3 of 5)

BW R FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 9x9C 9x9D 9x9E 9x9F 10x10A Array/Class

Clad Material (Note 2) Zr Zr Zr Zr Zr

Design Initial U < 173 <170 <170 <170 <182 (kg/assy.) (Note 3)

Maximum PLANAR- < 4.2 <4.2 <4.2 <4.2 <4.2 AVERAGE INITIAL ENRICHMENT (wt.% 235U)

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

No. of Fuel Rods 80 79 76 76 92/78 (Note 8)

Clad O.D. (in.) >0.4230 >0.4240 >0.4170 >0.4430 >0.4040

Clad I.D. (in.) <0.3640 <0.3640 <0.3590 <0.3810 <0.3520

Pellet Dia. (in.) <0.3565 <0.3565 <0.3525 <0.3745 <0.3455

Fuel Rod Pitch (in.) <0.572 < 0.572 <0.572 <0.572 <0.510

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

No. of W ater Rods 1 2 5 5 2

W ater Rod Thickness > 0.020 >0.0305 >0.0305 >0.0305 >0.0300 (in.)

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

Certificate of Compliance No. 1014 Appendix B 2-24 Approved Contents 2.0

Table 2.1-3 (page 4 of 5)

BW R FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 10x10B 10x10C 10x10D 10x10E

Clad Material (Note 2) Zr Zr SS SS

Design Initial U (kg/assy.) < 182 <180 <125 <125 (Note 3)

Maximum PLANAR-AVERAGE < 4.2 <4.2 <4.0 <4.0 INITIAL ENRICHMENT (wt.% 235U)

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

No. of Fuel Rods 91/83 96 100 96 (Note 9)

Clad O.D. (in.) >0.3957 >0.3790 >0.3960 >0.3940

Clad I.D. (in.) <0.3480 <0.3294 <0.3560 <0.3500

Pellet Dia. (in.) <0.3420 <0.3224 <0.3500 <0.3430

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

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

No. of W ater Rods 1 (Note 7) 5 (Note 10) 0 4

W ater Rod Thickness (in.) > 0.00 > 0.034 N/A >0.022

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

Certificate of Compliance No. 1014 Appendix B 2-25 Approved Contents 2.0

Table 2.1-3 (page 5 of 5)

BW R 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. Zr designates cladding material made of zirconium or zirconium alloys.
3. Design initial uranium weight is the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each BW R fuel assembly, the total initial uranium weight may be up to 1.5 percent higher than the design initial uranium weight due to manufacturer tolerances.
4. <0.612 wt. % 235U and <1.578 wt. % total fissile plutonium (239Pu and 241Pu).
5. This assembly class contains 74 total rods; 66 full length rods and 8 partial length rods.
6. Variable.
7. Square, replacing nine fuel rods.
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.

Certificate of Compliance No. 1014 Appendix B 2-26 Approved Contents 2.0

Table 2.1-4

FUEL ASSEMBLY COOLING AND AVERAGE BURNUP (Note 1)

Post-irradiation MPC-24 MPC-68 Cooling Time PWR Assembly BWR Assembly (years) Burnup Burnup (MWD/MTU) (MWD/MTU)

> 5< 31,300 <29,900

> 6< 35,400 <32,800

> 7< 35,600 <33,100

> 8< 37,700 <35,200

> 9< 39,400 <36,600

> 10 <40,600 <37,800

> 11 <41,700 <38,700

> 12 <42,600 <39,600

> 13 <43,400 <40,400

> 14 <44,100 <41,100

> 15 <44,700 <41,700

Note 1: Linear interpolation between points is permitted.

Certificate of Compliance No. 1014 Appendix B 2-27 Approved Contents 2.0

Table 2.1-5

FUEL ASSEMBLY COOLING AND DECAY HEAT (Note 1)

Post-irradiation MPC-24 MPC-68 Cooling Time PWR Assembly BWR Assembly (years) Decay Heat Decay Heat (Watts) (Watts)

> 5< 870.0 <314.7

> 6< 840.4 <298.7

> 7< 757.5 <270.7

> 8< 751.1 <268.5

> 9< 744.7 <266.2

> 10 <738.3 <264.0

> 11 <733.8 <262.5

> 12 <729.2 <261.0

> 13 <724.5 <259.6

> 14 <720.0 <258.1

> 15 <715.4 <256.6

Note 1: Linear interpolation between points is permitted.

Certificate of Compliance No. 1014 Appendix B 2-28 Design Features 3.0

3.0 DESIGN FEATURES

3.1 Site

3.1.1 Site Location

The HI-STORM 100 Cask Sy stem is authorized for use at various site locations under the general licens e pr ovisions of 10 CFR 72, Subpart K.

3.2 Design Features Important for Criticality Control

3.2.1 MPC-24

J. Flux trap size: >1.09 in.

K. 10B loading in the Boral neutron absorbers: >0.0267 g/cm 2

3.2.2 MPC-68

1. Fuel cell pitch: >6.43 in.

A. 10B loading in the Boral neutron absorbers: >0.0372 g/cm 2

3.2.3 MPC-68F

1. Fuel cell pitch: >6.43 in.

B. 10B loading in the Boral neutron absorbers: >0.01 g/cm 2

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 Cask System, as clarified in Specification 3.3.1 below. American Concrete Institute (ACI) 349-85 is the governing Code for plain concrete as clarified in Appendix 1.D of the Topical Safety Analysis Report for the HI-STORM 100 Cask System.

(continued)

Certificate of Compliance No. 1014 Appendix B 3-1 Design Features 3.0

DESIGN FEATURES

3.3 Codes and Standards (continued)

3.3.1 Exceptions to Codes, Standards, and Criteria

Table 3-1 lists approved exceptions to the ASME Code for the design of the HI-STORM 100 Cask System.

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

Proposed alternatives to the ASME Code,Section III, 1995 Edition with Addenda through 1997 including exceptions allowed by Specification 3.3.1 may be used 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 exceptions shall be submitted in accordance with 10 CFR 72.4

(continued)

Certificate of Compliance No. 1014 Appendix B 3-2 Design Features 3.0

DESIGN FEATURES

Table 3-1 (page 1 of 5)

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

Component Reference ASME Code Requirement Exception, Justification &

Code Compensatory Measures Section/Article MPC NB-1100 Statement ofMPC enclosure vessel is requirements for Code designed and will be fabricated stamping of components. in accordance with ASME Code,Section III, Subsection NB to the maximum practical extent, but Code stamping is not required.

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

MPC Lid and NB-4243 Full penetration weldsMPC lid and closure ring are Closure Ring required for Category C not full penetration welds.

Welds Joints (flat head to main They are welded independently shell per NB-3352.3). to provide a redundant seal.

Additionally, a weld efficiency factor of 0.45 has been applied to the analyses of these welds.

MPC Lid to NB-5230 Radiographic (RT) orOnly UT or multi-layer liquid Shell W eld ultrasonic (UT) penetrant (PT) examination is examination required permitted. If PT alone is used, at a minimum, it will include the root and final weld layers and each approximately 3/8 inch of weld depth.

MPC Closure NB-5230 Radiographic (RT) orRoot and final liquid penetrant Ring, Vent and ultrasonic (UT) examination to be performed in Drain Cover examination required accordance with NB-5245.

Plate W elds The MPC vent and drain cover plate welds are leak tested.

The closure ring provides independent redundant closure for vent and drain cover plates.

(continued)

Certificate of Compliance No. 1014 Appendix B 3-3 Design Features 3.0

3.0 DESIGN FEATURES

Table 3-1 (page 2 of 5)

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

Component Reference ASMECode Requirement Exception, Justification &

Code Compensatory Measures Section/Article MPC Enclosure NB-6111 All completed pressureThe MPC enclosure vessel is Vessel and Lid retaining systems shall be seal welded in the field pressure tested. following fuel assembly loading. The MPC enclosure vessel shall then be hydrostatically tested as defined in Chapter 9.

Accessibility for leakage inspections preclude a Code compliant hydrostatic test. 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.

(continued)

Certificate of Compliance No. 1014 Appendix B 3-4 Design Features 3.0

DESIGN FEATURES

Table 3-1 (page 3 of 5)

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

Component Reference ASMECode Requirement Exception, Justification &

Code Compensatory Measures Section/Article MPC Enclosure NB-6111 All completed pressureThe inspection process, Vessel and Lid retaining systems shall be including findings (indications),

(continued) pressure tested. 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 weld is confirmed by leakage testing and liquid penetrant examination and the closure ring weld is 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.

(continued)

Certificate of Compliance No. 1014 Appendix B 3-5 Design Features 3.0

DESIGN FEATURES

Table 3-1 (page 4 of 5)

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

Component Reference ASMECode Requirement Exception, Justification &

Code Compensatory Measures Section/Article MPC Enclosure NB-7000 Vessels are required toNo overpressure protection is Vessel have overpressure provided. The function of the protection MPC enclosure vessel is to contain the radioactive contents under normal, 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 Enclosure NB-8000 States requirements forThe HI-STORM100 Cask Vessel nameplates, stamping System is to be marked and and reports per NCA-identified in accordance with 8000. 10CFR71 and 10CFR72 requirements. Code stamping is not required. QA data package to be in accordance with Holtec approved QA program.

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

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

(continued)

Certificate of Compliance No. 1014 Appendix B 3-6 Design Features 3.0

DESIGN FEATURES

Table 3-1 (page 5 of 5)

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

Component Reference ASMECode Requirement Exception, Justification &

Code Compensatory Measures Section/Article OVERPACK NF-2000 Requires materials to beMaterials will be supplied by Steel Structure supplied by ASME-Holtec-approved supplier with approved material CMTRs in accordance with supplier. NF-2000 requirements.

TRANSFER NF-2000 Requires materials to beMaterials will be supplied by CASK Steel supplied by ASME-Holtec-approved supplier with Structure approved material CMTRs in accordance with supplier. NF-2000 requirements.

OVERPACK NF-4441 Requires specialThe large margins of safety in Baseplate and examinations or these welds under loads Lid Top Plate requirements for welds experienced during lifting where a primary member operations or accident of thickness 1 inch or conditions are quite large. The greater is loaded to OVERPACK baseplate welds transmit loads in the to the inner shell, pedestal through thickness shell, and radial plates are only direction. loaded during lifting conditions and have a minimum safety factor of > 12 during lifting.

The top lid plate to lid shell weld has a safety factor > 6 under a deceleration of 45 gs.

OVERPACK NF-3256 Provides requirements forW elds for which no structural Steel Structure welded joints. credit is taken are identified as Non-NF welds in the design drawings by an *. These non-structural welds are specified in accordance with the pre-qualified welds of AW S D1.1.

These welds shall be made by welders and weld procedures qualified in accordance with AW S D1.1 or ASME Section IX.

(continued)

Certificate of Compliance No. 1014 Appendix B 3-7 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:

1.01 The temperature of 80o F is the maximum average yearly temperature.

2. The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40o F and less than 125 o F.
3. The resultant horizontal acceleration (vectorial sum of two horizontal ZPAs at a three-dimensional seismic site), GH, and vertical acceleration, G V,

expressed as fractions of g, shall satisfy the following inequality:

GH +µGV < µ

where µ is the Coulomb friction coefficient for the HI-STORM 100/ISFSI pad interface. Unless demonstrated by appropriate testing that a higher value of

µ is appropriate for a specific ISFSI, the value of µ used shall be 0.53.

Representative values of GH and G V combinations for µ = 0.53 are provided in Table 3-2.

Table 3-2

Representative DBE Acceleration Values to Prevent HI-STORM 100 Sliding (µ = 0.53)

Equivalent Vectorial Sum of Two Corresponding Vertical ZPA (G V in gs)

Horizontal ZPAs (G H in gs) 0.445 0.160 0.424 0.200 0.397 0.250

(continued)

Certificate of Compliance No. 1014 Appendix B 3-8 Design Features 3.0

DESIGN FEATURES

3.4 Site-Specific Parameters and Analyses (continued)

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.

E. The potential for fire and explosion shall be addressed, based on site-specific considerations. This includes the condition that the on-site transporter fuel tank will contain no more than 50 gallons of diesel fuel while handling a loaded OVERPACK or TRANSFER CASK.

F. In addition to the requirements of 10CFR72.212(b)(2)(ii), the cask storage pads and foundation shall include the following characteristics as applicable to the drop and tipover analyses.

1.01 Concrete Thickness: <36 inches

1.02 Concrete Compressive Strength: <4,200 psi at 28 days

1.03 Reinforcement top and bottom (both directions):

Reinforcement area and spacing determined by analysis

Reinforcement shall be 60 ksi yield strength ASTM material

1.02 Soil Effective Modulus of Elasticity: <28,000 psi (measured prior to installation of ISFSI)

An acceptable method of defining the soil effective modulus of elasticity applicable to the drop and tipover analyses is provided in Table 13 of NUREG/CR-6608 (February, 1998) with soil classification in accordance with ASTM D2487-93, Standard Classification of Soils for Engineering Purposes (Unified Soil Classification System, USCS)and density determination in accordance with ASTM D1586-84, Standard Test Method for Penetration Test and Split/Barrel Sampling of Soils.

(continued)

Certificate of Compliance No. 1014 Appendix B 3-9 Design Features 3.0

DESIGN FEATURES

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

(continued)

Certificate of Compliance No. 1014 Appendix B 3-10 Design Features 3.0

DESIGN FEATURES

3.5 CASK TRANSFER FACILITY (CTF)

3.5.1 TRANSFER CASK and MPC Lifters

Lifting of a loaded TRANSFER CASK and MPC outside of 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 and the below clarifications. The CTF Structure requirements below do not apply to heavy loads bounded by the regulations of 10 CFR Part 50.

3.5.2 CTF Structure Requirements

3.5.2.1 Cask Transfer Facility 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 3-3. 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 3-3 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 Appendix B 3-11 Design Features 3.0

DESIGN FEATURES

3.5.2.2 Mobile Lifting 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 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 Appendix B 3-12 Design Features 3.0

DESIGN FEATURES

Table 3-3

Load Combinations and Service Condition Definitions for the CTF Structure (Note 1)

Load Combination ASME III ServiceComment Condition for Definition of Allowable Stress D* All primary load bearing Level A members must satisfy D+S Level A stress limits D+M+W Factor of safety against (Note 2) overturning shall be > 1.1

D+F Level D

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 Appendix B 3-13

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