ML22098A240

From kanterella
Jump to navigation Jump to search

Proposed Renewed Certificate of Compliance No. 1014, Appendix B: Technical Specifications for the HI-STORM 100 Cask System Amendment No. 1
ML22098A240
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: ML22098A240 (1)
v • d • e


Text

RENEWED CERTIFICATE OF COMPLIANCE NO. 1014

APPENDIX B

APPROVED CONTENTS AND DESIGN FEATURES

FOR THE HI-STORM 100 CASK SYSTEM

AMENDMENT NO. 1 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......................................................................................3-2 3.4 Site Specific Parameters and Analyses........................................................3-8 3.5 Cask Transfer Facility (CTF).........................................................................3-12 3.6 Forced Helium Dehydration System.............................................................3-15

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 (µ = 0.53).......................................................3-8 Table 3-3 Load Combinations and Service Condition Definitions For the CTF Structure.........................................................................3-14

Certificate of Compliance No. 1014 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 following (CTF) 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 devi ce 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, empty fuel rod locations that are not filled with dummy fuel rods, or those that cannot be handled by normal means. Fuel assemblies that 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. DFCs authorized for use in the HI-STORM 100 System are as follows:

1. Holtec Dresden Unit 1/Humboldt Bay design
2. Transnuclear Dresden Unit 1 design
3. Holtec Generic BWR design
4. Holtec Generic PWR design

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.

(continued)

Certificate of Compliance No. 1014 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.Fuel assemblies without fuel rods in fuel rod locations 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 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 included MPC transfer between the TRANSFER CASK and the OVERPACK.

MULTI-PURPOSE CANISTER MPCs are the sealed spent nuclear fuel canisters which (MPC) 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.

NON-FUEL HARDWARE NON-FUEL HARDWARE is defined as B urnable Poison Rod Assemblies (BPRAs), Thimble Plug Devices (TPDs),

Control Rod Assem blies (CRAs), Axial Power Shaping Rods (APSRs), Wet Annular Burnable Absorbers (WABAs), Rod Cluster Control Assemblies (RCCAs),

Control Element Assemblies (CEAs), water displacement guide tube plugs, and orifice rod assemblies.

(continued)

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

1.0 Definitions (continued)

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.

SPENT FUEL STORAGE An SFSC is a container approved for the storage of CASKS (SFSCs) 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 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 include transfer of the MPC between the OVERPACK and the TRANSFER CASK.

(continued)

Certificate of Compliance No. 1014 Appendix B 1-3 Definitions 1.0

1.0 Definitions (continued)

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 Appendix B 1-4 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, 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 DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, all remaining Zircaloy (or other alloy of zirconium) clad INTACT FUEL ASSEMBLIES in the MPC shall meet the decay heat generation limits for the DAMAGED FUEL ASSEMBLIES. This requirement applies only to uniform fuel loading.
d. For MPCs partially loaded with array/class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A fuel assemblies, all remaining Zircaloy (or other alloy of zirconium) clad INTACT FUEL ASSEMBLIES in the MPC shall meet the decay heat generation limits for the 6x6A, 6x6B, 6x6C, 7x7A and 8x8A fuel assemblies.
e. All BWR fuel assemblies may be stored with or without Zircaloy (or other alloy of zirconium) channels with the exception of array/class 10x10D and 10x10E fuel assemblies, which may be stored with or without Zircaloy or stainless steel channels.

(continued)

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

2.0 Approved Contents

2.1 Fuel Specifications and Loading Conditions (contd)

2.1.2 Uniform Fuel Loading

Preferential fuel loading shall be used during uniform loading (i.e., any authorized fuel assembly in any fuel storage location) 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.

Regionalized fuel loading as described in Technical Specification 2.1.3 below meets the intent of preferential fuel loading.

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. Regionalized loading is limited to those fuel assemblies with Zircaloy (or other alloy of zirconium) cladding. Figures 2.1-1 through 2.1-4 define the regions for the MPC-24, MPC-24E, MPC-24EF, MPC-32, MPC-68, and MPC-68FF models, respectively 1. Fuel assembly burnup, decay heat, and cooling time limits for regionalized loading are specified in Tables 2.1-6 and 2.1-

7. 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the NRC Operations Center.

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

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 Appendix B 2-2

Approved Contents 2.0

Table 2.1-1 (page 1 of 33)

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 s pecifications (Note 1):
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. 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 Tables 2.1-4 or 2.1-6.

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

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

Table 2.1-1 (page 2 of 33)

Fuel Assembly Limits

I. MPC MODEL: MPC-24 (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Assembly:
i. Array/Classes 14x14D, < 710 Watts 14x14E, and 15x15G

ii All Other Array/Classes As specified in Tables 2.1-5 or 2.1-7

e. Fuel Assembly Length: < 176.8 inches (nominal design)
f. Fuel Assembly Width: < 8.54 inches (nominal design)
g. Fuel Assembly Weight: < 1,680 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.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, or orifice rod assemblies may be stored in any fuel cell location. Fuel assemblies containing CRAs, RCCAs, CEAs, or APSRs may only be loaded in fuel storage locations 9, 10, 15, and/or 16. These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.

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

Table 2.1-1 (page 3 of 33)

Fuel Assembly Limits

II. MPC MODEL: MPC-68

A. Allowable Contents

1. Uranium oxide, BWR INTACT FUEL ASSEMBLIES listed in Table 2.1-3, with or without 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-AVERAGE As specified in Table 2.1-3 for the applicable INITIAL ENRICHMENT: fuel assembly array/class.
c. Initial Maximum Rod As specified in Table 2.1-3 for the applicable Enrichment: fuel assembly array/class.
d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Classes 6x6A, 6x6C, Cooling time > 18 years and an average 7x7A, and 8x8A: burnup < 30,000 MWD/MTU

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

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

iv. All Other Array/Classes As specified in Tables 2.1-4 or 2.1-6.

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

Table 2.1-1 (page 4 of 33)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

A. Allowable Contents (continued)

e. Decay Heat Per Assembly:
i. Array/Classes 6x6A, 6x6C, < 115 Watts 7x7A, and 8x8A

ii. Array/Class 8x8F < 183.5 Watts.

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

iv. All Other Array/Classes As specified in Tables 2.1-5 or 2.1-7.

f. Fuel Assembly Length: < 176.5 inches (nominal design)
g. Fuel Assembly Width: < 5.85 inches (nominal design)
h. Fuel Assembly Weight: < 700 lbs, including channels

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

Table 2.1-1 (page 5 of 33)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

A. Allowable Contents (continued)

2. Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES, with or without channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 and meet 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-AVERAGE INITIAL ENRICHMENT:
i. Array/Classes 6x6A, 6x6C, 7x7A, As specified in Table 2.1-3 for the applicable and 8x8A fuel assembly array/class.

ii. All Other Array/Classes specified 4.0 wt% 235U in Table 2.1-3

c. Initial Maximum Rod As specified in Table 2.1-3 for the applicable Enrichment: fuel assembly array/class.
d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Classes 6x6A, 6x6C, Cooling time > 18 years and an average 7x7A,and 8x8A burnup < 30,000 MWD/MTU.

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

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

iv. All Other Array Classes As specified in Tables 2.1-4 or 2.1-6.

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

Table 2.1-1 (page 6 of 33)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

A. Allowable Contents (continued)

e. Decay Heat Per Assembly:
i. Array/Class 6x6A, 6x6C, 7x7A, < 115 Watts and 8x8A

ii. Array/Class 8x8F < 183.5 Watts

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

iv. All Other Array/Classes As specified in Tables 2.1-5 or 2.1-7

f. Fuel Assembly Length:
i. Array/Class 6x6A, 6x6C, 7x7A, < 135.0 inches (nominal design) or 8x8A

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

g. Fuel Assembly Width:
i. Array/Class 6x6A, 6x6C, 7x7A, < 4.70 inches (nominal design) or 8x8A

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

h. Fuel Assembly Weight:
i. Array/Class 6x6A, 6x6C, 7x7A, < 550 lbs, including channels and DFC or 8x8A

ii. All Other Array/Classes < 700 lbs, including channels and DFC

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

Table 2.1-1 (page 7 of 33)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

A. Allowable Contents (continued)

3. Mixed oxide (MOX), BWR INTACT FUEL ASSEMBLIES, with or without 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: Zircaloy (Zr)
b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for fuel INITIAL ENRICHMENT: assembly array/class 6x6B.
c. Initial Maximum Rod As specified in Table 2.1-3 for fuel Enrichment: assembly array/class 6x6B.
d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTIHM.

Assembly:

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 Appendix B 2-13 Approved Contents 2.0

Table 2.1-1 (page 8 of 33)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

A. Allowable Contents (continued)

4. Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without channels, placed in DAMA GED 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: Zircaloy (Zr)
b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for array/class INITIAL ENRICHMENT: 6x6B.
c. Initial Maximum Rod As specified in Table 2.1-3 for array/class Enrichment: 6x6B.
d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTIHM.

Assembly:

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 Appendix B 2-14 Approved Contents 2.0

Table 2.1-1 (page 9 of 33)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

A.Allowable Contents (continued)

5. Thoria rods (ThO 2 and U O2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:
a. Cladding Type: Zircaloy (Zr)
b. Composition: 98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U.
c. Number of Rods Per Thoria Rod Canister: < 18
d. Decay Heat Per Thoria Rod Canister: < 115 Watts
e. Post-irradiation Fuel Cooling Time A fuel post-irradiation cooling time > 18 years and Average Burnup Per Thoria 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 Appendix B 2-15 Approved Contents 2.0

Table 2.1-1 (page 10 of 33)

Fuel Assembly Limits

II. MPC MODEL: MPC-68 (continued)

B. Quantity per MPC:

1. Up to one (1) Dresden Unit 1 Thoria Rod Canister;
2. Up to 68 array/class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS
3. Up to sixteen (16) other BWR DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS in fuel storage locations 1, 2, 3, 8, 9, 16, 25, 34, 35, 44, 53, 60, 61, 66, 67, and/or 68; and/or
4. Any number of BWR INTACT FUEL ASSEMBLIES up to a total of 68.

C. Array/Class 10x10D and 10x10E fuel assemblies in stainless steel channels must be lstored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 - 50.

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

E. FUEL DEBRIS is not authorized for loading in the MPC-68.

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

Table 2.1-1 (page 11 of 33)

Fuel Assembly Limits

III. MPC MODEL: MPC-68F

A. Allowable Contents

1. Uranium oxide, BWR INTACT FUEL ASSEMBLIES, with or without Zircaloy 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: Zircaloy (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 As specified in Table 2.1-3 for the Enrichment: applicable fuel assembly array/class.
d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTU.

Assembly:

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 Appendix B 2-17 Approved Contents 2.0

Table 2.1-1 (page 12 of 33)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

2. Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES, with or without Zircaloy 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: Zircaloy (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 As specified in Table 2.1-3 for the Enrichment: applicable fuel assembly array/class.
d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTU.

Assembly:

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 Appendix B 2-18 Approved Contents 2.0

Table 2.1-1 (page 13 of 33)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

3. Uranium oxide, BWR FUEL DEBRIS, with or without Zircaloy 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: 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 Enrichment: As specified in Table 2.1-3 for the applicable original fuel assembly array/class.

d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTU for the Assembly 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 Appendix B 2-19 Approved Contents 2.0

Table 2.1-1 (page 14 of 33)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

4. Mixed oxide (MOX), BWR INTACT FUEL ASSEMBLIES, with or without Zircaloy 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: 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 Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTIHM.

Assembly:

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 Appendix B 2-20 Approved Contents 2.0

Table 2.1-1 (page 15 of 33)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

5. Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without Zircaloy 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: 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 Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTIHM.

Assembly:

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 Appendix B 2-21 Approved Contents 2.0

Table 2.1-1 (page 16 of 33)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

6. Mixed Oxide (MOX), BWR FUEL DEBRIS, with or without Zircaloy 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: Zircaloy (Zr)
b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for original fuel INITIAL ENRICHMENT: 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 Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTIHM for the Assembly: 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 Appendix B 2-22 Approved Contents 2.0

Table 2.1-1 (page 17 of 33)

Fuel Assembly Limits

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

A.Allowable Contents (continued)

7. Thoria rods (ThO 2 and UO 2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:
a. Cladding Type: Zircaloy (Zr)
b. Composition: 98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U.
c. Number of Rods Per Thoria Rod Canister: < 18
d. Decay Heat Per Thoria Rod Canister: < 115 Watts
e. Post-irradiation Fuel Cooling A fuel post-irradiation cooling time > 18 Time and Average Burnup Per years and an average burnup < 16,000 Thoria 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 Appendix B 2-23 Approved Contents 2.0

Table 2.1-1 (page 18 of 33)

Fuel Assembly Limits

III. 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 Appendix B 2-24 Approved Contents 2.0

Table 2.1-1 (page 19 of 33)

Fuel Assembly Limits

IV. MPC MODEL: MPC-24E

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

ii. All Other Array/Classes As specified in Tables 2.1-4 or 2.1-6.

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

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

Table 2.1-1 (page 20 of 33)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

d. Decay Heat Per Assembly:
i. Array/Classes 14x14D, < 710 Watts.

14x14E, and 15x15G

ii. All other Array/Classes As specified in Tables 2.1-5 or 2.1-7.

e. Fuel Assembly Length: < 176.8 inches (nominal design)
f. Fuel Assembly Width: < 8.54 inches (nominal design)
g. Fuel Assembly Weight: < 1,680 lbs (including NON-FUEL HARDWARE)

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

Table 2.1-1 (page 21 of 33)

Fuel Assembly Limits

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

A.Allowable Contents (continued)

2. Uranium oxide, P WR DAMAGED FUEL ASSEMBLIES, with or without NON-FUEL HARDWARE, placed in DAMAGED FUEL CONTAINERS. Uranium oxide PWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-2 and meet the following specifications (Note 1):
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: < 4.0 wt% 235U.
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 Tables 2.1-4 or 2.1-6.

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

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

Table 2.1-1 (page 22 of 33)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

d. Decay Heat Per Assembly
i. Array/Classes 14x14D, < 710 Watts.

14x14E, and 15x15G

ii. All Other Array/Classes As specified in Tables 2.1-5 or 2.1-7.

e. Fuel Assembly Length < 176.8 inches (nominal design)
f. Fuel Assembly Width < 8.54 inches (nominal design)
g. Fuel Assembly Weight < 1,680 lbs (including NON-FUEL HARDWARE and DFC)

B. Quantity per MPC: Up to four (4) DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 3, 6, 19 and/or 22. The remaining MPC-24E fuel storage locations may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.

C. FUEL DEBRIS is not authorized for loading in the MPC-24E.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, or orifice rod assemblies may be stored in any fuel cell location. Fuel assemblies containing CRAs, RCCAs, CEAs, or APSRs may only be loaded in fuel storage locations 9, 10, 15, and/or 16. These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.

Certificate of Compliance No. 1014 Appendix B 2-28 Approved Contents 2.0

Table 2.1-1 (page 23 of 33)

Fuel Assembly Limits

V. MPC MODEL: MPC-32

A. Allowable Conten

B. 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: 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. 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 Tables 2.1-4 or 2.1-6.

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

Certificate of Compliance No. 1014 Appendix B 2-29 Approved Contents 2.0

Table 2.1-1 (page 24 of 33)

Fuel Assembly Limits lll

V. MPC MODEL: MPC-32 (continued) l l

A. Allowable Contents (continued) l l

d. Decay Heat Per Assembly
i. Array/Classes 14x14D, < 500 Watts 14x14E, and 15x15G

ii. All Other Array/Classes As specified in Tables 2.1-5 or 2.1-7.

e. Fuel Assembly Length < 176.8 inches (nominal design)
f. Fuel Assembly Width < 8.54 inches (nominal design)
g. Fuel Assembly Weight < 1,680 lbs (including NON-FUEL HARDWARE)

B. Quantity per MPC: Up to 32 PWR INTACT FUEL ASSEMBLIES.

C. DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS are not authorized for loading in the MPC-32.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, or orifice rod assemblies may be stored in any fuel cell location. Fuel assemblies containing CRAs, RCCAs, CEAs, or APSRs may only be loaded in fuel storage locations 13, 14, 19, and/or 20. These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.

Certificate of Compliance No. 1014 Appendix B 2-30 Approved Contents 2.0

Table 2.1-1 (page 25 of 33)

Fuel Assembly Limits

VI. MPC MODEL: MPC-68FF l l

VII. 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: Zircaloy (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 applicable INITIAL ENRICHMENT: 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 MTU/MTIHM).

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

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

iv. All Other Array/Classes As specified in Tables 2.1-4 or 2.1-6.

Certificate of Compliance No. 1014 Appendix B 2-31 Approved Contents 2.0

Table 2.1-1 (page 26 of 33)

Fuel Assembly Limits

VI. MPC MODEL: 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 and < 95 Watts 10x10E

iv. All Other Array/Classes As specified in Tables 2.1-5 or 2.1-7.

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, 6x6C, < 4.70 inches (nominal design) 7x7A, or 8x8A

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

h. Fuel Assembly Weight
i. Array/Class 6x6A, 6x6B, 6x6C, < 550 lbs, including channels and DFC 7x7A, or 8x8A

ii. All Other Array/Classes < 700 lbs, including channels and DFC

Certificate of Compliance No. 1014 Appendix B 2-32 Approved Contents 2.0

Table 2.1-1 (page 27 of 33)

Fuel Assembly Limits

VI. MPC MODEL: 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: Zircaloy (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 applicable 6x6C, 7x7A, and 8x8A. 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 Tables 2.1-4 or 2.1-6.

Certificate of Compliance No. 1014 Appendix B 2-33 Approved Contents 2.0

Table 2.1-1 (page 28 of 33)

Fuel Assembly Limits

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

A. Allowable Contents (continued)

e. Decay Heat Per Assembly
i. Array/Class 6x6A, 6x6B, 6x6C, < 115 Watts 7x7A, or 8x8A

ii. Array/Class 8x8F < 183.5 Watts

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

iv. All Other Array/Classes As specified in Tables 2.1-5 or 2.1-7

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

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

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

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

h. Fuel Assembly Weight
i. Array/Class 6x6A, 6x6B, 6x6C, < 550 lbs, including channels and DFC 7x7A, or 8x8A

ii. All Other Array/Classes < 700 lbs, including channels and DFC

Certificate of Compliance No. 1014 Appendix B 2-34 Approved Contents 2.0

Table 2.1-1 (page 29 of 33)

Fuel Assembly limits

VI. MPC MODEL: 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 MPC-68FF 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.

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

D. Array/Class 10x10D and 10x10E fuel assemblies in stainless steel channels must be lstored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 - 50.

Certificate of Compliance No. 1014 Appendix B 2-35 Approved Contents 2.0

Table 2.1-1 (page 30 of 33)

Fuel Assembly Limits

VII. MPC MODEL: 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: 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. Array/Classes 14x14D, 14x14E, Cooling time > 8 years and an average and 15x15G burnup < 40,000 MWD/MTU.

ii. All Other Array/Classes As specified in Tables 2.1-4 or 2.1-6.

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

Certificate of Compliance No. 1014 Appendix B 2-36 Approved Contents 2.0

Table 2.1-1 (page 31 of 33)

Fuel Assembly Limits

VII. MPC MODEL: MPC-24EF (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Assembly:
i. Array/Classes 14x14D, < 710 Watts.

14x14E, and 15x15G

ii. All other Array/Classes As specified in Tables 2.1-5 or 2.1-7.

e. Fuel Assembly Length: < 176.8 inches (nominal design)
f. Fuel Assembly Width: < 8.54 inches (nominal design)
g. Fuel Assembly Weight: < 1,680 lbs (including NON-FUEL HARDWARE)

Certificate of Compliance No. 1014 Appendix B 2-37 Approved Contents 2.0

Table 2.1-1 (page 32 of 33)

Fuel Assembly Limits

VII. MPC MODEL: 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: Zircaloy (Zr) or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class
b. Initial Enrichment: < 4.0 wt% 235U.
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 Tables 2.1-4 or 2.1-6.

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

Certificate of Compliance No. 1014 Appendix B 2-38 Approved Contents 2.0

Table 2.1-1 (page 33 of 33)

Fuel Assembly Limits

VII. MPC MODEL: MPC-24EF (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Assembly
i. Array/Classes 14x14D, < 710 Watts.

14x14E, and 15x15G

ii. All Other Array/Classes As specified in Tables 2.1-5 or 2.1-7.

e. Fuel Assembly Length < 176.8 inches (nominal design)
f. Fuel Assembly Width < 8.54 inches (nominal design)
g. Fuel Assembly Weight < 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 MPC-24EF fuel storage locations may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, or orifice rod assemblies may be stored in any fuel cell location. Fuel assemblies containing CRAs, RCCAs, CEAs, or APSRs may only be loaded in fuel storage locations 9, 10, 15, and/or 16. These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.

Certificate of Compliance No. 1014 Appendix B 2-39 Approved Contents 2.0 Table 2.1-2 (page 1 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

Clad Material Zr Zr Zr SS SS (Note 2)

Design Initial U < 407 < 407 < 425 < 400 < 206 (kg/assy.) (Note 3)

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

(MPC-24, 24E and 24EF without < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 soluble boron (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) credit)

(wt % 235U)

(Note 7)

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

- see Notes 5 and 7)

(wt % 235U)

No. of Fuel Rod 179 179 176 180 173 Locations

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

Fuel Rod Clad I.D. < 0.3514 < 0.3734 < 0.3880 < 0.3890 < 0.3175 (in.)

Fuel Pellet Dia. (in.) < 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 < 150 < 150 < 150 < 144 < 102 (in.)

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

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

Certificate of Compliance No. 1014 Appendix B 2-40 Approved Contents 2.0

Table 2.1-2 (page 2 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

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

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

(Note 3)

Initial Enrichment < 4.1 (24) < 4.1 (24) < 4.1 (24) < 4.1 (24) < 4.1 (24) < 4.1 (24)

(MPC-24, 24E and 24EF without soluble < 4.5 < 4.5 < 4.5 < 4.5 < 4.5 < 4.5 boron credit) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF)

(wt % 235U)

(Note 7)

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

see Notes 5 and 7)

(wt % 235U)

No. of Fuel Rod 204 204 204 208 208 208 Locations

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

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

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

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

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

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

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

Certificate of Compliance No. 1014 Appendix B 2-41 Approved Contents 2.0

Table 2.1-2 (page 3 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 15x15G 15x15H 16x16A 17x17A 17x17B 17x17C Array/ Class

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

Design Initial U < 420 < 475 < 443 < 467 < 467 < 474 (kg/assy.)

(Note 3)

Initial Enrichment < 4.0 (24) < 3.8 (24) < 4.6 (24) < 4.0 (24) < 4.0 (24) < 4.0 (24)

(MPC-24, 24E, and 24EF without < 4.5 < 4.2 < 5.0 < 4.4 < 4.4 < 4.4 soluble boron (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) credit)

(wt % 235U)

(Note 7)

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

- see Notes 5 and 7)

(wt % 235U)

No. of Fuel Rod 204 208 236 264 264 264 Locations

Fuel Rod Clad O.D. > 0.422 >0.414 >0.382 >0.360 >0.372 >0.377 (in.)

Fuel Rod Clad I.D. < 0.3890 < 0.3700 < 0.3320 < 0.3150 < 0.3310 < 0.3330 (in.)

Fuel Pellet Dia. (in.) < 0.3825 < 0.3622 < 0.3255 < 0.3088 < 0.3232 < 0.3252

Fuel Rod Pitch (in.) < 0.563 < 0.568 < 0.506 < 0.496 < 0.496 < 0.502

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

No. of Guide and/or 21 17 5 (Note 4) 25 25 25 Instrument Tubes

Guide/Instrument > 0.0145 >0.0140 > 0.0400 >0.016 >0.014 >0.020 Tube Thickness (in.)

Certificate of Compliance No. 1014 Appendix B 2-42 Approved Contents 2.0

Table 2.1-2 (page 4 of 4)

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. 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 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 to account for manufacturers tolerances.
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.

Certificate of Compliance No. 1014 Appendix B 2-43 Approved Contents 2.0

Table 2.1-3 (page 1 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

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

Design Initial U < 110 < 110 < 110 < 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 UO2 rods.

ENRICHMENT See Note 4 (wt.% 235U) for MOX (Note 14) rods

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

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

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

Fuel Rod Clad I.D. < 0.5105 < 0.4945 < 0.4990 < 0.4204 < 0.4990 < 0.3620 (in.)

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 < 120 < 77.5 < 80 < 150 < 120 (in.)

No. of Water Rods 1 or 0 1 or 0 0 0 0 1 or 0 (Note 11)

Water Rod > 0 > 0 N/A N/A N/A >0 Thickness (in.)

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

Certificate of Compliance No. 1014 Appendix B 2-44 Approved Contents 2.0

Table 2.1-3 (2 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 8x8B 8x8C 8x8D 8x8E 8x8F 9x9A Array/Class

Clad Material Zr Zr Zr Zr ZrZr (Note 2)

Design Initial U < 191 < 191 < 191 < 191 < 191 < 179 (kg/assy.) (Note 3)

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

(Note 14)

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

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

Fuel Rod Clad O.D. > 0.4840 >0.4830 >0.4830 >0.4930 > 0.4576 >0.4400 (in.)

Fuel Rod Clad I.D. < 0.4295 < 0.4250 < 0.4230 < 0.4250 < 0.3996 < 0.3840 (in.)

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 < 150 Length (in.)

No. of Water Rods 1 or 0 2 1 - 4 5 N/A 2 (Note 11) (Note 7) (Note 12)

Water Rod Thickness > 0.034 > 0.00 > 0.00 >0.034 >0.0315 > 0.00 (in.)

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

Certificate of Compliance No. 1014 Appendix B 2-45 Approved Contents 2.0

Table 2.1-3 (page 3 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

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

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

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

(Note 14)

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

No. of Fuel Rod 72 80 79 76 76 72 Locations

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 11) (Note 6)

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

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

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

Table 2.1-3 (page 4 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

Clad Material (Note 2) Zr Zr Zr SS SS

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

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

(Note 14)

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

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

Fuel Rod Clad O.D. (in.) >0.4040 >0.3957 >0.3780 >0.3960 >0.3940

Fuel Rod Clad I.D. (in.) < 0.3520 < 0.3480 < 0.3294 < 0.3560 < 0.3500

Fuel Pellet Dia. (in.) < 0.3455 < 0.3420 < 0.3224 < 0.3500 < 0.3430

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

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

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

Water Rod Thickness (in.) >0.0300 > 0.00 >0.031 N/A >0.022

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

Certificate of Compliance No. 1014 Appendix B 2-47 Approved Contents 2.0

Table 2.1-3 (page 5 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS

Notes:

1. All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
2. 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 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 to account for manufacturer tolerances.
4. < 0.635 wt. % 235U and < 1.578 wt. % total fissile plutonium ( 239Pu and 241Pu), (wt. % of total fuel lweight, i.e., UO 2 plus PuO2).

l

5. This assembly class contains 74 total rods; 66 full length rods and 8 partial length rods.
6. Square, replacing nine fuel rods.
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 those MPCs 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.

Certificate of Compliance No. 1014 Appendix B 2-48 Approved Contents 2.0

Table 2.1-4

FUEL ASSEMBLY COOLING AND MAXIMUM AVERAGE BURNUP (UNIFORM FUEL LOADING)

Post-MPC-24 MPC-24E/24EF MPC-24E/24EF MPC-32 MPC-68/68FF MPC-68/68FF irradiation PWR PWR Assembly PWR Assembly PWR BWR Assembly BWR Assembly Cooling Assembly Burnup Burnup Assembly Burnup Burnup Time Burnup (INTACT FUEL (DAMAGED FUEL Burnup (INTACT FUEL (DAMAGED FUEL (years) (INTACT FUEL ASSEMBLIES) ASSEMBLIES AND (INTACT FUEL ASSEMBLIES) ASSEMBLIES AND ASSEMBLIES) (MWD/MTU) FUEL DEBRIS) ASSEMBLIES (MWD/MTU) FUEL DEBRIS)

(MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU)

> 5 40,600 41,100 39,200 32,200 38,300 36,700

> 6 45,000 45,000 43,700 36,500 41,600 39,900

> 7 45,900 46,300 44,500 37,500 42,300 40,700

> 8 48,300 48,900 46,900 39,900 44,800 42,900

> 9 50,300 50,700 48,700 41,500 46,600 44,700

> 10 51,600 52,100 50,100 42,900 48,000 46,100

> 11 53,100 53,700 51,500 44,100 49,600 47,200

> 12 54,500 55,100 52,600 45,000 50,800 48,500

> 13 55,600 56,100 53,800 45,700 51,800 49,800

> 14 56,500 57,100 54,900 46,500 52,700 50,700

> 15 57,400 58,000 55,800 47,200 53,900 51,500

Notes: 1. Linear interpolation between points is permitted.

2. Burnup for fuel assemblies with cladding made of materials other than Zircaloy-2 or Zircaloy-4 is limited to 45,000 MWD/MTU or the value in this table, whichever is less.

Certificate of Compliance No. 1014 Appendix B 2-49 Approved Contents 2.0

Table 2.1-5

FUEL ASSEMBLY COOLING AND MAXIMUM DECAY HEAT (UNIFORM FUEL LOADING)

Post-MPC-24 MPC-24E/24EF MPC-24E/24EF MPC-32 MPC-68/68FF MPC-68/68FF irradiation PWR PWR PWR Assembly PWR BWR BWR Assembly Cooling Assembly Assembly Decay Heat Assembly Assembly Decay Heat Time Decay Heat Decay Heat (DAMAGED FUEL Decay Heat Decay Heat (DAMAGED FUEL (years) (INTACT FUEL (INTACT FUEL ASSEMBLIES AND (INTACT FUEL (INTACT FUEL ASSEMBLIES AND ASSEMBLIES) ASSEMBLIES) FUEL DEBRIS) ASSEMBLIES ASSEMBLIES) FUEL DEBRIS)

(Watts) (Watts) (Watts) (Watts) (Watts) (Watts)

> 5 1157 1173 1115 898 414 393

> 6 1123 1138 1081 873 394 374

> 7 1030 1043 991 805 363 345

> 8 1020 1033 981 800 360 342

> 9 1010 1023 972 794 358 340

> 10 1000 1012 962 789 355 337

> 11 996 1008 958 785 353 336

> 12 992 1004 954 782 352 334

> 13 987 999 949 773 350 332

> 14 983 995 945 769 348 331

> 15 979 991 941 766 347 329

Notes: 1. Linear interpolation between points is permitted.

2. Includes all sources of heat ( i.e., fuel and NON-FUEL HARDWARE).

Certificate of Compliance No. 1014 Appendix B 2-50 Approved Contents 2.0

Table 2.1-6 (page 1 of 2)

FUEL ASSEMBLY COOLING AND MAXIMUM AVERAGE BURNUP (REGIONALIZED FUEL LOADING)

Post-irradiation MPC-24 MPC-24 MPC-24E/24EF MPC-24E/24EF Cooling Time PWR Assembly PWR Assembly PWR Assembly PWR Assembly (years) Burnup Burnup Burnup Burnup for Region 1 for Region 2 for Region 1 for Region 2 (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU)

> 5 49,800 32,200 51,600 32,200

> 6 56,100 37,400 58,400 37,400

> 7 56,400 41,100 58,500 41,100

> 8 58,800 43,800 60,900 43,800

> 9 60,400 45,800 62,300 45,800

> 10 61,200 47,500 63,300 47,500

> 11 62,400 49,000 64,900 49,000

> 12 63,700 50,400 65,900 50,400

> 13 64,800 51,500 66,800 51,500

> 14 65,500 52,500 67,500 52,500

> 15 66,200 53,700 68,200 53,700

> 16 - 55,000 - 55,000

> 17 - 55,900 - 55,900

> 18 - 56,800 - 56,800

> 19 - 57,800 - 57,800

> 20 - 58,800 - 58,800

Notes: 1. Linear interpolation between points is permitted.

2. These limits apply to INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, and FUEL DEBRIS.
3. Burnup for fuel assemblies with cladding made of materials other than Zircaloy-2 or Zircaloy-4 is limited to 45,000 MWD/MTU or the value in this table, whichever is less.

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

Table 2.1-6 (page 2 of 2)

FUEL ASSEMBLY COOLING AND MAXIMUM AVERAGE BURNUP (REGIONALIZED FUEL LOADING)

Post-irradiation MPC-32 MPC-32 MPC-68/68FF MPC-68/68FF Cooling Time PWR Assembly PWR Assembly BWR Assembly BWR Assembly (years) Burnup Burnup Burnup Burnup for Region 1 for Region 2 for Region 1 for Region 2 (MWD/MTU) (MWD/MTU) (MWD/MTU) (MWD/MTU)

> 5 39,800 22,100 45,100 26,200

> 6 43,400 26,200 47,400 30,500

> 7 44,500 29,100 47,400 33,600

> 8 46,700 31,200 50,400 35,900

> 9 48,400 32,700 52,100 37,600

> 10 49,600 34,100 53,900 39,000

> 11 50,900 35,200 55,500 40,200

> 12 51,900 36,200 56,500 41,200

> 13 52,900 37,000 57,500 42,300

> 14 53,800 37,800 58,800 43,300

> 15 54,700 38,600 59,900 44,200

> 16 - 39,400 - 45,000

> 17 - 40,200 - 45,900

> 18 - 40,800 - 46,700

> 19 - 41,500 - 47,500

> 20 - 42,200 - 48,500

Notes: 1. Linear interpolation between points is permitted.

2. These limits apply to INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, and FUEL DEBRIS.
3. Burnup for fuel assemblies with cladding made of materials other than Zircaloy-2 or Zircaloy-4 is limited to 45,000 MWD/MTU or the value in this table, whichever is less.

Certificate of Compliance No. 1014 Appendix B 2-52 Approved Contents 2.0

Table 2.1-7 (page 1 of 2)

FUEL ASSEMBLY COOLING AND MAXIMUM DECAY HEAT (REGIONALIZED FUEL LOADING)

Post-irradiation MPC-24 MPC-24 MPC-24E/24EF MPC-24E/24EF Cooling Time PWR Assembly PWR Assembly PWR Assembly PWR Assembly (years) Decay Heat Decay Heat Decay Heat Decay Heat for Region 1 for Region 2 for Region 1 for Region 2 (Watts) (Watts) (Watts) (Watts)

> 5 1470 900 1540 900

> 6 1470 900 1540 900

> 7 1335 900 1395 900

> 8 1,301 900 1360 900

> 9 1268 900 1325 900

> 10 1235 900 1290 900

> 11 1221 900 1275 900

> 12 1207 900 1260 900

> 13 1193 900 1245 900

> 14 1179 900 1230 900

> 15 1165 900 1215 900

> 16 - 900 - 900

> 17 - 900 - 900

> 18 - 900 - 900

> 19 - 900 - 900

> 20 - 900 - 900

Notes: 1. Linear interpolation between points is permitted.

2. Includes all sources of decay heat (i.e., fuel and NON-FUEL HARDWARE).
4. These limits apply to INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, and FUEL DEBRIS.

Certificate of Compliance No. 1014 Appendix B 2-53 Approved Contents 2.0

Table 2.1-7 (page 2 of 2)

FUEL ASSEMBLY COOLING AND MAXIMUM DECAY HEAT (REGIONALIZED FUEL LOADING)

Post-irradiation MPC-32 MPC-32 MPC-68/68FF MPC-68/68FF Cooling Time PWR Assembly PWR Assembly BWR Assembly BWR Assembly (years) Decay Heat Decay Heat Decay Heat Decay Heat for Region 1 for Region 2 for Region 1 for Region 2 (Watts) (Watts) (Watts) (Watts)

> 5 1131 600 500 275

> 6 1072 600 468 275

> 7 993 600 418 275

> 8 978 600 414 275

> 9 964 600 410 275

> 10 950 600 405 275

> 11 943 600 403 275

> 12 937 600 400 275

> 13 931 600 397 275

> 14 924 600 394 275

> 15 918 600 391 275

> 16 - 600 - 275

> 17 - 600 - 275

> 18 - 600 - 275

> 19 - 600 - 275

> 20 - 600 - 275

Notes: 1. Linear interpolation between points is permitted.

2. Includes all sources of decay heat (i.e., fuel and NON-FUEL HARDWARE).
3. These limits apply to INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, and FUEL DEBRIS.

Certificate of Compliance No. 1014 Appendix B 2-54 Approved Contents 2.0

Table 2.1-8 NON-FUEL HARDWARE COOLING AND AVERAGE BURNUP

Post-irradiation NEUTRON POISON GUIDE TUBE CONTROL APSR Cooling Time INSERTS HARDWARE COMPONENT BURNUP (years) (Note 3) (Note 4) (Note 5) (MWD/MTU)

BURNUP BURNUP BURNUP (MWD/MTU) (MWD/MTU) (MWD/MTU)

> 3 < 20,000 NA (Note 6) NA NA

> 4 < 25,000 < 20,000 NA NA

> 5 < 30,000 < 25,000 < 630,000 < 45,000

> 6 < 40,000 < 30,000 - < 54,500

> 7 < 45,000 < 40,000 - < 68,000

> 8 < 50,000 < 45,000 - < 83,000

> 9 < 60,000 < 50,000 - < 111,000

> 10 - < 60,000 - < 180,000

> 11 - < 75,000 - < 630,000

> 12 - < 90,000 - -

> 13 - < 180,000 - -

> 14 - < 630,000 - -

Notes: 1. Linear interpolation between points is permitted, except that TPD and APSR burnups > 180,000 MWD/MTU and < 630,000 MWD/MTU must be cooled > 14 years and > 11 years, respectively.

2. Applicable to uniform loading and regionalized loading.
3. Includes Burnable Poison Rod Assemblies (BPRAs) and Wet Annular Burnable Absorbers (WABAs).
4. Includes Thimble Plug Devices (TPDs), water displacement guide tube plugs, and orifice rod assemblies.
5. Includes Control Rod Assemblies (CRAs), Control Element Assemblies (CEAs), and Rod Cluster Control Assemblies (RCCAs).
6. NA means not authorized for loading.

2-55 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 use at various site locations under the general license 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 Boral neutron absorbers: > 0.0267 g/cm 2

3.2.2 MPC-68 and MPC-68FF

1. Fuel cell pitch: > 6.43 in.
2. 10B loading in the Boral neutron absorbers: > 0.0372 g/cm 2

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 Boral neutron absorbers: > 0.0372 g/cm 2

3.2.5 MPC-32

1. Fuel cell pitch: > 9.158 inches
2. 10B loading in the Boral neutron absorbers: > 0.0372 g/cm 2

3.2.6 Fuel spacers shall be sized to ensure that the active fuel region of intact fuel assemblies

remains within the Boral neutron poison region of the MPC basket with water in the MPC.

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

DESIGN FEATURES

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, 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 Final Safety Analysis Report for the HI-STORM 100 Cask System.

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 of requirementsMPC enclosure vessel is for Code stamping of designed and will be fabricated 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 supplier. Certified Material Test Reports (CMTRs) in accordance with NB-2000 requirements.

MPC Lid and NB-4243 Full penetration weldsMPC lid and closure ring are not Closure Ring required for Category C full penetration welds. They are Welds Joints (flat head to main welded independently to provide shell per NB-3352.3). 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) or Only UT or multi-layer liquid Shell Weld 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) or Root (if more than one weld Ring, Vent and ultrasonic (UT) pass is required) and final liquid Drain Cover examination required penetrant examination to be Plate Welds performed in accordance with NB-5245. 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 ASME Code 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 following pressure tested. 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 ASME Code 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 ASME Code 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 System is to Vessel nameplates, stamping and be marked and identified in reports per NCA-8000. accordance with 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 supplier. CMTRs in accordance with NG-2000 requirements.

MPC Basket NG-8000 States requirements forThe HI-STORM100 System is to Assembly nameplates, stamping and be marked and identified in reports per NCA-8000. accordance with 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 ASME Code 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 supplier. CMTRs in accordance with 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 supplier. CMTRs in accordance with NF-2000 requirements.

OVERPACK NF-4441 Requires special The 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 of operations or accident thickness 1 inch or greater conditions are quite large. The is loaded to transmit loads OVERPACK baseplate welds to in the through thickness the inner shell, pedestal shell, direction. and radial plates are only 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 forWelds 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 AWS D1.1.

These welds shall be made by welders and weld procedures qualified in accordance with AWS 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. The temperature of 80o F is the maximum average yearly temperature.
2. The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40o F and less than 125o F.
3. a. For free-standing casks, the resultant horizontal acceleration (vectorial sum of two horizontal Zero Period Accelerations (ZPAs) at a three-dimensional seismic site), GH, and vertical ZPA, GV, expressed as fractions of g, shall satisfy the following inequality:

GH + : G V < :

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

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

Representative values of GH and GV combinations for : = 0.53 are provided in Table 3-2.

Table 3-2

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

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

Horizontal ZPAs (GH 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)

b. For those ISFSI sites with design basis seismic acceleration values higher than those allowed for free-standing casks, the HI-STORM 100 System 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

NOTE: The above anchorage specifications are required for the seismic spectra defined in item 3.4.3.b.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

(continued)

Certificate of Compliance No. 1014 Appendix B 3-9 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.
5. 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.
6. a. For free-standing 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 lift height above the ISFSI pad is not required to be established if the cask is lifted with a device designed in accordance with ANSI N14.6 and having 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 lift height above the ISFSI pad is not required to be established if the cask is lifted with a device design in accordance with ANSI N14.6 and having redundant drop protection features.

(continued)

Certificate of Compliance No. 1014 Appendix B 3-10 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 > 0 o F.
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.

(continued)

Certificate of Compliance No. 1014 Appendix B 3-11 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 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 3-3. 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 requirements applies to CTFs with either stationary or mobile lifting devices.

(continued)

Certificate of Compliance No. 1014 Appendix B 3-12 Design Features 3.0

DESIGN FEATURES

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, is 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 Appendix B 3-13 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 Service Condition Comment for Definition of Allowable Stress

D* All primary load bearing Level A members must satisfy Level D + S 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 3-14 Design Features 3.0

DESIGN FEATURES

3.6 Forced Helium Dehydration System

3.6.1 System Description

Use of the 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) and mandatory for drying MPCs containing one or more high burnup fuel assemblies. 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).

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

3.6.2.4The partial pressure of the water vapor in the MPC cavity will not exceed 3 torr if the helium temperature at the demoisturer outlet is < 21oF for a period of 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.

(continued)

Certificate of Compliance No. 1014 Appendix B 3-15 Design Features 3.0

DESIGN FEATURES

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 Subsections 4.4.1.1.1 through 4.4.1.1.4, 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.

Certificate of Compliance No. 1014 Appendix B 3-16

Retrieved from "https://kanterella.com/w/index.php?title=ML22098A240&oldid=3730626"