ML23068A397

13. Renewed Certificate of Compliance No. 1014, Amendment No. 3, Appendix B

ML23068A397
Person / Time
Site:	Holtec
Issue date:	06/29/2023
From:	Storage and Transportation Licensing Branch
To:	Holtec
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References
CAC 001028, EPID L-2020-RNW-0007
Download: ML23068A397 (1)

Text

RENEWED CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX 13 APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STORM 100 GASK SYSTEM AMENDMENT NO. 3

TABLE OF CONTENTS 1.0 DEFIN ITIO NS.................................................

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

2-1 3.0 DESIGN FEATURES............................................

3-1 3.1 3.2 3.3 3.4 3.5 3.6 S ite 3 -1 Design Features Important for Criticality Control.................

3-1 Codes and Standards......................................

3-2 Site Specific Parameters and Analyses........................

3-8 Cask Transfer Facility (CTF)................................

3-12 Forced Helium Dehydration System..........................

3-15 List of ASME Code Alternatives for HI-STORM 100 System........

3-3 Representative DBE Acceleration Values to Prevent HI-STORM 100 Sliding (p = 0.53).......................

3-8 Load Combinations and Service Condition Definitions For the CTF Structure................................

3-14 Table 3-1 Table 3-2 Table 3-3 Certificate of Compliance No. 1014 Appendix B i

Renewed Amendment No. 3 3-20

1.0 Definitions Definitions 1.0

---

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

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

Term CASK TRANSFER FACILITY (CTF)

DAMAGED FUEL ASSEMBLY DAMAGED FUEL CONTAINER (DFC)

Certificate of Compliance No. 1014 Appendix B Definition The CASK TRANSFER FACILITY includes the 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 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, whose structural integrity has been impaired such that geometric rearrangement of fuel or gross failure of the cladding is expected, or 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.

DFCs are specially designed enclosures for 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 1-1 Renewed Amendment No. 3

1. 0 Definitions (continued)

FUEL DEBRIS INTACT FUEL ASSEMBLY LOADING OPERATIONS MINIMUM ENRICHMENT MUL Tl-PURPOSE CANISTER (MPC)

NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B Definitions 1.0 FUEL DEBRIS is ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting these loose fuel assembly parts, or fuel assemblies with known or suspected defects which cannot be handled by normal means due to fuel cladding damage.

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 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.

MINIMUM ENRICHMENT is the minimum assembly average enrichment. Natural uranium blankets are not considered in determining minimum enrichment.

MPCs are the sealed spent nuclear fuel canisters 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.

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

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

Control Element Assemblies (CEAs), Neutron Source Assemblies (NSAs), water displacement guide tube plugs, orifice rod assemblies, and vibration suppressor inserts.

1-2 Renewed Amendment No. 3

Definitions 1.0 1.0 Definitions (continued)

OVERPACK PLANAR-AVERAGE INITIAL ENRICHMENT SPENT FUEL STORAGE CASKS (SFSCs)

TRANSFER CASK TRANSPORT OPERATIONS UNLOADING OPERATIONS 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 INITIAL ENRICHMENT is the average of the distributed fuel rod initial enrichments within a given axial plane of the assembly lattice.

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

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 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.

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 1-3 Renewed Amendment No. 3

Definitions 1.0 1.0 Definitions (continued)

ZR ZR means any zirconium-based fuel cladding or fuel channel material authorized for use in a commercial nuclear power plant reactor..

Certificate of Compliance No. 1014 Appendix B 1-4 Renewed Amendment No. 3

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 ZR 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.

a.

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

b.

All BWR fuel assemblies may be stored with or without ZR channels with the exception of array/class 10xi0D and 10xl OE fuel assemblies, which may be stored with or without ZR or stainless steel channels.

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

(continued)

Certificate of Compliance No. 1014 Appendix B 2-1 Renewed Amendment No. 3

Approved Contents 2.0 2.0 Approved Contents 2.1 Fuel Specifications and Loading Conditions (cont'd) 2.1.3 Reqionalized Fuel Loadinq 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 ZR cladding. Figures 2.1-1 through 2.1-4 define the regions for the MPC-24, MPC-24E, MPC-24EF, MPC-32, MPC-32F, MPC-68, and MPC-68FF models, respectively1. Fuel assembly burnup, decay heat, and cooling time limits for regionalized loading are specified in Section 2.4.2. 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.

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 Renewed Amendment No. 3

Approved Contents

2.0 LEGEND

REGION 1:

REGION 2:

[ I Figure 2.1-1 Fuel Loading Regions - MPC-24 Certificate of Compliance No. 1014 Appendix 8 2-3 Renewed Amendment No. 3

Approved Contents 2.0 LE]GEND:

REGION 1:

REGION 2:

I 91, Ll Figure 2.1-2 Fuel Loading Regions - MPC-24E/24EF Certificate of Compliance No. 1014 Appendix B 2-4 Renewed Amendment No. 3

Approved Contents

2.0 LEGEND

REGION 1:

REGION 2:

193 I

J

. I

. I I

I I I I

... t..

.. I......

..I J....

Figure 2.1-3 Fuel Loading Regions - MPC-32/32F Certificate of Compliance No. 1014 Appendix B 2-5 Renewed Amendment No. 3

Approved Contents

2.0 LEGEND

REGION 1:

REGION 2-:

90' 1

2 a*zNK A

3 4

6 7

8 I

45 0

4 59 50 J

XV ~

F

~

Y U

NP fl I '7, 61 95i U6V Illa 270' J

68 Figure 2.1-4 Fuel Loading Regions - MPC-68/68FF Certificate of Compliance No. 1014 Appendix B 2-6 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 1 of 39)

Fuel Assembly Limits I. MPC MODEL: MPC-24 A. Allowable Contents

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

a. Cladding Type:

b. Initial Enrichment:

ZR or Stainless Steel (SS) as specified in

• Table 2.1-2 for the applicable fuel assembly array/class.

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, and 15x1 5G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B Cooling time > 8 years and an average burnup < 40,000 MWD/MTU.

Cooling time and average burnup as specified in Section 2.4.

As specified in Table 2.1-8.

2-7 Renewed Amendment No. 3

Table 2.1-1 (page 2 of 39)

Fuel Assembly Limits Approved Contents 2.0 I. MPG MODEL: MPC-24 (continued)

A. Allowable Contents (continued) d.

Decay Heat Per Fuel Storage Location:

i.

Array/Classes 14x14D, 14x14E, and 15x15G ii All Other Array/Classes e.

Fuel Assembly Length:

f.

Fuel Assembly Width:

g.

Fuel Assembly Weight:

l 710 Watts As specified in Section 2.4.

} 176.8 inches (nominal design) l 8.54 inches (nominal design) l 1,680 lbs (including NON-FUEL HARDWARE)

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

C. Deleted.

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

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

Note 1:

Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, APSRs or NSAs 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 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 3 of 39)

Fuel Assembly Limits

11. 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:

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

c. Initial Maximum Rod Enrichment:

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

ZR or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array/class.

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

i. Array/Classes 6x6A, 6x6C, 7x7A, and 8x8A:

ii. Array/Class 8x8F iii. Array/Classes 10xlOD and 10xl0E iv. All Other Array/Classes Certificate of Compliance No. 1014 Appendix B Cooling time > 18 years and an average burnup < 30,000 MWD/MTU Cooling time > 10 years and an average burnup < 27,500 MWD/MTU.

Cooling time > 10 years and an average burnup < 22,500 MWD/MTU.

As specified in Section 2.4.

2-9 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 4 of 39)

Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)

A. Allowable Contents (continued)

e. Decay Heat Per Assembly:

i.

Array/Classes 6x6A, 6x6C, 7x7A, and 8x8A ii. Array/Class 8x8F iii. Array/Classes 10xlOD and 1 Oxl OE iv. All Other Array/Classes

f.

Fuel Assembly Length:

g. Fuel Assembly Width:

h. Fuel Assembly Weight:

Certificate of Compliance No. 1014 Appendix B

< 115 Watts

< 183.5 Watts.

< 95 Watts As specified in Section 2.4.

< 176.5 inches (nominal design)

< 5.85 inches (nominal design)

< 700 Ibs, including channels 2-10 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 5 of 39)

Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)

A. Allowable Contents (continued)

2. Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES, with orwithout 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:

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, and 8x8A ii.

All Other Array/Classes specified in Table 2.1-3

c. Initial Maximum Rod Enrichment:

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

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

4.0 wt% 2-U As specified in Table 2.1-3 for the applicable fuel assembly array/class.

i. Array/Classes 6x6A, 6x6C, 7x7A,and 8x8A ii. Array/Class 8x8F iii. Array/Classes 10x1 OD and 1 0x1 OE iv. All Other Array Classes Certificate of Compliance No. 1014 Appendix B Cooling time > 18 years and an average burnup < 30,000 MWD/MTU.

Cooling time > 10 years and an average burnup < 27,500 MWD/MTU.

Cooling time > 10 years and an average burnup _ 22,500 MWD/MTU.

As specified in Section 2.4.

2-11 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 6 of 39)

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 1 0x1 OD and

< 95 Watts 10xl0E iv.

All Other Array/Classes As specified ir

f. Fuel Assembly Length:

i.

Array/Class 6x6A, 6x6C, 7x7A,

< 135.0 inche, or8x8A ii.

All Other Array/Classes

< 176.5 inchec

g. Fuel Assembly Width:

i.

Array/Class 6x6A, 6x6C, 7x7A,

< 4.70 inches or8x8A ii.

All Other Array/Classes

< 5.85 inches

h. Fuel Assembly Weight:

i.

Array/Class 6x6A, 6x6C, 7x7A,

< 550 Ibs, inclL or 8x8A ii.

All Other Array/Classes

< 700 Ibs, inclu Section 2.4.

s (nominal design)

(nominal design)

(nominal design) nominal-design) iding channels and DFC ding channels and DFC Certificate of Compliance No. 1014 Appendix B 2-12 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 7 of 39)

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:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

c. Initial Maximum Rod Enrichment:

d.

Post-irradiation Cooling Time and Average Burnup Per Assembly:

e. Decay Heat Per Assembly:

f. Fuel Assembly Length:

g. Fuel Assembly Width:

h. Fuel Assembly Weight:

Certificate of Compliance No. 1014 Appendix B 2-As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

Cooling time > 18 years and an average burnup < 30,000 MWD/MTIHM.

< 115 Watts

< 135.0 inches (nominal design)

< 4.70 inches (nominal design)

< 400 Ibs, including channels 13 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 8 of 39)

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 DAMAGED FUEL CONTAINERS. MOX BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

c. Initial Maximum Rod Enrichment:

d.

Post-irradiation Cooling Time and Average Burnup Per Assembly:

e. Decay Heat Per Assembly:

f. Fuel Assembly Length:

g. Fuel Assembly Width:

h. Fuel Assembly Weight:

Certificate of Compliance No. 1014 Appendix B 2-As specified in Table 2.1-3 for array/class 6x6B.

As specified in Table 2.1-3 for array/class 6x6B.

Cooling time > 18 years and an average burnup < 30,000 MWD/MTIHM.

< 115 Watts

< 135.0 inches (nominal design)

< 4.70 inches (nominal design)

< 550 Ibs, including channels and DFC 14 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 9 of 39)

Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)

A. Allowable Contents (continued)

5.

Thoria rods (ThO2 and U0 2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

b. Composition:

c. Number of Rods Per Thoria Rod Canister:

d. Decay Heat Per Thoria Rod Canister:

e. Post-irradiation Fuel Cooling Time and Average Burnup Per Thoria Rod Canister:

f. Initial Heavy Metal Weight:

g. Fuel Cladding O.D.:

h. Fuel Cladding I.D.:

i. Fuel Pellet O.D.:

j. Active Fuel Length:

k. Canister Weight:

ZR 98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 23U.

<18

< 115 Watts A fuel post-irradiation cooling time > 18 years and an average burnup < 16,000 MWD/MTIHM.

< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches

< 550 Ibs, including fuel Certificate of Compliance No. 1014 Appendix B 2-15 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 10 of 39)

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 10xi0D and 10xl0E fuel assemblies in stainless steel channels must be stored 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 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 11 of 39)

Fuel Assembly Limits II1. MPC MODEL: MPC-68F A. Allowable Contents

1.

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

a. Cladding Type:

ZR b Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

c. Initial Maximum Rod Enrichment:

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

e. Decay Heat Per Assembly

f. Fuel Assembly Length:

g. Fuel Assembly Width:

h. Fuel Assembly Weight:

Certificate of Compliance No. 1014 Appendix B 2

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

Cooling time > 18 years and an average burnup < 30,000 MWD/MTU.

< 115 Watts

< 135.0 inches (nominal design)

< 4.70 inches (nominal design)

< 400 Ibs, including channels

-17 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 12 of 39)

Fuel Assembly Limits II1. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

2.

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

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

c. Initial Maximum Rod Enrichment:

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

e. Decay Heat Per Assembly:

f. Fuel Assembly Length:

g. Fuel Assembly Width:

h. Fuel Assembly Weight:

Certificate of Compliance No. 1014 Appendix B 2

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

Cooling time > 18 years and an average burnup < 30,000 MWD/MTU.

< 115 Watts

< 135.0 inches (nominal design)

< 4.70 inches (nominal design)

< 550 Ibs, including channels and DFC

.-18 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 13 of 39)

Fuel Assembly Limits I1l. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

3.

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

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

c Initial Maximum Rod Enrichment:

d. Post-irradiation Cooling Time and Average Burnup Per Assembly e, Decay Heat Per Assembly

f. Original Fuel Assembly Length

g. Original Fuel Assembly Width

h. Fuel Debris Weight Certificate of Compliance No. 1014 Appendix B As specified in Table 2.1-3 for the applicable original fuel assembly array/class.

As specified in Table 2.1-3 for the applicable original fuel assembly array/class.

Cooling time > 18 years and an average burnup <30,000 MWD/MTU for the original fuel assembly.

< 115 Watts

< 135.0 inches (nominal design)

< 4.70 inches (nominal design)

< 550 Ibs, including channels and DFC

?-1 9 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 14 of 39)

Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

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

a. Cladding Type:

ZR

b.

Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

c.

Initial Maximum Rod Enrichment:

d.

Post-irradiation Cooling Time and Average Burnup Per Assembly:

e. Decay Heat Per Assembly

f. Fuel Assembly Length:

g. Fuel Assembly Width:

h. Fuel Assembly Weight:

Certificate of Compliance No. 1014 Appendix B 2

As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

Cooling time > 18 years and an average burnup < 30,000 MWD/MTIHM.

< 115 Watts

< 135.0 inches (nominal design)

< 4.70 inches (nominal design)

< 400 Ibs, including channels

-20 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 15 of 39)

Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

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

a. Cladding Type:

ZR

b.

Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

c.

Initial Maximum Rod Enrichment:

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

e. Decay Heat Per Assembly

f. Fuel Assembly Length:

g. Fuel Assembly Width:

h. Fuel Assembly Weight:

Certificate of Compliance No. 1014 Appendix B As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

As specified in Table 2.1-3 for fuel assembly array/class 6x6B.

Cooling time > 18 years and an average burnup < 30,000 MWD/MTIHM.

< 115 Watts

< 135.0 inches (nominal design)

< 4.70 inches (nominal design)

< 550 Ibs, including channels and DFC 2-21 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 16 of 39)

Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

6.

Mixed Oxide (MOX), BWR FUEL DEBRIS, with orwithoutZR channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the MOX BWR FUEL DEBRIS shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:

a. Cladding Type:

ZR

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

c. Initial Maximum Rod Enrichment:

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

e. Decay Heat Per Assembly

f. Original Fuel Assembly Length:

g. OriginalFuel Assembly Width:

h. Fuel Debris Weight:

Certificate of Compliance No. 1014 Appendix 8 2

As specified in Table 2.1-3 for original fuel assembly array/class 6x6B.

As specified in Table 2.1-3 for original fuel assembly array/class 6x6B.

Cooling time > 18 years and an average burnup < 30,000 MWD/MTIHM for the original fuel assembly.

< 115 Watts

< 135.0 inches (nominal design)

< 4.70 inches (nominal design)

< 550 Ibs, including channels and DFC

-22 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 17 of 39)

Fuel Assembly Limits III. MPC MODEL: MPC-68F (continued)

A. Allowable Contents (continued)

7.

Thoria rods (ThO 2 and U0 2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

b. Composition:

c. Number of Rods Per Thoria Rod Canister:

d. Decay Heat Per Thoria Rod Canister:

e. Post-irradiation Fuel Cooling Time and Average Burnup Per Thoria Rod Canister:

f. Initial Heavy Metal Weight:

g. Fuel Cladding O.D.:

h. Fuel Cladding I.D.:

i. Fuel Pellet O.D.:

j. Active Fuel Length:

k. Canister Weight:

ZR 98.2 wt.% ThO2, 1.8-wt. % U0 2 with an enrichment of 93.5 wt. % 235 U.

<18

< 115 Watts A fuel post-irradiation cooling time > 18 years and an average burnup < 16,000 MWD/MTIHM.

< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches

< 550 Ibs, including fuel Certificate of Compliance No. 1014 Appendix B 2-23 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 18 of 39)

Fuel Assembly Limits Ill. 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 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 19 of 39)

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:

b. Initial Enrichment:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class 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, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B 2

Cooling time > 8 years and an average burnup < 40,000 MWD/MTU.

As specified in Section 2.4.

As specified in Table 2.1-8.

-25 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 20 of 39)

Fuel Assembly Limits IV. MPC MODEL: MPC-24E (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All other Array/Classes Fuel Assembly Length:

Fuel Assembly Width:

Fuel Assembly Weight:

e.

f.

g.

< 710 Watts.

As specified in Section 2.4.

< 176.8 inches (nominal design)

< 8.54 inches (nominal design)

< 1,680 lbs (including NON-FUEL HARDWARE)

Certificate of Compliance No. 1014 Appendix B 2-26 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 21 of 39)

Fuel Assembly Limits IV. MPC MODEL: MPC-24E (continued)

A. Allowable Contents (continued)

2.

Uranium oxide, PWR 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:

b. Initial Enrichment:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class 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, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B Cooling time > 8 years and an average burnup < 40,000 MWD/MTU.

As specified in Section 2.4.

As specified in Table 2.1-8.

2-27 Renewed Amendment No. 3

Table 2.1-1 (page 22 of 39)

Fuel Assembly Limits IV. MPC MODEL: MPC-24E (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

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

!::: 710 Watts.

Approved Contents 2.0 ii. All Other Array/Classes As specified in Section 2.4.

e.

Fuel Assembly Length f.

Fuel Assembly Width g.

Fuel Assembly Weight

!::: 176.8 inches (nominal design)

!::: 8.54 inches (nominal design)

!::: 1,680 lbs (including NON-FUEL HARDWARE and DFC) 8.

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.

D.

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

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration supressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, APSRs or NSAs 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 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 23 of 39)

Fuel Assembly Limits V. MPC MODEL: MPC-32 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:

b. Initial Enrichment:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class 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, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B Cooling time > 9 years and an average burnup < 30,000 MWD/MTU or cooling time > 20 years and an average burnup <

40,000 MWD/MTU.

As specified-in-Section 2.4.

As specified in Table 2.1-8.

2-29 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 24 of 39)

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

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes

e. Fuel Assembly Length

f.

Fuel Assembly Width

g. Fuel Assembly Weight Certificate of Compliance No. 1014 Appendix B 2-30

< 500 Watts As specified in Section 2.4.

< 176.8 inches (nominal design)

< 8.54 inches (nominal design)

< 1,680 lbs (including NON-FUEL HARDWARE)

Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 25 of 39)

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

A. Allowable Contents (continued)

2.

Uranium oxide, PWR 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:

b. Initial Enrichment:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for th-e-applicable fuel assembly array/class 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, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B Cooling time > 9 years and an average burnup <30,000 MWD/MTU or cooling time > 20 years and an average burnup <

40,000 MWD/MTU.

As specified in Section 2.4.

As specified in Table 2.1-8.

2-31 Renewed Amendment No. 3

Table 2.1-1 (page 26 of 39)

Fuel Assembly Limits V. MPG MODEL: MPC-32 (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

L Array/Classes 14x14D, t500 Watts.

14x14E, and 15x15G Approved Contents 2.0 ii. All Other Array/Classes As specified in Section 2.4.

e.

Fuel Assembly Length f.

Fuel Assembly Width g.

Fuel Assembly Weight t 176.8 inches (nominal design) t 8.54 inches (nominal design) t 1,680 lbs (including NON-FUEL HARDWARE and DFC)

8.. Quantity per MPG: Up to eight (8) DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 1, 4, 5, 10, 23, 28, 29, and/or 32. The remaining MPC-32 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-32.

D.

One NSA is authorized for loading in the MPC-32.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, APSRs or NSAs 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 2-32 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 27 of 39)

Fuel Assembly Limits VI. MPC MODEL: MPC-68FF A. Allowable Contents

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

a. Cladding Type:

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

c. Initial Maximum Rod Enrichment

e. Post-irradiation Cooling Time and Average Burnup Per Assembly ZR or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array/class As specified in Table 2.1-3 for the applicable fuel assembly array/class.

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

i. Array/Classes 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A ii. Array/Class 8x8F iii. Array/Classes 10xlOD and 1 0x1 OE iv. All Other Array/Classes Certificate of Compliance No. 1014 Appendix B Cooling time > 18 years and an average burnup < 30,000 MWD/MTU (or MTU/MTIHM).

Cooling time > 10 years and an average burnup < 27,500 MWD/MTU.

Cooling time > 10 years and an average burnup < 22,500 MWD/MTU.

As specified in Section 2.4.

2-33 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 28 of 39)

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 Wattc iii. Array/Classes 1OxIOD and

< 95 Watts 10xl0E iv. All Other Array/Classes As specified ii

f. Fuel Assembly Length

i. Array/Class 6x6A, 6x6B,

< 135.0 inche 6x6C, 7x7A, or 8x8A ii. All Other Array/Classes

< 176.5 inche.

g. Fuel Assembly Width

i. Array/Class 6x6A, 6x6B, 6x6C,

< 4.70 inches 7x7A, or 8x8A ii. All Other Array/Classes

< 5.85 inches

h. Fuel Assembly Weight

i. Array/Class 6x6A, 6x6B, 6x6C,

< 550 lbs, inch 7x7A, or 8x8A ii. All Other Array/Classes

< 700 lbs, incl S

n Section 2.4.

s (nominal design) s (nominal design)

(nominal design)

(nominal design) uding channels uding channels Certificate of Compliance No. 1014 Appendix B 2-34 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 29 of 39)

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:

ZR or Stainless Steel (SS) in accordance with Table 2.1-3 for the-6applicable fuel assembly array/class.

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

i. Array/Classes 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A.

ii. All Other Array Classes

c.

Initial Maximum Rod Enrichment

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

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

< 4.0 wt.% 23 U.

As specified in Table 2.1-3 for the applicable fuel assembly array/class.

i.

Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A ii.

Array/Class 8x8F iii.

Array/Class 1 0x1 OD and 10x10E iv.

All Other Array/Classes Certificate of Compliance No. 1014 Appendix B Cooling time > 18 years and an average burnup < 30,000 MWD/MTU (or MWD/MTIHM).

Cooling time> 10 years and an average burnup < 27,500 MWD/MTU.

Cooling time > 10 years and an average burnup < 22,500 MWD/MTU.

As specified in Section 2.4.

2-35 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 30 of 39)

Fuel Assembly Limits Vl. MPC MODEL: MPC-68FF (continued)

A. Allowable Contents (continued)

e. Decay Heat Per Assembly

i.

Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A ii.

Array/Class 8x8F iii.

Array/Classes 10xl0D and 10x10E iv.

All Other Array/Classes

f. Fuel Assembly Length

i.

Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A ii.

All Other Array/Classes

g. Fuel Assembly Width

i.

Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A ii.

All Other Array/Classes

h. Fuel Assembly Weight I.

Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A ii.

All Other Array/Classes Certificate of Compliance No. 1014 Appendix B

< 115 Watts

< 183.5 Watts

< 95 Watts As specified in Section 2.4.

< 135.0 inches (nominal design)

< 176.5 inches (nominal design)

< 4.70 inches (nominal design)

< 5.85 inches (nominal design)

< 550 Ibs, including channels and DFC

< 700 lbs, including channels and DFC 36 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 31 of 39)

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 shall be in a water rod location.

D. Array/Class 1 0x1 OD and 1 0x1 OE fuel assemblies in stainless steel channels must be stored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 - 50.

Certificate of Compliance No. 1014 Appendix B 2-37 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 32 of 39)

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:

b. Initial Enrichment:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class 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, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B Cooling time > 8 years and an average burnup < 40,000 MWD/MTU.

As specified in Section 2.4.

As specified in Table 2.1-8.

38 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 33 of 39)

Fuel Assembly Limits VII. MPC MODEL: MPC-24EF (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All other Array/Classes

e. Fuel Assembly Length:

f.

Fuel Assembly Width:

g. Fuel Assembly Weight:

Certificate of Compliance No. 1014 Appendix B

< 710 Watts.

As specified in Section 2.4.

< 176.8 inches (nominal design)

< 8.54 inches (nominal design)

_< 1,680 lbs (including NON-FUEL HARDWARE) 2-39 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 34 of 39)

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:

b. Initial Enrichment:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class 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, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B Cooling time > 8 years and an average burnup < 40,000 MWD/MTU.

As specified in Section 2.4.

As specified in Table 2.1-8.

2-40 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 35 of 39)

Fuel Assembly Limits VII. MPG MODEL: MPC-24EF (continued)

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes e.

Fuel Assembly Length f.

Fuel Assembly Width g.

Fuel Assembly Weight

.=:: 710 Watts.

As specified in Section 2.4.

.=:: 176.8 inches (nominal design)

.=:: 8.54 inches (nominal design)

.=:: 1,680 lbs (including NON-FUEL HARDWARE and DFC) 8.

Quantity per MPG: 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.

C.

One NSA is permitted for loading in the MPC-24EF.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, APSRs or NSAs may only be loaded in fuel storage locations 9, 1 O, 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 2-41 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 36 of 39)

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

1.

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

a. Cladding Type:

b. Initial Enrichment:

ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class 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, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B Cooling time_> 9 years and an average burnup <30,000 MWD/MTU or cooling time > 20 years and an average burnup <

40,000 MWD/MTU.

As specified in Section 2.4.

As specified in Table 2.1-8.

2-42 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 37 of 39)

Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (cont'd)

A.

Allowable Contents (cont'd)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes

e. Fuel Assembly Length

f.

Fuel Assembly Width

g. Fuel Assembly Weight Certificate of Compliance No. 1014 Appendix B

< 500 Watts.

As specified in Section 2.4.

< 176.8 inches (nominal design)

< 8.54 inches (nominal design)

< 1,680 lbs (including NON-FUEL HARDWARE) 2-43 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 38 of 39)

Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (cont'd)

A.

Allowabe Contents (c-nt'd)...

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. CladdingType"....

b. Initial Enrichment:

ZR -or-Stainless Steel (SS) as-specified in Table 2.1-2 for the applicable fuel assembly array/class 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, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B Cooling time > 9 years and an average burnup <30,000 MWD/MTU or cooling time > 20 years and an average burnup <

40,000 MWD/MTU.

As specified in Section 2.4.

As specified in Table 2.1-8.

2-44 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-1 (page 39 of 39)

Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (cont'd)

A.

Allowable Contents (cont'd)

d. Decay Heat Per Fuel Storage Location:

i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes

e. Fuel Assembly Length f.

Fuel Assembly Width

g. Fuel Assembly Weight

.s 500 Watts.

As specified in Section 2.3.

.s 176.8 inches (nominal design)

.s 8.54 inches (nominal design)

.s 1,680 lbs (including NON-FUEL HARDWARE and DFC)

B.

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

C.

One NSA is permitted for loading in the MPC-32F.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, APSRs or NSAs 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 2-45 Renewed Amendment No. 3

Table 2.1-2 (page 1 of 4)

Approved Contents 2.0 PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 14x14A Array/Class Clad Material ZR Design Initial U s 365 (kg/assy.) (Note 3)

Initial Enrichment (MPC-24, 24E and S 4.6 (24) 24EF without soluble boron s5.0 credit)

(24E/24EF)

(wt% 235U)

(Note 7)

Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F s5.o with soluble boron credit - see Note 5)

(wt% 23sU)

No. of Fuel Rod 179 Locations Fuel Rod Clad O.D.

,:!0.400 (in.)

Fuel Rod Clad 1.D.

_s 0.3514 (in.)

Fuel Pellet Dia.

(in.)

_s 0.3444 (Note 8)

Fuel Rod Pitch (in.)

.s 0.556 Active Fuel Length

.s 150 (in.)

No. of Guide and/or 17 Instrument Tubes G uide/lnstrument Tube

.:! 0.017 Thickness (in.}

Certificate of Compliance No. 1014 Appendix B 14x14B 14x14C 14x14D 14x14E ZR ZR ss ss S 412

.:5.438

.:5.400

.:5.206 s 4.6 (24) s 4.6 (24)

.:5.4.0 (24) s 5.0 (24) s5.o s5.0 s5.o sS.O (24E/24EF)

(24E/24EF)

(24E/24EF)

(24E/24EF) s5.o s5.0 sS.O ss.o 179 176 180 173

.:! 0.417

.:! 0.440

.:! 0.422

.:! 0.3415

_s 0.3734 s0.3880

.s 0.3890

.s 0.3175 s0.3659 s 0.3805

.s0.3835 s 0.3130

.s 0.556

.s 0.580 s0.556 Note 6

.s 150

.s 150

.s 144

.s 102 17 5 (Note 4) 16 0

.:! 0.017

.:! 0.038

.:! 0.0145 NIA 2-46 Renewed Amendment No. 3

Table 2.1-2 (page 2 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class Clad Material Design Initial U (kg/assy.)

(Note 3)

Initial Enrichment (MPC-24, 24E and

• 24EF without soluble boron credit)

- (wt% 23su)

(Note 7)

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

(wt% 235U)

No. of Fuel Rod Locations Fuel Rod Clad O.D.

(in.)

Fuel Rod Clad I.D.

(in.)

Fuel Pellet Dia. (in.)

(Note 8)

Fuel Rod Pitch {in.)

Active Fuel Length (in.)

No. of Guide and/or Instrument Tubes Guide/Instrument Tube Thickness (in.)

15x15A ZR

,:s 473

,:s 4.1 (24)

,:s 4.5 (24E/24EF)

,:s 5.0 204

' 0.418

,:s 0.3660

!S 0.3580

!S 0.550

,:s 150 21

' 0.0165 Certificate of Compliance No. 1014 Appendix B 15x15B 15x15C 15x15D ZR ZR ZR

!S473

!S473

!S495

,:s 4.1 (24)

,:s 4.1 (24)

!S 4.1 (24)

,:s 4.5

!S4.5

!S 4.5 (24E/24EF) _ (24E/24EF)

(24E/24EF)

!S5.0

!S 5.0

!S5.0 204 204 208

' 0.420

' 0.417

' 0.430

!S 0.3736

,:s 0.3640

!S0.3800

!S 0.3671

!S 0.3570

!:0.3735

!S 0.563

!S0.563

!S 0.568

,:s 150

,:s 150

!S 150 21 21 17

'0.015

'0.0165

'0.0150 2-47 Approved Contents 2.0 15x15E

- 15x15F ZR ZR

,:s 495

!S495

!S4.1 (24)

,:s 4.1 (24)

,:s 4.5

!S4.5 (24E/24EF)

(24E/24EF)

,:s 5.0

!S5,0 208 208

' 0.428

'0.428

!S 0.3790

!S 0.3820

!S 0.3707

!S 0.3742

,:s 0.568

,:s 0.568

,:s 150

!S 150 17 17

' 0.0140

'0.0140 Renewed Amendment No. 3

Table 2.1-2 (page 3 of 4)

Approved Contents 2.0 PW R FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly 15x15G Array/ Class Clad Material ss Design Initial U (kg/assy.)

.s 420 (Note 3)

Initial Enrichment (MPC-24, 24E, and

.s 4.0 (24) 24EF without soluble boron

.54.5 credit)

(24E/24EF)

(wt% 2JsU)

(Note-7)

Initial Enrichment (MPC-24, 24E, 24EF,32,or32F

.55.0 with soluble boron credit - see Note 5)

(wt% 23sU)

No. of Fuel Rod 204 Locations Fuel Rod Clad O.D.

>0.422 (in.)

Fuel Rod Clad I.D.

.s 0.3890 (in.)

Fuel Pellet Dia.

(in.)

.s 0.3825 (Note 8)

Fuel Rod Pitch (in.)

.s 0.563 Active Fuel Length

.s 144 (in.)

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

>0.0145 Thickness (in.)

Certificate of Compliance No. 1014 Appendix B 15x15H ZR

.s 495 S 3.8 (24)

<4.2 (24E/24EF)

.s 5.0 208 0.414

_:s0.3700

.S 0.3622

.50.568

.:s 150 17 0.0140 16x16A 17x17A 17x178 17x17C ZR ZR ZR ZR

.s 448

.s 433

.s 474

.5480

.s 4.6 (24)

.s 4.0 (24)

.s 4.0 (24)

.s 4.0 (24)

.s 5.0

.54.4

.s 4.4

.s 4.4 (24E/24EF)

(24E/24EF)

(24E/24EF)

(24E/24EF)

.s 5.0 s 5.0

.s 5.0

.55.0 236 264 264 264

>0.382 0.360 0.372

>0.377

.s 0.3320

.s 0.3150

.s 0.3310

.s 0.3330

.s 0.3255

.s 0.3088

.S 0.3232

.s 0.3252

.50.506

.s 0.496

.s 0.496

.s 0.502

.:s 150

.:s 150

.:s 150

.s 150 5 (Note 4) 25 25 25

>0.0400

>0.016 0.014 0.020 2-48 Renewed Amendment No. 3

Table 2.1-2 (page 4 of 4)

PWR FUEL ASSEMBLY CHARACTERISTICS Notes:

Approved Contents 2.0

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

2. Deleted.

3. Design initial uranium weight i$ 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 manufacturer's 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.

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

Certificate of Compliance No. 1014 Appendix B 2-49 Renewed Amendment No. 3

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

<110

<110

<110

<100

<198

<120 Maximum PLANAR-

< 2.7 for the AVERAGE INITIAL UO2 rods.

ENRICHMENT

< 2.7 See Note 4

< 2.7

< 2.7

< 4.2

< 2.7 (wt.% 235U) for MOX (Nbtdf4)-

rods Initial Maximum Rod Enrichment

< 4.0

< 4.0

< 4.0

< 5.5

< 5.0

< 4.0 (wt.% 2-U)

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

Fuel Rod Clad O.D.

(in.)

> 0.5550

> 0.5625

> 0.5630

> 0.4860

> 0.5630

> 0.4120 Fuel Rod Clad 1.0.

(in.)

< 0.5105

< 0.4945

< 0.4990

< 0.4204

< 0.4990

< 0.3620 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 ActiveFuelLength

< 120

< 120

< 77.5

< 80

< 150

< 120 (in.)

No. of Water Rods 1 orO 1 orO 0

0 0

1 orO (Note 11)

__r__1or0_

0 0

1_or_0 Water Rod Thickness (in.)

> 0

> 0 N/A N/A N/A

> 0 Channel Thickness (in.)

< 0.060

< 0.060

< 0.060

< 0.060

<0.120

< 0.100 Certificate of Compliance No. 1014 Appendix B 2-50 Renewed Amendment No. 3

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 ZR ZR Design Initial U (kg/assy.) (Note 3)

<192

< 190

<190

<190

<191

<180 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT

< 4.2

< 4.2

< 4.2

< 4.2

< 4.0

< 4.2 (wt.% 2-U)

(Note 14)

Initial Maximum Rod Enrichment

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0 (wt.% 2U)

No. of Fuel Rod 74/66 No.tof 63 or 64 62 60 or 61 59 64 74/66 Locations

_______(Note 5)

Fuel Rod Clad O.D.

(in.)

> 0.4840

> 0.4830

> 0.4830

> 0.4930

> 0.4576

> 0.4400 Fuel Rod Clad I.D.

(in.)

< 0.4295

<0.4250

< 0.4230

< 0.4250

< 0.3996

< 0.3840 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 Length (in.)

<150

<150

<150

<150

<150

<150 No. of Water Rods 1orO 2

1-4 N/A 2

(Note 11) 1_or 0_2 (Note 7)

(Note 12) 2 Water Rod Thickness (in.)

> 0.034

> 0.00

> 0.00

> 0.034

> 0.0315

> 0.00 Channel Thickness (in.)

< 0.120

< 0.120

< 0.120

< 0.100

< 0.055

< 0.120 Certificate of Compliance No. 1014 Appendix B 2-51 Renewed Amendment No. 3

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

ASSEMBLY CHARACTERISTICS (Note 1)

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

(Note 13)

Clad Material ZR ZR ZR ZR ZR ZR Design Initial U

< 1

<183

<183

<164 (kg/assy.) (Note 3)

<180

<182

<182 Maximum PLANAR-AVERAGE INITIAL

-ENRICHMENT

< 4.2

< 4.2

< 4.2

< 4.0

< 4.0

<4.2 (wt.% 2U)

(Note 14)

Initial Maximum Rod Enrichment

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0 (wt.% 2U)

No. of Fuel Rod 72 80 79 76 76 72 Locations Fuel Rod Clad O.D.

(in.)

> 0.4330

> 0.4230

> 0.4240

> 0.4170

> 0.4430

> 0.4240 Fuel Rod Clad I.D.

(in.)

<0.3810

< 0.3640

<0.3640

<0.3640

<0.3860

<0.3640 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 Length (in.)

<_5__5__5__5

<_150_<_150 No. of Water Rods 1 (Note 6) 1 2

5

(

1 (Note 11) 1_(Noe__)_

2

_(Note 6) water Rod Thickness (in.)

> 0.00

> 0.020

> 0.0300

> 0.0120

> 0.0120

> 0.0320 (in.)

Channel Thickness (in.)

_< 0.120 -T

< 0.100

_< 0.100

_< 0.120

_< 0.120

_< 0.120 Certificate of Compliance No. 1014 Appendix B 2-52 Renewed Amendment No. 3

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

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 1OxlOA 10x10B 1Oxl0C lOxIOD 1Oxl0E Clad Material ZR ZR ZR SS SS Design Initial U (kglassy.) (Note 3)

<188

< 188

<179

<125

<125 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT

<4.2

<4.2

<4.2

<4.0

<4.0 (wt.% MiU)

(Note 14)

Initial-Maximum Rod Enrichment (wt.% -SU)

< 5.0

.5.0 5.0

5.

< 5.

No. of Fuel Rod Locations 92178 91/83 (Note 8)

(Note 9) 96 100 96 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 1

< 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

<50.055

< 0.080

< 0.080 Certificate of Compliance No. 1014 Appendix B 2-53 Renewed Amendment No. 3

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.

Deleted.

3.

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

4.

< 0.635 wt. % 2 5U and < 1.578 wt. % total fissile plutonium (239Pu and 241Pu), (wt. % of total fuel weight, i.e., U0 2 plus PuO 2).

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.

11i 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.% 21U, as applicable.

Certificate of Compliance No. 1014 Appendix B 2-54 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-4 TABLE DELETED Certificate of Compliance No. 1014 Appendix B 2-55 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-5 TABLE DELETED Certificate of Compliance No. 1014 Appendix B 2-56 Renewed Amendment No. 3

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

TABLE DELETED Certificate of Compliance No. 1014 Appendix B 2-57 Renewed Amendment No. 3

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

TABLE DELETED Certificate of Compliance No. 1014 Appendix B 2-58 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-7 (page 1 of 2)

TABLE DELETED Certificate of Compliance No. 1014 Appendix B 2-59 Renewed Amendment No. 3

Approved Contents 2.0 Table 2.1-7 (page 2 of 2)

TABLE DELETED Certificate of Compliance No. 1014 Appendix B 2-60 Renewed Amendment No. 3

Table 2.1-8 Approved Contents 2.0 NON-FUEL HARDWARE COOLING AND AVERAGE BURNUP (Notes 1, 2, and 3)

Post-Irradiation Cooling Time (years)

?:.3

?:.4

?:.5

?:.6

?:.7

?:.8

?:.9

?:,.10

?:. 11

?:,.12

?:. 13

?:. 14 INSERTS (Note 4)

BURNUP (MWO/MTU) s24,635 s3o,ooo S 36,748 S 44,102 s52,900 S 60,000 NSAorGUIDE TUBE HARDWARE (Note 5)

BURNUP (MWD/MTU)

NA (Note 7) s20,ooo s25,ooo s 30,000 s4o,ooo s 45,000 s 50,000 s 60,000 s 75,000 S 90,000

!: 180,000 s 630,000 CONTROL COMPONENT (Note 6)

BURNUP (MWD/MTU)

NA NA s63o,ooo APSR BURNUP (MWD/MTU)

NA NA

!: 45,000 s54,500 s 68,000 s 83,000

• s 111,000 S 180,000 s 630,000 Notes: 1. Burnups for NON-FUEL HARDWARE are to be determined based on the burnup and uranium mass of the fuel assemblies in which the component was inserted during reactor operation.

2.

Linear interpolation between points is permitted, except that NSA or Guide Tube Hardware and APSR burnups > 180,000 MWD/MTU ands 630,000 MWD/MTU must be cooled?:. 14 years and?:. 11 years, respectively.

3.

Applicable to uniform loading and regionalized loading.

4.

Includes Burnable Poison Rod Assemblies {BPRAs), Wet Annular Burnable Absorbers (WABAs), and vibration suppressor inserts..

5.

Includes Thimble Plug Devices {TPDs), water displacement guide tube plugs, and orifice rod assemblies.

6.

Includes Control Rod Assemblies {CRAs), Control Element Assemblies {CEAs), and Rod Cluster Control Assemblies {RCCAs).

7.

NA means not authorized for loading at this cooling time.

2-61 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 2.4 Decay Heat, Burnup, and Cooling Time Limits for ZR-Clad Fuel This section provides the limits on ZR-clad fuel assembly decay heat, burnup, and cooling time for storage in the HI-STORM 100 System. A detailed discussion of how to calculate the limits and verify compliance, including examples, is provided in Chapter 12 of the HI-STORM 100 FSAR.

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

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

MPC Mode II Decay Heat per Fuel Storage Location I_

(kW)

Intact Fuel Assemblies MPC-24

< 1.157 MPC-24E/24EF

< 1.173 MPC-32/32F

< 0.898 MPC-68/68FF

< 0.414 Damaged Fuel Assemblies and Fuel Debris MPC-24

< 1.099 MPC-24E/24EF

< 1.114 MPC-32/32F

< 0.718 MPC-68/68FF

< 0.393 2.4.2 Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel Table 2.4-2 provides the maximum allowable decay heat per fuel storage location for ZR-clad fuel in regionalized loading for each MPC model.

2-62 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 2.4.2 Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel (cont'd)

Table 2.4-2 Fuel Storage Regions and Maximum Decay Heat per MPC Number of Fuel Inner Region Outer Region MPC Model Storage Locations Maximum Decay Maximum Decay in Inner and Outer Heat per Assembly Heat per Assembly Regions (kW)

(kW)

MPC-24 4 and 20 1.470 0.900 MPC-24E/24EF 4 and 20 1.540 0.900 MPC-32/32F 12 and 20 1.131 0.600 MPC-68/68FF 32 and 36 0.500 0.275 2.4.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel The maximum allowable fuel assembly average burnup varies with the following parameters:

0 0

0 Minimum fuel assembly cooling time Maximum fuel assembly decay heat Minimum fuel assembly average enrichment The maximum allowable ZR-clad fuel assembly average burnup for a given MINIMUM ENRICHMENT is calculated as described below for minimum cooling times between 3 and 20 years using the maximum permissible decay heat determined in Section 2.4.1 or 2.4.2.

Different fuel assembly average burnup limits may be calculated for different-minimum enrichments (by individual fuel assembly) for use in choosing the fuel assemblies to be loaded into a given MPC.

2.4.3.1 Choose a fuel assembly minimum enrichment, F_2.

2.4.3.2 Calculate the maximum allowable fuel assembly average burnup for a minimum cooling time between 3 and 20 years using the equation below.

Bu = (A x q) + (B x q1) + (C x q3) + [D x (E) 21 + (E x q x E) + (F x q2 x E)

+ G Equation 2.4.3 Where:

Bu = Maximum allowable average burnup per fuel assembly (MWD/MTU) 2-63 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 2.4.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel (cont'd) q Maximum allowable decay heat per fuel storage location determined in Section 2.4.1 or 2.4.2 (kW)

E23 = Minimum fuel assembly average enrichment (wt. % 23U)

(e.g., for 4.05 wt.%, use 4.05)

A through G =

Coefficients from Tables 2.4-3 and 2.4-4 for the applicable fuel assembly array/class and minimum cooling time 2.4.3.3 Calculated burnup limits shall be rounded down to the nearest integer.

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

2.4.3.5 Linear interpolation of calculated burnups between cooling times for a given fuel assembly maximum decay heat and minimum enrichment is permitted. For example, the allowable burnup for a cooling time of 4.5 years may be interpolated between those burnups calculated for 4 year and 5 years.

2.4.3.6 Each ZR-clad fuel assembly to be stored must have a MINIMUM ENRICHMENT greater than or equal to the value used in Step 2.4.3.2.

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

2-64 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Cooling Time (years}

n3 n4

>5 n6 n7

-n8 n9 n10

 11 n12

13 n14 n'15 r16 r17 r18

19 r20 Table 2.4-3 (Page 1 of 8)

Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

A 20277.1 35560.1 48917.9 59110.3 67595.6 74.424.9 81405.8 86184.3 92024.9 94775.8 100163 103971 q108919 110622 115582 119195 121882 124649 B

303.592

-6034.67

-14499.5

-22507

-30158.1

-3687j.1

-44093.1

-49211.7

-55666;8

-58559.7

-64813.8

-69171

-75171.1

-76715.2

-82929.7

-87323.5

-90270.6

-93573.5 Array/Class 14x14A C

-68.329 985.415 2976.09 5255.61 7746.6 10169.4 12910.8 15063.4 11779.6 19249.9 22045.1 24207 27152.4 28210.2 31411.9 33881.4 35713.7 37853.1 2-65 D

-139.41

-132.734

-150o707

-177.017

-200.128

-218.676

-227.916

-237.641

-240.973

-246.369

-242.572

-242.651

-243.154

-240.235

-235.234

-233.28

-231.873

-230.22 E

2993.67 3578.92 4072p55 4517.03 4898.71 5203.64 5405.34 5607.96 5732.25 5896.27 5861.86 5933.96 6000.2 6028.33 5982.3 6002.43 6044.42 6075.82 F

-498.159

-723.721

-892.691

-1024.01

-1123.21

-1190.24

-1223.27

-1266.21

-1282.12

-1345.42

-1261.66

-1277.48

-1301.19

-1307.74

-1244.11

-1245.95

-1284.55

-1306.57 G

-615.411

-609.84

-54.8362 613.36 716.004 741.163 250.224 134.435

-401.456

-295.435

-842.159

-1108.99

-1620.63

-1425.5

-1948.05

-2199.41

-2264.05

-2319.63 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-3 (Page 2 of 8)

PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 14x14B Time (years)

A B

C D

E F

G

> 3 18937.9 70.2997

-28.6224

-130.732 2572.36

-383.393

-858.17

> 4 32058.7

-4960.63 745.224

-125.978 3048.98

-551.656

-549.108

> 5 42626.3

-10804.1 1965.09

-139.722 3433.49

-676.643 321.88

> 6 51209.6

-16782.3 3490.45

-158.929 3751.01

-761.524 847.282

> 7 57829.9

-21982 5009.12

-180.026 4066.65

-846.272 1200.45

> 8 62758

-26055.3 6330.88

-196.804 4340.18

-928.336 1413.17

> 9 68161.4

-30827.6 7943.87

-204.454 4500.52

-966.347 1084.69

> 10 71996.8

-34224.3 9197.25

-210.433 4638.94

-1001.83 1016.38

> 11 75567.3

-37486.1 10466.9

-214.95 4759.55

-1040.85 848.169

> 12 79296.7

-40900.3 11799.6

-212.898 4794.13

-1040.51 576.242

> 13 82257.3

-43594 12935

-212.8 4845.81

-1056.01 410.807

> 14 83941.2

-44915.2 13641

-215.389 4953.19

-1121.71 552.724

> 15 87228.5

-48130 15056.9

-212.545 4951.12

-1112.5 260.194

> 16 90321.7

-50918.3 16285.5

-206.094 4923.36

-1106.35

-38.7487

> 17 92836.2

-53314.5 17481.7

-203.139 4924.61

-1109.32

-159.673

> 18 93872.8

-53721.4 17865.1

-202.573 4956.21

-1136.9 30.0594

> 19 96361.6

-56019.1 19075.9

-199.068 4954.59

-1156.07

-125.917

> 20 98647.5

-57795.1 19961.8

-191.502 4869.59

-1108.74

-217.603 2-66 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-3 (Page 3 of 8)

PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 14x1 4C Time (years)

A B

C D

E F

G

> 3 19176.9 192.012

-66.7595

-138.112 2666.73

-407.664

-1372.41

> 4 32040.3

-4731.4 651.014

-124.944 3012.63

-530.456

-890.059

> 5 43276.7

-11292.8 2009.76

-142.172 3313.91

-594.917

-200.195

>6 51315.5

-16920.5 3414.76

-164.287 3610.77

-652.118 463.041

> 7 57594.7

-21897.6 4848.49

-189.606 3940.67

-729.367 781.46

> 8 63252.3

-26562.8 6273.01

-199.974 4088.41

-732.054 693.879

> 9 67657.5

-30350.9 7533.4

-211.77 4283.39

-772.916 588.456

> 10 71834.4

-34113.7 8857.32

-216.408 4383.45

-774.982 380.243

> 11 75464.1

-37382.1 10063

-218.813 4460.69

-776.665 160.668

> 12 77811.1

-39425.1 10934.3

-225.193 4604.68

-833.459 182.463

> 13 81438.3

-42785.4 12239.9

-220.943 4597.28

-803.32

-191.636

> 14 84222.1

-45291.6 13287.9

-218.366 4608.13

-791.655

-354.59

>_ 15 86700.1

-47582.6 14331.2

-218.206 4655.34

-807.366

-487.316

> 16 88104.7

-48601.1 14927.9

-219.498 4729.97

-849.446

-373.196

> 17 91103.3

-51332.5 16129

-212.138 4679.91

-822.896

-654.296

> 18 93850.4

-53915.8 17336.9

-207.666 4652.65

-799.697

-866.307

> 19 96192.9

-55955.8 18359.3

-203.462 4642.65

-800.315

-1007.75

> 20 97790.4

-57058.1 19027.7

-200.963 4635.88

-799.721

-951.122 2-67 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Cooling Time (years) 2!3 2!4 2!5 2!6 2!7 2!8 2!9 2!10 2! 11 2! 12 2! 13 2! 14 15 2! 16 17 2! 18 19

>20 Table 2.4-3 (Page 4 of 8)

Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

A 1§.789.2 26803.8 36403.6 44046.1 49753.5 55095.4 58974.4 62591.8 65133.1 68448.4 71084.4 73459.5 75950.7 76929.1 79730 81649.2 83459 86165.4 B

119.829

-3312.93

-7831.93

-12375.9

-16172.6

-20182.5

-23071.6

-25800.8

-27747.4

-30456

-32536.4

-34352.3

-36469.4

-36845.6

-39134.8

-40583

-41TT1.8

-44208.8 Array/Class 15x15A/B/C C.8071 415.027 1219.66 2213.52 3163.61 4287.03 5156.53 5995.95 6689 7624.9 8381.78 9068.86 9920.52 10171.3 11069.4 11736.1 12265.9 13361.2 2-68 D

• -27.422

-116.279

-126.065

-145.727

-166.946

-183.047

-191.718

-195.105

-203.095

-202.201

-201.624

-197.988

-199.791

-197.88

-190.865

-187.604

-181.461

-178.89 E

2152.53 2550.15 2858.32 3153.45 3428.38 3650.42 3805.41 3884.14 4036.91 4083.52 4117.93 4113.16 4184.91 4206.24 4160.42 4163.36 4107.51 4107.62 F

-267.117

-386.33

-471.785

-539.715

-603.598

-652.92

-687.18

-690.659

-744.034

-753.391

-757.16

-747.015

-TT9.222

-794.541

-773.448

-785.838

-758.496

-768.671 G

-5803-68

-367.168 326.863 851.971 1186.31 1052.4 1025 868.556 894.607 577.914 379.105 266.536 57.9429 256.099

-42.6853

-113.614

-193.442

-479.778 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Cooling Time (years)

3 4

5 6

7 8

9 2:10 11 2:12 13 14 2: 15

-- 16 17 18 19

>20 Table 2.4-3 (Page 5 of 8)

Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

A 15192.5 25782.5 35026.5 42234.9 47818.4 52730.7 56254.6 59874.6 62811 65557.6 67379.4 69599.2 71806.7 73662.6 76219.8

- -. --

76594.4 78592.7 80770.5 B

§0.5722

-3096.5

-7299.87

-11438.4

-15047

-18387.2

-20999.9

-23706.5

-25848.4

-27952.4

-29239.2

-30823.8

-32425

-33703.5

-35898.1

---

--

-35518.2

-36920.8

-38599.9 Array/Class 1Sx15D/E/F/H C

D E 2.3042

-26.906 2009.71 369.096

-113.289 2357.75 1091.93

-124.619 2664 1967.63

-145.948 2945.81 2839.22

-167.273 3208.95 3702.43

-175.057 3335.58 4485.93

-190.489 3547.98 5303.88

-193.807 3633.01 5979.64

-194.997 3694.14 6686.74

-198.224 3767.28 719_7.49

-200.164 3858.53 7768.51

-196.788 3868.2 8360.38

-191.935 3851.65 8870.78

-187.366 3831.59 9754.72

-189.111 3892.07 9719.78

-185.11 3897.04 10316.5

-179.54 3865.84 11051.3

-175.106 3858.67 2-69 F

-235.879

-334.695

-414.527

-474.981

-531.296

-543.232

-600.64

-611.892

-618.968

-635.126

-677.958

-679.88

-669.917

-658.419

-694.244

-712.82

-709.551

-723.211 G 1.574

-254.964 470.916 1016.84 1321.12 1223.61 1261.55 1028.63 862.738 645.139 652.601 504.443 321.146 232.335

-46.924 236.047 82.478

-116.014 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-3 (Page 6 of 8)

PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 16X16A Time (years)

A B

C D

E F

G

> 3 17038.2 158.445

-37.6008

-1 36.707

-2368-1 1.58

-700.033

> 4 29166.3

-3919.95 508.439

-125.131 2782.53

-455.722

-344.199

> 5 40285

-9762.36 1629.72

-139.652 3111.83

-539.804 139.67

> 6 48335.7

-15002.6 2864.09

-164.702 3444.97

-614.756 851.706

> 7 55274.9

-20190 4258.03

-185.909 3728.11

-670.841 920.035

> 8 60646.6

-24402.4 5483.54

-199.014 3903.29

-682.26 944.913

> 9 64663.2

-27753.1 6588.21

-215.318 4145.34

-746.822 967.914

> 10 69306.9

-31739.1 7892.13

-218.898 4237.04

-746.815 589.277

> 11 72725.8

-34676.6 8942.26

-220.836 4312.93

-750.85 407.133

> 12 76573.8

-38238.7 10248.1

-224.934 4395.85

-757.914 23.7549

> 13 78569

-39794.3 10914.9

-224.584 4457

-776.876 69.428

> 14 81559.4

-42453.6 11969.6

-222.704 4485.28

-778.427

-203.031

> 15 84108.6

-44680.4 12897.8

-218.387 4460

-746.756

-329.078

> 16 86512.2

-46766.8 13822.8

-216.278 4487.79

-759.882

-479.729

> 17 87526.7

-47326.2 14221

-218.894 4567.68

-805.659

-273.692

> 18 90340.3

-49888.6 15349.8

-212.139 4506.29

-762.236

-513.316

> 19 93218.2

-52436.7 16482.4

-207.653 4504.12

-776.489

-837.1

> 20 95533.9

-54474.1 17484.2

-203.094 4476.21

-760.482

-955.662 2-70 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-3 (Page 7 of 8)

PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 17x17A Time (years)

A B

C D

E F

G

> 3 16784.4 3.90244

-10.476

-128.835 2256.98

-287;108

-263.081

> 4 28859

-3824.72 491.016

-120.108 2737.65

-432.361

-113.457

> 5 40315.9

-9724 1622.89

-140.459 3170.28

-547.749 425.1,36

> 6 49378.5

-15653.1 3029.25

-164.712 3532.55

-628.93 842.73

> 7 56759.5

-21320.4 4598.78

-190.58 3873.21

-698.143 975.46

> 8 63153.4

-26463.8 6102.47

-201.262 4021.84

-685.431 848.497

> 9 67874.9

-30519.2 7442.84

-218.184 4287.23

-754.597 723.305

> 10 72676.8

-34855.2 8928.27

-222.423 4382.07

-741.243 387.877

> 11 75623

-37457.1 9927.65

-232.962 4564.55

-792.051 388.402

> 12 80141.8

-41736.5 11509.8

-232.944 4624.72

-787.134

-164.727

> 13 83587.5

-45016.4 12800.9

-230.643 4623.2

-745.177

-428.635

> 14 86311.3

-47443.4 13815.2

-228.162 4638.89

-729.425

-561.758

> 15 87839.2

-48704.1 14500.3

-231.979 4747.67

-775.801

-441.959

> 16 91190.5

-51877.4 15813.2

-225.768 4692.45

-719.311

-756.537

> 17 94512

-55201.2 17306.1

-224.328 4740.86

-747.11

-1129.15

> 18 96959

-57459.9 18403.8

-220.038 4721.02

-726.928

-1272.47

> 19 99061.1

-59172.1 19253.1

-214.045 4663.37

-679.362

-1309.88 a>20 100305

-59997.5 19841.1

-216.112 4721.71

-705.463

-1148.45 2-71 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-3 (Page 8 of 8)

PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 17x17B/C Time (years)

A B

C D

E F

G

> 3 15526.8 18.0364

-9.36581

-128.415 2050.81

-243.915

-426.07

> 4 26595.4

-3345.47 409.264

-115.394 2429.48

-350.883

-243.477

> 5 36190.4

-7783.2 1186.37

-130.008 2769.53

-438.716 519:95

> 6 44159

-12517.5 2209.54

-150.234 3042.25

-489.858 924.151

> 7 50399.6

-16780.6 3277.26

-173.223 3336.58

-555.743 1129.66

> 8 55453.9

-20420 4259.68

-189.355 3531.65

-581.917 1105.62

> 9 59469.3

-23459.8 5176.62

-199.63 3709.99

-626.667 1028.74

> 10 63200.5

-26319.6 6047.8

-203.233 3783.02

-619.949 805.311

> 11 65636.3

-28258.3 6757.23

-214.247 3972.8

-688.56 843.457

> 12 68989.7

-30904.4 7626.53

-212.539 3995.62

-678.037 495.032

> 13 71616.6

-32962.2 8360.45

-210.386 4009.11

-666.542 317.009

> 14 73923.9

-34748 9037.75

-207.668 4020.13

-662.692 183.086

> 15 76131.8

-36422.3 9692.32

-203.428 4014.55

-655.981 4_7.5234

>16 77376.5

-37224.7 10111.4

-207.581 4110.76

-703.37 161.128

> 17 80294.9

-39675.9 11065.9

-201.194 4079.24

-691.636

-173.782

> 18 82219.8

-41064.8 11672.1

-195.431 4043.83

-675.432

-286.059

> 19 84168.9

-42503.6 12309.4

-190.602 4008.19

-656.192

-372.411

> 20 86074.2

-43854.4 12935.9

-185.767 3985.57

-656.72

-475.953 2-72 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Cooling Time (years)

?_3 4

5

?.6 7

8 9

10 11 12

?. 13

?. 14

15 16

?. 17 18 19 20 Table 2.4-4 (Page 1 of 10)

Approved Contents 2.0 BWA Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

A 26409.1 61967.8 91601.1 111369 126904 139181 150334 159897 166931 173691 180312 185927 191151 195761 200791 206068 210187 213731 B

28347.5

-6618.31

-49298.3

-80890.1

-108669

-132294

-154490

-173614

-186860

-201687

-215406

-227005

-236120

-244598

-256573

-266136

-273609

-278120 Array/Class 7x78 C

--16858

-4131.96 17826.5 35713.8 53338.1 69852.5 86148.1 100819 111502 125166 137518 148721 156781 165372 179816 188841 197794 203074 2-73 D

-47.076

-113.949

-132.045

-150.262

-167.764

-187.317

-193.899

-194.156

-193.776

-202.578

-201.041

-197.938

-191.625

-187.043

-197.26

-187.191

-182.151

-175.864 E

5636.32 6122.77 8_4.14 7288.51 7650.57 8098.66 8232.84 8254.99 8251.55 8626.84 8642.19 8607.6 8451.86 8359.19 8914.28 8569.56 8488.23 8395.63 F

-1606.75

-2042.85

-2418.49

-2471.1

-2340.78

_ -2336.13

-2040.37

-1708.32

-1393.91

-1642.3

-1469.45

-1225.95

-846.27

-572.561

-1393.37

-730.898

-584.727

-457.304 G 17788

-96.7439

-185;189 86.6363 150.403 97.5285

-123.029

-373.605

-543.677

-650.814

-810.024

-892.876

-1019.4

-1068.19

-1218.63

-1363.79

-1335.59

-1364.38 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Cooling Time (years)

3

4

?5 2.6

>7 2.8

>9 2.10

2. 11

? 12

2. 13

2. 14

15

?16 17

?18

2. 19

>_20 Table 2.4-4 (Page 2 of 10)

Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

A 2821-9.6 66061.8 95790.7 117477 134090 148186 159082 168816 177221 183929 191093 196787 203345 207973--

213891 217483 220504 227821 B

28963.7

-10742.4

-53401.7

-90055.9

-120643

-149181

-172081

-191389

-210599

-224384

-240384

-252211

"-267656

-- -276838

- -290411

-294066

-297897

-318395 Array/Class 8x8B C

D E 7616,2

-147.68-5887.41

-1961.82

-123.066 6565.54 19836.7

-134.584 714.41 41383.9

-154.758 7613.43 60983

-168.675 7809 81418.7

-185.726 8190.07 99175.2

-197.185 8450.86 113810

-195.613 8359.87 131099

-208.3 8810 143405

-207.497 8841.33 158327

-204.95 8760.17 169664

-204.574 8810.95 186057

-208.962 9078.41 196071

-204.592 9024.17 211145

-202.169 9024.19 214600

-194.243 8859.35 219704

-190.161 8794.97 245322

-194.682 9060.96 2-74 F

-1730.96

-2356.05

-2637.09

-2612.69

-2183.3

-2040.31

-1792.04

-1244.22

-1466.49

-1227.71

-811.708

-610.928

-828.954

-640.808

-482.1

-244.684

-10.9863

-350.308 G

1048.21

-298.005

-298.858

. -64.9921

-40.8885

-260.773

-381.705

-613.594

-819.773

-929.708

-1154.76

-1208.97

-1383.76

-1436.43

-1595.28

• -1529.61

-1433.86

-1741.16 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-4 (Page 3 of 10)

BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 8x8C/D/E Time (years)

A B

C D

E F

G

> 3 28592.7 28691.5

-17773.6

-149.418 5969.45

-1746.07 1063.62

>4 66720.8

-12115.7

-1154

-128.444 6787.16

-2529.99

-302.155

>5 96929.1

-55827.5 21140.3

-136.228 7259.19

-2685.06

-334.328

• 6 118190

-92000.2 42602.5

-162.204 7907.46

-2853.42

-47.5465

• 7 135120

-123437 62827.1

-172.397 8059.72

-2385.81

-75.0053

>8 149162

-152986 84543.1

-195.458 8559.11

-2306.54

-183.595

>9 161041

-177511 103020

-200.087 8632.84

-1864.4

-433.081

? 10 171754

-201468 122929

-209.799 8952.06

-1802.86

-755.742

>11 179364

-217723 137000

-215.803 9142.37

-1664.82

-847.268

>12 186090

-232150 150255

-216.033 9218.36

-1441.92

-975.817

>13 193571

-249160 165997

-213.204 9146.99

-1011.13

-1119.47

> 14 200034

-263671 180359

-210.559 9107.54

-694.626

-1312.55

> 15 205581

-275904 193585

-216.242 9446.57

-1040.65

-1428.13

> 16 212015

-290101 207594

-210.036 9212.93

-428.321

-1590.7 k 17 216775

-299399 218278

-204.611 9187.86

-398.353

-1657.6

>18 220653

-306719 227133

-202.498 9186.34

-181.672

-1611.86

> 19 224859

-314004 235956

-193.902 8990.14 145.151

-1604.71

>20 228541

-320787 245449

-200.727 9310.87

-230.252

-1570.18 2-75 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Cooling Time (years)

?.3

?.4

?.5

?.6

?. 7

?. 8

?.9

?. 10

?. 11

?. 12

?. 13

?. 14

?. 15

?. 6--'

17

?.18

?. 19

?. 20 A

Table 2.4-4 (Page 4 of 10)

BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Array/Class 9x9A B

C D

E Approved Contents 2.0 F

G 30538,7 2-8463.2

-18105,5

-50.039 6226.92

-1876.69 1034.06 71040.1 100888 124846 143516 158218 172226 182700 190734 199997 207414 215263 221920 226532 232959

. -- - - --

240810 244637 248112

. -16692.2

-60277.7

-102954

-140615

-171718

-204312

-227938

. -246174

-269577

-287446

-306131

-321612

-331778

-348593

-369085

-375057

-379262 1164.15 24150.1 50350.8 76456.5 99788.2 126620 146736 163557 186406 204723 223440 239503 252234 272609 296809 304456 309391 2-76

-128.241

-142.541

-161.849

-185.538

-196.315

-214.214

-215.793

-218.071

-223.975

-228.808

-220.919

-217.949

-216.189

-219.907

-219.729

-210.997

-204.191 7105.27 7?6.11 8350.16 8833.04 9048.88 9511.56 9555.41 9649.43 9884.92 10131.7 9928.27 9839.02 9893.43 10126.3 10294.6 10077.8 9863.67

-2728.58

-3272.86

-3163.44

-2949.38

-2529.26

-2459.19

-1959.92

-1647.5

-1534.34

-1614.49

-988.276

-554.709

-442.149

-663.84

-859.302

-425.446 100.27

-414.09

-232.197

-91.1396

-104.802

-259.929

-624.954

-830.943

-935.021

-1235.27

-1358.61

-1638.05

-1784.04

-1754.72

-1915.3

-2218.87

-2127.83

-2059.39 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Cooling Time (years) r3 r4 r5 r6 r7 r8 r9 u10 r 11 

r12 r13 u14

15 r16 v17 r18 r19 r20 Table 2.4-4 (Page 5 of 1 0)

Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

A B

30613.2 28985.3 71346.6

-15922.9 102131

-60654.1 127187

-105842 146853

-145834 162013

-178244 176764

-212856 186900

-235819 196178

-257688 205366

-280266 215012

-306103 222368

-324558 226705

-332738 233846

-349835 243979

-379622 247774

-386203 254041

-401906 256003

-402034 C

--s8371 631.132 23762.7 51525.2 79146.5 103205 131577 151238 171031 192775

• 218866 238655 247316 265676 300077 308873 327901 330566 Array/Class 9x9B D

-t61.1-17

-128.876

-140.748

-162.228

-185.192

-197.825

-215.41

-218.98

-220.323

-223.715

-231.821

. -228.062

-224.659.

-221.533

-222.351

-220.306

-213.96

-215.242 E

6321.55 7232.47 7881.6 8307.4 8718.74 8896.39 9328.18 9388.08 9408.47 9592.12 9853.37 9834.57 9696.59 9649.93 9792.17 9791.37 9645.47 9850.42 2-77 F

-1881.28

-2810.64

-3156.38

-2913.08

-2529.57

-1921.58

-1737.12

-1179.87

-638.53

-472.261

-361.449 3.47358 632.172 913.747 1011.04 1164.58 1664.94 1359.46 G

988.92-

-471.737

-417.979

-342.13

-484.885

-584.013

-1041.11

-1202.83

-1385.16

-1661.6

-1985.56

-2178.84

-2090.75

-2243.34

-2753.36

-2612.25

-2786.2

-2550.06 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-4 (Page 6 of 10)

BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 9x9C/D Time (years)

A B

C D

E F

G

> 3 30051i6 29548.7

--18614.2

-148.276 6148.44

-1810.34 t1006-

> 4 70472.7

-14696.6

-233.567

-127.728 7008.69

-2634.22

-444.373

> 5 101298

-59638.9 23065.2

-138.523 7627.57

-2958.03

-377.965

> 6 125546

-102740 49217.4

-160.811 8096.34

-2798.88

-259.767

> 7 143887

-139261 74100.4

-184.302 8550.86

-2517.19

-275.151

> 8 159633

-172741 98641.4

-194.351 8636.89

-1838.81

-486.731

> 9 173517

-204709 124803

-212.604 9151.98

-1853.27

-887.137

> 10 182895

-225481 142362

-218.251 9262.59

-1408.25

-978.356

> 11 192530

-247839 162173

-217.381 9213.58

-818.676

-1222.12

> 12 201127

-268201 181030

-215.552 9147.44

-232.221

-1481.55

> 13 209538

-289761 203291

-225.092 9588.12

-574.227

-1749.35

> 14 216798

-306958 220468

-222.578 9518.22

-69.9307

-1919.71

> 15 223515

-323254 237933

-217.398 9366.52 475.506

-2012.93

> 16 228796

-334529 250541

-215.004 9369.33 662.325

-2122.75

> 17 237256

-356311 273419

-206.483 9029.55 1551.3

-2367.96

> 18 242778

-369493 290354

-215.557 9600.71 659.297

-2589.32

> 19 246704

-377971 302630

-210.768 9509.41 1025.34

-2476.06

>_ 20 249944

-382059 308281

-205.495 9362.63 1389.71

-2350.49 2-78 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-4 (Page 7 of 10)

BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 9x9E/F Time (years)

A B

C D

E F

G

> 3 30284.3 26949.5

-16926.4

-147.914 6017.02

-1854.81 1026.15

> 4 69727.4

-17117.2 1982.33

-127.983 6874.68

-2673.01

-359.962

>5 98438.9

-58492 23382.2

-138.712 7513.55

-3038.23

-112.641

>6 119765

-95024.1 45261

-159.669 8074.25

-3129.49 221.182

> 7 136740

-128219 67940.1

-182.439 8595.68

-3098.17 315.544

> 8 150745

-156607 88691.5

-193.941 8908.73

-2947.64 142.072

>9 162915

-182667 109134

-198.37 8999.11

-2531

-93.4908

>10 174000

-208668 131543

-210.777 9365.52

-2511.74

-445.876

> 11 181524

-224252 145280

-212.407 9489.67

-2387.49

-544.123

> 12 188946

-240952 160787

-210.65 9478.1

-2029.94

-652.339

> 13 193762

-250900 171363

-215.798 9742.31

-2179.24

-608.636

>14 203288

-275191 196115

-218.113 9992.5

-2437.71

-1065.92

> 15 208108

-284395 205221

-213.956 9857.25

-1970.65

-1082.94

> 16 215093

-301828 224757

-209.736 9789.58

-1718.37

-1303.35

> 17 220056

-310906 234180

-201.494 9541.73

-1230.42

-1284.15

• 18 224545

-320969 247724

-206.807 9892.97

-1790.61

-1381.9

>19 226901

-322168 250395

-204.073 9902.14

-1748.78

-1253.22

>20 235561

-345414 276856

-198.306 9720.78

-1284.14

-1569.18 2-79 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-4 (Page 8 of 10)

BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 9x9G Time (years)

A B

C D

E F

G

> 3 35158.5 26918.5

-17976.7

-149.915 6787.19

-2154.29 836.894

> 4 77137.2

-19760.1 2371.28

-130.934 8015.43

-3512.38

-455.424

> 5 113405

-77931.2 35511.2

-150.637 8932.55

-4099.48

-629.806

> 6 139938

-128700 68698.3

-173.799 9451.22

-3847.83

-455.905

> 7 164267

-183309 109526

-193.952 9737.91

-3046.84

-737.992

> 8 182646

-227630 146275

-210.936 10092.3

-2489.3

-1066.96

> 9 199309

-270496 184230

-218.617 10124.3

-1453.81

-1381.41

> 10 213186

-308612 221699

-235.828 10703.2

-1483.31

-1821.73

> 11 225587

-342892 256242

-236.112 10658.5

-612.076

-2134.65

> 12 235725

-370471 285195

-234.378 10604.9 118.591

-2417.89

> 13 247043

-404028 323049

-245.79 11158.2

-281.813

-2869.82

> 14 253649

-421134 342682

-243.142 11082.3 400.019

-2903.88

> 15 262750

-448593 376340

-245.435 11241.2 581.355

-3125.07

> 16 270816

-470846 402249

-236.294 10845.4 1791.46

-3293.07

> 17 279840

-500272 441964

-241.324 11222.6 1455.84

-3528.25

> 18 284533

-511287 458538

-240.905 11367.2 1459.68

-3520.94

> 19 295787

-545885 501824

-235.685 11188.2 2082.21

-3954.2

> 20 300209

-556936 519174

-229.539 10956 2942.09

-3872.87 2-80 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-4 (Page 9 of 10)

BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 10x1A0B Time (years)

A B

C D

E F

G

> 3 29285.4 27562.2

-16985

-148.415 5960.56

-1810.79 1001.45

> 4 67844.9

-14383 395.619

-127.723 6754.56

-2547.96

-369.267

> 5 96660.5

-55383.8 21180.4

-137.17 7296.6

-2793.58

-192.85

> 6 118098

-91995 42958

-162.985 7931.44

-2940.84 60.9197

> 7 135115

-123721 63588.9

-171.747 8060.23

-2485.59 73.6219

> 8 148721

-151690 84143.9

-190.26 8515.81

-2444.25

-63.4649

> 9 160770

-177397 104069

-197.534 8673.6

-2101.25

-331.046

> 10 170331

-198419 121817

-213.692 9178.33

-2351.54

-472.844

> 11 179130

-217799 138652

-209.75 9095.43

-1842.88

-705.254

> 12 186070

-232389 151792

-208.946 9104.52

-1565.11

-822.73

> 13 192407

-246005 164928

-209.696 9234.7

-1541.54

-979.245

> 14 200493

-265596 183851

-207.639 9159.83

-1095.72

-1240.61

> 15 205594

-276161 195760

-213.491 9564.23

-1672.22

-1333.64

> 16 209386

-282942 204110

-209.322 9515.83

-1506.86

-1286.82

> 17 214972

-295149 217095

-202.445 9292.34

-893.6

-1364.97

> 18 219312

-302748 225826

-198.667 9272.27

-878.536

-1379.58

> 19 223481

-310663 235908

-194.825 9252.9

-785.066

-1379.62

>20 227628

-319115 247597

-199.194 9509.02

-1135.23

-1386.19 2-81 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Approved Contents 2.0 Table 2.4-4 (Page 10 of 10)

BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)

Cooling Array/Class 10xiOC Time (years)

A B

C D

E F

G

> 3 31425.3 27358.9

-17413.3

-152.096 6367.53

-1967.91 925.763

> 4 71804

-16964.1 1000.4

-129.299 7227.18

-2806.44

-416.92

> 5 102685

-62383.3 24971.2

-142.316 7961

-3290.98

-354.784

> 6 126962

-105802 51444.6

-164.283 8421.44

-3104.21

-186.615

> 7 146284

-145608 79275.5

-188.967 8927.23

-2859.08

-251.163

> 8 162748

-181259 105859

-199.122 9052.91

-2206.31

-554.124

> 9 176612

-214183 133261

-217.56 9492.17

-1999.28

-860.669

> 10 187756

-239944 155315

-219.56 9532.45

-1470.9

-1113.42

> 11 196580

-260941 174536

-222.457 9591.64

-944.473

-1225.79

> 12 208017

-291492 204805

-233.488 10058.3

-1217.01

-1749.84

> 13 214920

-307772 221158

-234.747 10137.1

-897.23

-1868.04

> 14 222562

-326471 240234

-228.569 9929.34

-183.47

-2016.12

> 15 228844

-342382 258347

-226.944 9936.76 117.061

-2106.05

> 16 233907

-353008 270390

-223.179 9910.72 360.39

-2105.23

> 17 244153

-383017 304819

-227.266 10103.2 380.393

-2633.23

> 18 249240

-395456 321452

-226.989 10284.1 169.947

-2623.67

> 19 254343

-406555 335240

-220.569 10070.5 764.689

-2640.2

> 20 260202

-421069 354249

-216.255 10069.9 854.497

-2732.77 2-82 Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B

Design Features 3.0 3.0 DESIGN FEATURES 3.1 Site 3.1.1 Site Location The HI-STORM 100 Cask System is authorized for general use by 10 CFR Part 50 license holders at various site locations under the provisions of 10 CFR 72, Subpart K.

3.2 Design Features Important for Criticality Control 3.2.1 MPC-24

1.

Flux trap size: > 1.09 in.

2.

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

1.

Fuel cell pitch: > 6.43 in.

2.

'1B loading in the neutron absorbers: > 0.0372 g/cm 2 (Boral) and > 0.0310 g/cm2 (METAMIC) 3.2.3 MPC-68F

1.

Fuel cell pitch: > 6.43 in.

2.

'11 loading in the Boral neutron absorbers: > 0.01 g/cm2 3.2.4 MPC-24E and MPC-24EF

1.

Flux trap size:

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

2.

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

1.

Fuel cell pitch: > 9.158 inches

2.

'0B loading in the neutron absorbers: > 0.0372 g/cm 2 (Boral) and > 0.0310 g/cm 2 (METAMIC)

Certificate of Compliance No. 1014 Appendix B 3-1 Renewed Amendment No. 3

Design Features 3.0 DESIGN FEATURES 3.2 Design features important for Criticality Control (cont'd) 3.2.6 Fuel spacers shall be sized to ensure that the active fuel region of intact fuel assemblies remains within the neutron poison region of the MPC basket with water in the MPC.

3.2.7 The B4C content in METAMIC shall be < 33.0 wt.%.

3.2.8 Neutron Absorber Tests Section 9.1.5.3 of the HI-STORM 100 FSAR is hereby incorporated by reference into the HI-STORM 100 CoC. The minimum 10B for the neutron absorber shall meet the minimum requirements for each MPC model specified in Sections 3.2.1 through 3.2.5 above.

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, except for Code Sections V and IX. The latest effective editions of ASME Code Sections V and IX, including addenda, may be used for activities governed by those sections, provided a written reconciliation of the later edition against the 1995 Edition, including addenda, is performed by the certificate holder. American Concrete Institute (ACI) 349-85 is the governing Code for plain concrete as clarified in Appendix 1.D of the Final Safety Analysis Report for the HI-STORM 100 Cask System.

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

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

1.

The proposed alternatives would provide an acceptable level of quality and safety, or (continued)

Certificate of Compliance No. 1014 Appendix B 3-2 Renewed Amendment No. 3

Design Features 3.0 DESIGN FEATURES 3.3.2 Construction/Fabrication Alternatives to Codes, Standards, and Criteria (cont'd)

2.

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

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

(continued)

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

Design Features 3.0 DESIGN FEATURES Table 3-1 (page 1 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory Measures ASME Code Section/Article MPC, MPC Subsection NCA General Because the MPC, OVERPACK, and TRANSFER CASK basket Requirements.

are not ASME Code stamped vessels, none of the assembly, HI-Requires preparation specifications, reports, certificates, or other general STORM of a Design requirements specified by NCA are required. In lieu of a OVERPACK Specification, Design Design Specification and Design Report, the HI-STORM steel Report, Overpressure FSAR includes the design criteria, service conditions, and structure, and Protection Report, load combinations for the design and operation of the HI-HI-TRAC Certification of STORM 100 System as well as the results of the stress TRANSFER Construction-Report, analyses to demonstrate that applicable Code&stress limits CASK steel Data Report, and are met. Additionally, the fabricator is not required to have structure other administrative an ASME-certified QA program. All important-to-safety controls for an ASME activities are governed by the NRC-approved Holtec QA Code stamped program.

vessel.

Because the cask components are not certified to the Code, the terms "Certificate Holder" and "Inspector" are not germane to the manufacturing of NRC-certified cask components. To eliminate ambiguity, the responsibilities assigned to the Certificate Holder in the various articles of Subsections NB, NG, and NF of the Code, as applicable, shall be interpreted to apply to the NRC Certificate of Compliance (CoC) holder (and by extension, to the component fabricator) if the requirement must be fulfilled. The Code term "Inspector" means the QA/QC personnel of the CoC holder and its vendors assigned to oversee and inspect the manufacturing process.

MPC NB-1 100 Statement of MPC enclosure vessel is designed and will be fabricated requirements for In accordance with ASME Code,Section III, Subsection Code stamping of NB to the maximum practical extent, but Code stamping components.

is not required.

Certificate of Compliance No. 1014 Appendix B 3-4 Renewed Amendment No. 3

Design Features 3.0 Table 3-1 (page 2 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM.100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory Measures ASME Code Section/Article MPC basket NB-1 130 NB-1 132.2(d)

The MPC basket supports (nonpressure-retaining supports and requires that the first structural attachments)and lift lugs (nonstructural lift lugs connecting weld of a attachments (relative to the function of lifting a loaded nonpressure-MPC) that are used exclusively for lifting an empty MPC) retaining structural are welded to the inside of the pressure-retaining MPC attachment to a shell, but are not designed in accordance with component shall be Subsection NB. The basket supports and associated considered part of attachment welds are designed to satisfy the stress limits the component of Subsection NG and the lift lugs and associated unless the weld is attachment welds are designed to satisfy the stress limits more than 2t from the of Subsection NF, as a minimum. These attachments pressure-retaining

-and-their welds are shown by analysis to-meet-the portion of the respective stress limits for their service conditions.

component, where t Likewise, non-structural items, such as shield plugs, is the nominal spacers, etc. if used, can be attached to pressure-thickness of the retaining parts in the same manner.

pressure-retaining material.

NB-1 132.2(e) requires that the first connecting weld of a welded nonstructural attachment to a component shall conform to NB-4430 if the connecting weld is within 2t from the pressure-retaining portion of the component.

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

material supplier.

Certificate of Compliance No. 1014 Appendix B 3-5 Renewed Amendment No. 3

Design Features 3.0 Table 3-1 (page 3 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory Measures ASME Code Section/Article MPC, MPG NB-31 00 Provides These requirements are not applicable. The HI-STORM basket NG-3100 requirements for FSAR, serving as the Design Specification, establishes assembly, HI-NF-3100 determining design the service conditions and load combinations for the STORM loading conditions, storage system.

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

CASK MPC NB-3350 NB-3352.3 requires, Due to MPC basket-to-shell interface requirements, the for Category C joints, MPC shell-to-baseplate weld joint design (designated

-that the minimum.

.CategoryC) does not-include a-reinforcing-fillet-weld-or-a -

dimensions of the bevel in the MPC baseplate, which makes it different than welds and throat any of the representative configurations depicted in Figure thickness shall be as NB-4243-1. The transverse thickness of this weld is equal shown in Figure NB-to the thickness of the adjoining shell (1/2 inch). The weld 4243-1.

is designed as a full penetration weld that receives VT and RT or UT, as well as final surface PT examinations.

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

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

Certificate of Compliance No. 1014 Appendix B 3-6 Renewed Amendment No. 3

Design Features 3.0 Table 3-1 (page 4 of 9)

LIST OF ASME CODE AL TEA NATIVES FOR HI-STORM 100 CASK SYSTEM Component MPC,MPC Basket Assembly, HI-STORM OVERPACK steel structure and HI-TRAC TRANSFER CASK steel structure MPC,MPC basket assembly, HI-STORM QVERPACK steel structure, and HI-TRAC TRANSFER CASK steel structure MPC Lid and Closure Ring Welds

-Reference ASME Code Section/ Article NB-4120 NG-4120 NF-4120 NB-4220 NF-4220 NB-4243

- Code Requarement NB-4121.2, NG-4121.2, and-NF-4121.2 provide requirements for repetition of tensile or impact tests for material subjected to heat treatment during fabrication or installation.

Requires certain forming tolerances to be met for cylindrical, conical, or spherical shells of a vessel.

Full penetration welds required for Category C Joints (flat head to main shell per NB-3352.3).

Certificate of Compliance No. 1014 Appendix B 3-7

- Alternative-, JustJficatlon & Compensatory-Measures In-shop operations of short duration that apply heat to a component, sue:h as plasma cutting of plate stock, welding, machining, coating, and pouring of lead are not, unless explicitly stated by the Code, defined as heat treatment operations.

For the steel oarts in the HI-STORM 1 0(LSystern___

components, the duration for which a part exceeds the off-normal temperature limit defined in Chapter 2 of the FSAR shall be limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a particular manufacturing process (such as the HI-TRAC lead

-pouring process) - - -

The cylindricity measurements on the rolled shells are not specifically recorded in the shop travelers, as would be the case for a Code-stamped pressure vessel.

Rather, the requirements on inter-component clearances (such as he M_PC-to-TRANSFER CASK) are guaranteed through fixture-controlled manufacturing. The fabrication specification and shop procedures ensure that all dimensional design objectives, including inter-component annular clearances are satisfied. The dimensions required to be met in fabrication are chosen to meet the functional requirements of the dry storage components.

Thus, although the post-forming Code cylindricity requirements are not evaluated for compliance directly, they are indirectly satisfied (actually exceeded) in the final manufactured components.

MPC lid and closure ring are not full penetration welds.

They are welded independently to provide a redundant seal. Additionally, a weld efficiency factor of 0.45 has been applied to the analyses of these welds.

Renewed Amendment No. 3

Design Features 3.0 Table 3-1 (page 5 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM MPG Lid to Shell Weld MPC Closure Ring, Vent ana-main Cover Plate Welds Reference ASMECode Section/ Article NB-5230 NB-5230 NB-6111 Code Requirement Radiographic (RT) or ultrasonic (UT) examination required Radiographic (AT) or ultrasonic (UT) examrnation-required All completed MPC

-Enclosure Vessel and Lid pressure reta1n1ng Certificate of Compliance No. 1014 Appendix B systems shall be pressure tested.

3-8 Alternative, Justification & Compensatory Measures Only UT or multi-layer liquid penetrant (PT} examination is permitted. If PT alone is used, at a minimum, it will include the root and fin al weld layers and each approximately 3/8 inch of weld depth.

Root (if more than one weld pass is required) and final liquid penetrant examination to be performed in accordance-with NB-5245. The closure ring provides independent redundant closure for vent and drain cover plates.

The MPC enclosure vessaj ³ 'µatwelded in the field-following

-fijel assembly loading. The MPC enclosure vessel shall then be pressure tested as defined in Chapter 9. Accessibility for leakage Inspections preclude a Code compliant pressure test. -

All MPC enclosure vessel welds (except closure ring and vent/drain cover plate) are Inspected by volumetric examination, 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 critii:;al _flaw size shall npt cause the primary stress limits of NB-3000 to be exceeded.

The Inspection results, Including relevant findings (indications),

shall be made a permanent part of the user's 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 venVdrain cover plate and the closure ring welds are confirmed by liquicf¶ -

penetrant examination. The inspection of the weld must be performed by qualified personnel and shall meet the acceptance requirements of ASME Code Section Ill, NB-5350 for PT or NB-5332 for UT.

Renewed Amendment No. 3

Design Features 3.0 Table 3-1 (page 6 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory Measures ASME Code Section/Article MPC NB-7000 Vessels are required No overpressure protection is provided. The function of Enclosure to have overpressure the MPC enclosure vessel is to contain the radioactive Vessel protection 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 NB-8000 States requirements The HI-STORM100 System is to be marked and Enclosure for nameplates, identified in accordance with 1 OCFR71 and 1 OCFR72 Vessel stamping and reports requirements. Code stamping is not required. QA data per NCA-8000.

package to be in accordance with Holtec approved QA program.

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

ASME-approved material supplier.

.Certificate of Compliance No. 1014 Appendix B 3-9 Renewed Amendment No. 3

Design Features 3.0 Table 3-1 (page 7 of 9)

LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement ASME Code Section/ Article MPG basket NG-4420 NG-4427(a) allows a assembly fillet weld in any single continuous weld to be less than the specified fillet weld dimension by not more than 1 /16 inch, provided that the total undersize portion of the weld does not exceed 10 percent of the length

• • **** - oftheweld.-lndividua1-undersize weld portions shall not exceed 2 inches in length.

MPC Basket NG-8000 States requirements Assembly for nameplates, stamping and reports per NCA-8000.

OVERPACK NF-2000 Requires materials to Steel be supplied by Structure AS ME-approved material supplier.

Certificate of Compliance No. 1014 Appendix B 3-10 Alternative, Justification & Compensatory Measures Modify the Code requirement (intended for core support structures) with the following text prepared to accord with the geometry and stress analysis imperatives for the fuel basket: For the longitudinal MPC basket fillet welds, the following criteria apply: 1) The specified fillet weld throat dimension must be maintained over at least 92 percent of the total weld length. All regions of undersized weld must be less than 3 inches long and separated from each other by at least 9 inches. 2) Areas of undercuts and porosity beyond that allowed by the applicable ASME Code shall not exceed 1/2 inch in weld length. The total length of undercut and porosity over any 1-foot length shall not exceed 2 inches. 3) The total weld length in which items (1) and (2) apply shall not exceed a total of 10 percent of the overall weld length.The limited-access of-lhe*MPC basket panel lon-gituaina.I-fillet welds makes it difficult to perform effective repairs of these welds and creates the potential for causing additional damage to the basket assembly (e.g., to the neutron absorber and its sheathing) if repairs are attempted. The acceptance criteria provided in the foregoing have been established to comport with the objectives of the basket design and preserve the margins demonstrated in the supporting stress analysis.

From the structural standpoint, the weld acceptance criteria are established to ensure that any departure from the Ideal, continuous fillet weld seam would not alter the primary bending stresses on which the design of the fuel baskets Is predicated.

Stated differently, the permitted.weld discontinuities are limited In size fo ensure that they remain classifiable as local stress elevators ("peak stress", F, In the ASME Code for which specific stress Intensity limits do not apply).

The HI-STORM100 System is to be marked and identified in accordance with 1 0CFR71 and 1 0CFA72 requirements. Code stamping is not required. The MPC basket data package to be in accordance with Holtec approved QA program.

Materials will be supplied by Holtec-approved supplier with CMTRs in accordance with NF-2000 requirements.

Renewed Amendment No. 3

Table 3-1 (page 8 of 9)

Design Features 3.0 LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM

- Component Reference ASME Code Section/ Article TRANSFER NF-2000 CASK Steel Structure OVERPACK NF-4441 Baseplate and lid Top Plate OVERPACK NF-3256 Steel NF-3266 Structure Certificate of Compliance No. 1014 Appendix B

-Code Requfrement Requires materials to be supplied by ASME-approved material supplier.

Requires special examinations or reqi.mements-for -*

welds where a primary member of thickness 1 inch or greater is loaded to transmit-loads in-the through thickness direction.

Provides requirements for welded joints.

3-11 Alternative, justification & Compensatory Measures Materials will be supplied by Holtec-approved supplier with CMTRs in accordance with NF-2000 requirements.

The margins of safety in these welds under loads experienced during lifting operations or accident conartions are quiiefarge. *The OVERPACK hasepiate welds to the inner shell, pedestal shell, and radial plates are only loaded during lifting conditions and have large safety factors during lifting. Likewise, the top lid plate to lid shell weld has a large structural margin __ l!n_dJ:lr the

- inertia loads impos-ed during a non-mechanistic tipover event.

Welds for which no structural credit is taken are identified as uNon-NF" welds in the design drawings. These non-structural welds are -specified in accorcfan-ce with tlie pre-qualified welds of AWS D1.1. These welds shall be made by welders and weld procedures qualified in accordance with AWS 01.1 or ASME Section IX.

Welds for which structural credit is taken -in the safety * -

• analyses shall meet the stress limits for NF-3256.2, but are not required to meet the Joint configuration requirements specified in these Code articles. The geometry of the joint designs in the cask structures are based on the f abricability and accessibility of the joint, not generally contemplated by this Code section governing supports.

Renewed Amendment No. 3

Table 3-1 (page 9 of 9)

Design Features 3.0 LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component HI-STORM OVERPACK and HI-TRAC TRANSFER CASK Reference ASMECode Section/ Article NF-3320 NF-4720 Certificate of Compliance No. 1014 Appendix B Code Requirement NF-3324.6 and NF-4720 provide requirements for bolting 3-12 Alternative, Justification & Compensatory Measures These Code requirements are applicable to linear structures wherein bolted joints carry axial, shear, as well as rotational (torsional) loads. The OVERPACK and TRANSFER CASK bolted connections in the structural load path are qualified by design based on the design loadings defined in the FSAR. Bolted joints in these components see no shear or torsional loads under normal storage conditions. Larger clearances between bolts and holes may be necessary to ensure shear interfaces located elsewhere in the structure engage prior to the bolts experiencing shear loadings (which occur only during side impact scenarios).

Boltedjoinls that are subject to shear loads in accident conditions are qualified by appropriate stress analysis.

Larger bolt-to-hole clearances help ensure more efficient operations in making these bolted connections, thereby minimizing time spent by operations personnel in a radiation area. Additionally, larger bolt-to-hole clearances allow interchangeability of the lids from one particular fabricated cask to another.

Renewed Amendment No. 3

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

1.

The temperature of 80° F is the maximum average yearly temperature.

2.

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

3.

a.

The resultant horizontal acceleration (vectorial sum of two horizontal Zero Period Accelerations (ZPAs) at a three-dimensional seismic site), GH, and vertical ZPA, Gv, on the top surface of the ISFSI pad, expressed as fractions of 'g', shall satisfy the following inequality:

where µ is either the Coulomb friction coefficient for the cask/1S FSI pad interface or the ratio r/h, where 'r' is the radius of the cask and 'h' is the height of the cask center-of-gravity above the ISFSI pad surface. The above inequality must be met for both definitions of µ, but only applies to ISFSls where the casks are deployed in a freestanding configuration. Unless demonstrated by appropriate testing that a higher coefficient of friction value is appropriate for a specific ISFSI, the value used shall be 0.53. If acceleration time-histories on the ISFSI pad surface are available, GH and Gv may be the coincident values of the instantaneous net horizontal and vertical accelerations. If instantaneous accelerations are used, the inequality shall be evaluated at each time step in the acceleration time history over the total duration of the seismic event.

If this static equilibrium based inequality cannot be met, a dynamic analysis of the cask/lSFSI pad assemblage with appropriate recognition of soil/structure interaction effects shall be performed to ensure that the casks will not tip over or undergo excessive sliding under the site's Design Basis Earthquake.

Certificate of Compliance No. 1014 Appendix B Table 3-2 (not used) 3-13 (continued}

Renewed Amendment No. 3

DESIGN FEATURES 3.4 Site-Specific Para²eters and Analyses (continued)

Design Features 3.0 b.

For free-standing casks, under environmental conditions that may degrade the pad/cask interface friction (such as due to icing} the response of the casks under the site's Design Basis Earthquake shall be established using the best estimate of the friction coefficient in an appropriate analysis model. The analysis should demonstrate that the earthquake will not result in cask tipover or cause a cask to fall off the pad. In addition, impact between casks st1ould be precluded, or should be considered an accident for which the maximum g-load experienced by the stored fuel shall be limited to 45 g's.

c.

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:

AND Where:

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

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:³ 80 ksi Ultimate Strength at Ambient Temperature:³ 125 ksi Initial Tensile Pre-Stress::::. 55 ksi AND,=s 65 ksi NOTE:

The above anchorage specifications are required for the seismic (continued)

Certificate of Compliance No. 1014 Appendix B 3-14 Renewed Amendment No. 3

DESIGN FEATURES Design Features 3.0 3.4 Site-Specific Parameters and Analyses (continued) 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 ACl-349-97. A later edition of this Code may be used, provided a written reconciliation is performed.

iii.

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

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

5.

The potential for fire and explosion 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 g's 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 _s 45 g's 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.

7.

In cases where engineered features (i.e., berms and shield walls) are used to ensure that the requirements of 10CFR72.104(a) ae met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category.

Certificate of Compliance No. 1014 Appendix B 3-15 (continued)

Renewed Amendment No. 3

Certificate of Compliance No. 1014 Appendix B 3-16 Design Features 3.0 Renewed Amendment No. 3

DESIGN FEATURES 3.4 Site-Specific Parameters and Analyses {continued)

Design Features 3.0 8.

LOADING OPERATIONS, TRANSPORT OPERATIONS, and UNLOADING OPERATIONS shall only be conducted with working area ambient temperatures 0° 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 perlormed 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 shorf term temperature limit for the duration of the event, provisions shall be established to provide alternate means of cooling to accomplish this objective.

10.

Users shall establish procedural and/or mechanical barriers to ensure that during LOADING OPERATIONS and UNLOADING OPERATIONS, either the fuel cladding is covered by water, or the MPC is filled with an inert gas.

Certificate of Compliance No. 1014 Appendix B 3-17 (continued)

Renewed Amendment No. 3

DESIGN FEATURES Design Features 3.0 3.5 Cask Tran sf er Facility (CTF) 3.5.1 TRANSFER CASK and MPC Lifters Lifting of a loaded TRANSFER CASK and MPC using devices that are not integral to structures governed by 10 CFR Part 50 shall be performed with a CTF that is designed, operated, fabricated, tested, inspected, and maintained in accordance with the guidelines of NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" and the below clarifications. The CTF Structure requirements below do not apply to heavy loads bounded by the regulations of 1 O 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-err structure shall be designed to comply with the stress limits of ASME Section Ill, 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 JII, Subsection NF.

2.

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

3.

The TRANSFER CASK and MPG 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 MPG is dropped during inter-cask transfer operations, its confinement boundar.y_would not be breached. This requirements applies to CTFs with either stationary or mobile lifting devices.

(continued)

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

DESIGN FEATURES 3.5.2.2 Mobile Lift Devices Design Features 3.0 If a mobile lifting device is used as the lifting device, in lieu of a stationary lifting device, it shall meet the guidelines of NUREG- 0612, Section 5.1, with the following clarifications:

1.

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

2.

Mobile lifting devices shall conform to meet the requirements of ANSI 830.5, "Mobile and Locomotive Cranes," in lieu of the requirements of ANSI 830.2, "Overhead and Gantry Cranes."

3.

Mobile cranes are not required to meet the requirements of NUAEG-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 3-19 Renewed Amendment No. 3

DESIGN FEATURES Table 3-3 Design Features 3.0 Load Combinations and Service Condition Definitions for the CTF Structure {Note 1)

Load Combination ASME Ill Service Condition for Definition of Allowable D*

D+S D+M+W' (Note 2)

D+F 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 Stress Level A LevelD

Comment All primary load bearing members must satisfy Level A stress limits Factor of safety against overturning shall be s 1.1 Notes:

1.

The reinforced concrete portion of the CTF structure shall also meet the factored combinations of loads set forth in ACl-318(89).

2.

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

Certificate of Compliance No. 1014 Appendix B 3-20 Renewed Amendment No. 3

DESIGN FEATURES 3.6 Forced Helium Dehydration System 3.6.1

System Description

Design Features 3.0 Use of the Forced Helium Dehydration (FHD) system, (a closed-loop system) is an alternative to vacuum drying the MPG for moderatz burn up fuel{ 45,000 MWD/MTU}

and mandatory for drying MPCs containing one or more high burn up 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 MPG shall be at least 15°F higher than the saturation temperature at coincident pressure.

3.6.2.2 The.pressure in-the MPG cavity space shall-bes 60.3 psig (75 psia).

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

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

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

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 MPG meets these design criteria.

Certificate of Compliance No. 1014 Appendix B 3-21

( continued)

Renewed Amendment No. 3

DESIGN FEATURES 3.6 Forced Helium Dehydration System (continued) 3.6.3

• Fuel Cladding Temperature Design Features 3.0 A steady*state thermal analysis of the MPC under the forced helium flow scenario shall be performed using the methodology described in HI-STORM 100 FSAR Section 4.4, with due recognition of the forced convection process during FHD system operation. This analysis shall demonstrate that the peak temperature of the fuel cladding under the most adverse condition of FHD system operation, is below the peak cladding temperature limit for normal conditions of storage for the applicable fuel type (PWR or BWR) and cooling time at the start of dry storage.

3.6.4 Pressure Monitoring During FHD Malfunction During an FHD malfunction event, described in HI-STORM 100 FSAR Section 11.1 as a loss_of helium circulation, the system pressure must be monitored to ensure that the conditions listed therein are met.

Certificate of Compliance No. 1014 Appendix B 3-22 Renewed Amendment No. 3

DESIGN FEATURES 3.7 Supplemental Cooling System 3.7.1

System Description

Design Features 3.0 The SCS is a water circulation system for cooling the MPC inside the HI-TRAC transfer cask during on-site transport. Use of the Supplemental Cooling System (SCS) is required for post-backfill HI-TRAC operations of an MPG containing one or more high burnup (> 45,000 MWD/MTU) fuel assemblies. The SGS shall be designed for normal operation (i.e., excluding startup and shutdown ramps) in accordance with the criteria in Section 3.7.2.

3.7.2 Design Criteria 3.7.2.1 The system shall consist of a skid-mounted coolant pump and an air-cooled heat exchanger.

3.7.2.2 The pump shall be sized to limit the coolant temperature rise (from annulus inlet to outlet) to a reasonably low value (202F) and the air-cooled heat exchanger sized for the design basis heat load at an ambient air*

temperature of 1002F. The pump and aircooler fan shall be powered by electric motors with a backup power supply for uninterrupted operation.

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

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

3.7.2.5 The heat dissipation capacity of the SCS shall be equal to or greater than the minimum necessary to ensure that the peak cladding temperature is below 4002C (7522F). All heat transfer surf aces in heat exchangers shall be assumed to be fouled to the maximum limits specified in a widely used heat exchange equipment standard such as the Standards of Tubular Exchanger Manufacturers Association.

3. 7.2.6 The coolant utilized to extract heat from the MPG.shall be high purity water.

Antifreeze may be used to prevent water from freezing if warranted by operating conditions.

Certificate of Compliance No. 1014 Appendix B 3-23 Renewed Amendment No. 3

DESIGN FEATURES 3.7 Supplemental Cooling System (continued)

Design Features 3.0

3. 7.2. 7 All pressure boundaries (as defined in the ASME Boiler and Pressure Vessel Code,Section VIII Division 1) shall have pressure ratings that are greater than the maximum system operating pressure by at least 15 psi.

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

3. 7.2.9 All gasketed and packed joints shall have a minimum design pressure rating of the pump shut-off pressure plus 15 psi.

Certificate of Compliance No. 1014 Appendix B 3-24 Renewed Amendment No. 3

DESIGN FEATURES 3.8 Combustible Gas Monitoring During MPC Lid Welding Design Features 3.0 During MPC lid-to-shell welding operations, combustible gas monitoring of the space under the MPC lid is required, to ensure that there is no combustible mixture present in the welding area.

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