ML21068A387

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HI-STORM 100 Amendment 16 Certificate of Compliance, Appendix B-100U Reorganization
ML21068A387
Person / Time
Site: Holtec
Issue date: 03/09/2021
From:
Holtec
To:
Office of Nuclear Material Safety and Safeguards
Shared Package
ML21068A360 List:
References
5014917
Download: ML21068A387 (57)
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Text

PROPOSED CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX B - 100U TECHNICAL SPECIFICATIONS FOR THE HI-STORM 100 CASK SYSTEM 5 to Holtec Letter 5014917 1 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U i

TABLE OF CONTENTS 1

Definitions, Use, and Application...................................................................................... 1-1 1.1 Definitions................................................................................................................. 1-1 1.2 Logical Connectors................................................................................................... 1-1 1.3 Completion Times...................................................................................................... 1-1 1.4 Frequency................................................................................................................. 1-1 2

Approved Contents.......................................................................................................... 2-1 2.1 Fuel Specifications and Loading Conditions.............................................................. 2-1 2.1.1 Fuel To Be Stored In The HI-STORM SFSC System Model 100U..................... 2-1 2.1.2 Uniform Fuel Loading......................................................................................... 2-1 2.1.3 Regionalized Fuel Loading................................................................................. 2-1 2.2 Decay Heat, Burnup, and Cooling Time Limits for ZR-Clad Fuel............................. 2-26 2.2.1 Uniform Fuel Loading Decay Heat Limits for ZR-clad Fuel............................... 2-26 2.2.2 Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel (INTACT FUEL only)

........................................................................................................................ 2-26 2.2.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel........................ 2-27 2.2.4 Compliance with Maximum Fuel Storage Location Decay Heat Limits............. 2-27 3

Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs)............. 3-1 3.0 Applicability............................................................................................................... 3-1 3.1 SFSC INTEGRITY.................................................................................................... 3-3 3.1.1 Multi-Purpose Canister (MPC)........................................................................... 3-3 3.1.2 SFSC Heat Removal System............................................................................. 3-7 3.1.3 MPC Cavity Reflooding...................................................................................... 3-9 3.1.4 Impressed Current Cathodic Protection System (ICCPS)...................................... 1 3.2 SFSC RADIATION PROTECTION............................................................................ 3-3 3.2.1 Not Used............................................................................................................ 3-3 3.2.2 TRANSFER CASK Surface Contamination........................................................ 3-4 3.3 SFSC CRITICALITY CONTROL............................................................................... 3-6 3.3.1 Boron Concentration.......................................................................................... 3-6 4

Administrative Controls.................................................................................................... 4-3 4.1 Radioactive Effluent Control Program....................................................................... 4-3 4.2 Cask Transport Evaluation Program........................................................................... 4-3 4.2.1 Transfer Cask.................................................................................................... 4-3 4.3 Radiation Protection Program.................................................................................... 4-4 4.4 Violations of Fuel Specifications or Loading Conditions............................................ 4-7 5 to Holtec Letter 5014917 2 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U ii 4.5 Heavy Loads Requirements...................................................................................... 4-7 FIGURES Figure 2-1: Fuel Loading Regions - MPC-24.......................................................................... 2-2 Figure 2-2: Fuel Loading Regions - MPC-24E........................................................................ 2-3 Figure 2-3: Fuel Loading Regions - MPC32........................................................................... 2-4 Figure 2-4: Fuel Loading Regions - MPC-68........................................................................... 2-5 TABLES Table 2-1:Fuel Assembly Limits.............................................................................................. 2-6 Table 2-2: PWR Fuel Assembly Characteristics.................................................................... 2-14 Table 2-3: BWR Fuel Assembly Characteristics.................................................................... 2-19 Table 2-4: Non-Fuel Hardware Cooling and Average Burnup................................................ 2-24 Table 2-5: Maximum Allowable Decay Heat per Fuel Storage Location (Uniform Loading, ZR-Clad)..................................................................................................................................... 2-26 Table 2-6: Fuel Storage Regions per MPC............................................................................ 2-27 Table 2-7: PWR Fuel Assembly Burnup and Cooling Time Limits......................................... 2-28 Table 2-8: BWR Fuel Assembly Burnup and Cooling Time Limits......................................... 2-29 Table 3-1: MPC Cavity Drying Limits for All MPC Types......................................................... 3-1 Table 3-2: MPC Helium Backfill Limits1................................................................................... 3-1 Table 4-1: Transfer Cask and Free-Standing Overpack Lifting Requirements......................... 4-4 5 to Holtec Letter 5014917 3 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 1-1 1 DEFINITIONS, USE, AND APPLICATION 1.1 Definitions Refer to Definitions in Appendix B.

1.2 Logical Connectors Refer to Logical Connectors in Appendix B.

1.3 Completion Times Refer to Completion Times in Appendix B.

1.4 Frequency Refer to Frequency in Appendix B. 5 to Holtec Letter 5014917 4 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-1 2 APPROVED CONTENTS 2.1 Fuel Specifications and Loading Conditions 2.1.1 Fuel To Be Stored In The HI-STORM SFSC System Model 100U

a.

INTACT FUEL ASSEMBLIES, and NON-FUEL HARDWARE meeting the limits specified in Table 2-1 and other referenced tables may be stored.

b.

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

c.

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

d.

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

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

2.1.3 Regionalized Fuel Loading Users may choose to store fuel using regionalized loading in lieu of uniform loading to allow higher heat emitting fuel assemblies to be stored than would otherwise be able to be stored using uniform loading. Regionalized loading is limited to those fuel assemblies with ZR cladding. Figures 2-1 through 2-4 define the regions for the MPC-24, MPC-24E, MPC-32, MPC-68 models, respectively. Fuel assembly burnup, decay heat, and cooling time limits for regionalized loading are specified in Section 2.2.2. Fuel assemblies used in regionalized loading shall meet all other applicable limits specified in Tables 2-1 through 2-3.

5 to Holtec Letter 5014917 5 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-2 Figure 2-1: Fuel Loading Regions - MPC-24 5 to Holtec Letter 5014917 6 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-3 Figure 2-2: Fuel Loading Regions - MPC-24E 5 to Holtec Letter 5014917 7 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-4 Figure 2-3: Fuel Loading Regions - MPC32 5 to Holtec Letter 5014917 8 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-5 Figure 2-4: Fuel Loading Regions - MPC-68 5 to Holtec Letter 5014917 9 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-6 Table 2-1:Fuel Assembly Limits Table 2-1 (page 1 of 8)

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

1.

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

a. Cladding Type:

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

b. Initial Enrichment:

As specified in Table 2-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Classes 14x14D,14x14E, and 15x15G Cooling time 8 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes Cooling time and average burnup as specified in Section 2.2.

ii. NON-FUEL HARDWARE As specified in Table 2-4. 5 to Holtec Letter 5014917 10 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-7 Table 2-1 (page 2 of 8)

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

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:
i. Array/Classes 14x14D, 14x14E, and 15x15G 710 Watts ii. All Other Array/Classes As specified in Section 2.2.
e. Fuel Assembly Length:

176.8 inches (nominal design)

f. Fuel Assembly Width:

8.54 inches (nominal design)

g. Fuel Assembly Weight:

1720 lbs (including NON-FUEL HARDWARE) for assemblies that do not require fuel spacers, otherwise 1680 lbs (including NON-FUEL HARDWARE)

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

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

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing APSRs or NSAs may only be loaded in fuel storage locations 9, 10, 15, and/or 16. Fuel assemblies containing CRAs, RCCAs, CEAs may only be stored in fuel storage locations 4, 5, 8

- 11, 14 - 17, 20 and/or 21 (see Figure 2-1). These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading. 5 to Holtec Letter 5014917 11 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-8 Table 2-1 (page 3 of 8)

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

1. Uranium oxide or MOX BWR INTACT FUEL ASSEMBLIES listed in Table 2-3, with or without channels and meeting the following specifications:
a. Cladding Type:

ZR or Stainless Steel (SS) as specified in Table 2-3 for the applicable fuel assembly array/class

b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:

As specified in Table 2-3 for the applicable fuel assembly array/class.

c. Initial Maximum Rod Enrichment As specified in Table 2-3 for the applicable fuel assembly array/class.
d. Post-irradiation Cooling Time and Average Burnup Per Assembly
i. Array/Classes 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A Cooling time 18 years and an average burnup 30,000 MWD/MTU (or MWD/MTIHM).

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

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

iv. All Other Array/Classes As specified in Section 2.2. 5 to Holtec Letter 5014917 12 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-9 Table 2-1 (page 4 of 8)

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

A. Allowable Contents (continued)

e. Decay Heat Per Assembly
i. Array/Classes 6x6A, 6X6B, 6x6C, 7x7A, and 8x8A 115 Watts ii. Array/Class 8x8F 183.5 Watts iii. Array/Classes 10x10D and 10x10E 95 Watts iv. All Other Array/Classes As specified in Section 2.2.
f. Fuel Assembly Length
i.

Array/Class

6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 135.0 inches (nominal design) ii. All Other Array/Classes 176.5 inches (nominal design)
g. Fuel Assembly Width
i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 4.70 inches (nominal design) ii. All Other Array/Classes 5.85 inches (nominal design)
h. Fuel Assembly Weight
i. Array/Class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A 400 lbs, including channels ii. All Other Array/Classes 730 lbs, including channels B. Quantity per MPC: Up to 68 fuel assemblies.

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

D. Array/Class 10x10D and 10x10E fuel assemblies in stainless steel channels must be stored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 - 50 (see Figure 2-4). 5 to Holtec Letter 5014917 13 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-10 Table 2-1 (page 5 of 8)

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

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

ZR or Stainless Steel (SS) as specified in Table 2-2 for the applicable fuel assembly array/class

b. Initial Enrichment:

As specified in Table 2-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Classes 14x14D, 14x14E, and 15x15G Cooling time 8 years and an average burnup 40,000 MWD/MTU.

ii. All Other Array/Classes As specified in Section 2.2.

iii. NON-FUEL HARDWARE As specified in Table 2-4. 5 to Holtec Letter 5014917 14 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-11 Table 2-1 (page 6 of 8)

Fuel Assembly Limits III. 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.

ii. All other Array/Classes As specified in Section 2.2.

e. Fuel Assembly Length:

176.8 inches (nominal design)

f. Fuel Assembly Width:

8.54 inches (nominal design)

g. Fuel Assembly Weight:

1,720 lbs (including NON-FUEL HARDWARE) for assemblies that do not require fuel

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

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

C. One NSA is permitted for loading.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing APSRs or NSAs may only be loaded in fuel storage locations 9, 10, 15, and/or 16 (see Figure 2-2). Fuel assemblies containing CRAs, RCCAs, or CEAs may only be stored in fuel storage locations 4, 5, 8 - 11, 14 - 17, 20 and/or 21 (see Figure 2-2). These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading. 5 to Holtec Letter 5014917 15 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-12 Table 2-1 (page 7 of 8)

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

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

ZR or Stainless Steel (SS) as specified in Table 2-2 for the applicable fuel assembly array/class

b. Initial Enrichment:

As specified in Table 2-2 for the applicable fuel assembly array/class.

c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i. Array/Classes 14x14D, 14x14E, and 15x15G 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.

ii. All Other Array/Classes As specified in Section 2.2.

iii. NON-FUEL HARDWARE As specified in Table 2-4. 5 to Holtec Letter 5014917 16 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-13 Table 2-1 (page 8 of 8)

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

A. Allowable Contents (continued)

d. Decay Heat Per Fuel Storage Location:
i. Array/Classes 14x14D, 14x14E, and 15x15G 500 Watts.

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

e. Fuel Assembly Length 176.8 inches (nominal design)
f. Fuel Assembly Width 8.54 inches (nominal design)
g. Fuel Assembly Weight 1,720 lbs (including NON-FUEL HARDWARE) for assemblies that do not require fuel spacers, otherwise, 1,680 lbs (including NON-FUEL HARDWARE)

B. Quantity per MPC: Up to 32 fuel assemblies.

C. One NSA is permitted for loading.

Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts, with or without ITTRs, may be stored in any fuel storage location. Fuel assemblies containing NSAs may only be loaded in fuel storage locations 13, 14, 19 and/or 20 (see Figure 2-3). Fuel assemblies containing CRAs, RCCAs, CEAs or APSRs may only be loaded in fuel storage locations 7, 8, 12-15, 18-21, 25 and/or 26 (see Figure 2-3). These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.

5 to Holtec Letter 5014917 17 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-14 Table 2-2 (page 1 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Table 2-2: PWR Fuel A ssembly Charact eristics Fuel Assembly Array/Class 14x14A 14x14B 14x14C 14x14D 14x14E Clad Material ZR ZR ZR SS SS Design Initial U

(kg/assy.) (Note 3) 365 412 438 400 206 Initial Enrichment (MPC-24 and 24E without soluble boron credit) (wt %

235U) 4.6 (24) 5.0 (24E) 4.6 (24) 5.0 (24E) 4.6 (24) 5.0 (24E) 4.0 (24) 5.0 (24E) 5.0 (24) 5.0 (24E)

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

5)

(wt % 235U) 5.0 5.0 5.0 5.0 5.0 No. of Fuel Rod Locations 179 179 176 180 173 Fuel Rod Clad O.D.

(in.)

0.400 0.417 0.440 0.422 0.3415 Fuel Rod Clad I.D.

(in.)

0.3514 0.3734 0.3880 0.3890 0.3175 Fuel Pellet Dia.

(in.)(Note 7) 0.3444 0.3659 0.3805 0.3835 0.3130 Fuel Rod Pitch (in.)

0.556 0.556 0.580 0.556 Note 6 Active Fuel Length (in.)

150 150 150 144 102 No. of Guide and/or Instrument Tubes 17 17 5 (Note 4) 16 0

Guide/Instrument Tube Thickness (in.)

0.017 0.017 0.038 0.0145 N/A 5 to Holtec Letter 5014917 18 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-15 Table 2-2 (page 2 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 15x15A 15x15B 15x15C 15x15D 15x15E 15x15F Clad Material ZR ZR ZR ZR ZR ZR Design Initial U

(kg/assy.) (Note 3)

< 473

< 473

< 473

< 495

< 495

< 495 Initial Enrichment (MPC-24 and 24E without soluble boron credit)

(wt 235U)

< 4.1 (24)

< 4.5 (24E)

< 4.1 (24)

< 4.5 (24E)

< 4.1 (24)

< 4.5 (24E)

< 4.1 (24)

< 4.5 (24E)

< 4.1 (24)

< 4.5 (24E)

< 4.1 (24)

< 4.5 (24E)

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

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0 No. of Fuel Rod Locations 204 204 204 208 208 208 Fuel Rod Clad O.D. (in.)

> 0.418

> 0.420

> 0.417

> 0.430

> 0.428

> 0.428 Fuel Rod Clad I.D.

(in.)

< 0.3660

< 0.3736

< 0.3640

< 0.3800

< 0.3790

< 0.3820 Fuel Pellet Dia.

(in.) (Note 7)

< 0.3580

< 0.3671

< 0.3570

< 0.3735

< 0.3707

< 0.3742 Fuel Rod Pitch (in.)

< 0.550

< 0.563

< 0.563

< 0.568

< 0.568

< 0.568 Active Fuel Length (in.)

< 150

< 150

< 150

< 150

< 150

< 150 No.

of Guide and/or Instrument Tubes 21 21 21 17 17 17 Guide/Instrument Tube Thickness (in.)

> 0.0165

> 0.015

> 0.0165

> 0.0150

> 0.0140

> 0.0140 5 to Holtec Letter 5014917 19 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-16 Table 2-2 (page 3 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/ Class 15x15G 15x15H 16x16A 16x16B 16x16C Clad Material SS ZR ZR ZR ZR Design Initial U

(kg/assy.)(Note 3)

< 420

< 495

< 448

< 427

< 426 Initial Enrichment (MPC-24and 24E without soluble boron credit)

(wt % 235U)

< 4.0 (24)

< 4.5 (24E)

< 3.8 (24)

< 4.2 (24E)

< 4.6 (24)

< 5.0 (24E)

< 4.6 (24)

< 5.0 (24E/24EF)

< 4.6 (24)

< 5.0 (24E/24EF)

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

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0 No. of Fuel Rod Locations 204 208 236 236 235 Fuel Rod Clad O.D. (in.)

> 0.422

> 0.414

> 0.382

> 0.374

> 0.374 Fuel Rod Clad I.D.

(in.)

< 0.3890

< 0.3700

< 0.3350

< 0.3290

< 0.3290 Fuel Pellet Dia.

(in.) (Note 7)

< 0.3825

< 0.3622

< 0.3255

< 0.3225

< 0.3225 Fuel Rod Pitch (in.)

< 0.563

< 0.568

< 0.506

< 0.506

< 0.485 Active Fuel Length (in.)

< 144

< 150

< 150

< 150

< 150 No.

of Guide and/or Instrument Tubes 21 17 5 (Note 4) 5 (Note 4) 21 Guide/Instrument Tube Thickness (in.)

> 0.0145

> 0.0140

> 0.0350

> 0.0400

> 0.0157 5 to Holtec Letter 5014917 20 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-17 Table 2-2 (page 4 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/ Class 17x17A 17x17B 17x17C Clad Material ZR ZR ZR Design Initial U

(kg/assy.)(Note 3)

< 433

< 474

< 480 Initial Enrichment (MPC-24and 24E without soluble boron credit)

(wt % 235U)

< 4.0 (24)

< 4.4 (24E)

< 4.0 (24)

< 4.4 (24E)

< 4.0 (24)

< 4.4 (24E)

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

< 5.0

< 5.0

< 5.0 No. of Fuel Rod Locations 264 264 264 Fuel Rod Clad O.D. (in.)

> 0.360

> 0.372

> 0.377 Fuel Rod Clad I.D.

(in.)

< 0.3150

< 0.3310

< 0.3330 Fuel Pellet Dia.

(in.) (Note 7)

< 0.3088

< 0.3232

< 0.3252 Fuel Rod Pitch (in.)

< 0.496

< 0.496

< 0.502 Active Fuel Length (in.)

< 150

< 150

< 150 No.

of Guide and/or Instrument Tubes 25 25 25 Guide/Instrument Tube Thickness (in.)

> 0.016

> 0.014

> 0.020 5 to Holtec Letter 5014917 21 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-18 Table 2-2 (page 5 of 5)

PWR FUEL ASSEMBLY CHARACTERISTICS Notes:

1. All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
2. Deleted.
3. Design initial uranium weight is the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each PWR fuel assembly, the total uranium weight limit specified in this table may be increased up to 2.0 percent for comparison with users fuel records to account for manufacturers tolerances.
4. Each guide tube replaces four fuel rods.
5. Soluble boron concentration per LCO 3.3.1of Appendix A-100U.
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. Annular fuel pellets are allowed in the top and bottom 12" of the active fuel length.

5 to Holtec Letter 5014917 22 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-19 Table 2-3 (page 1 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Table 2-3: BWR Fuel A ssembly Characterist ics Fuel Assembly Array/Class 6x6A 6x6B 6x6C 7x7A 7x7B 8x8A Clad Material ZR ZR ZR ZR ZR ZR Design Initial U (kg/assy.) (Note 3)

< 110

< 110

< 110

< 100

< 198

< 120 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (wt.%

235U)

< 2.7

< 2.7 for the UO2 rods.

See Note 4 for MOX rods

< 2.7

< 2.7

< 4.2

< 2.7 Initial Maximum Rod Enrichment (wt.% 235U)

< 4.0

< 4.0

< 4.0

< 5.5

< 5.0

< 4.0 No. of Fuel Rod Locations 35 or 36 35 or 36 (up to 9 MOX rods) 36 49 49 63 or 64 Fuel Rod Clad O.D. (in.)

> 0.5550

> 0.5625

> 0.5630

> 0.4860

> 0.5630

> 0.4120 Fuel Rod Clad I.D.

(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 Active Fuel Length (in.)

< 120

< 120

< 77.5

< 80

< 150

< 120 No. of Water Rods (Note 11) 1 or 0 1 or 0 0

0 0

1 or 0 Water Rod Thickness (in.)

> 0

> 0 N/A N/A N/A

> 0 Channel Thickness (in.)

< 0.060

< 0.060

< 0.060

< 0.060

< 0.120

< 0.100 5 to Holtec Letter 5014917 23 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-20 Table 2-3 (2 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 8x8B 8x8C 8x8D 8x8E 8x8F 9x9A Clad Material ZR ZR ZR ZR ZR ZR Design Initial U (kg/assy.) (Note 3)

< 192

< 190

< 190

< 190

< 191

< 180 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (wt.%

235U)

< 4.2

< 4.2

< 4.2

< 4.2

< 4.0

< 4.2 Initial Maximum Rod Enrichment (wt.% 235U)

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0 No. of Fuel Rod Locations 63 or 64 62 60 or 61 59 64 74/66 (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 (Note 11) 1 or 0 2

1 - 4 (Note 7) 5 N/A (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 5 to Holtec Letter 5014917 24 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-21 Table 2-3 (page 3 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 9x9B 9x9C 9x9D 9x9E (Note 13) 9x9F (Note 13) 9x9G Clad Material ZR ZR ZR ZR ZR ZR Design Initial U

(kg/assy.)(Note 3)

< 180

< 182

< 182

< 183

< 183

< 164 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (wt.%

235U)

< 4.2

< 4.2

< 4.2

< 4.0

< 4.0

< 4.2 Initial Maximum Rod Enrichment (wt.% 235U)

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0 No. of Fuel Rod Locations 72 80 79 76 76 72 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 Length (in.)

< 150

< 150

< 150

< 150

< 150

< 150 No. of Water Rods (Note 11) 1 (Note 6) 1 2

5 5

1 (Note 6)

Water Rod Thickness (in.)

> 0.00

> 0.020

> 0.0300

> 0.0120

> 0.0120

> 0.0320 Channel Thickness (in.)

< 0.120

< 0.100

< 0.100

< 0.120

< 0.120

< 0.120 5 to Holtec Letter 5014917 25 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-22 Table 2-3 (page 4 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 10x10A 10x10B 10x10C 10x10D 10x10E Clad Material ZR ZR ZR SS SS Design Initial U (kg/assy.)

(Note 3)

< 188

< 188

< 179

< 125

< 125 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (wt.% 235U)

< 4.2

< 4.2

< 4.2

< 4.0

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

< 5.0

< 5.0

< 5.0

< 5.0

< 5.0 No. of Fuel Rod Locations 92/78 (Note 8) 91/83 (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

< 0.488

< 0.565

< 0.557 Design Active Fuel Length (in.)

< 150

< 150

< 150

< 83

< 83 No. of Water Rods (Note 11) 2 1 (Note 6) 5 (Note 10) 0 4

Water Rod Thickness (in.)

> 0.0300

> 0.00

> 0.031 N/A

> 0.022 Channel Thickness (in.)

< 0.120

< 0.120

< 0.055

< 0.080

< 0.080 5 to Holtec Letter 5014917 26 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-23 Table 2-3 (page 5 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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.

Not Used.

3.

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

4.

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

5.

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

6.

Square, replacing nine fuel rods.

7.

Variable.

8.

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

9.

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

10. One diamond-shaped water rod replacing the four center fuel rods and four rectangular water rods dividing the assembly into four quadrants.
11. These rods may also be sealed at both ends and contain Zr material in lieu of water.
12. This assembly is known as QUAD+. It has four rectangular water cross segments dividing the assembly into four quadrants.
13. For the SPC 9x9-5 fuel assembly, each fuel rod must meet either the 9x9E or the 9x9F set of limits for clad O.D., clad I.D., and pellet diameter.

5 to Holtec Letter 5014917 27 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-24 Table 2.1-4 NON-FUEL HARDWARE COOLING AND AVERAGE BURNUP (Notes 1, 2, 3, and 8)

Table 2-4: Non-Fuel Hardware Cooling and Average Burnup Post-irradiation Cooling Time (years)

INSERTS (Note 4)

BURNUP (MWD/MTU)

NSA or GUIDE TUBE HARDWARE (Note 5)

BURNUP (MWD/MTU)

CONTROL COMPONENT (Note 6)

BURNUP (MWD/MTU)

APSR BURNUP (MWD/MTU)

> 3

< 24,635 NA (Note 7)

NA NA

> 4

< 30,000

< 20,000 NA NA

> 5

< 36,748

< 25,000

< 630,000

< 45,000

> 6

< 44,102

< 30,000

< 54,500

> 7

< 52,900

< 40,000

< 68,000

> 8

< 60,000

< 45,000

< 83,000

> 9

< 50,000

< 111,000

> 10

< 60,000

< 180,000

> 11

< 75,000

< 630,000

> 12

< 90,000

> 13

< 180,000

> 14

< 630,000 Notes: 1.

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 and < 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. 5 to Holtec Letter 5014917 28 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-25

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

5 to Holtec Letter 5014917 29 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-26 2.2 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 Model 100U. The method to calculate the limits and verify compliance, including examples, is provided in Chapter 12 of the HI-STORM 100 FSAR.

2.2.1 Uniform Fuel Loading Decay Heat Limits for ZR-clad Fuel Table 2-5 provides the maximum allowable decay heat per fuel storage location for ZR-clad fuel in uniform fuel loading for each MPC model.

Table 2-5: Maximum Allowable Decay Heat per Fuel Storage Location (Uniform Loading, ZR-Clad)

MPC Model Decay Heat per Fuel Storage Location (kW)

Intact Fuel Assemblies MPC-24

< 1.266 MPC-24E

< 1.266 MPC-32

< 0.949 MPC-68

< 0.447 2.2.2 Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel (INTACT FUEL only)

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

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

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

X = Inner region to outer region assembly decay heat ratio (0.5 X 3) n1 = Number of storage locations in inner region from Table 2-6.

n2 = Number of storage locations in outer region from Table 2-6.

5 to Holtec Letter 5014917 30 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-27 Table 2-6: Fuel Storage Regions per MPC MPC Model Number of Storage Locations in Inner Region (Region 1)

Number of Storage Locations in Outer Region (Region 2)

MPC-24 and MPC-24E 12 12 MPC-32 12 20 MPC-68 32 36 2.2.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel The maximum allowable ZR-clad fuel assembly average burnup varies with the minimum required fuel assembly cooling time. Tables 2-7 and 2-8 provide for each MPC the allowable maximum burnup based on the assemblys particular cooling time.

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

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

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

2.2.4 Compliance with Maximum Fuel Storage Location Decay Heat Limits 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.

5 to Holtec Letter 5014917 31 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-28 Table 2-7: PWR Fuel Assembly Burnup and Cooling Time Limits (ZR Clad Fuel)

Minimum Cooling Time (years)

Maximum Allowable Burnup, MWd/mtU MPC-24/24E/24EF 1.0 5,000 1.4 15,000 1.8 25,000 2.0 35,000 2.2 40,000 2.4 45,000 2.6 50,000 2.8 55,000 3.0 60,000 4.0 69,000 5.0 75,000 MPC-32/32F 1.0 5,000 1.4 10,000 1.8 20,000 2.0 25,000 2.2 30,000 2.4 35,000 2.6 40,000 3.0 45,000 4.0 60,000 5.0 69,000 5 to Holtec Letter 5014917 32 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2-29 Table 2-8: BWR Fuel Assembly Burnup and Cooling Time Limits (ZR Clad Fuel)

Minimum Cooling Time (years)

Maximum Allowable Burnup, MWd/mtU MPC-68/68FF/68M 1.0 10,000 1.2 15,000 1.4 20,000 2.0 25,000 2.2 30,000 2.4 35,000 2.6 40,000 3.0 50,000 4.0 62,000 5.0 65,000 6.0 70,000 5 to Holtec Letter 5014917 33 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-1 3 LIMITING CONDITIONS FOR OPERATION (LCOS)

AND SURVEILLANCE REQUIREMENTS (SRS) 3.0 Applicability Limiting Conditions for Operation (LCO) Applicability LCO 3.0.1 LCOs shall be met during specified conditions in the Applicability, except as provided in LCO 3.0.2.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

LCO 3.0.3 Not applicable.

LCO 3.0.4 When an LCO is not met, entry into a specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in specified conditions in the Applicability that are required to comply with ACTIONS or that are related to the unloading of an SFSC.

LCO 3.0.5 Equipment removed from service or not in service in compliance with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate it meets the LCO or that other equipment meets the LCO. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing.

5 to Holtec Letter 5014917 34 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-2 Surveillance Requirement (SR) Applicability SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3.

Surveillances do not have to be performed on equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as once, the above interval extension does not apply. If a Completion Time requires periodic performance on a once per...

basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is less. This delay period is permitted to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

SR 3.0.3 (continued)

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered. 5 to Holtec Letter 5014917 35 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-3 SR 3.0.4 Entry into a specified condition in the Applicability of an LCO shall not be made unless the LCO's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with Actions or that are related to the unloading of an SFSC.

3.1 SFSC INTEGRITY 3.1.1 Multi-Purpose Canister (MPC)

LCO 3.1.1 The MPC shall be dry and helium filled.

Table 3-1 provides decay heat and burnup limits for forced helium dehydration (FHD) and vacuum drying. FHD is not subject to time limits.

Vacuum drying of MPCs may be subject to time limits, from the end of bulk water removal until the start of helium backfill:

MPC Total Decay Heat (Q)

Vacuum Drying Time Limit Q < 26 kW None 26 kW < Q <30 kW 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Q > 30 kW Not Permitted (see Table 3-1) 5 to Holtec Letter 5014917 36 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-4 APPLICABILITY:

During TRANSPORT OPERATIONS and STORAGE OPERATIONS.

ACTIONS

NOTES---------------------------------------------------------

Separate Condition entry is allowed for each MPC.

CONDITION REQUIRED ACTION COMPLETION TIME A.

MPC cavity vacuum drying pressure or demoisturizer exit gas temperature limit not met.

A.1 Perform an engineering evaluation to determine the quantity of moisture left in the MPC.

7 days AND A.2 Develop and initiate corrective actions necessary to return the MPC to compliance with Table 3-1.

30 days 5 to Holtec Letter 5014917 37 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-5 ACTIONS (continued)

B.

MPC cavity vacuum drying acceptance criteria not met during allowable time.

B.1 Backfill the MPC cavity with helium to a pressure of at least 0.5 atm.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C.

MPC helium backfill limit not met.

C.1 Perform an engineering evaluation to determine the impact of helium differential.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND C.2.1 Develop and initiate corrective actions necessary to return the MPC to an analyzed condition by adding helium to or removing helium from the MPC.

14 days OR C.2.2 Develop and initiate corrective actions necessary to demonstrate through analysis, using the models and methods from the HI-STORM FSAR, that all limits for cask components and contents will be met.

D.

MPC helium leak rate limit for vent and drain port cover plate welds or cover plate base metal not met.

D.1 Perform an engineering evaluation to determine the impact of increased helium leak rate on heat removal capability and offsite dose.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND D.2 Develop and initiate corrective actions necessary to return the MPC to compliance with SR 3.1.1.3.

7 days 5 to Holtec Letter 5014917 38 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-6 E.

Required Actions and associated Completion Times not met.

E.1 Remove all fuel assemblies from the SFSC.

30 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify that the MPC cavity has been dried in accordance with the applicable limits in Table 3-1, within the specified vacuum drying time limits as applicable.

Once, prior to TRANSPORT OPERATIONS SR 3.1.1.2 Verify MPC helium backfill quantity is within the limit specified in Table 3-2 for the applicable MPC model.

Re-performance of this surveillance is not required upon successful completion of Action C.2.2.

Once, prior to TRANSPORT OPERATIONS SR 3.1.1.3 Verify that the helium leak rate through the MPC vent and drain port confinement welds meets the leaktight criteria of ANSI N14.5-1997. This surveillance does not need to be performed in the MPC utilizing the REDUNDANT PORT COVER DESIGN.
Once, prior to TRANSPORT OPERATIONS 5 to Holtec Letter 5014917 39 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-7 3.1.2 SFSC Heat Removal System LCO 3.1.2 The SFSC Heat Removal System shall be operable

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

The SFSC Heat Removal System is operable when 50% or more of the inlet and outlet vent areas are unblocked and available for flow or when air temperature requirements are met.

APPLICABILITY:

During STORAGE OPERATIONS.

ACTIONS

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

Separate Condition entry is allowed for each SFSC.

CONDITION REQUIRED ACTION COMPLETION TIME A. SFSC Heat Removal System

operable, but partially (<50%) blocked.

A.1 Remove blockage.

N/A B. SFSC Heat Removal System inoperable.

B.1 Restore SFSC Heat Removal System to operable status.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. Required Action B.1 and associated Completion Time not met.

C.1 Measure SFSC dose rates in accordance with the Radiation Protection Program.

Immediately and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.2.1 Restore SFSC Heat Removal System to operable status.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> 5 to Holtec Letter 5014917 40 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-8 CONDITION REQUIRED ACTION COMPLETION TIME OR C.2.2 Transfer the MPC into a TRANSFER CASK.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2 Verify all VVM inlets and outlets are free of blockage from solid debris or floodwater.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> OR For VVMs with installed temperature monitoring equipment, verify that the difference between the average VVM air outlet temperature and ISFSI ambient temperature is 85oF for VVMs containing PWR MPCs and 93oF for VVMs containing BWR MPCs.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> 5 to Holtec Letter 5014917 41 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-9 3.1.3 MPC Cavity Reflooding LCO 3.1.3 The MPC cavity pressure shall be < 100 psig

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

The LCO is only applicable to wet UNLOADING OPERATIONS.

APPLICABILITY:

UNLOADING OPERATIONS prior to and during re-flooding.

ACTIONS

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

Separate Condition entry is allowed for each MPC.

CONDITION REQUIRED ACTION COMPLETION TIME A.

MPC cavity pressure not within limit.

A.1 Stop re-flooding operations until MPC cavity pressure is within limit.

Immediately AND A.2 Ensure MPC vent port is not closed or blocked.

Immediately 5 to Holtec Letter 5014917 42 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Ensure via analysis or direct measurement that MPC cavity pressure is within limit.

Once, prior to MPC re-flooding operations.

AND Once every 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> thereafter when using direct measurement.

5 to Holtec Letter 5014917 43 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 1

3.1.4 Impressed Current Cathodic Protection System (ICCPS)

LCO 3.1.4 The ICCPS shall be maintained operative APPLICABILITY:

During STORAGE OPERATIONS for any ISFSI that uses an ICCPS for corrosion mitigation.

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

Separate condition entry is allowed for each ICCPS at a particular ISFSI site.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

ICCPS inoperable after initial startup period.

A.1 Restore ICCPS to operable status 6 months OR A.2 Perform engineering evaluation to determine that the affected VVMs will maintain adequate integrity for at least 4 more years.

1 year B.

ICCPS 70%

operable status not met.

B.1 Perform engineering evaluation to determine that the affected VVMs will maintain adequate integrity for at least 3 more years.

1 year OR B.2 Perform repairs necessary to re-establish integrity of the affected VVMs 3 years 5 to Holtec Letter 5014917 44 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 2

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Actions and associated Completion Times not met.

C.1 Transfer MPCs from affected VVMs to unaffected VVMs or other approved overpacks.

3 years SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify the ICCPS is operable 1 year after installation of the first VVM and remains operable after initial startup. The ICCPS may be shutdown temporarily as necessary for power outages, repair or preventive maintenance and testing, or system modifications after which the system should be returned to operable status as soon as practicable. This surveillance requirement is suspended for one year after action A.2 has been met Once within 1 year AND Every 1 month thereafter SR 3.1.5.2 Verify the ICCPS has been operable for at least 70% of the time after initial startup. The verification shall not be performed prior to 8 years from the time of initial startup.

If the integrity of the VVM has previously been re-established per ACTION B.2, then the initial startup period may be reset. This surveillance is no longer applicable upon initiation of ACTION C.1.

Once within 10 years AND Every 5 years thereafter 5 to Holtec Letter 5014917 45 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-3 3.2 SFSC RADIATION PROTECTION.

3.2.1 Not Used LCO 3.2.1 Not Used.

5 to Holtec Letter 5014917 46 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-4 3.2.2 TRANSFER CASK Surface Contamination.

LCO 3.2.2 Removable contamination on the exterior surfaces of the TRANSFER CASK and accessible portions of the MPC shall each not exceed:

a. 1000 dpm/100 cm2 from beta and gamma sources
b. 20 dpm/100 cm2 from alpha sources.

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

This LCO is not applicable to the TRANSFER CASK if MPC TRANSFER operations occur inside the FUEL BUILDING.

APPLICABILITY:

During TRANSPORT OPERATIONS.

ACTIONS

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

Separate Condition entry is allowed for each TRANSFER CASK.

CONDITION REQUIRED ACTION COMPLETION TIME A.

TRANSFER CASK or MPC removable surface contamination limits not met.

A.1 Restore removable surface contamination to within limits.

7 days 5 to Holtec Letter 5014917 47 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify that the removable contamination on the exterior surfaces of the TRANSFER CASK and accessible portions of the MPC containing fuel is within limits.

Once, prior to TRANSPORT OPERATIONS 5 to Holtec Letter 5014917 48 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-6 3.3 SFSC CRITICALITY CONTROL 3.3.1 Boron Concentration LCO 3.3.1 As required by Table 2-2, the concentration of boron in the water in the MPC shall meet the following limits for the applicable MPC model and the most limiting fuel assembly array/class and classification to be stored in the MPC:

a.

MPC-24 with one or more fuel assemblies having an initial enrichment greater than the value in Table 2-2 for no soluble boron credit and <

5.0 wt% 235U: > 400 ppmb

b.

MPC-24E with one or more fuel assemblies having an initial enrichment greater than the value in Table 2-2 for no soluble boron credit and < 5.0 wt% 235U: > 300 ppmb

c. MPC-32: Minimum soluble boron concentration as required by the table below.

Array/Class All INTACT FUEL ASSEMBLIES Maximum Initial Enrichment

< 4.1 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb) 14x14A/B/C/D/E 1,300 1,900 15x15A/B/C/G 1,800 2,500 15x15D/E/F/H 1,900 2,600 16x16A/B/C 1,400 2,000 17x17A/B/C 1,900 2,600 For maximum initial enrichments between 4.1 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.1 wt% and 5.0 wt%.

APPLICABILITY:

During PWR fuel LOADING OPERATIONS with fuel and water in the MPC AND During PWR fuel UNLOADING OPERATIONS with fuel and water in the MPC.

5 to Holtec Letter 5014917 49 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-7 ACTIONS

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

Separate Condition entry is allowed for each MPC.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Boron concentration not within limit.

A.1 Suspend LOADING OPERATIONS or UNLOADING OPERATIONS.

Immediately AND A.2 Suspend positive reactivity additions.

Immediately AND A.3 Initiate action to restore boron concentration to within limit.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

This surveillance is only required to be performed if the MPC is submerged in water or if water is to be added to, or recirculated through the MPC.

SR 3.3.1.1 Verify boron concentration is within the applicable limit using two independent measurements.

Once, within 4

hours prior to entering the Applicability of this LCO.

AND Once per 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> thereafter. 5 to Holtec Letter 5014917 50 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-1 Table 3-1: MPC Cavity Drying Limits for All MPC Types Fuel Burnup (MWD/MTU)

MPC Heat Load Q (kW)

Method of Moisture Removal (Notes 1 and 2)

All Assemblies < 45,000

< 30 VDS or FHD All Assemblies < 45,000

> 30 FHD One or more assemblies >

45,000

< 36.9 FHD Notes:

1.

VDS means a vacuum drying system. The acceptance criterion when using a VDS is the MPC cavity pressure shall be < 3 torr for > 30 minutes.

2.

FHD means a forced helium dehydration system. The acceptance criterion when using an FHD System is the gas temperature exiting the demoisturizer shall be

< 21oF for > 30 minutes or the gas dew point exiting the MPC shall be < 22.9oF for > 30 minutes.

3.

Vacuum drying of the MPC must be performed with the annular gap between the MPC and the HI-TRAC filled with water.

Table 3-2: MPC Helium Backfill Limits1 MPC MODEL LIMIT MPC-24/24E

i.

Cask Heat Load < 27.77 kW (MPC-24) or <

28.17 kW (MPC-24E) 0.1212 +/-10% g-moles/l OR

> 29.3 psig and < 48.5 psig ii. Cask Heat Load >27.77 kW (MPC-24) or >

28.17 kW (MPC-24E)

> 45.5 psig and < 48.5 psig MPC-32

i.

Cask Heat Load < 28.74 kW

> 29.3 psig and < 48.5 psig ii. Cask Heat Load >28.74 kW

> 45.5 psig and < 48.5 psig MPC-68

i.

Cask Heat Load < 28.19 kW 5 to Holtec Letter 5014917 51 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 3-2 0.1218 +/-10% g-moles/l OR

> 29.3 psig and < 48.5 psig ii. Cask Heat Load > 28.19 kW

> 45.5 psig and < 48.5 psig 1Helium used for backfill of MPC shall have a purity of > 99.995%. Pressure range is at a reference temperature of 70ºF 5 to Holtec Letter 5014917 52 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 4-3 4 ADMINISTRATIVE CONTROLS 4.1 Radioactive Effluent Control Program

a.

The HI-STORM 100 Cask System does not create any radioactive materials or have any radioactive waste treatment systems. Therefore, specific operating procedures for the control of radioactive effluents are not required. Specification 3.1.1, Multi-Purpose Canister (MPC), provides assurance that there are not radioactive effluents from the SFSC.

b.

This program includes an environmental monitoring program. Each general license user may incorporate SFSC operations into their environmental monitoring programs for 10 CFR Part 50 operations.

c.

An annual report shall be submitted pursuant to 10 CFR 72.44(d)(3).

4.2 Cask Transport Evaluation Program This program provides a means for evaluating various transport configurations and transport route conditions to ensure that the design basis drop limits are met. For lifting of the loaded TRANSFER CASK using devices which are integral to a structure governed by 10 CFR Part 50 regulations, 10 CFR 50 requirements apply. This program is not applicable when the TRANSFER CASK is in the FUEL BUILDING or is being handled by a device providing support from underneath (i.e., on a rail car, heavy haul trailer, air pads, etc...) or is being handled by a device designed in accordance with the increased safety factors of ANSI N14.6 and having redundant drop protection.

Pursuant to 10 CFR 72.212, this program shall evaluate the site-specific transport route conditions.

4.2.1 Transfer Cask For the TRANSFER CASK, the following requirements apply: 5 to Holtec Letter 5014917 53 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 4-4 4.2.1.1 The lift height above the transport route surface(s) shall not exceed the limits in Table 4-1 except as provided for in Specification 4.2.1.2. Also, if applying the limits in Table 4-1, the program shall ensure that the transport route conditions (i.e., surface hardness and pad thickness) are equivalent to or less limiting than either Set A or Set B in HI-STORM FSAR Table 2.2.9.

4.2.1.2 The program may determine lift heights by analysis based on the site-specific conditions to ensure that the impact loading due to design basis drop events does not exceed 45 gs at the top of the MPC fuel basket. These alternative analyses shall be commensurate with the drop analyses described in the Final Safety Analysis Report for the HI-STORM 100 Cask System. The program shall ensure that these alternative analyses are documented and controlled.

4.2.1.3 The TRANSFER CASK, when loaded with spent fuel, may be lifted to any height necessary during TRANSPORT OPERATIONS, provided the lifting device is designed in accordance with applicable stress limits from ANSI N14.6, and/or NUREG-0612, and has redundant drop protection features.

4.2.1.4 The TRANSFER CASK and MPC, when loaded with spent fuel, may be lifted to those heights necessary to perform cask handling operations, including MPC TRANSFER, provided the lifts are made with structures and components operated, fabricated, tested, inspected, and maintained in accordance with the guidelines of NUREG-0612, Control of Heavy Loads at Nuclear Power Plants,as applicable, and has devices that prevent uncontrolled lowering of the load.

Table 4-1: Transfer Cask and Free-Standing Overpack Lifting Requirements ITEM ORIENTATION LIFTING HEIGHT LIMIT (in.)

TRANSFER CASK Horizontal 42 Notes 1 and 2 TRANSFER CASK Vertical None Established Note 2 Notes:

1.

To be measured from the lowest point on the TRANSFER CASK (i.e., the bottom edge of the cask/lid assemblage)

2.

See Technical Specification 4.2.1.3 and 4.2.1.4 4.3 Radiation Protection Program 4.3.1.1 Each cask user shall ensure that the Part 50 radiation protection program appropriately addresses dry storage cask loading and unloading, as well as ISFSI operations, including transport of the loaded OVERPACK or TRANSFER CASK outside of facilities governed by 10 CFR Part 50. The radiation protection program shall include appropriate controls for direct radiation and contamination, ensuring compliance with applicable regulations, and implementing actions to maintain personnel occupational exposures As Low As Reasonably Achievable (ALARA). The actions and criteria to be included in the program are provided below. 5 to Holtec Letter 5014917 54 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 4-5 4.3.1.2 Based on the analysis performed pursuant to 10 CFR 72.212(b)(5)(iii), the licensee shall establish individual cask surface dose rate limits for the HI-TRAC TRANSFER CASK and the HI-STORM VVM to be used at the site. Total (neutron plus gamma) dose rate limits shall be established at the following locations:

a.

The top of the TRANSFER CASK and the VVM.

b.

The side of the TRANSFER CASK

c.

The outlet vent on the VVM 5 to Holtec Letter 5014917 55 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 4-6 4.3.1.3 Notwithstanding the limits established in Section 4.3.1.2, the measured dose rates on a loaded VVM shall not exceed 30 mrem/hr (gamma+neutron) on the top of the VVM.

4.3.1.4 The licensee shall measure the TRANSFER CASK and OVERPACK surface neutron and gamma dose rates as described in Section 4.3.1.7 for comparison against the limits established in Section 4.3.1.2 or Section 4.3.1.3, whichever are lower.

4.3.1.5 If the measured surface dose rates exceed the lower of the two limits established in Section 4.3.1.2 or Section 4.3.1.3, the licensee shall:

a.

Administratively verify that the correct contents were loaded in the correct fuel storage cell locations.

b.

Perform a written evaluation to verify whether a VVM at the ISFSI containing the as-loaded MPC will cause the dose limits of 10 CFR 72.104 to be exceeded.

c.

Perform a written evaluation within 30 days to determine why the surface dose rate limits were exceeded.

4.3.1.6 If the evaluation performed pursuant to Section 4.3.1.5 shows that the dose limits of 10 CFR 72.104 will be exceeded, the MPC shall not be placed into storage or the MPC shall be removed from storage until appropriate corrective action is taken to ensure the dose limits are not exceeded.

4.3.1.7 TRANSFER CASK and VVM surface dose rates shall be measured at approximately the following locations:

a.

A minimum of four (4) dose rate measurements shall be taken on the side of the TRANSFER CASK approximately at the cask mid-height plane. The measurement locations shall be approximately 90 degrees apart around the circumference of the cask. Dose rates shall be measured between the radial ribs of the water jacket.

b.

A minimum of four (4) TRANSFER CASK top lid dose rates shall be measured at locations approximately half way between the edge of the hole in the top lid and the outer edge of the top lid, 90 degrees apart around the circumference of the top lid.

c.

A minimum of four (4) dose rate measurements shall be taken on the top of the VVM.

These measurements shall be taken approximately 90 degrees apart around the circumference of the lid, approximately 18 inches radially inward from the edge of the lid.

d.

A minimum of four (4) dose rate measurements shall be taken adjacent to the outlet vent screen of the VVM, approximately 90 degrees apart.

4.3.1.8 The Radiation Protection Space (RPS) is a prismatic subgrade buffer zone surrounding a loaded VVM. The RPS boundary is located at a minimum of fourteen (14) feet from the centerline of a loaded VVM located on the periphery of an operating ISFSI, and at a minimum of twenty-one (21) feet from the centerline of a loaded VVM not located on the periphery. The RPS boundary shall not be encroached upon during any site construction activity. The jurisdictional boundary of the RPS extends from the top surface of the foundation pad to the top of the VVM interface pad and the top surface pad. The ISFSI design shall ensure that there is no significant loss of shielding in the RPS due to a credible accident or an extreme environment event during construction involving excavation adjacent to the RPS boundary.

5 to Holtec Letter 5014917 56 of 57

Certificate of Compliance No. 1014 Amendment No. 16 Appendix B-100U 4-7 4.4 Violations of Fuel Specifications or Loading Conditions If any Fuel Specifications or Loading Conditions of 2.1 are violated, the following actions shall be completed:

a.

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

b.

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.

c.

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

4.5 Heavy Loads Requirements Each lift of an MPC or a HI-TRAC transfer cask must be made in accordance to the existing heavy loads requirements and procedures of the licensed facility at which the lift is made. A plant specific review (under 10 CFR 50.59 or 10 CFR 72.48, if applicable) is required to show operational compliance with existing plant specific heavy loads requirements. Lifting operations outside of structures governed by 10 CFR Part 50 must be in accordance with Section 4.2 of Appendix B-100U.

5 to Holtec Letter 5014917 57 of 57

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