Text

Attachment 4 - HI-STORM 100 Amendment 15 Certificate of Compliance, Appendix B (Nonproprietary)
	ML19092A177
Person / Time
Site:	Holtec
Issue date:	03/20/2019
From:	; Holtec
To:	; Division of Spent Fuel Management
Shared Package
ML19092A192	List: ML19092A172; ML19092A173; ML19092A175; ML19092A176; ML19092A177; ML19092A178; ML19092A179; ML19092A189;
References
	5014867
	Download: ML19092A177 (10)
	v • d • e

Certificate of Compliance No. 1014 Amendment No. 15 Appendix B i

TABLE OF CONTENTS 1.0 DEFINITIONS........................................................................................................ 1-1 2.0 APPROVED CONTENTS...................................................................................... 2-1 2.1 Fuel Specification and Loading Conditions........................................................ 2-1 2.2 Violations........................................................................................................... 2-2 2.3 Not Used............................................................................................................ 2-2 2.4 Decay Heat, Burnup & Cooling Time Limits for ZR Clad Fuel......................... 2-47 Figure 2.1-1 Fuel Loading Regions - MPC-24........................................................ 2-3 Figure 2.1-2 Fuel Loading Regions - MPC-24E/24EF............................................ 2-4 Figure 2.1-3 Fuel Loading Regions - MPC-32/32F................................................. 2-5 Figure 2.1-4 Fuel Loading Regions - MPC-68/68FF/68M....................................... 2-6 Table 2.1-1 Fuel Assembly Limits.......................................................................... 2-7 Table 2.1-2 PWR Fuel Assembly Characteristics................................................ 2-36 Table 2.1-3 BWR Fuel Assembly Characteristics................................................ 2-41 Table 2.1-4 Table Deleted................................................................................... 2-42 Table 2.1-5 Table Deleted................................................................................... 2-43 Table 2.1-6 Table Deleted................................................................................... 2-44 Table 2.1-7 Table Deleted................................................................................... 2-45 Table 2.1-8 Non-Fuel Hardware Cooling and Average Burnup............................ 2-45 Table 2.1-9 Restrictions for Partial Gadolinium Credit in MPC-68M..2-50 Table 2.4-1 Maximum Allowable Decay Heat per Fuel Storage Location............ 2-46 Table 2.4-2 Fuel Storage Locations per MPC...................................................... 2-47 Table 2.4-3 PWR Fuel Assembly Cooling Time-Dependent Coefficients. 2-54 Table 2.4-4 BWR Fuel Assembly Cooling Time-Dependent Coefficients. 2-62 Table 2.4-5 Heat Load for Damaged Fuel Assemblies and Fuel Debris under Regionalized Loading.............................................................................................. 2-50 3.0 DESIGN FEATURES............................................................................................. 3-1 3.1 Site.................................................................................................................... 3-1 3.2 Design Features Important for Criticality Control............................................... 3-1 3.3 Codes and Standards........................................................................................ 3-2 3.4 Site Specific Parameters and Analyses........................................................... 3-14 3.5 Cask Transfer Facility (CTF)............................................................................ 3-18 3.6 Forced Helium Dehydration System................................................................ 3-21 3.7 Supplemental Cooling System......................................................................... 3-23 3.8 Combustible Gas Monitoring During MPC Lid Welding and Cutting................ 3-26 3.9 Environmental Temperature Requirements..................................................... 3-26 Table 3-1 List of ASME Code Alternatives for HI-STORM 100 Cask System......... 3-4 ATTACHMENT 4 TO HOLTEC LETTER 5014867 1 of 10

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 15 Appendix B 2-42 Table 2.1-3 (page 1 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 6x6A 6x6B 6x6C 7x7A 7x7B 8x8A Clad Material ZR ZR ZR ZR ZR ZR Design Initial U (kg/assy.) (Note 3)

< 110

< 100

< 198

< 120 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68, 68F, and 68FF)

(wt.% 235U)

(Note 14)

< 2.7

< 2.7 for the UO2 rods.

See Note 4 for MOX rods

< 2.7

< 4.2

< 2.7 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68M)

(wt.% 235U)

(Note 16, 19)

Note 18 Note 18 Note 18 Note 18 4.8 Note 18 Initial Maximum Rod Enrichment (wt.% 235U)

< 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

< 0.740

< 0.631

< 0.738

< 0.523 Active Fuel Length (in.)

< 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

< 0.120

< 0.100 ATTACHMENT 4 TO HOLTEC LETTER 5014867 2 of 10

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 15 Appendix B 2-43 Table 2.1-3 (2 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

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

< 192

< 190

< 191

< 180 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68, 68F, and 68FF)

(wt.% 235U)

(Note 14)

< 4.2

< 4.0

< 4.2 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68M)

(wt.% 235U)

(Note 16, 19) 4.8 4.8 4.8 4.8 4.5 (Note 15) 4.8 Initial Maximum Rod Enrichment (wt.% 235U)

< 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

> 0.4930

> 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

< 0.609

< 0.566 Design Active Fuel Length (in.)

< 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

> 0.034

> 0.0315

> 0.00 Channel Thickness (in.)

< 0.120

< 0.100

< 0.055

< 0.120 ATTACHMENT 4 TO HOLTEC LETTER 5014867 3 of 10

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 15 Appendix B 2-44 Table 2.1-3 (page 3 of 6)

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

< 183

< 164 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68, 68F, and 68FF)

(wt.% 235U)

(Note 14)

< 4.2

< 4.0

< 4.2 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68M)

(wt.% 235U)

(Note 16, 19) 4.8 4.8 4.8 4.5 (Note 15) 4.5 (Note 15) 4.8 Initial Maximum Rod Enrichment (wt.% 235U)

< 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

< 0.3860

< 0.3640 Fuel Pellet Dia. (in.)

< 0.3740

< 0.3565

< 0.3530

< 0.3745

< 0.3565 Fuel Rod Pitch (in.)

< 0.572

< 0.572 Design Active Fuel Length (in.)

< 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

> 0.0320 Channel Thickness (in.)

< 0.120

< 0.100

< 0.120

< 0.120 ATTACHMENT 4 TO HOLTEC LETTER 5014867 4 of 10

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 15 Appendix B 2-45 Table 2.1-3 (page 4 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array/Class 10x10A 10x10B 10x10C 10x10D 10x10E 10x10F 10x10G Clad Material ZR ZR ZR SS SS ZR ZR Design Initial U (kg/assy.)

(Note 3)

< 188

< 179

< 125

< 125 192 188 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT(MPC-68, 68F, and 68FF)

(wt.% 235U) (Note 14)

< 4.2

< 4.0

< 4.0 Note 17 Note 17 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT (MPC-68M)

(wt.% 235U)

(Note 16, 19) 4.8 4.8 4.8 Note 18 Note 18 4.7 (Note 15) 5.0 (Note 25) 4.75 (Note 20) 5.0 (Note 25)

Initial Maximum Rod Enrichment (wt.% 235U)

< 5.0

< 5.0 No. of Fuel Rod Locations 92/78 (Note 8) 91/83 (Note 9) 96 100 96 92/78 (Note 8) 96/84 Fuel Rod Clad O.D. (in.)

> 0.4040

> 0.3957

> 0.3780

> 0.3960

> 0.3940 0.4035 0.387 Fuel Rod Clad I.D. (in.)

< 0.3520

< 0.3480

< 0.3294

< 0.3560

< 0.3500 0.3570 0.340 Fuel Pellet Dia. (in.)

< 0.3455

< 0.3420

< 0.3224

< 0.3500

< 0.3430 0.3500 0.334 Fuel Rod Pitch (in.)

< 0.510

< 0.488

< 0.565

< 0.557 0.510 0.512 Design Active Fuel Length (in.)

< 150

< 83

< 83 150 150 No. of Water Rods (Note 11) 2 1

(Note 6) 5 (Note 10) 0 4

2 5

(Note 10)

Water Rod Thickness (in.)

> 0.030

> 0.00

> 0.031 N/A

> 0.022 0.030 0.031 Channel Thickness (in.)

< 0.120

< 0.055

< 0.080

< 0.080 0.120 0.060 ATTACHMENT 4 TO HOLTEC LETTER 5014867 5 of 10

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 15 Appendix B 2-46 Table 2.1-3 (page 5 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)

Fuel Assembly Array and Class 10x10I (Note 17,

21) 10x10J (Note 17,

22) 11x11A (Note 17,

23)

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

(Note 3) 194 194 194 Maximum Planar-Average Initial Enrichment (wt.%

235U) (Note 16, 19) 4.8 4.8 4.8 Maximum Planar-Average Initial Enrichment with Partial Gadolinium Credit (wt.%235U) (Note 25) 5.0 5.0 5.0 Initial Rod Maximum Enrichment (wt.% 235U) 5.0 5.0 5.0 No. of Fuel Rod Locations 91/79 96/80 112/92 Fuel Clad O.D. (in.)

> 0.4047

>0.3999

>0.3701 Fuel Clad I.D. (in.)

< 0.3559

< 0.3603

< 0.3252 Fuel Pellet Dia. (in.)

< 0.3492

< 0.4484

< 0.3193 Fuel Rod Pitch (in.)

< 0.5100

< 0.3514

< 0.4705 Design Active Fuel Length (in.)

< 150

< 150 No. of Water Rods (Note 24) 1 1

1 Water Rod Thickness (in.)

> 0.0315

> 0.0297

> 0.0340 Channel Thickness (in.)

< 0.100

< 0.938

< 0.100 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. % 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.

ATTACHMENT 4 TO HOLTEC LETTER 5014867 6 of 10

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 15 Appendix B 2-47 Table 2.1-3 (page 6 of 6)

BWR FUEL ASSEMBLY CHARACTERISTICS

8.

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

9.

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

25. The restrictions in Table 2.1-9 apply.

ATTACHMENT 4 TO HOLTEC LETTER 5014867 7 of 10

Approved Contents 2.0 Certificate of Compliance No. 1014 Amendment No. 15 Appendix B 2-49 Table 2.1-9 RESTRICTIONS FOR PARTIAL GADOLINIUM CREDIT IN MPC-68M FUEL ASSEMBLY ARRAY AND CLASS RESTRICTION All 10x10 and 11x11 The gadolinium rod loading is not less than 3.0 wt%

Gd2O3 All 10x10 and 11x11 The gadolinium rods located in the peripheral row of the fuel lattice cannot be credited All 10x10 and 11x11 Gadolinium rods are NOT required to be present in damaged fuel in DFIs or damaged fuel/fuel debris in DFCs 10x10A, 10x10B, 10x10F, 10x10I, 10x10J, and 11x11A At least one gadolinium rod must be present.

10x10C and 10x10G At least two gadolinium rods must be present ATTACHMENT 4 TO HOLTEC LETTER 5014867 8 of 10

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 15 Appendix B 3-16 DESIGN FEATURES (continued) 3.4 Site-Specific Parameters and Analyses (continued)

7.

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

8.

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

a.

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

b.

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

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

9.

For those users whose site-specific design basis includes an event or events (e.g., flood) that result in the blockage of any OVERPACK inlet or outlet air ducts for an extended period of time (i.e, longer than the total Completion Time of LCO 3.1.2), an analysis or evaluation may be performed to demonstrate adequate heat removal is available for the duration of the event. Adequate heat removal is defined as fuel cladding temperatures remaining below the short term temperature limit. If the analysis or evaluation is not performed, or if fuel cladding temperature limits are unable to be demonstrated by analysis or evaluation to remain below the short term temperature limit for the duration of the event, provisions shall be established to provide alternate means of cooling to accomplish this objective.

10.

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

11.

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

(continued)

ATTACHMENT 4 TO HOLTEC LETTER 5014867 9 of 10

Design Features 3.0 Certificate of Compliance No. 1014 Amendment No. 15 Appendix B 3-25 DESIGN FEATURES (continued) 3.8 Combustible Gas Monitoring During MPC Lid Welding and Cutting During MPC lid-to-shell welding and cutting operations, combustible gas monitoring of the space under the MPC lid is required, to ensure that there is no combustible mixture present.

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

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

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

ATTACHMENT 4 TO HOLTEC LETTER 5014867 10 of 10

ML19092A177

Text

Navigation menu

Search