ML21288A526

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Attachment 4: HI-STORM FW Amendment 7 Certificate of Compliance Appendix B, Changed Pages
ML21288A526
Person / Time
Site: 07201032
Issue date: 10/15/2021
From:
Holtec
To:
Office of Nuclear Material Safety and Safeguards
Shared Package
ML21288A521 List:
References
5018091, CAC 001028, CoC No. 1032, EPID L2021-LLA-0053
Download: ML21288A526 (6)
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Text

Approved Contents 2.0 3-1 3-2 3-3 3-4 2-1 2-2 3-5 3-6 3-7 2-3 2-4 2-5 2-6 3-8 3-9 2-7 2-8 1-1 1-2 2-9 2-10 3-10 3-11 2-11 2-12 1-3 1-4 2-13 2-14 3-12 3-13 2-15 2-16 2-17 2-18 3-14 3-15 3-16 2-19 2-20 3-17 3-18 3-19 3-20 Figure 2.1-5 MPC-44 Cell Identification Certificate of Compliance No.1032 Amendment No. 76 Appendix B 2-6

Approved Contents 2.0 Table 2.1-1 (page 9 of 10)

Fuel Assembly Limits V. MPC MODEL: MPC-44 A. Allowable Contents

1. Uranium oxide PWR UNDAMAGED FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES meeting the criteria for array/class 14x14A and 14x14B in Table 2.1-2 and/or FUEL DEBRIS, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):
a. Cladding Type: ZR
b. Maximum Initial Enrichment: 5.0 wt. % U-235
c. Post-irradiation Cooling Time Cooling Time 3 years and meeting the and Average Burnup Per equation in Section 2.5 Assembly:

Assembly Average Burnup 60.0 GWD/MTU

d. Decay Heat Per Fuel Storage As specified in Section 2.3 Location:
e. Fuel Assembly Length: 170.5 inches (nominal design including DFC)
f. Fuel Assembly Width: 7.81 inches (nominal design)
g. Fuel Assembly Weight: 1250 lbs (including DFC)

B. Quantity per MPC: 44 FUEL ASSEMBLIES with up to twelve (12) DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS in DAMAGED FUEL CONTAINERS (DFCs). DFCs may be stored in fuel storage locations 3-1 through 3-3, 3-6, 3-9 through 3-12, 3-15, and 3-18 through 3-20 (see Figure 2.1-5). The remaining fuel storage locations may be filled with PWR UNDAMAGED FUEL ASSEMBLIES meeting the applicable specifications.

C. Up to twenty-two (22) BPRAs and/or WABAs are authorized for loading in the MPC-44.

Certificate of Compliance No.1032 Amendment No. 76 Appendix B 2-15

Approved Contents 2.0 Table 2.1-3 (2 of 5)

BWR FUEL ASSEMBLY CHARACTERISTICS (Notes 1, 17)

Fuel Assembly 8x8G 8x8F 9x9 A 9x9 B 9x9 C 9x9 D Array and Class Maximum Planar-Average Initial < 4.5 < 4.8

< 4.8 < 4.8 < 4.8 < 4.8 Enrichment (wt.% (Note 12) 235U) (Note 14)

No. of Fuel Rod 60 74/66 64 72 80 79 Locations (Note 16) (Note 4)

Fuel Clad O.D. (in.) > 0.4576 > 0.5015 > 0.4400 > 0.4330 > 0.4230 > 0.4240 Fuel Clad I.D. (in.) < 0.3996 < 0.4295 < 0.3840 < 0.3810 < 0.3640 < 0.3640 Fuel Pellet Dia. (in.) < 0.3913 < 0.4195 < 0.3760 < 0.3740 < 0.3565 < 0.3565 Fuel Rod Pitch (in.) < 0.609 < 0.642 < 0.566 < 0.572 < 0.572 < 0.572 Design Active Fuel < 150

< 150 < 150 < 150 < 150 < 150 Length (in.)

No. of Water Rods N/A 4 1 2 1 2 (Note 10) (Note 2) (Note 15) (Note 5)

Water Rod > N/A Thickness (in.) 0.031502 > 0.00 > 0.00 > 0.020 > 0.0300 5

Channel Thickness < 0.120

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

Certificate of Compliance No.1032 Amendment No. 76 Appendix B 2-23

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

BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1,17 )

Fuel Assembly Array 10x10 C 10x10 F 10x10 G 10x10 I 10x10 J 11x11 A and Class Maximum Planar-Average

< 4.7 < 4.6 Initial Enrichment (wt.% < 4.8 < 4.8 < 4.8 < 4.8 235U) (Note 14) (Note 13) (Note 12)

No. of Fuel Rod Locations 92/78 91/79 96/80 112/92 96 96/84 (Note 16) (Note 7) (Note 18) (Note 19) (Note 20)

Fuel Clad O.D. (in.) > 0.3780 > 0.4035 > 0.387 > 0.4047 > 0.3999 > 0.3701 Fuel Clad I.D. (in.) < 0.3294 < 0.3570 < 0.340 < 0.3559 < 0.3603 < 0.3252 Fuel Pellet Dia. (in.) < 0.3224 < 0.3500 < 0.334 < 0.3492 < 0.3501 < 0.3193 Fuel Rod Pitch (in.) < 0.4705

< 0.488 < 0.510 < 0.512 < 0.5100 < 0.5149 (Note 21)

Design Active Fuel

< 150 < 150 < 150 < 150 < 150 < 150 Length (in.)

No. of Water Rods (Note 5 5 1 1 2 1

10) (Note 9) (Note 9) (Note 5) (Note 5)

Water Rod Thickness (in.) >

> 0.031 > 0.030 > 0.031 > 0.0315 > 0.0297 0.034003 20 Channel Thickness (in.) < 0.055 < 0.120 < 0.060 < 0.100 < 0.0938 < 0.100 Certificate of Compliance No.1032 Amendment No. 76 Appendix B 2-25

Approved Contents

2.0 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. This assembly is known as QUAD+. It has four rectangular water cross segments dividing the assembly into four quadrants.
3. For the SPC 9x9-5 fuel assembly, each fuel rod must meet either the 9x9E or the 9x9F set of limits or clad O.D., clad I.D., and pellet diameter.
4. This assembly class contains 74 total rods; 66 full length rods and 8 partial length rods.
5. Square, replacing nine fuel rods.
6. Variable.
7. This assembly contains 92 total fuel rods; 78 full length rods and 14 partial length rods.
8. This assembly class contains 91 total fuel rods; 83 full length rods and 8 partial length rods.
9. One diamond-shaped water rod replacing the four center fuel rods and four rectangular water rods dividing the assembly into four quadrants.
10. These rods may also be sealed at both ends and contain ZR material in lieu of water.
11. Not used.
12. When loading fuel assemblies classified as DAMAGED FUEL, all assemblies in the MPC are limited to 4.0 wt.% U-235.
13. When loading fuel assemblies classified as DAMAGED FUEL, all assemblies in the MPC are limited to 4.6 wt.% U-235.
14. In accordance with the definition of UNDAMAGED FUEL, certain assemblies may be limited to 3.3 wt.% U-235. When loading these fuel assemblies, all assemblies in the MPC are limited to 3.3 wt.% U-235.
15. These fuel designs do not have water rods, but instead contain solid zirc rods.
16. Any number of fuel rods in an assembly can be replaced by irradiated or unirradiated Steel or Zirconia rods. If the rods are irradiated, the site specific dose and dose rate analyses performed under 10 CFR 72.212 should include considerations for the presence of such rods.
17. Any number of fuel rods in an assembly can be contain BLEU fuel. If the BLEU rods are present, the site specific dose and dose rate analyses performed under 10 CFR 72.212 should include considerations for the presence of such rods.
18. Contains in total 91 fuel rods; 79 full length rods, 12 long partial length rods, and one square water rod replacing 9 fuel rods.
19. 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 or 12 fuel rods.
20. 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.
21. This is the maximum fixed rod pitch. The assembly may have areas of variable pitch that exceed this value and remains acceptable for storage.

Certificate of Compliance No.1032 Amendment No. 76 Appendix B 2-26

Approved Contents 2.0 TABLE 2.3-1A MPC-37 AND MPC-37P HEAT LOAD DATA (See Figure 2.1-1)

Number of Regions: 3 Number of Storage Cells: 37 Maximum Design Basis Heat Load (kW): 44.09 (Pattern A); 45.0 (Pattern B)

Region Decay Heat Limit per Cell, Number of Cells Decay Heat Limit per No. kW per Region Region, kW Pattern A Pattern B Pattern A Pattern B 1 1.05 1.0 9 9.45 9.0 2 1.70 1.2 12 20.4 14.4 3 0.89 1.35 16 14.24 21.6 TABLE 2.3-1B MPC-37 HEAT LOAD DATA (See Figure 2.1-1)

Number of Regions: 3 Number of Storage Cells: 37 90% of Pattern A - Sub-design Heat Load (kW): 39.68 Region No. Decay Heat Limit per Number of Cells Decay Heat Limit per Cell, kW per Region Region, kW 1 0.945 9 8.505 2 1.530 12 18.36 3 0.801 16 12.816 TABLE 2.3-1C MPC-37 HEAT LOAD DATA (See Figure 2.1-1)

Number of Regions: 3 Number of Storage Cells: 37 80% of Pattern A - Sub-design Heat Load (kW): 35.27 Region No. Decay Heat Limit per Number of Cells Decay Heat Limit per Cell, kW per Region Region, kW 1 0.84 9 7.56 2 1.36 12 16.32 3 0.712 16 11.392 Certificate of Compliance No.1032 Amendment No. 76 Appendix B 2-29

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