ML25216A286
| ML25216A286 | |
| Person / Time | |
|---|---|
| Site: | HI-STORM 100 |
| Issue date: | 08/04/2025 |
| From: | Holtec |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML25216A283 | List: |
| References | |
| 5021081 | |
| Download: ML25216A286 (1) | |
Text
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL HI-2115090 Proposed Rev. 8BA7 2-51 Table 2.1.15 HI-STORM UMAX Version B2 PERMISSIBLE HEAT LOADS MPC Type Fuel Type (See Table 2.1.7 for length data)
Fuel Assembly Array and Class Heat Load limit per Storage Cell (Note 1)
Permissible Aggregate Heat Load (Note 2),
kW MPC-37 Standard Fuel 16x16 A Figure 2.1.29 11.6510.87 Note 1: See Figure 2.1.29 for more details about cell heat load.
Note 2: The aggregate heat load is defined as a sum of all stored fuel assemblies. Thermal evaluations in Chapter 4 are performed with maximum per storage cell heat load in all locations.
to Holtec Letter 5021081
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL HI-2115090 Proposed Rev. 8BA7 2-81 1
0.33005 2
0.24023 3
0.3050.33 0
4 0.291315 5
0.36539 6
0.3670.39 5
7 0.3390.36 5
8 0.2910.31 5
9 0.3050.33 0
10 0.3390.36 5
11 0.26544 12 0.2440.26 5
13 0.2440.26 5
14 0.3390.36 5
15 0.3050.33 0
16 0.2230.24 0
17 0.395367 18 0.2440.26 5
19 0.2440.17 5
20 0.2440.26 5
21 0.39567 22 0.2230.24 0
23 0.3050.33 0
24 0.3390.36 5
25 0.2440.26 5
26 0.2440.26 5
27 0.2440.26 5
28 0.3390.36 5
29 0.3050.33 0
30 0.2910.31 5
31 0.3390.36 5
32 0.39567 33 0.3390.36 5
34 0.2910.31 5
35 0.3050.33 0
36 0.2230.24 0
37 0.3050.33 0
Figure 2.1.29: HI-STORM UMAX B2 MPC-37 Permissible Heat Load for Standard Fuel 16x16A Legend Cell ID Heat Load, kW to Holtec Letter 5021081 I
l l I
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL HI-2115090 Proposed Rev. 8BA7 2-104 Table 2.3.7 TEMPERATURE LIMITS (General Note)
Component Normal &
Mechanical Accident Condition Design Temperature Limits (oF) (Note 1)
Short-Term Events Temperature Limits (oF) (Note 6)
Off-Normal and Accident Condition Temperature Limits (oF ) (Note 2)
MPC shell 650 800 1058 MPC basket 752 932 1058 (Note 5)
MPC basket shims 752 932 1058 MPC lid 752 800 1058 MPC closure ring 752 800 1058 MPC baseplate 752 800 1058 CEC shell 650 650 1058 CEC Flange 650 650 1058 Fuel Cladding 752 (Normal Storage) 752 or 1058 (Note 6) 1058 (Note 3)
Damaged Fuel Containers (DFCs) 752 (Normal Storage) 1058 1058 Closure Lid concrete (section average) 300350 (Note 7) 300350 (Note 7) 600 (Note 4)
Closure Lid Top and Bottom Plate 650 650 1058 Remainder of VVM steel structure 650 650 1058 Divider Shell 650 650 1058 Insulation 650 650 1058 SES in Space A for UMAX Version B1/B2 MSE option (section average) (see Figure 2.4.4 and Table 2.3.10) 300 (Note 7) 300 (Note 7) 600 HI-TRAC VW inner shell 500 700 HI-TRAC VW bottom lid 350 700 HI-TRAC VW top flange 400 650 to Holtec Letter 5021081
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL HI-2115090 Proposed Rev. 8BA7 2-106 Note 7: The normal condition design temperature limit for the closure lid concrete and the concrete used for SES in Space A is the same as the temperature limit for the plain concrete in the HI-STORM 100 closure lid and cask body, as established in Appendix 1.D of the HI-STORM 100 FSAR [2.3.4]. Conservatively, the temperature limit for normal conditions is also adopted for short-term events. For SES in Space A for UMAX Version B1/B2, dolostone aggregate is prohibited from being used in concrete mix due to its potential instability at sustained high temperatures [2.3.5].
General Note:
The normal condition temperature limits are used in the design basis structural evaluations for MPC and HI-STORM UMAX system. The short-term condition temperature limits are used in the design basis structural evaluations for HI-TRAC. All other short-term, off-normal and accident condition structural evaluations are based on bounding temperatures from thermal evaluations presented in Chapter 4.
to Holtec Letter 5021081
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL HI-2115090 Proposed Rev. 8BA7 2-167 2.13 REFERENCES
[2.0.1]
Final Safety Analysis Report on the HI-STORM FW System, Holtec Report No.
HI-2114830, Revision 8.
[2.0.2]
USNRC Memorandum from Christopher L. Brown to M. Wayne Hodges, Scoping Calculations for Cladding Hoop Stresses in Low Burnup Fuel, dated January 29, 2004.
[2.1.1]
ORNL/TM-10902, "Physical Characteristics of GE BWR Fuel Assemblies", by R.S. Moore and K.J. Notz, Martin Marietta (1989).
[2.1.2]
U.S. DOE SRC/CNEAF/96-01, Spent Nuclear Fuel Discharges from U.S. Reactors 1994, Feb. 1996.
[2.1.3]
S.E. Turner, Uncertainty Analysis - Axial Burnup Distribution Effects, presented in Proceedings of a Workshop on the Use of Burnup Credit in Spent Fuel Transport Casks, SAND-89-0018, Sandia National Laboratory, Oct., 1989.
[2.1.4]
Commonwealth Edison Company, Letter No. NFS-BND-95-083, Chicago, Illinois.
[2.2.1]
ACI 229R-99, Controlled Low-Strength Materials, American Concrete Institute, 1999.
[2.2.2]
ANSI/ASCE 7-05 (formerly ANSI A58.1), Minimum Design Loads for Buildings and Other Structures, American Society of Civil Engineers, New York, NY, 2006.[2.2.3]
"Debris Collection System for Boiling Water Reactor Consolidation Equipment", EPRI Project 3100-02 and ESEERCO Project EP91-29, October 1995.
[2.3.1]
Portland Cement Association, Structural Bureau, Concrete Information Bulletin No. ST32, Effect of Long Exposure of Concrete to High Temperature
[2.3.2]
Handbook of Aluminum, 3rd Edition, ALCAN Aluminum Corporation (1970),
Page 147.
[2.3.3]
Crane Manufacturer's Association of America (CMAA), Specification #70, 1988, Section 3.3.
[2.3.4]
HI-STORM 100 Final Safety Analysis Report, Holtec Report No. HI-2002444, Revision 24.
[2.3.5]
Carette and Malhotra, Performance of Dolostone and Limestone Concretes at Sustained High Temperatures, ASTM Special Technical Publication 858, ASTM PCN 04-858000-07, p. 38-67.
[2.4.1]
NUREG/CR-6865, Parametric Evaluation of Seismic Behavior of Freestanding Spent Fuel Dry Storage Systems, U.S. Nuclear Regulatory Commission, February 2005.
[2.4.2]
NUREG-0800, SRP 3.7.1, Seismic Design Parameters, USNRC, Revision 3, March 2007 to Holtec Letter 5021081 A
i
HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL HI-2115090 Proposed Rev. 8B7 4-9 Table 4.1.3 PEAK CLADDING TEMPERATURE RESULTS FOR DIFFERENT HI-STORM UMAX DESIGN VERSIONS*
UMAX Versions Temperature oC (oF)
Standard 367 (693)**
Version B 367 (693)
Version B1 348 (659)
Version B2 246 (475)
Version B1 (with MPC-37 Type 1) 331 (628)***
- The PCT results tabulated herein are for normal storage condition of HI-STORM UMAX design versions under quiescent (no wind) conditions.
UMAX Standard and Version B designs are loaded with short MPC-37 under Heat Load Chart 1. UMAX Version B1 and Version B2 are loaded with MPC-37 and MPC-37 Type 1 containing 16x16A fuel under heat loads defined in Table 2.1.13, Table 2.1.14, Table 2.1.15 and Table 2.1.16.
- Standard version is adopted to perform all the licensing basis calculations for HI-STORM UMAX System in this safety report.
- The PCT result for Version B1 loaded with MPC-37 Type 1 is bounded by Version B1 with MPC-37. The normal long-term storage of Version B2 is evaluated only for MPC-37 and not with MPC-37 Type 1 as Version B2 loaded with MPC-37 also bounds Version B2 loaded with MPC-37 Type 1 as reported in Holtec Report HI-2230586 [4.4.11].
to Holtec Letter 5021081