ML23068A394
| ML23068A394 | |
| Person / Time | |
|---|---|
| Site: | Holtec |
| Issue date: | 06/29/2023 |
| From: | Storage and Transportation Licensing Branch |
| To: | Holtec |
| Shared Package | |
| ML23068A384 | List:
|
| References | |
| CAC 001028, EPID L-2020-RNW-0007 | |
| Download: ML23068A394 (1) | |
Text
RENEWED CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX B APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STORM 100 CASK SYSTEM AMENDMENT NO. 2
TABLE OF CONTENTS 1.0 DEFINITIONS.............................................................................................. 1-1 2.0 APPROVED CONTENTS.......................................................................... :.. 2-1 3.0 DESIGN FEATURES..................................................................................... 3-1 3.1 Site..................................................................................................... 3-1 3.2 Design Features Important for Criticality Control................................ 3-2 3.3 Codes and Standards............................................... ;......................... 3-2 3.4 Site Specific Parameters and Analyses............................................ 3-13 3.5 Cask Transfer Facility (CTF)............................................................. 3-17 3.6 Forced Helium Dehydration System................................................. 3-20 Certificate of Compliance No. 1014 Appendix B
\\
Renewed Amendment No. 2 3.8 Combustible Gas Monitoring During MPC Lid Welding...................3-24 3.7 Supplemental Cooling System........................................................3-22 Table 2.1-1 Fuel Assembly Limits...........................................................................2-7 Table 2.1-2 PWR Fuel Assembly Characteristics (Note 1)....................................2-46 Table 2.1-3 BWR Fuel Assembly Characteristics (Note 1)....................................2-50 Table 2.1-4 TABLE DELETED Table 2.1-7 TABLE DELETED Table 2.1-8 Non Fuel Hardware Cooling and Average Burnup............................2-61 Table 2.4-1 Maximum Allowable Decay Heat per Fuel Storage Locattion..........2-62 Table 2.4-2 Fuel Storage Regions and Maximum Heat per MPC.......................2-63 Table 2.4-3 PWR Fuel Assembly Cooling Time-Dependent Coefficients............2-65 Table 2.4-4 BWR Fuel Assembly Cooling Time-Dependent Coefficients............2-73 Table 3-1 LIST OF ASME CODE ALTERNATIVES FOR HI-STORM CASK SYSTEM..............................................................................3-4 Table 3-3 Load Combinations and Service Conditions Definitions for the CTF Structure.................................................................................3-19
Definitions 1.0 1.0 Definitions
--NOTE-The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term Definition CASK TRANSFER FACILITY (CTF)
DAMAGED FUEL ASSEMBLY
-DAMAGED FUEL CONTAINER (DFC)
The CASK TRANSFER FACILITY includes the following components and equipment: (1) a CaskTransferStructure used to stabilize the TRANSFER CASK and MPC during lifts involving spent fuel not bounded by the regulations of 10 CFR Part 50, and (2) Either a stationary lifting device or a mobile lifting device used in concert with the stationary structure to lift the OVERPACK, TRANSFER CASK, and MPC DAMAGED FUEL ASSEMBLIES are fuel assemblies with known or suspected cladding defects, as determined by a review of records, greater than pinhole leaks or hairline cracks, empty fuel rod locations that are not filled with dummy fuel rods, or those that cannot be handled by normal means. Fuel assemblies that cannot be handled by normal means due to fuel cladding damage are considered FUEL DEBRIS.
DFCs are specially designed enclosures for DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS which permit gaseous and liquid media to escape while minimizing dispersal of gross particulates.
DFCs authorized for use in the HI-STORM 100 System are as follows:
- 1. Holtec Dresden Unit 1/Humboldt Bay design
- 2. Transnuclear Dresden Unit 1 design
- 3. Holtec Generic BWR design
- 4. Holtec Generic PWR design FUEL DEBRIS FUEL DEBRIS is ruptured fuel rods, severed rods, loose fuel pellets or fuel assemblies with known or suspected defects which cannot be handled by normal means due to fuel cladding damage.
(continued)
Certificate of Compliance No. 1014 Appendix B 1-1 Renewed Amendment No. 2
1.0 Definitions (continued)
INTACT FUEL ASSEMBLY LOADING OPERATIONS MINIMUM ENRICHMENT MUL Tl-PURPOSE CANISTER (MPG)
NON-FUEL HARDWARE OVERPACK Certificate of Compliance No. 1014 Appendix B Definitions 1.0 INTACT FUEL ASSEMBLIES are fuel assemblies without known or suspected cladding defects greater than pinhole leaks or hairline cracks and which can be handled by normal means. Fuel assemblies without fuel rods in fuel rod locations shall not be classified as INTACT FUEL ASSEMBLIES unless dummy fuel rods are used to displace an amount of water greater than or equal to that displaced by the fuel rod(s).
LOADING OPERATIONS include all licensed activities on an OVERPACK or TRANSFER CASK while it is being loaded with fuel assemblies. LOADING OPERATIONS begin when the first fuel assembly is placed in the MPG and end when the OVERPACK or TRANSFER CASK is suspended from or secured on the transporter. LOADING OPERATIONS does not included MPG transfer between the TRANSFER CASK and the OVERPACK.
MINIMUM ENRICHMENT is the minimum assembly average enrichment. Natural uranium blankets are not considered in determining minimum enrichment.
MP Cs are the sealed spent nuclear fuel canisters which consist of a honeycombed fuel basket contained in a cylindrical canister shell which is welded to a baseplate, lid with welded port cover plates, and closure ring. The MPG provides the confinement boundary for the contained radioactive materials.
NON-FUEL HARDWARE is defined as Burnable Poison Rod Assemblies (BPRAs), Thimble Plug Devices {TPDs),
Control Rod Assemblies (CRAs), Axial Power Shaping Rods (APSRs), Wet Annular Burnable Absorbers (WABAs), Rod Cluster Control Assemblies (RCCAs),
Control Element Assemblies (CEAs), water displacement guide tube plugs, orifice rod assemblies, and vibration suppressor inserts.
OVERPACKs are the casks which receive and contain the sealed MPCs for interim storage on the ISFSI. They provide gamma and neutron shielding, and provide for ventilated air flow to promote heat transfer from the MPG to the environs. The OVERPACK does not include the TRANSFER CASK.
(continued) 1-2 Renewed Amendment No. 2
1.0 Definitions (continued}
PLANAR-AVERAGE INITIAL ENRICHMENT SPENT FUEL STORAGE CASKS (SFSCs)
TRANSFER CASK TRANSPORT OPERATIONS UNLOADING OPERATIONS ZR Certificate of Compliance No. 1014 Appendix B Definitions 1.0 PLANAR-AVERAGE INITIAL ENRICHMENT is the average of the distributed fuel rod initial enrichments within a given axial plane of the assembly lattice.
An SFSC is a container approved for the storage of spent fuel assemblies at the ISFSI. The HI-STORM 100 SFSC System consists of the OVERPACK and its integral MPG.
TRANSFER CASKs are containers designed to contain the MPG during and after loading of spent fuel assemblies
- and to transfer the MPG to or from the OVERPACK. The HI-STORM 100 System employs either the 125-Ton or the 100-Ton HI-TRAC TRANSFER CASK.
TRANSPORT OPERATIONS include all licensed activities performed on an OVERPACK or TRANSFER CASK loaded with one or more fuel assemblies when it is being moved to and from the ISFSI.
TRANSPORT OPERATIONS begin when. the OVERPACK or TRANSFER CASK is first suspended from or secured on the transporter and end when the OVERPACK or TRANSFER CASK is at its destination and no longer secured on or suspended from the transporter.
TRANSPORT OPERATIONS include transfer of the MPG between the OVERPACK and the TRANSFER CASK.
UNLOADING OPERATIONS include all licensed activities on an SFSC to be unloaded of the contained fuel assemblies. UNLOADING OPERATIONS begin when the OVERPACK or TRANSFER CASK is no longer suspended from or secured on the transporter and end when the last
. fuel assembly is removed from the SFSC. UNLOADING OPERATIONS does not include MPG transfer between the TRANSFER CASK and the OVERPACK.
ZR means any zirconium-based fuel cladding or fuel channel material authorized for use in a commercial nuclear power plant reactor.
1-3 Renewed Amendment No. 2
2.0 APPROVED CONTENTS 2.1 Fuel Specifications and Loading Conditions 2.1.1 Fuel To Be Stored In The HI-STORM 100 SFSC System Approved Contents 2.0 a.
INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, FUEL DEBRIS, and NON-FUEL HARDWARE meeting the limits specified in Table 2.1-1 and other referenced tables may be stored in the HI-STORM 100 SFSC System.
b.
For MPCs partially loaded with stainless steel clad fuel assemblies, all remaining fuel assemblies in the MPC shall meet the decay heat generation limit for the stainless steel clad fuel assemblies.
c.
For MPCs partially loaded with DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, all remaining ZR clad INTACT FUEL ASSEMBLIES in the MPC shall meet the decay heat generation limits for the DAMAGED FUEL ASSEMBLIES. This requirement applies only to uniform fuel loading.
d.
For MPCs partially loaded with array/class 6x6A, 6x6B, 6x6C, 7x7 A, 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, 7x7 A and 8x8A fuel assemblies.
e.
All BWR fuel assemblies may be stored with or without ZR channels with the exception of array/class 1 0x1 OD and 1 0x1 OE 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.
Certificate of Compliance No. 1014 Appendix B 2-1 (continued}
Renewed Amendment No. 2
2.0 Approved Contents 2.1 Fuel Specifications and Loading Conditions (cont'd) 2.1.3 Regionalized Fuel Loading Approved Contents 2.0 Users may choose to store fuel using regionalized loading in lieu of uniform loading to allow higher heat emitting fuel assemblies to be stored than would otherwise be able to be stored using uniform loading. Regionalized loading is limited to-those fuel assemblies with ZR cladding. Figures 2.1-1 through 2.1-4 define the regions for the MPC-24, MPC-24E, MPC-24EF, MPC-32, MPC-32F, MPC-68, and MPC-68FF models, respectively1* Fuel assembly burnup, decay heat, and cooling time limits for regionalized loading are specified in Section 2.4.2. Fuel assemblies used in regionalized loading shall meet all other applicable limits specified in Tables 2.1-1 through 2.1-3.
2.2 Violations If any Fuel Specifications or Loading Conditions of 2.1 are violated, the following actions shall be completed:
2.2.1 The affected fuel assemblies shall be placed in a safe condition.
2.2.2 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the NRC Operations Center.
2.2.3 Within 30 days, submit a special report which describes the cause of the violation, and actions taken to restore compliance and prevent recurrence.
1 These figures are only intended to distinguish the fuel loading regions. Other details of the basket design are illustrative and may not reflect the actual basket design details. The design drawings should be consulted for basket design details.
Certificate of Compliance No. 1014 Appendix B 2-2 Renewed Amendment No. 2
APPROVED CONTENTS
2.0 LEGEND
REGION 1:
REGION 2:
270 FIGURE 2.1-1 FUEL LOADING REGIONS - MPC-24 CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX B 2-3 Renewed Amendment No. 2
LEGEND:
REGION 1:
APPROVED CONTENTS 2.0 REGION 2:
91.
270 FIGURE 2.1-2 FUEL LOADING REGIONS -
MPC-24E/24EF CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX B 2-4
&ISAR DOWCUNTSIHI-STORN CoC/AXEND,(NT REQUESTS/LAR 1014-2/FIG 212 Renewed Amendment No. 2
LEGEND:
REGION 1:
REGION 2:
180' APPROVED CONTENTS 2.0 FIGURE 2.1-3 FUEL LOADING REGIONS -
MPC-32/32F CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX B 2-5 W/SAR DXUHNTS/I-STORMH CIMPEN[ENT REQUESTS/AR 1014-2/FIG2 Renewed Amendment No. 2
APPROVED CONTENTS
2.0 LEGEND
REGION 1:
REGION 2:
90° 00 OF DRAIN PIPE 270 FIGURE 2.1-4 FUEL LOADING REGIONS - MPC-68/68FF CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX B 2-6 W/SAR DOCUMENTS/HI-STORM CoC/AK-NDlENT RE[UESTS/LAR 1014-2/FIG 214 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 1 of 39)
Fuel Assembly Limits
)
I. MPC MODEL: MPC-24 A. Allowable Contents
- 1. Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):
- a. Cladding Type:
- b. Initial Enrichment:
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 14x14D,14x14E, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class.
As specified in Table 2.1-2 for the applicable fuel assembly array/class.
Cooling time Q 8 years and an average burnup R 40,000 MWD/MTU.
Cooling time and average burnup as specified in Section 2.4.
As specified in Table 2.1-8.
2-7 Renewed Amendment No. 2
Table 2.1-1 (page 2 of 39)
Fuel Assembly Limits Approved Contents 2.0 I. MPC MODEL: MPC-24 (continued)
A. Allowable Contents (continued) d.
Decay Heat Per Fuel Storage Location:
i.
Array/Classes 14x14D, 14x14E, and 15x15G ii All Other Array/Classes e.
Fuel Assembly Length:
f.
Fuel Assembly Width:
g.
Fuel Assembly Weight:
s 710 Watts As specified in Section 2.4.
s 176.8 inches (nominal design) s 8.54 inches (nominal design) s 1,680 lbs (including NON-FUEL
. HARDWARE)
- 8. Quantity per MPC: Up to 24 fuel assemblies.
C. Deleted.
D. Neutron sources and DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS are not authorized for loading into the MPC-24.
Note 1:
Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, or APSRs may only be loaded in fuel storage locations 9, 10, 15, and/or 16. These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.
Certificate of Compliance No. 1014 AppendixB 2-8 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 3 of 39)
II. MPG MODEL: MPC-68 A. Allowable Contents
- 1.
Uranium oxide, BWR INTACT FUEL ASSEMBLIES listed in Table 2.1-3, with or without channels, and meeting the following specifications:
- a. Cladding Type:
- b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
- c. Initial Maximum Rod Enrichment:
- d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i.
Array/Classes 6x6A, 6x6C, 7x7 A, and 8x8A:
ii.
Array/Class 8x8F iii. Array/Classes 1 0x1 OD and 10x10E iv. All Other Array/Classes Certificate of Compliance No. 1014 Appendix B ZR or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array/class.
As specified in Table 2.1-3 for the applicable fuel assembly array/class.
As specified in Table 2.1-3 for the applicable fuel assembly array/class.
Cooling time Q 18 years and an average burnup R 30,000 MWD/MTU Cooling time Q 1 O years and an average burnup R 27,500 MWD/MTU.
Cooling time Q 10 years and an average burnup R 22,500 MWD/MTU.
As specified in Section 2.4.
2-9 Renewed Amendment No. 2 Fuel Assembly Limits
Approved Contents 2.0 Table 2.1-1 (page 4 of 39}
Fuel Assembly Limits II. MPG MODEL: MPC-68 (continued)
A. Allowable Contents (continued)
- e. Decay Heat Per Assembly:
i.
Array/Classes 6x6A, 6x6C, 7x7 A, and 8x8A ii.
Array/Class 8x8F iii. Array/Classes 1 0x1 OD and 10x10E iv. All Other Array/Classes f.
Fuel Assembly Length:
g.
Fuel Assembly Width:
- h. Fuel Assembly Weight:
Certificate of Compliance No. 1014 Appendix B s 115 Watts s 183.5 Watts.
s 95 Watts As specified in Section 2.4.
s 176.5 inches (nominal design) s 5.85 inches (nominal design) s 700 lbs, including channels 2-10 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 5 of 39)
Fuel Assembly Limits
- 11. MPC MODEL: MPC-68 (continued)
A. Allowable Contents (continued)
- 2. Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES, with or without channels, placed in DAMAGED FUEL CONTAINERS.
Uranium oxide BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 and meet the following specifications:
- a. Cladding Type:
- b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
i.
Array/Classes 6x6A, 6x6C, 7x7 A, and 8x8A ii.
All Other Array/Classes specified in Table 2.1-3
- c. Initial Maximum Rod Enrichment:
- d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 6x6A, 6x6C, 7x7 A,and 8x8A ii. Array/Class 8x8F iii. Array/Classes 1 0x1 OD and 10x10E iv. All Other Array Classes Certificate of Compliance No. 1014 Appendix B ZR or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array/class.
As specified in Table 2.1-3 for the applicable fuel assembly array/class.
4.6 wt% 235U As specified in Table 2.1-3 for the applicable fuel assembly array/class.
Cooling timeQ 18 years and an average burnup s 30,000 MWD/MTU.
Cooling timeQ 10 years and an average burnup s 27,500 MWD/MTU.
Cooling time Q 1 0 years and an average burnup s 22,500 MWD/MTU.
As specified in Section 2.4.
2-11 Renewed Amendment No. 2
Table 2.1-1 {page 6 of 39)
Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)
A. Allowable Contents (continued)
- e. Decay Heat Per Assembly:
i.
Array/Class 6x6A, 6x6C, 7x7A,
!:. 115 Watts and 8x8A ii.
Array/Class 8x8F
!:. 183.5 Watts iii.
Array/Classes 1 0x1 OD and 10x10E
!:. 95 Watts Approved Contents 2.0 iv.
All Other Array/Classes
- f. Fuel Assembly Length:
As specified in Section 2.4.
i.
Array/Class 6x6A, 6x6C, 7x7A,
!:. 135.0 inches (nominal design) or 8x8A ii.
All Other Array/Classes
!:. 176.5 inches (nominal design)
- g. Fuel Assembly Width:
i.
Array/Class 6x6A, 6x6C, 7x7A,
!:. 4.70 inches (nominal design) or 8x8A ii.
All Other Array/Classes
!:. 5.85 inches (nominal design)
- h. Fuel Assembly Weight:
i.
Array/Class 6x6A, 6x6C, 7x7A,
!:. 550 lbs, including channels and DFC or 8x8A ii.
All Other Array/Classes
!:. 700 lbs, including channels and DFC Certificate of Compliance No. 1014 Appendix B 2-12 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 7 of 39)
II. MPC MODEL: MPC-68 (continued)
A. Allowable Contents (continued) 3.
Mixed oxide (MOX), BWR INTACT FUEL ASSEMBLIES, with or without channels. MOX BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
- a. Cladding Type:
ZR
- b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for fuel INITIAL ENRICHMENT:
assembly array/class 6x6B.
- c. Initial Maximum Rod Enrichment:
d.
Post-irradiation Cooling Time and Average Burnup Per Assembly:
- e. Decay Heat Per Assembly:
- f. Fuel Assembly Length:
- g. Fuel Assembly Width:
- h. Fuel Assembly Weight:
Certificate of Compliance No. 1014 Appendix B As specified in Table 2.1-3 for fuel assembly array/class 6x6B.
Cooling time U 18 years and an average burnup s 30,000 MWD/MTIHM.
s 115 Watts s 135.0 inches (nominal design) s 4.70 inches (nominal design) s 400 lbs, including channels 2-13 Renewed Amendment No. 2 Fuel Assembly Limits
Table 2.1-1 (page 8 of 39)
II. MPC MODEL: MPC-68 {continued)
A. Allowable Contents {continued)
Approved Contents 2.0 4.
Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without channels, placed in DAMAGED FUEL CONTAINERS. MOX BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
- a. Cladding Type:
ZR
- b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for array/class INITIAL ENRICHMENT:
6x6B.
- c. Initial Maximum Rod As specified in Table 2.1-3 for array/class Enrichment:
6x6B.
d.
Post-irradiation Cooling Time and Average Burnup Per Assembly:
- e. Decay Heat Per Assembly:
- f. Fuel Assembly Length:
- g. Fuel Assembly Width:
- h. Fuel Assembly Weight:
Certificate of Compliance No. 1014 Appendix B Cooling time M 18 years and an average burnup.s 30,000 MWD/MTIHM.
.s 115 Watts
.s 135.0 inches (nominal design)
.s 4.70 inches {nominal design)
.s 550 lbs, including channels and DFC 2-14 Renewed Amendment No. 2 Fuel Assembly Limits
Approved Contents 2.0 Table 2.1-1 (page 9 of 39)
Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)
A. Allowable Contents (continued) 5.
Thoria rods (ThO2 and UO2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:
- a. Cladding Type:
- b. Composition:
- c. Number of Rods Per Thoria Rod Canister:
- d. Decay Heat Per Thoria Rod Canister:
- e. Post-irradiation Fuel Cooling Time and Average Burnup Per Thoria Rod Canister:
- f. Initial Heavy Metal Weight:
- g. Fuel Cladding O.D.:
- h. Fuel Cladding 1.D.:
- i. Fuel Pellet O.D.:
- j. Active Fuel Length:
- k. Canister Weight:
ZR 98.2 wt.% Th 02, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U.
.$.115 Watts A fuel post-irradiation cooling timeH 18 years and an average burnup.$. 16,000 MWD/MTIHM.
.$. 27 kg/canister H 0.412 inches
.$. 0.362 inches
.$. 0.358 inches
.$. 111 inches
.$. 550 lbs, including fuel Certificate of Compliance No. 1014 Appendix B 2-15 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 10 of 39)
Fuel Assembly Limits
- 11. MPC MODEL: MPC-68 (continued)
B.
Quantity per MPC:
- 1. Up to one (1) Dresden Unit I Thoria Rod Canister;
- 2. Up to 68 array/class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS;
- 3. Up to sixteen (16) other BWR DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS in fuel storage locations 1,2,3,8,9,16,25,34,35,44,53,60,61,66, 67, and/or 68; and/or
- 4. Any number of BWR INTACT FUEL ASSEMBLIES up to a total of 68.
C. Array/Class 10x1OD and 1Ox1iE fuel assemblies in stainless steel channels must be stored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 - 50.
D. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC-68. The Antimony-Beryllium source material shall be in a water rod location.
E. FUEL DEBRIS is not authorized for loading in the MPC-68.
Certificate of Compliance No. 1014 Appendix B 2-16 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 11 of 39)
Fuel Assembly Limits Ill. MPC MODEL: MPC-68F A. Allowable Contents 1.
Uranium oxide, BWR INTACT FUEL ASSEMBLIES, with or without ZR channels. Uranium oxide BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array class 6x6A, 6x6C, 7x7 A or BxBA, and meet the following specifications:
- a. Cladding Type:
b Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
- c. Initial Maximum Rod Enrichment:
- d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- e. Decay Heat Per Assembly
- f. Fuel Assembly Length:
- g. Fuel Assembly Width:
- h. Fuel Assembly Weight:
Certificate of Compliance No. 1014 Appendix B ZR As specified in Table 2.1-3 for the applicable fuel assembly array/class.
As specified in Table 2.1-3 for the applicable fuel assembly array/class.
Cooling time U 18 years and an average burnup s 30,000 MWD/MTU..
s 115 Watts
,:s 135.0 inches (nominal design) s 4.70 inches (nominal design) s 400 lbs, including channels 2-17 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 12 of 39)
Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued) 2.
Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6A, 6x6C, 7x7 A, or 8x8A, and meet the following specifications:
- a. Cladding Type:
- b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
- c. Initial Maximum Rod Enrichment:
- d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- e. Decay Heat Per Assembly:
- f. Fuel Assembly Length:
- g. Fuel Assembly Width:
- h. Fuel Assembly Weight:
Certificate of Compliance No. 1014 Appendix B ZR As specified in Table 2.1-3 for the applicable fuel assembly array/class.
As specified in Table 2.1-3 for the applicable fuel assembly array/class.
Cooling timeN 18 years and an average
. burnup 5 30,000 MWD/MTU.
5115 Watts 5 135.0 inches (nominal design) 5 4.70 inches (nominal design) 5 550 lbs, including channels and DFC 2-18 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 13 of 39)
Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued) 3.
Uranium oxide, BWR FUEL DEBRIS, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the uranium oxide BWR FUEL DEBRIS shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6A, 6x6C, 7x7 A, or 8x8A, and meet the following specifications:
- a. Cladding Type:
- b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
c Initial Maximum Rod Enrichment:
- d. Post-irradiation Cooling Time and Average Burnup Per Assembly
- e. Decay Heat Per Assembly
- f. Original Fuel Assembly Length
- g. Original Fuel Assembly Width
- h. Fuel Debris Weight Certificate of Compliance No. 1014 Appendix B ZR As specified in Table 2.1-3 for the applicable original fuel assembly array/class.
As specified in Table 2.1-3 for the applicable original fuel assembly array/class.
Cooling time > 18 years and an average burnup.s 30,000 MWD/MTU for the original fuel assembly.
.s 115 Watts
.s 135.0 inches (nominal design)
.s 4.70 inches (nominal design)
.s 550 lbs, including channels and DFC 2-19 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 14 of 39)
Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
- 4. Mixed oxide (MOX), BWR INTACT FUEL ASSEMBLIES, with or without ZR channels. MOX BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
- a. Cladding Type:
b.
Maximum PLANAR AVERAGE INITIAL ENRICHMENT:
c.
Initial Maximum Rod Enrichment:
d.
Post-irradiation Cooling Time and Average Burnup Per Assembly:
- e. Decay Heat Per Assembly
- f. Fuel Assembly Length:
- g. Fuel Assembly Width:
- h. Fuel Assembly Weight:
Certificate of Compliance No. 1014 Appendix B ZR As specified in Table 2.1-3 for fuel ass,embly array/class 6x6B.
As specified in Table 2.1-3 for fuel assembly array/class 6x6B.
Cooling time > 18 years and an average burnup _s 30,000 MWD/MTIHM.
_s 115 Watts s 135.0 inches (nominal design)
_s 4.70 inches (nominal design)
_s 400 lbs, including channels 2-20 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 15 of 39)
Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
- 5. Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. MOX BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
- a. Cladding Type:
b.
Maximum PLANAR AVERAGE INITIAL ENRICHMENT:
c.
Initial Maximum Rod Enrichment:
- d. Post-irradiation Cooling Time_
and Average Burnup Per Assembly:
- e. Decay Heat Per Assembly
- f. Fuel Assembly Length:
- g. Fuel Assembly Width:
- h. Fuel Assembly Weight:
Certificate of Compliance No. 1014 Appendix B ZR As specified in Table 2.1-3 for fuel assembly array/class 6x6B.
As specified in Table 2.1-3 for fuel assembly array/class 6x6B.
Cooling time R 18 years and an average burnup S 30,000 MWD/MTIHM.
S115 Watts
=:: 135.0 inches (nominal design)
S 4.70 inches (nominal design)
S 550 lbs, including channels and DFC 2-21 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 16 of 39)
Fuel Assembly Limits Ill. MPG MODEL: MPC-68F (continued)
A. Allowable Contents (continued) 6.
Mixed Oxide (MOX}, BWR FUEL DEBRIS, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the MOX BWR FUEL DEBRIS shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
- a. Cladding Type:
- b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
- c. Initial Maximum Rod Enrichment:
- d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- e. Decay Heat Per Assembly
- f. Original Fuel Assembly Length:
- g. Original Fuel Assembly Width:
- h. Fuel Debris Weight:
Certificate of Compliance No. 1014 Appendix B ZR As specified in Table 2.1-3 for original fuel assembly array/class 6x6B.
As specified in Table 2.1-3 for original fuel assembly array/class 6x6B.
Cooling time > 18 years and an average burnup s 30,000 MWD/MTIHM for the original fuel assembly.
s 115 Watts s 135.0 inches (nominal design) s 4.70 inches (nominal design) s 550 lbs, including channels and DFC 2-22 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 17 of 39)
Fuel Assembly Limits Ill. MPG MODEL: MPC-68F (continued)
A. Allowable Contents (continued) 7.
Thoria rods (ThO2 and UO2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:
- a. Cladding Type:
- b. Composition:
- c. Number of Rods Per Thoria Rod Canister:
- d. Decay Heat Per Thoria Rod Canister:
- e. Post-irradiation Fuel Cooling Time and Average Burnup Per Thoria Rod Canister:
- f. Initial Heavy Metal Weight:
- g. Fuel Cladding O.D.:
- h. Fuel Cladding I.D.:
- i. Fuel Pellet O.D.:
- j. Active Fuel Length:
- k. Canister Weight:
ZR 98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U.
!:: 115 Watts A fuel post-irradiation cooling time E 18 years and an average burnup !:: 16,000 MWD/MTIHM.
!:: 27 kg/canister E 0.412 inches
!:: 0.362 inches
!:: 0.358 inches
!:: 111 inches
!:: 550 lbs, including fuel Certificate of Compliance No. 1014 Appendix B 2-23 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 18 of 39)
Fuel Assembly Limits I
Ill. MPC MODEL: MPC-68F (continued)
B. Quantity per MPC (up to a total of 68 assemblies):
(All fuel assemblies must be array/class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A):
Up to four (4) DFCs containing uranium oxide BWR FUEL DEBRIS or MOX BWR FUEL DEBRIS. The remaining MPC-68F fuel storage locations may be filled with fuel assemblies of the following type, as applicable:
- 5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.
C. Fuel assemblies with stainless steel channels are not authorized for loading in the MPC-68F.
D. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC-68F. The Antimony-Beryllium source material shall be in a water rod location.
Certificate of Compliance No. 1014 Appendix B 2-24 Renewed Amendment No. 2
IV. MPC MODEL: MPC-24E A. Allowable Contents Table 2.1-1 (page 19 of 39)
Fuel Assembly Limits Approved Contents 2.0
- 1. Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1 ):
- a. Cladding Type:
- b. Initial Enrichment:
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class As specified in Table 2.1-2 for the applicable fuel assembly array/class.
- i. Array/Classes 14x14D, 14x14E, Cooling timeQ 8 years and an average and 15x15G burnup,=:; 40,000 MWD/MTU.
ii. All Other Array/Classes As specified in Section 2.4.
iii. NON-FUEL HARDWARE As specified in Table 2.1-8.
Certificate of Compliance No'. 1014 Appendix B 2-25 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 20 of 39)
Fuel Assembly Limits IV. MPC MODEL: MPC-24E (continued)
A. Allowable Contents (continued)
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All other Array/Classes
- e. Fuel Assembly Length:
f.
Fuel Assembly Width:
- g. Fuel Assembly Weight:
Certificate of Compliance No. 1014 Appendix B
? 710 Watts.
As specified in Section 2.4.
? 176.8 inches (nominal design)
? 8.54 inches (nominal design)
? 1,680 lbs (including NON-FUEL HARDWARE) 2-26 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 21 of 39)
Fuel Assembly Limits IV. MPC MODEL: MPC-24E (continued)
A. Allowable Contents {continued) 2.
Uranium oxide, PWR DAMAGED FUEL ASSEMBLIES, with or without NON FUEL HARDWARE, placed in DAMAGED FUEL CONTAINERS. Uranium oxide PWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-2 and meet the following specifications (Note 1 ):
- a. Cladding Type:
- b. Initial Enrichment:
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i.
Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class As specified in Table 2.1-2 for the applicable fuel assembly array/class.
Cooling time 8 years and an average burnup 40,000 MWD/MTU.
As specified in Section 2.4.
As specified in Table 2.1-8.
2-27 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 22 of 39)
Fuel Assembly Limits IV. MPG MODEL: MPC-24E (continued)
A. Allowable Contents (continued)
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes
- e. Fuel Assembly Length f.
Fuel Assembly Width g.
Fuel Assembly Weight s 710 Watts.
As specified in Section 2.4.
s 176.8 inches (nominal design) s 8.54 inches (nominal design) s 1,680 lbs (including NON-FUEL HARDWARE and DFC) 8.
Quantity per MPC: Up to four (4) DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 3, 6, 19 and/or 22. The remaining MPC-24E fuel storage locations may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.
C.
Neutron sources and FUEL DEBRIS are not authorized for loading in the MPC-24E.
Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration supressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, or APSRs may only be loaded in fuel storage locations 9, 1 o, 15, and/or 16.
These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.
Certificate of Compliance No. 1014 Appendix B 2-28 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 23 of 39)
Fuel Assembly Limits V. MPC MODEL: MPC-32 A. Allowable Contents
- 1. Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):
- a. Cladding Type:
- b. Initial Enrichment:
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly
- i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class As specified in Table 2.1-2 for the applicable fuel assembly array/class.
Cooling time K 9 years and an average burnup.s 30,000 MWD/MTU or cooling time K 20 years and an average burnup.s 40,000 MWD/MTU.
As specified in Section 2.4.
As specified in Table 2.1-8.
2-29 Renewed Amendment No. 2
Table 2.1-1 (page 24 of 39)
Fuel Assembly Limits V. MPC MODEL: MPC-32 (continued)
A. Allowable Contents (continued)
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D,
!S 500 Watts 14x14E, and 15x15G Approved Contents 2.0 ii. All Other Array/Classes As specified in Section 2.4.
- e. Fuel Assembly Length
!S 176.8 inches (nominal design) f.
Fuel Assembly Width
!S 8.54 inches (nominal design) g.. Fuel Assembly Weight
!S 1,680 lbs (including NON-FUEL HARDWARE)
Certificate of Compliance No. 1014 Appendix B 2-30 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 25 of 39)
Fuel Assembly Limits V. MPC MODEL: MPC-32 (continued)
A. Allowable Contents (continued) 2.
Uranium oxide, PWR DAMAGED FUEL ASSEMBLIES, with or without NON FUEL HARDWARE, placed in DAMAGED FUEL CONTAINERS. Uranium oxide PWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-2 and meet the following specifications (Note 1 ):
- a. Cladding Type:
- b. Initial Enrichment:
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
i.
Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class As specified in Table 2.1-2 for the applicable fuel assembly array/class.
Cooling time 2! 9 years and an average burnup Y 30,000 MWD/MTU or cooling time 2! 20 years and an average burnup Y 40,000 MWD/MTU.
As specified in Section 2.4.
As specified in Table 2.1-8.
2-31 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 26 of 39)
Fuel Assembly Limits V. MPC MODEL: MPC-32 (continued)
A. Allowable Contents (continued)
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes e.
Fuel Assembly Length f.
Fuel Assembly Width
- g.
- Fuel Assembly Weight s 500 Watts.
As specified in Section 2.4.
s 176.8 inches (nominal design) s 8.54 inches (nominal design) s 1,680 lbs (including NON-FUEL HARDWARE and DFC)
B.
Quantity per MPC: Upto eight(8) DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 1, 4, 5, 10, 23, 28, 29, and/or 32. The remaining MPC-32 fuel storage locations rriay be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.
C.
Neutron sources and FUEL DEBRIS are not authorized for loading in the MPC-32.
Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, or APSRs may only be loaded in fuel storage locations 13, 14, 19, and/or 20.
These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.
Certificate of Compliance No. 1014 Appendix B 2-32 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 27 of 39)
Fuel Assembly Limits VI. MPC MODEL: MPC-68FF A. Allowable Contents
- 1. Uranium oxide or MOX BWR INTACT FUEL ASSEMBLIES listed in Table 2.1-3, with or without channels and meeting the following specifications:
- a. Cladding Type:
b.
Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
- c. Initial Maximum Rod Enrichment d.
Post-irradiation Cooling Time and Average Burnup Per Assembly
- i. Array/Classes 6x6A, 6x6B, 6x6C, 7x7 A, and 8x8A ii. Array/Class BxBF iii. Array/Classes 1 0x1 OD and 10x10E iv. All Other Array/Classes Certificate of Compliance No. 1014 Appendix B ZR or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array/class As specified in Table 2.1-3 for the applicable fuel assembly array/class.
As specified in Table 2.1-3 for the applicable fuel assembly array/class.
Cooling time U 18 years and an average burnup.s 30,000 MWD/MTU (or MTU/MTIHM).
Cooling time U 1 0 years and an average burnup.s 27,500 MWD/MTU.
Cooling time U 10 years and an average burnup.s 22,500 MWD/MTU.
As specified in Section 2.4.
2-33 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 28 of 39)
Fuel Assembly Limits VI. MPC MODEL: MPC-68FF (continued)
A. Allowable Contents (continued)
- e. Decay Heat Per Assembly
- i. Array/Classes 6x6A, 6X6b, 6x6C, 7x7 A, and 8x8A ii. Array/Class 8x8F iii. Array/Classes 1 0x1 OD and 10x10E iv. All Other Array/Classes
- f. Fuel Assembly Length
- i. Array/Class 6x6A, 6x6B, 6x6C,7x7A,or 8x8A ii. All Other Array/Classes
- g. Fuel Assembly Width
- i. Array/Class 6x6A, 6x6B, 6x6C, 7x7 A, or 8x8A ii. All Other Array/Classes
- h. Fuel Assembly Weight
- i. Array/Class 6x6A, 6x6B, 6x6C, 7x7 A, or 8x8A ii. All Other Array/Classes
- s. 115 Watts
.$. 183.5 Watts
- s. 95 Watts As specified in Section 2.4.
- s. 135.0 inches (nominal design)
- s. 176.5 inches (nominal design)
.$. 4.70 inches (nominal design)
- s. 5.85 inches (nominal design)
- s. 550 lbs, including channels
- s. 700 lbs, including channels Certificate of Compliance No. 1014 Appendix B 2-34 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 29 of 39)
Fuel Assembly Limits VI. MPC MODEL: MPC-68FF (continued)
A. Allowable Contents (continued) 2.
Uranium oxide or MOX BWR DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, with or without channels, placed in DAMAGED FUEL CONTAINERS. Uranium oxide and MOX BWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2.1-3, and meet the following specifications:
- a. Cladding Type:
- b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
- i. Array/Classes 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A.
ii. All Other Array Classes c.
Initial Maximum Rod Enrichment
- d. Post-irradiation Cooling Time ZR or Stainless Steel (SS) in accordance with Table 2.1-3 for the applicable fuel assembly array/class.
As specified in Table 2.1-3 for the applicable fuel assembly array/class.
!:. 4.o wt.% 235U.
As specified in Table 2.1-3 for the applicable fuel assembly array/class.
and Average Burnup Per Assembly:
i.
Array/Class 6x6A, 6x6B, Cooling timeT 18 years and an average 6x6C, 7x7A, or 8x8A burnup !:. 30,000 MWD/MTU (or MWD/MTIHM).
ii.
Array/Class 8x8F Cooling time2 1 0 years and an average burnup.$. 27,500 MWD/MTU.
iii.
Array/Class 1 0x1 OD and Cooling time T 10 years and an average 1 0x1 OE burnup.$. 22,500 MWD/MTU.
iv.
All Other Array/Classes As specified in Section 2.4.
Certificate of Compliance No. 1014 Appendix B 2-35 Renewed Amendment No. 2
Table 2.1-1 (page 30 of 39)
Fuel Assembly Limits Approved Contents 2.0 VI. MPG MODEL: MPC-68FF (continued)
A. Allowable Contents (continued)
- e. Decay Heat Per Assembly
- f.
i.
Array/Class 6x6A, 6x6B, 6x6C,
.s 115 Watts 7x7 A, or 8x8A ii.
Array/Class 8x8F
.s 183.5 Watts iii.
Array/Classes 1 0x1 OD and
.s 95 Watts 10x10E iv.
All Other Array/Classes As specified in Section 2.4.
Fuel Assembly Length i.
Array/Class 6x6A, 6x68, 6x6C,.s 135.0 inches (nominal qesign) 7x7A, or 8x8A ii.
All Other Array/Classes
.s 176.5 inches (nominal design)
- g. Fuel Assembly Width i.
Array/Class 6x6A, 6x6B, 6x6C,
.s 4.70 inches (nominal design) 7x7 A, or 8x8A ii.
All Other Array/Classes
.s 5.85 inches (nominal design)
- h. Fuel Assembly Weight i.
Array/Class 6x6A, 6x68, 6x6C,
.s 550 lbs, including channels and DFC 7x7 A, or 8x8A ii.
All Other Array/Classes
.s 700 lbs, including channels and DFC Certificate of Compliance No. 1014 Appendix B 2-36 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 31 of 39)
Fuel Assembly limits I
VI. MPC MODEL: MPC-68FF (continued)
B. Quantity per MPC (up to a total of 68 assemblies)
- 1. For fuel assembly array/classes 6x6A, 6X6B, 6x6C, 7x7A, or 8x8A, up to 68 BWR INTACT FUEL ASSEMBLIES and/or DAMAGED FUEL ASSEMBLIES. Up to eight (8) DFCs containing FUEL DEBRIS from these array/classes may be stored.
- 2.
For all other array/classes, up to sixteen (16) DFCs containing BWR DAMAGED FUEL ASSEMBLIES and/or up to eight (8) DFCs containing FUEL DEBRIS. DFCs shall be located only in fuel storage locations 1, 2, 3, 8, 9, 16, 25, 34, 35, 44, 53, 60, 61, 66, 67, and/or 68. The remaining MPC-68FF fuel storage locations may be filled with fuel assemblies of the following type:
- i.
Uranium Oxide BWR INTACT FUEL ASSEMBLIES; or ii.
MOX BWR INTACT FUEL ASSEMBLIES.
C. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC-68FF. The Antimony-Beryllium source material shall be in a water rod location.
D. Array/Class 1 Ox1 OD and 1 Ox1 OE fuel assemblies in stainless steel channels must be stored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 - 50.
Certificate of Compliance No. 1014 Appendix B 2-37 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 32 of 39)
Fuel Assembly Limits VII. MPG MODEL: MPC-24EF A. Allowable Contents
- 1. Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1 ):
- a. Cladding Type:
- b. Initial Enrichment:
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class As specified in Table 2.1-2 for the applicable fuel assembly array/class.
i.
Array/Classes 14x14D, 14x14E, Cooling time 2!. 8 years and an average and 15x15G burnup _::; 40,000 MWD/MTU.
ii.
All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B As specified in Section 2.4.
As sp*ecified in Table 2.1-8.
2-38 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 33 of 39)
Fuel Assembly Limits VII. MPG MODEL: MPC-24EF (continued)
A. Allowable Contents (continued)
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All other Array/Classes e.
Fuel Assembly Length:
f.
Fuel Assembly Width:
- g. Fuel Assembly Weight:
Certificate of Compliance No. 1014 Appendix B
!:. 710 Watts.
As specified in Section 2.4.
!:. 176.8 inches (nominal design)
!:. 8.54 inches (nominal design)
!:. 1,680 lbs (including NON-FUEL HARDWARE) 2-39 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 34 of 39)
Fuel Assembly Limits
-VII. MPG MODEL: MPC-24EF (continued)
A. Allowable Contents (continued) 2.
Uranium oxide, PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS, with or without NON-FUEL HARDWARE, placed in DAMAGED FUEL CONTAINERS. Uranium oxide PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2.1-2 and meet the following specifications (Note 1):
- a. Cladding Type:
- b. Initial Enrichment:
c.
Post-irradiation Cooling Time and Average Burnup Per Assembly:
i.
Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class As specified in Table 2.1-2 for the applicable fuel assembly array/class.
Cooling time S 8 years and an average burnup T 40,000 MWD/MTU.
As specified in Section 2.4.
As specified in Table 2.1-8.
Certificate of Compliance No. 1014 Appendix B 2-40 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 35 of 39)
Fuel Assembly Limits VII. MPC MODEL: MPC-24EF (continued)
A. Allowable Contents (continued)
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes
- e. Fuel Assembly Length f.
Fuel Assembly Width
- g. Fuel Assembly Weight L 71 O Watts.
As specified in Section 2.4.
L 176.8 inches (nominal design)
L 8.54 inches (nominal design)
L 1,680 lbs (including NON-FUEL HARDWARE and DFC) 8.
Quantity per MPC: Up to four (4) DAMAGED FUEL ASSEMBLIES and/or FUEL DEBRIS in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 3, 6, 19 and/or 22. The remaining MPC-24EF fuel storage locations may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.
C.
Neutron sources are not permitted for loading in the MPC-24EF.
Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, or APSRs may only be loaded in fuel storage locations 9, 1 O, 15, and/or 16.
These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.
Certificate of Compliance No. 1014 Appendix B 2-41 Renewed Amendment No. 2
Approved Contents
- 2. 0 Table 2.1 -1 (page 36 of
- 39) Fuel Assembly Limits VIII.
MPC MODEL: MPC-32F A. Allowable Contents
- 1.
Uranium ox ide, PWR INTACT FUEL ASSEMBLIES listed in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):
- a. Cladding Type:
- b. Initial Enrichment:
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i.
Array/Classes 14x14D, 14x14E, and15x15G ii. All Other Array/Classes iii. NON-FUEL HARDWARE Certificate of Compliance No. 1014 Appendix B ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class As specified in Table 2.1-2 for the applicable fuel assembly array/class.
Cooling time I 9 years and an average burnup J 3 0,000 MWD/MTU or cooling time I 20 years and an average burnup J 40,000 MWD/MTU.
As specified in Section 2. 4.
- As specified in Table 2.1-8.
2-42 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 37 of 39}
Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (cont'd)
A.
Al_lowable Contents (cont'd)
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D, 14x14E, and 15x15G ii. All Other Array/Classes e.
Fuel Assembly Length f.
Fuel Assembly Width g.
Fuel Assembly Weight Certificate of Compliance No. 1014 Appendix B
.::: 500 Watts.
As specified in Section 2.4.
.::: 176.8 inches (nominal design)
.::; 8.54 inches (nominal design)
.::: 1,680 lbs (including NON-FUEL HARDWARE) 2-43 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 {page 38 of 39)
Fuel Assembly Limits VIII. MPG MODEL: MPC-32F {cont'd)
A.
Allowable Contents {cont'd)
- 2. Uranium oxide, PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS, with or without NON-FUEL HARDWARE, placed in DAMAGED FUEL CONTAINERS. Uranium oxide PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2.1-2 and meet the following specifications {Note 1 ):
- a. Cladding Type:
- b. Initial Enrichment:
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
ZR or Stainless Steel {SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class As specified in Table 2.1-2 for the applicable fuel assembly array/class.
i.
Array/Classes 14x14D, Cooling timeC 9 years and an average 14x14E, and 15x15G burnup.s 30,000 MWD/MTU or cooling timeC 20 years and an average burnup.s 40,000 MWD/MTU.
ii. All Other Array/Classes As specified in Section 2.4.
iii. NON-FUEL HARDWARE As specified in Table 2.1-8.
Certificate of Compliance No. 1014 Appendix B 2-44 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-1 (page 39 of 39)
Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (cont'd}
A.
Allowable Contents (cont'd}
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D, 14x14E,and 15x15G ii. All Other Array/Classes
- e. Fuel Assembly Length f.
Fuel Assembly Width
- g. Fuel Assembly Weight
!:: 500 Watts.
As specified in Section 2.3.
!:: 176.8 inches (nominal design}
!:: 8.54 inches (nominal design}
!:: 1,680 lbs (including NON-FUEL HARDWARE and DFC}
B.
Quantity per MPC: Up to eight (8) DAMAGED FUEL ASSEMBLIES and/or FUEL.
DEBRIS in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 1, 4, 5, 10, 23, 28, 29, and/or 32. The remaining MPC-32F fuel storage locations may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.
C.
Neutron sources are not permitted for loOding in the MPC-32F.
Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, or APSRs may only be loaded in fuel storage locations 13, 14, 19 and/or 20.
These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.
Certificate of Compliance No. 1014 Appendix B 2-45 Renewed Amendment No. 2
Table 2.1-2 (page 1 of 4)
Approved Contents 2.0 PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 14x14A Array/Class Clad Material ZR Design Initial U s 365 (kg/assy.) (Note 3)
Initial Enrichment (MPC-24, 24E and s4.6 (24) 24EF without soluble boron s5.o credit)
(wt% 23sU)
(24E/24EF)
(Note 7)
Initial Enrichment (MPC-24, 24E, 24EF,32,or 32F s5.0 with soluble boron credit - see Note 5)
(wt% 235U)
No. of Fuel Rod 179 Locations Fuel Rod Clad O.D.
d 0.400 (in.)
Fuel Rod Clad 1.0.
S 0.3514 (in.)
Fuel Pellet Dia.
(in.)
s0.3444 Fuel Rod Pitch (in.)
s 0.556 Active Fuel Length S 150 (in.)
No. of Guide and/or 17 Instrument Tubes Guide/Instrument Tube
- ! 0.017 Thickness (in.)
Certificate of Compliance No. 1014
- Appendix B 14x14B ZR s412 s 4.6 (24) s5.o (24E/24EF) s5.o 179 d 0.417 s0.3734 s0.3659 s0.556 s150 17
- ! 0.017 2-46 14x14C 14x14D 14x14E ZR ss ss s438 s400 s206 s 4.6 (24) s 4.0 (24) s5.o (24) s5.o s5.o s5.o (24E/24EF)
(24E/24EF)
(24E/24EF) sS.0 s5.o s5.o 176 180 173 d 0.440 d 0.422 d0.3415 s 0.3880 s 0.3890 s 0.3175 s0.3805 s 0.3835 s 0.3130 s0.580 s0.556 Note 6 S 150 S 144 s 102 5 (Note 4) 16 0
d0.038 d 0.0145 N/A Renewed Amendment No. 2
Table 2.1-2 (page 2 of 4)
PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly Array/Class Clad Material Design Initial U (kg/assy.)
(Note 3)
Initial Enrichment (MPC-24, 24E and 24EF without soluble boron credit)
(wt% 23sU)
(Note 7)
Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F with soluble boron credit - see Note 5}
(wt% 23sU}
No. of Fuel Rod Locations Fuel Rod Clad O.D.
- (in.)
Fuel Rod Clad I.D.
(in.)
Fuel Pellet Dia. (in.)
Fuel Rod Pitch (in.)
Active Fuel Length (in.)
No. of Guide and/or Instrument Tubes Guide/Instrument Tube Thickness (in.)
15x15A ZR
_s473 s 4.1 (24}
.=:; 4.5 (24E/24EF}
_s5.0 204 p 0.418
_s0.3660
_s0.3580
_s0.550 S 150 21 p 0.0165 Certificate of Compliance No. 1014 Appendix B 15x15B ZR s 473 s 4.1 (24}
.=:;4.5 (24E/24EF}
_s5.0 204 p 0.420
_s0.3736 s 0.3671
.=:; 0.563
.=:; 150 21 p 0.015 15x15C ZR s 4.1 (24}
.=:;4.5 (24E/24EF}
_s5.0 204 p 0.417
_s0.3640
_s0.3570
_s0.563
.s 150 21 p 0.0165 2-47 15x15D ZR
.=:;4.5 (24E/24EF}
208 p0.430
_s0.3800
_s0.3735
_s0.568
.=:; 150 17 p 0.0150 Approved Contents 2.0 15x15E ZR S 4.1 (24}
.=:;4.5 (24E/24EF}
_s5.0 208 p 0.428
_s0.3790
_s0.3707
_s0.568 S 150 17 p 0.0140 15x15F ZR s 4.1 (24}
.=:;4.5 (24E/24EF}
_s5.0 208 p 0.428
_s0.3820 s 0.3742
_s0.568 S 150 17 p 0.0140 Renewed Amendment No. 2
Table 2.1-2 (page 3 of 4)
Approved Contents 2.0 PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 15x15G Array/ Class Clad Material ss Design Initial U (kg/assy.}
s420 (Note 3)
Initial Enrichment (MPC-24, 24E, and s 4.0 (24}
24EF without soluble boron s4.5 credit}
(wt% 23sU}
(24E/24EF)
(Note 7)
Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F S 5.0 with soluble boron credit - see Note 5)
(wt% 23sU)
No. of Fuel Rod 204 Locations Fuel Rod Clad O.D.
2=, 0.422 (in.}
Fuel Rod Clad I.D.
s0.3890 (in.)
Fuel Pellet Dia.
!;:0,3825 (in.)
Fuel Rod Pitch (in.)
s0.563 Active Fuel Length
!:: 144 (in.)
No. of Guide and/or 21 Instrument Tubes Guide/Instrument Tube 2=, 0.0145 Thickness (in.)
Certificate of Compliance No. 1014 Appendix B 15x15H ZR s495 s 3.8 (24}
S 4.2 (24E/24EF) s5.o 208 2=. 0.414 s0.3700 s0.3622 s0.568 s 150 17 2=, 0.0140 16x16A 17x17A 17x17B 17x17C ZR ZR ZR ZR s448 s433 s474 s 480 S 4.6 (24}
s 4.0 (24}
s 4.0 (24}
s 4.0 (24}
s5.o S 4.4
. S 4.4 S 4.4 (24E/24EF)
(24E/24EF)
(24E/24EF)
(24E/24EF) s5.0 s5.o s5.0 s 5.0 236 264 264 264 2=, 0.382 2=, 0.360 2=, 0.372 2=, 0.377 s0.3320 s 0.3150 s 0.3310 s0.3330
!:: 0.3255
!:: 0.3088
!:: 0.3232
!:: 0.3252 s 0.506
!:: 0.496
!:: 0.496
!:: 0.502 S 150 S 150 S 150 s 150 5 (Note 4) 25 25 25 2=, 0.0400
_0.016 2=, 0.014 2=, 0.020 2-48 Renewed Amendment No. 2
Table 2.1-2 (page 4 of 4)
PWR FUEL ASSEMBLY CHARACTERISTICS Notes:
Approved Contents 2.0
- 1. All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
- 2. Deleted.
- 3. Design initial uranium weight 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 *manufacturer's tolerances.
- 4. Each guide tube replaces four fuel rods.
- 6. This fuel assembly array/class includes only the Indian Point Unit 1 fuel assembly. This fuel assembly has two pitches in different sectors of the assembly. These pitches are 0.441 inches and 0.453 inches.
- 7. For those MPCs loaded with both INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, the maximum initial enrichment of the INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS is 4.o*wt.% 235U.
Certificate of Compliance No. 1014 Appendix B 2-49 Renewed Amendment No. 2
Table 2.1-3 (page 1 of 5).
BWR FUEL ASS EMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 6x6A Array/Class Clad Material ZR Design Initial U S 110 (kg/assy.) (Note 3)
Maximum PLANA R-AVE RAGE INITIAL ENRICHMENT s:2.1 (wt.% 23sU)
(Note 14)
Initial Maximum Rod Enrichment s4.o (wt.% 23sU)
No. of Fuel Rod L ocati ons 35 or36 Fuel Rod Clad 0.0.
{0.5550 (in.)
Fuel Rod Clad 1.0.
S 0.5105 (in.)
Fuel Pellet Dia. (in.)
s0.4980 Fuel Rod Pitch (in.)
so.110 Active Fuel Length S 120 (in.)
No. of Water Rods 1 or 0 (Note 11)
>0 Thickness (in.)
Channel Thickness so.060 (in.)
Certificate of Compliance No. 1014 Appendix B 6x6B ZR S 110
< 2.7 for the
-U02 rods.
See Note 4 for MOX rods s4.o 35 or 36 (up t o 9 MOX rods)
{0.5625 S 0.4945 S 0.4820 so.110 S 120 1 or 0
>0 so.060 6x6C 7x7A 7x7B ZR ZR ZR S 110 s:100 S 198 s2.7 s2.7 s4.2 s4.o s5.5 s5.o 36 49 49
- {0.5630
{ 0.4860
{0.5630 S 0.4990 s0.4204 S 0.4990 so.4sso s 0.4110 S 0.4910 so.140 S 0.631 s0.738 s:77.5 s:80 S 150 0
0 0
NIA NIA NIA so.060 so.060 so.120 2-50 Approved Contents 2.0 8x8A ZR S 120 s:2.1 s4.o 63 or64
{ 0.4120 S 0.3620 s0.3580 s0.523 S 120 1 or0
{o s 0.100 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-3 (2 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 8x8B 8x8C 8x8D 8x8E 8x8F 9x9A Array/Class__
Clad Material ZR ZR ZR ZR ZR ZR (kgDassin (Note 3)
< 192
< 190
< 190
< 190
< 191
< 180 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT
< 4.2
< 4.2
< 4.2
< 4.2
< 4.0
< 4.2 (Wt.% 235U)
(Note 14)
Initial Maximum Rod Enrichment
< 5.0
< 5.0
< 5.0
< 5.0
< 5.0
< 5.0 (wt.% 2 35U)
No. of Fuel Rod 63 or 64 62 60 or 61 59 64 74/66 Locations 63___or__64 62_60_or61_59_64(Note 5)
Fuel Rod Clad O.D.
> 0.4840
> 0.4830
> 0.4830
> 0.4930
> 0.4576
> 0.4400 (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 DesignActiveFuel
< 150
< 150
< 150
< 150
< 150
< 150 Length (in.)
No. of Water Rods 1 or O 2
1 - 4 5
N/A2 (Note 11)
(Note 7)
(Note 12)
Want)
Ro4Thickness
>.0
> 0.00
> 0.00
> 0.034
> 0.0315
> 0.00 Channel Thickness (in.)
<50.120
<50.120
< 0.120
< 0.100
< 0.055
< 0.120 Certificate of Compliance No. 1014 Appendix B 2-51 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-3 (page 3 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 9xB99 xD9x9E 9x9 F 9
Array/Classe y
x9B 99C 9x9D (Note 13)
(Note 13) 9 Clad Material ZR ZR ZR ZR ZR ZR (kg/ass;)(Note 3)
< 180
< 182
< 182
< 183
< 183
< 164 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT
< 4.2
< 4.2
< 4.2
< 4.0
< 4.0
< 4.2 (Wt.% 231U)
(Note 14)
Initial Maximum Rod Enrichment
< 5.0
< 5.0
< 5.0
< 5.0
< 5.0
< 5.0 (wt.% MU)
No. of Fuel Rod 72 80 79 76 76 72 Locations Fuel Rod Clad O.D.
> 0.4330
> 0.4230
> 0.4240
> 0.4170
> 0.4430
> 0.4240 Fuel Rod Clad I.D.
< 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 DesignActiveFuel
< 150
< 1 50
< 150
<o
< 150
< 150 Length (in.)
No. of Water Rods 1 (Note 6) 1 2
(Note 6 (Note 11) 1 (Note_6)_.(Note 6)
Water Rod Thickness
> 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 I
I Certificate of Compliance No. 1014 Appendix B 2-52 Renewed Amendment No. 2
Approved Contents 2.0 Table 2.1-3 (page 4 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly Array/Class 1Ox1OA 10x10B 1Ox10C 1Ox1OD 10x1iE Clad Material ZR ZR ZR Ss Ss Design Initial U (kglassy.) (Note 3)
< 188
< 188
< 179
< 125
< 125 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT
< 4.2
< 4.2
< 4.2
< 4.0
< 4.0 (Note 14)
Initial Maximum Rod Enrichment
<5.0
< 5.0
<5.0
<5.0
< 5.0 (Wt.% 235U)
No. of Fuel Rod Locations 92/78 91/83 96 100 96 (Note 8)
(Note 9)
Fuel Rod Clad O.D. (in.)
> 0.4040
> 0.3957
> 0.3780
> 0.3960
> 0.3940 Fuel Rod Clad l.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 Certificate of Compliance No. 1014 Appendix B 2-53 Renewed Amendment No. 2
Table 2.1-3 (page 5 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS Notes:
Approved Contents 2.0 1.
All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
2.
Deleted.
3.
Design initial uranium weight 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.
.s 0.635 wt. % 235U and.s 1.578 wt. % total fissile plutonium {239Pu and 241Pu), (wt. % of total fuel weight, i.e., UO2 plus PuO2).
5.
This assembly class contains 7 4 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.
1 O.
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 those MPCs loaded with both INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, the maximum PLANAR AVERAGE INITIAL ENRICHMENT for the INTACT FUEL ASSEMBLIES is limited to 3.7 wt.% 235U, as applicable.
Certificate of Compliance No. 1014 Appendix B 2-54 Renewed Amendment No. 2
Certificate of Compliance No. 1014 Appendix B Table 2.1-4 TABLE DELETED Approved Contents 2.0 Renewed Amendment No. 2
Certificate of Compliance No. 1014 Appendix B Table 2.1-5 TABLE DELETED 2-56 Approved Contents 2.0 Renewed Amendment No. 2
Certificate of Compliance No. 1014 Appendix B Table 2.1-6 (page 1 of 2)
TABLE DELETED 2-57 Approved Contents 2.0 Renewed Amendment No. 2
Certificate of Compliance No. 1014 Appendix B Table 2.1-6 (page 2 of 2)
TABLE DELETED 2-58 Approved Contents 2.0 Renewed Amendment No. 2
Certificate of Compliance No. 1014 Appendix B Table 2.1-7 (page 1 of 2)
TABLE DELETED 2-59 Approved Contents 2.0 Renewed Amendment No. 2
Certificate of Compliance No. 1014 Appendix B Table 2.1-7 (page 2 of 2)
TABLE DELETED 2-60 Approved Contents 2.0 Renewed Amendment No. 2
Table 2.1-8 Approved Contents 2.0 NON-FUEL HARDWARE COOLING AND AVERAGE BURNUP (Notes 1, 2, and 3)
Post-irradiation Cooling Time (years)
3
4
5
6
7
8
9
.V 10 V 11 V12 INSERTS (Note 4)
BURNUP (MWD/MTU)
_s24,635
.s 30,000
.s 36,748
.s 44,102
.s 52,900
.s 60,000 GUIDE TUBE HARDWARE (Note 5)
BURNUP (MWD/MTU)
NA (Note 7)
.s 20,000
.s 25,000
.s 30,000
.s 40,000
.s 45,000
.s 50,000
.s 60,000
.s75,000
.s 90,000
.s 180,000
.s 630,000 CONTROL COMPONENT (Note 6)
BURNUP (MWD/MTU)
NA NA
.s 630,000 APSR BURNUP (MWD/MTU)
NA NA
_s45,000
.s 54,500
.s 68,000
.s 83,000
.s 111,000
.s 180,000
.s 630,000 Notes: 1. Burnups for NON-FUEL HARDWARE are to be determined based on the burnup and uranium mass of the fuel assemblies in which the component was inserted during reactor operation.
2.
Linear interpolation between points is permitted, except that TPD and APSR burn ups> 180,000 MWD/MTU and.s 630,000 MWD/MTU must be cooledV 14 years andV 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 DevicWs (TPDs), water displacement guide tube plugs, and orifice rod assemblies.
6.
Includes Control Rod Assemblies (CRAs), Control Element Assemblies (CEAs), and Rod Cluster Control Assemblies (RCCAs).
7.
NA means not authorized for loading at this cooling time.
2-61 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
2.4 Decay Heat, Burnup, and Cooling Time Limits for ZR-Clad Fuel Approved Contents 2.0 This section provides the limits on ZR-clad fuel assembly decay heat, burnup, and cooling time for storage in the HI-STORM 100 System. A detailed discussion of how to calculate the limits and verify compliance, including examples, is provided in Chapter 12 of the HI-STORM 100 FSAR.
2.4.1 Uniform Fuel Loading Decay Heat Limits for ZR-clad fuel Table 2.4-1 provides the maximum allowable decay heat per fuel storage location for ZR-clad fuel in uniform fuel loading for each MPC model.
Table 2.4-1 Maximum Allowable Decay Heat per Fuel Storage Location (Uniform Loading, ZR-Clad)
MPC Model Decay Heat per Fuel Storage Location (kW)
Intact Fuel Assemblies MPC-24
$ 1.157 MPC-24E/24EF
$ 1.173 MPC-32/32F
$ 0.898 MPC-68/68FF
$ 0.414 Damaged Fuel Assemblies and Fuel Debris MPC-24
$1,099 MPC-24E/24EF
$1,114 MPC-32/32F
$ 0.718 MPC-68/68FF
$ 0.393 2.4.2 Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel Table 2.4-2 provides the maximum allowable decay heat per fuel storage location for ZR clad fuel in regionalized loading for each MPC model.
2-62 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Approved Contents 2.0 2.4.2 Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel (cont'd)
Table 2.4-2 Fuel Storage Regions and Maximum Decay Heat per MPC Number of Fuel Inner Region MPC Model Storage Locations Maximum Decay in Inner and Outer Heat per Assembly Regions (kW)
MPC-24 4 and 20 1.470 MPC-24E/24EF 4 and 20 1.540 MPC-32/32F 12 and 20 1.131 MPC-68/68FF 32 and 36 0.500 2.4.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel Outer Region Maximum Decay Heat per Assembly (kW) 0.900 0.900 0.600 0.275 The maximum allowable fuel assembly average burnup varies with the following parameters:
Minimum fuel assembly cooling time Maximum fuel assembly decay heat Minimum fuel assembly average enrichment The maximum allowable ZR-clad fuel assembly average burnup for a given MINIMUM ENRICHMENT is calculated as described below for minimum cooling times between 3 and 20 years using the maximum permissible decay tieat determined in Section 2.4.1 or 2.4.2.
Different fuel assembly average burnup limits may be calculated for different minimum enrichments (by individual fuel assembly) for use in choosing the fuel assemblies to be loaded into a given MPC.
2.4.3.1 Choose a fuel assembly minimum enrichment, Ei35*
2.4.3.2 Calculate the maximum allowable fuel assembly average burn up for a minimum cooling time between 3 and 20 years using the equation below.
Equation 2.4.3 Where:
Bu = Maximum allowable average burnup per fuel assembly (MWD/MTU) 2-63 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Approved Contents 2.0 2.4.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel (cont'd) q =
Maximum allowable decay heat per fuel storage location determined in Section 2.4.1 or 2.4.2 (kW)
E235 = Minimum fuel assembly average enrichment (wt. % 235U)
(e.g., for 4.05 wt.%, use 4.05)
A through G = Coefficients from Tables 2.4-3 and 2.4-4 for the applicable fuel assembly array/class and minimum cooling time 2.4.3.3 Calculated burnup limits shall be rounded down to the nearest integer.
2.4.3.4 Calculated 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.
2.4.3.5 Linear interpolation of calculated burnups between cooling times for a given fuel assembly maximum decay heat and minimum enrichment is permitted. For example, the allowable _burnup for a cooling time of 4.5 years may be interpolated between those burnups calculated for 4 year and 5 years.
2.4.3.6 Each ZR-clad fuel assembly to be stored must have a MINIMUM ENRICHMENT
- greater than or equal to the value used in Step 2.4.3.2.
2.4.4 When complying with the maximum fuel storage location decay heat limits, users must account for the decay heat from both the fuel assembly and any NON-FUEL HARDWARE, as applicable for the particular fuel storage location, to ensure the decay heat emitted by all contents in a storage location does not exceed the limit.
2-64 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years)
?.3
?. 4
?.5
?. 6
?. 7
?. 8
. ?.9
?. 10
?. 11
. ?. 12
?. 13
?. 14
?. 15
?. 16
?. 17
?. 18
?. 19
>20 Table 2.4-3 (Page 1 of 8)
Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 14x14A A
B C
D E
F G
20277.1 303.592
-68.329
-139.41 2993.67
-498.159
-615.411 35560.1
-6034.67 985.415
-132.734 3578.92
-723.721
-609.84 48917.9
-14499.5 2976.09
-150.707 4072.55
-892.691
-54.8362 59110.3
-22507 5255.61
-177.017 4517.03
-1024.01 613.36 67595.6
-30158.1 7746.6
-200.128 4898.71
-1123.21 716.004 74424.9
-36871.1 10169.4
-218.676 5203.64
-1190.24 741.163 81405.8
-44093.1 12910.8
-227.916 5405.34
-1223.27 250.224 86184.3
-49211.7 15063.4
-237.641 5607.96
-1266.21 134.435 92024.9
-55666.8 17779.6
-240.973 5732.25
-1282.12
-401.456 94775.8
-58559.7 19249.9
-246.369 5896.27
-1345.42
-295.435 100163
-64813.8 22045.1
-242.572 5861.86
-1261.66
-842.159 103971
-69171 24207
-242.651 5933.96
-1277.48
-1108.99 108919
-75171.1 27152.4
-243.154 6000.2
-1301.19
-1620.63 110622
-76715.2 28210.2
-240.235 6028.33
-1307.74
-1425.5 115582
-82929.7 31411.9
-235.234 5982.3
-1244.11
-1948.05 119195
-87323.5 33881.4
-233.28 6002.43
-1245.95
-2199.41 121882
-90270.6 35713.7
-231.873 6044.42
-1284.55
-2264.05 124649
-93573.5 37853.1
-230.22 6075.82
-1306.57
-2319.63
.2-65 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years) 2!3 2!4 2!5
- ! 6
- ! 7
- ! 8
- ! 9 2! 10 2! 11 2! 12 2! 13 2! 14 2! 15 2! 16 2! 17 2! 18 2! 19 2!20 Table 2.4-3 (Page 2 of 8)
Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 14x14B A
B C
D E
F G
18937.9 70.2997
-28.6224
-130.732 2572.36
-383.393
-858.17 32058.7
-4960.63 745.224,
-125.978 3048.98
-551.656
-549.108 42626.3
-10804.1 1965.09
-139.722 3433.49
-676.643 321.88 51209.6
-16782.3 3490.45
-158.929 3751.01
-761.524 847.282 57829.9
-21982 5009.12
-180.026 4066.65
-846.272 1200.45 62758
-26055.3 6330.88
-196.804 4340.18
-928.336 1413.17 68161.4
-30827.6 7943.87
-204.454 4500.52
-966.347 1084.69 71996.8
-34224.3 9197.25
-210.433 4638.94
-1001.83 1016.38 75567.3
-37486.1 10466.9
-214.95 4759.55
-1040.85 848.169 79296.7
-40900.3 11799.6
-212.898 4794.13
-1040.51 576.242 82257.3
-43594 12935
-212.8 4845.81
-1056.01 410.807 83941.2
-44915.2 13641
-215.389 4953.19
-1121.71 552.724 87228.5
-48130 15056.9
-212.545 4951.12
-1112.5 260.194 90321.7
-50918.3 16285.5
-206.094 4923.36
-1106.35
-38.7487 92836.2
-53314.5 17481.7
-203.139 4924.61
-1109.32
-159.673 93872.8
-53721.4 17865.1
-202.573 4956.21
-1136.9 30.0594 96361.6
-56019.1 19075.9
-199.068 4954.59
-1156.07
-125.917 98647.5
-57795.1 19961.8
-191.502 4869.59
-1108.74
-217.603 2-66 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years) 43 44 45 46 47 48 49 4 10 4 11 412 413 414 4 15 4 16 417 4 18 4 19
>20 Table 2.4-3 (Page 3 of 8)
Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 14x14C A
B C
D E
F G
19176.9 192.012
-66.7595
-138.112 2666.73
-407.664
-1372.41 32040.3
-4731.4 651.014
-124.944 3012.63
-530.456
-890.059 43276.7
-11292.8 2009.76
-142.172 3313.91
-594.917
-200.195 51315.5
-16920.5 3414.76
-164.287 3610.77
-652.118 463.041 57594.7
-21897.6 4848.49
-189.606 3940.67
-729.367 781.46 63252.3
-26562.8 6273.01
-199.974 4088.41
-732.054 693.879 67657.5
-30350.9 7533.4
-211.77 4283.39
-772.916 588.456 71834.4
-34113.7 8857.32
-216.408 4383.45
-774.982 380.243 75464.1
-37382.1 10063
-218.813 4460.69
-776.665 160.668 77811.1
-39425.1 10934.3
-225.193 4604.68
-833.459 182.463 81438.3
-42785.4 12239.9
-220.943 4597.28
-803.32
-191.636 84222.1
-45291.6 13287.9
-218.366
. 4608.13
-791.655
-354.59 86700.1
-47582.6 14331.2
-218.206 4655.34
-807.366
-487.316 88104.7
-48601.1 14927.9
-219.498 4729.97
-849.446
-373.196 91103.3
-51332.5 16129
-212.138 4679.91
-822.896
-654.296 93850.4
-53915.8 17336.9
-207.666 4652.65
-799.697
-866.307 96192.9
-55955.8 18359.3
-203.462 4642.65
-800.315
-1007.75 97790.4
-57058.1 19027.7
-200.963 4635.88
-799.721
-951.122 2-67 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years)
3
?4
?5
?6
?7
?8
?9
?10
? 11
? 12
?13
?14
?15
?16
? 17
?18
? 19
?20 Table 2.4-3 (Page 4 of 8)
Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 15x15NB/C A
B C
D E
F G
15789.2 119.829
-21.8071
-127.422 2152.53
-267.717
-580.768 26803.8
-3312.93 415.027
-116.279 2550.15
-386.33
-367.168 36403.6
-7831.93 1219.66
-126.065 2858.32
-471.785 326:863 44046.1
-12375.9 2213.52
-145.727 3153.45
-539.715 851.971 49753.5
-16172.6 3163.61
-166.946 3428.38
-603.598 1186.31 55095.4
-20182.5 4287.03
-183.047 3650.42
-652.92 1052.4 58974.4
-23071.6 5156.53
-191.718 3805.41
-687.18 1025 62591.8
-25800.8 5995.95
-195.105 3884.14
-690.659 868.556 65133.1
-27747.4 6689
-203.095 4036.91
-744.034 894.607 68448.4
-30456 7624.9
-202.201 4083.52
-753.391 577.914 71084.4
-32536.4 8381.78
-201.624 4117.93
-757.16 379.105 73459.5
-34352.3 9068.86
-197.988 4113.16
-747.015 266.536 75950.7
-36469.4 9920.52
-199.791 4184.91
-779.222 57.9429 76929.1
-36845.6 10171.3
-197.88 4206.24
-794.541 256.099 79730
-39134.8 11069.4
-190.865 4160.42
-773.448
-42.6853 81649.2
-40583 11736.1
-187.604 4163.36
-785.838
-113.614 83459
-41771.8 12265.9
-181.461 4107.51
-758.496
-193.442 86165.4
-44208.8 13361.2
-178.89 4107.62
-768.671
-479.778 2-68 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years) 73 74 75 76 77 78 79 7 10 7 11 712 713 714 7 15 7 16 717 718 7 19 720 Table 2.4-3 (Page 5 of 8)
Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 15x15D/E/F/H A
B C
D E
F G
15192.5 50.5722
-12.3042
-126.906 2009.71
-235.879
-561.574 25782.5
-3096.5 369.096
-113.289 2357.75
-334.695
-254.964
'35026.5
-7299.87 1091.93
-124.619 2664
-414.527 470.916 42234.9
-11438.4 1967.63
-145.948 2945.81
-474.981 1016.84 47818.4
-15047 2839.22
-167.273 3208.95
-531.296 1321.12 52730.7
-18387.2 3702.43
-175.057 3335.58
-543.232 1223.61 56254.6
-20999.9 4485.93
-190.489 3547.98
-600.64 1261.55 59874.6
-23706.5 5303.88
-193.807 3633.01
-611.892 1028.63 62811
-25848.4 5979.64
-194.997 3694.14
-618.968 862.738 65557.6
-27952.4 6686.74
-198.224 3767.28
-635.126 645.139 67379.4
-29239.2 7197.49
-200.164 3858.53
-677.958 652.601 69599.2
-30823.8 7768.51
-196.788 3868.2
-679.88 504.443 71806.7
-32425 8360.38
-191.935 3851.65
-669.917 321.146 73662.6
-33703.5 8870.78
-187.366 3831.59
-658.419 232.335 76219.8
-35898.1 9754.72
-189.111 3892.07
-694.244
-46.924 76594.4
-35518.2 9719.78
-185.11 3897.04
-712.82 236.047 78592.7
-36920.8 10316.5
-179.54 3865.84
-709.551 82.478 80770.5
-38599.9 11051.3
-175.106 3858.67
-723.211.
-116.014 2-69 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years) 63 64 65 66 67 68 69 610 6 11 6 12 613 614 6 15 6 16 617 6 18 6 19 620 Table 2.4-3 (Page 6 of 8)
Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 16X16A A
8 C
D E
F G
17038.2 158.445
-37.6008
-136.707 2368.1
-321.58
-700.033 29166.3
-3919.95 508.439
-125.131 2782.53
-455.722
-344.199 40285
-9762.36 1629.72
-139.652 3111.83
-539.804 139.67 48335.7
-15002.6 2864.09
-164.702 3444.97
-614.756 851.706 55274.9
-20190 4258.03
-185.909 3728.11
-670.841 920.035 60646.6
-24402.4 5483.54
-199.014 3903.29
-682.26 944.913 64663.2
-27753.1 6588.21
-215.318 4145.34
-746.822 967.914 69306.9
-31739.1 7892.13
-218.898 4237.04
-746.815 589.277 72725.8
-34676.6 8942.26
-220.836 4312.93
-750.85 407.133 76573.8
-38238.7 10248.1
-224.934 4395.85
-757.914 23.7549 78569
-39794.3 10914.9
-224.584 4457
-776.876 69.428 81559.4
-42453.6 11969.6
-222.704 4485.28
-778.427
-203.031 84108.6
-44680.4 12897.8
-218.387 4460
-746.756
-329.078 86512.2
-46766.8 13822.8
-216.278 4487.79
-759.882
-479.729 87526.7
-47326.2 14221
-218.894 4567.68
-805.659
-273.692 90340.3
-49888.6 15349.8
-212.139 4506.29
-762.236
-513.316 93218.2
-52436.7 16482.4
-207.653 4504.12
-776.489
-837.1 95533.9
-54474.1 17484.2
-203.094 4476.21
-760.482
-955.662 2-70 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years) 73 74 75 76 77 78 79 710 7 11 712 7 13 714 7 15 7 16 717 7 18 7 19 720 Table 2.4-3 (Page 7 of 8)
Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 17x17 A A
B C
D E
F G
16784.4 3.90244
-10.476
-128.835 2256.98
-287.108
-263.081 28859
-3824.72 491.016
-120.108 2737.65
-432.361
-113.457 40315.9
-9724 1622.89
-140.459 3170.28
-547.749 425.136 49378.5
-15653.1 3029.25
-164.712 3532.55
-628.93 842.73 56759.5
-21320.4 4598.78
-190.58 3873.21
-698.143 975.46 63153.4
-26463.8 6102.47
-201.262 4021.84
-685.431 848.497 67874.9
-30519.2 7442.84
-218.184 4287.23
-754.597 723.305 72676.8
-34855.2 8928.27
-222.423 4382.07
-741.243 387.877 75623
-37457.1 9927.65
-232.962 4564.55
-792.051 388.402 80141.8
-41736.5 11509.8
-232.944 4624.72
-787.134
-164.727 83587.5
-45016.4 12800.9
-230.643 4623.2
-745.177
-428.635 86311.3
-47443.4 13815.2
-228.162 4638.89
-729.425
-561.758 87839.2
-48704.1 14500.3
-231.979 4747.67
-775.801
-441.959 91190.5
-51877.4 15813.2
-225.768 4692.45
-719.311
-756.537 94512
-55201.2 17306.1
-224.328 4740.86
-747.11
-1129.15 96959
-57459.9 18403.8
-220.038 4721.02
-726.928
-1272.47 99061.1
-59172.1 19253.1
-214.045 4663.37
-679.362
-1309.88 100305
-59997.5 19841.1
-216.112 4721.71
-705.463
-1148.45 2-71 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years)
?.3
?.4
?. 5
?. 6
?. 7
?. 8
?. 9
?. 10
?. 11
?. 12
?.13
?.14
?. 15
?. 16
?.17
?.18
?.19
>20 Table 2.4-3 (Page 8 of 8)
Approved Contents 2.0 PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 17x178/C A
B C
D E
F G
15526.8 18.0364
-9.36581
-128.415 2050.81
-243.915
-426.07 26595.4
-3345.47 409.264
-115.394 2429.48
-350.883
-243.477 36190.4
-7783.2 1186.37
-130.008 2769.53
-438.716 519.95 44159
-12517.5 2209.54
-150.234 3042.25
-489.858 924.151 50399.6
-16780.6 3277.26
-173.223 3336.58
-555.743 1129.66 55453.9
-20420 4259.68
-189.355 3531.65
-581.917 1105.62 59469.3
-23459.8 5176.62*
.;199.63 3709.99
-626.667 1028.74 63200.5
-26319.6 6047.8
-203.233 3783.02
-619.949 805.311 65636.3
-28258.3 6757.23
-214.247 3972.8
-688.56 843.457 68989.7
-30.904.4 7626.53.
-212.539 3995.62
-678.037 495.032 71616.6
-32962.2 8360.45
-210.386 4009.11
-666.542 317.009 73923.9
-34748 9037.75
-207.668 4020.13
-662.692 183.086 76131.8
-36422.3 9692.32
-203.428 4014.55
-655.981 47.5234 77376.5
-37224.7 10111.4
-207.581 4110.76
-703.37 161.128 80294.9
-39675.9 11065.9
-201.194 4079.24
-691.636
-173.782 82219.8
-41064.8 11672.1
-195.431 4043.83
-675.432
-286.059 84168.9
-42503.6 12309.4
-190.602 4008.19
-656.192
-372.411 86074.2
-43854.4 12935.9
-185.767 3985.57
-656.72
-475.953 2-72 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years) 73 74 75 76 77 78 79 7 10 7 11 7 12.
713 714 715 7 16 717 7 18 7 19 720 Table 2.4-4 (Page 1 of 1 0)
Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 7x7B A
B C
D E
F G
26409.1 28347.5
-16858
-147.076 5636.32
-1606.75 1177.88 61967.8
-6618.31
-4131.96
-113.949 6122.77
-2042.85
-96.7439 91601.1
-49298.3 17826.5
-132.045 6823.14
-2418.49
-185.189 111369
-80890.1 35713.8
-150.262 7288.51
-2471.1 86.6363 126904
-108669 53338.1
-167.764 7650.57
-2340.78 150.403 139181
-132294 69852.5
. -187.317 8098.66
-2336.13 97.5285 150334
-154490 86148.1
-193.899 8232.84
-2040.37
-123.029 159897
-173614 100819
-194.156 8254.99
-1708.32
-373.605 166931
-186860 111502
-193.776 8251.55
-1393.91
-543.677 173691
-201687 125166
-202.578 8626.84
-1642.3
-650.814 180312
-215406 137518
-201.041 8642.19
-1469.45
-810.024 185927
-227005 148721
-197.938 8607.6
-1225.95
-892.876 191151
-236120 156781
-191.625 8451.86
-846.27
-1019.4 195761
-244598 165372
-187.043 8359.19
-572.561
-1068.19 200791
-256573 179816
-197.26 8914.28
-1393.37
-1218.63 206068
-266136 188841
-187.191 8569.56
-730.898
-1363.79 210187
-273609 197794
-182.151 8488.23
-584.727
-1335.59 213731
-278120 203074
-175.864 8395.63
-457.304
-1364.38 2-73 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years)
S3 S4 S5 S6 S7 S8 S9 S 10 S 11 S 12*
S 13 S14 S15 S 16 S17 S 18 S 19
>20 Table 2.4-4 (Page 2 of 10)
Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 8x8B A
B C
D E
F G
28219.6 28963.7
-17616.2
-147.68 5887.41
-1730.96 1048.21 66061.8
-10742.4
-1961.82
-123.066 6565.54
-2356.05
-298.005 95790.7
-53401.7 19836.7
-134.584 7145.41
-2637.09
-298.858 117477
-90055.9 41383.9
-154.758 7613.43
-2612.69
-64.9921 134090
-120643 60983
-168.675 7809
-2183.3
-40.8885 148186
-149181 81418.7
-185.726 8190.07
-2040.31
-260.773 159082
-172081 99175.2.
-197.185 8450.86
-1792.04
-381.705 168816
-191389 113810
-195.613 8359.87
-1244.22
-613.594 177221
-210599 131099
-208.3 8810
-1466.49
-819.773 183929
-224384 143405.
-207.497 8841.33
-1227.71
-929.708 191093
-240384 158327
-204.95 8760.17
-811.708
-1154.76 196787
-252211 169664
-204.574 8810.95
-610.928
-1208.97 203345
-267656 186057
-208.962 9078.41
-828.954
-1383.76 207973
-276838 196071
-204.592 9024.17
-640.808
-1436.43 213891
-290411 211145
-202.169 9024.19
-482.1
-1595.28 217483
-294066 214600
-194.243 8859.35
-244.684
-1529.61 220504
-297897 219704
-190.161 8794.97
-10.9863
-1433.86 227821
-318395 245322
-194.682 9060.96
-350.308
-1741.16 2-74 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years) 93 94 95 96 97 98 99 910 9 11 912 913 914 915 9 16 917 918 919 920 Table 2.4-4 (Page 3 of 10)
Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 8x8C/D/E A
B C
D E
F G
28592.7 28691.5
-17773.6
-149.418 5969.45
-1746.07 1063.62 66720.8
-12115.7
- -1154
-128.444 6787.16
-2529.99
-302.155 96929.1
-55827.5 21140.3
-136.228 7259.19
-2685.06
-334.328 118190
-92000.2 42602.5
-162.204 7907.46
-2853.42
-47.5465 135120
-123437 62827.1
-172.397 8059.72
-2385.81
-75.0053 149162
-152986 84543.1
-195.458 8559.11
-2306.54
-183.595 161041
-177511 103020
-200.087 8632.84
-1864.4
-433.081 171754
-201468 122929
-209.799
. 8952.06
-1802.86
-755.742 179364
-217723 137000
-215.803 9142.37
-1664.82
-847.268 186090
-232150 150255
-216.033 9218.36
-1441.92
-975.817 193571
-249160 165997
-213.204 9146.99
-1011.13
-1119.47 200034
-263671 180359
-210.559 9107.54
-694.626
-1312.55 205581
-275904 193585
-216.242 9446.57
-1040.65
-1428.13 212015
-290101 207594
-210.036 9212.93
-428.321
-1590.7 216775
-299399 218278.
-204.611 9187.86
-398.353
-1657.6 220653
-306719 227133
-202.498 9186.34
-181.672
-1611.86 224859
-314004 235956
-193.902 8990.14 145.151
-1604.71 228541
-320787 245449
-200.727 9310.87
-230.252
-1570.18 2-75 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years)
>3
>4
>5
>6
>7
>8
>9
>10
> 11
>12
>13
>14
>15
> 16
>17
>18
> 19
>20 Table 2.4-4 (Page 4 of 10)
Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 9x9A A
B C
D E
F G
30538.7 28463.2
-18105.5
-150.039 6226.92
-1876.69 1034.06 71040.1
-16692.2 1164.15
-128.241 7105.27
-2728.58
-414.09 100888
-60277.7 24150.1
-142.541 7896.11
-3272.86
-232.197 124846
-102954 50350.8
-161.849 8350.16
-3163.44
-91.1396 143516
-140615 76456.5
-185.538 8833.04
-2949.38
-104.802 158218
-171718 99788.2
-196.315 9048.88
-2529.26
-259.929 172226
-204312 126620
- .214.214 9511.56
-2459.19
-624.954 182700
-227938 146736
-215.793 9555.41
-1959.92
-830.943 190734
-246174 163557
-218.071 9649.43
-1647.5
-935.021 199997
-269577 186406
-223.975 9884.92
-1534.34
-1235.27 207414
-287446 204723
-228.808 10131.7
-1614.49
-1358.61 215263
'-306131 223440
-220.919 9928.27
-988.276
-1638.05 221920
-321612 239503
-217.949 9839.02
-554.709
-1784.04 226532
-331778 252234
-216.189 9893.43
-442.149
-1754.72 232959
-348593 272609
-219.907 10126.3
-663.84
-1915.3 240810
-369085 296809
-219.729 10294.6
-859.302
-2218.87 244637
-375057 304456
-210.997 10077.8
-425.446
-2127.83 248112
-379262 309391
-204.191 9863.67 100.27
-2059.39 2-76 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years)
3
- 4
- 5
- 6
- 7
- 8
- 9
- 10
- 11
- 12
- 13
- 14
- 15
- 16
- 17
- 18
- 19
- 20 Table 2.4-4 (Page 5 of 10)
Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 9x9B A
B C
D E
F G
30613.2 28985.3
-18371
-151.117 6321.55
-1881.28 988.92 71346.6
-15922.9 631.132
-128.876 7232.47
-2810.64
-471.737 102131
-60654.1 23762.7
-140.748 7881.6
-3156.38
-417.979 127187
-105842 51525.2
-162.228 8307.4
-2913.08
-342.13 146853
-145834 79146.5
-185.192 8718.74
-2529.57
-484.885 162013
-178244 103205
-197.825 8896.39
-1921.58
-584.013 176764
-212856 131577
-215.41 9328.18
-1737.12
-1041.11 186900
-235819 151238
-218.98 9388.08
-1179.87
-1202.83 196178
-257688 171031
-220.323 9408.47
-638.53
-1385.16 205366
-280266 192775
-223.715 9592.12
-472.261
-1661.6 215012
-306103 218866
-231.821 9853.37
-361.449
-1985.56 222368
-324558 238655
-228.062 9834.57 3.47358
-2178.84 226705
-332738 247316
-224.659 9696.59 632.172
-2090.75 233846
-349835 265676
-221.533 9649.93 913.747
-2243.34 243979
-379622 300077
-222.351 9792.17 1011.04
-2753.36 247774
-386203 308873
-220.306 9791.37 1164.58
-2612.25 254041
-401906 327901
-213.96 9645.47 1664.94
-2786.2 256003
-402034 330566
-215.242 9850.42 1359.46
-2550.06 2-77 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years) e3 e4 e5 e6 e7 e8 e9 e10 e 11 e 12 e13 e14 e15 f 16 e17 e18 e 19
>20 Table 2.4-4 (Page 6 of 10)
Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 9x9C/D A
B C
D E
F G
30051.6 29548.7
-18614.2
-148.276 6148.44
-1810.34 1006 70472.7
-14696.6
-233.567
-127.728 7008.69
-2634.22
-444.373 101298
-59638.9 23065.2
-138.523 7627.57
-2958.03
-377.965 125546
-102740 49217.4
-160.811 8096.34
-2798.88
-259.767 143887.
-139261 74100.4
-184.302 8550.86
-2517.19
-275.151 159633
-172741 98641.4
-194.351 8636.89
-1838.81
-486.731 173517
-204709 124803
-212.604 9151.98
-1853.27
-887.137 182895
-225481 142362
-218.251 9262.59
-1408.25
-978.356 192530
-247839 162173
-217.381 9213.58
-818.676
-1222.12 201127
-268201 181030
-215.552 9147.44
-232.221
-1481.55 209538
-289761 203291
-225.092 9588.12
-574.227
-1749.35 216798
-306958 220468
-222.578 9518.22
-69.9307
-1919.71 223515
-323254 237933
-217.398 9366.52 475.506
-2012.93 228796
-334529 250541
-215.004 9369.33 662.325
-2122.75 237256
-356311 273419
-206.483 9029.55 1551.3
-2367.96 242778
-369493 290354
-215.557 9600.71 659.297
-2589.32 246704
-377971 302630
-210.768 9509.41 1025.34
-2476.06 249944
-382059 308281
-205.495 9362.63 1389.71
-2350.49 2-78 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years)
?!_3
?!_4
?!_5
?!_6
?!_7
?!_8
?!_9
?! 10
?! 11
?!_12.
?! 13
?! 14
?! 15
?! 16
?! 17
?! 18
?! 19
?! 20 Table 2.4-4 (Page 7 of 10)
Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 9x9E/F A
B C
D E
F G
30284.3 26949.5
-16926.4
-147.914 6017.02
-1854.81 1026.15 69727.4
-17117.2 1982.33
-127.983 6874.68
-2673.01
-359.962 98438.9
-58492 23382.2
-138.712 7513.55
-3038.23
-112.641 119765
-95024.1 45261
-159.669 8074.25
-3129.49 221.182 136740
-128219 67940.1
-182.439 8595.68
-3098.17 315.544 150745
-156607 88691.5
-193.941 8908.73
-2947.64 142.072 162915
-182667 109134
-198.37 8999.11
-2531
-93A908 174000
-208668 131543
-210.777 9365.52
-2511.74
-445.876 181524
-224252 145280
-212.407 9489.67
-2387.49
-544.123 188946
-240952 160787
-210.65 9478.1
-2029.94
-652.339 193762
-250900 171363
-215.798 9742.31
-2179.24
-608.636 203288
-275191 196115
-218.113 9992.5
-2437.71
-1065.92 208108
-284395 205221
-213.956 9857.25
-1970.65
-1082.94 215093
-301828 224757
-209.736 9789.58
-1718.37
-1303.35 220056
-310906 234180
-201.494 9541.73
-1230.42
-1284.15 224545
-320969 247724
-206.807 9892.97
-1790.61
-1381.9 226901
-322168 250395
-204.073 9902.14
-1748.78
-1253.22 235561
-345414 276856
-198.306 9720.78
-1284.14
-1569.18 2-79 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years)
- !3
- ! 4
- !5
- ! 6
- ! 7
- ! 8
- ! 9
- ! 10
- ! 11
- ! 12
- ! 13
- ! 14
- ! 15
- ! 16
- ! 17
- ! 18
- ! 19
- !20 Table 2.4-4 (Page 8 of 10)
Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 9x9G A
B C
D E
F G
35158.5 26918.5
-17976.7
-149.915 6787.19
-2154.29 836.894 77137.2
-19760.1 2371.28
-130.934 8015.43
-3512.38
-455.424 113405
-77931.2 35511.2
-150.637 8932.55
-4099.48
-629.806 139938
-128700 68698.3
-173.799 9451.22
-3847.83
-455.905 164267
-183309 109526
-193.952 9737.91
-3046.84
-737.992 182646
-227630 146275
-210.936 10092.3
-2489.3
-1066.96 199309
-270496 184230
-218.617 10124.3
-1453.81
-1381.41 213186
-308612 221699.
-235.828 10703.2
-1483.31
-1821.73 225587
-342892 256242
-236.112 10658.5
-612.076
-2134.65 235725
-370471 285195
-234.378 10604.9 118.591
-2417.89 247043
-404028 323049
-245.79 11158.2
-281.813
-2869.82 253649
-421134 342682
-243.142 11082.3 400.019
-2903.88 262750
-448593 376340
-245.435 11241.2 581.355
-3125.07 270816
-470846 402249 l
-236.294 10845.4 1791.46
-3293.07 279840
-500272 441964
-241.324 11222.6 1455.84
-3528.25 284533
-511287 458538
-240.905 11367.2 1459.68
-3520.94 295787
-545885 501824
-235.685 11188.2 2082.21
-3954.2 300209
-556936 519174
-229.539 10956 2942.09
-3872.87 80 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years)
?.3
?.4
?.5
?. 6
?.7
?. 8
?. 9
?. 10
?. 11
?.12
?. 13
?. 14
?. 15
?. 16
?. 17
?. 18
?.19
?.20 Table 2.4-4 (Page 9 of 10)
Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 1 0x1 0A/8 A
B C
D E
F G
29285.4 27562.2
-16985
-148.415 5960.56
-1810.79 1001.45 67844.9
-14383 395.619
-127.723 6754.56
-2547.96
-369.267 96660.5
-55383.8 21180.4
-137.17 7296.6
-2793.58
-192.85 118098
-91995 42958
-162.985 7931.44
-2940.84 60.9197 135115
-123721 63588.9
-171.747 8060.23
-2485.59 73.6219 148721
-151690 84143.9
-190.26 8515.81
-2444.25
-63.4649 160770
-177397 104069
-197.534 8673.6
-2101.25
-331.046 170331
-198419 121817
-213.692 9178.33
-2351.54
-472.844 179130
-217799 138652
-209.75 9095.43
-1842.88
-705.254 186070
-232389 151792
-208.946 9104.52
-1565.11
-822.73 192407
-246005 164928
-209.696 9234.7
-1541.54
-979.245 200493
-265596 183851
-207.639 9159.83
-1095.72
-1240.61 205594
-276161 195760
-213.491 9564.23
-1672.22
-1333.64 209386
-282942 204110
-209.322 9515.83
-1506.86
-1286.82 214972
-295149 217095
-202.445 9292.34
-893.6
-1364.97 219312
-302748 225826
-198.667 9272.27
-878.536
-1379.58 223481
-310663 235908
-194.825 9252.9
-785.066
-1379.62 227628
-319115 247597
-199.194 9509.02
-1135.23
-1386.19 2-81 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Cooling Time (years) 43 44 45 46 47 48 49 4 10 4 11 412 413 414
?. 15 4 16 417 4 18 4 19 420 Table 2.4-4 (Page 10 of 10)
Approved Contents 2.0 BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Array/Class 1 Ox1 0C A
B C
D E
F G
31425.3 27358.9
-17413.3
-152.096 6367.53
-1967.91 925.763 71804
-16964.1 1000.4
-129.299 7227.18
-2806.44
-416.92 102685
-62383.3 24971.2
-142.316 7961
-3290.98
-354.784 126962
-105802 51444.6
-164.283 8421.44
-3104.21
-186.615 146284
-145608 79275.5
-188.967 8927.23
-2859.08
-251.163 162748
-181259 105859
-199.122 9052.91
-2206.31
-554.124 176612
-214183 133261
-217.56 9492.17
-1999.28
-860.669 187756
-239944 155315
-219.56 9532.45
-1470.9
-1113.42 196580
-260941 174536
-222.457-9591.64
-944.473
-1225.79 208017
-291492 204805
-233.488 10058.3
-1217.01
-1749.84 214920
-307772 221158
-234.747 10137.1
-897.23
-1868.04 222562
-326471 240234
-228.569 9929.34
-183.47
-2016.12 228844
-342382 258347
-226.944 9936.76 117.061
-2106.05 233907
-353008 270390
-223.179 9910.72 360.39
-2105.23 244153
-383017 304819
-227.266 10103.2 380.393
-2633.23 249240
-395456 321452
-226.989 10284.1 169.947
-2623.67 254343
-406555 335240
-220.569 10070.5 764.689
-2640.2 260202
-421069 354249
-216.255 10069.9 854.497
-2732.77 2-82 Renewed Amendment No. 2 Certificate of Compliance No. 1014 Appendix B
Design Features 3.0 3.0 DESIGN FEATURES 3.1 Site 3.1.1 Site Location The HI-STORM 100 Cask System is authorized for use at various site locations under the general license provisions of 1 O CFR 72, Subpart K.
3.2 Design Features Important for Criticality Control 3.2.1 MPC-24 1.
Flux trap size: ?. 1.09 in.
2.
108 loading in the neutron absorbers: ?. 0.0267 g/cm2 (Boral) and ?. 0.0223 g/cm2 (METAMIC) 3.2.2 MPC-68 and MPC-68FF 1.
Fuel cell pitch: ?. 6.43 in.
2.
108 loading in the neutron absorbers:?. 0.0372 g/cm2 (Boral) and?. 0.0310 g/cm2 (METAMIC)
.3.2.3 MPC-68F 1.
Fuel cell pitch: ?. 6.43 in.
- 2.
108 loading in the Boral neutron absorbers:?. 0.01 g/cm2 3.2.4 MPC-24E and MPC-24EF 1.
Flux trap size:
- i. Cells 3, 6, 19, and 22:?. 0.776 inch ii. All Other Cells: ?. 1.076 inches
- 2.
108 loading in the neutron absorbers: ?. 0.0372 g/cm2 (Boral) and ?. 0.031 o g/cm2 (METAMIC) 3.2.5 MPC-32 and MPC-32F 1.
Fuel cell pitch: ?. 9.158 inches 2.
108 loading in the neutron absorbers: ?. 0.0372 g/cm2 (Boral) and ?. 0.031 O g/cm2 (METAMIC)
Certificate of Compliance No. 1014 Appendix B 3-1 Renewed Amendment No. 2
DESIGN FEATURES 3.2 Design features Important for Criticality Control (cont'd)
Design Features 3.0 3.2.6 Fuel spacers shall be sized to ensure that the active fuel region of intact fuel assemblies remains within the neutron poison region of the MPC basket with water in the MPC.
3.2.7 The 84C content in METAMIC shall be.=::. 33.0 wt.%.
3.2.8 Neutron Absorber Tests Section 9.1.5.3 of the HI-STORM 100 FSAR is hereby incorporated by reference into the HI-STORM 100 CoC. The minimum 108 for the neutron absorber shall meet the minimum requirements for each MPC model specified in Sections 3.2.1 through 3.2.5 above.
3.3 Codes and Standards The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
1995 Edition with Addenda through 1997, is the governing Code for the HI-STORM 100 System, as clarified in Specification 3.3.1 below, except for Code Sections V and IX. The latest effective editions of ASME Code Sections V and IX, including addenda, may be used for activities governed by those sections, provided a written reconciliation of the later edition against the 1995 Edition, including addenda, is performed by the certificate holder. American Concrete Institute (ACI) 349-85 is the governing Code for plain concrete as clarified in* Appendix 1.D of the Final Safety Analysis Report for the HI-STORM 100 Cask System.
3.3.1 Alternatives to Codes, Standards, and Criteria Table 3-1 lists approved alternatives to the ASME Code for the design of the HI STORM 100 Cask System.
3.3.2 Construction/Fabrication Alternatives to Codes, Standards, and Criteria Proposed alternatives to the ASME Code, Section Ill, 1995 Edition with Addenda through 1997 including modifications to the alternatives allowed by Specification 3.3.1 may be used on a case-specific basis when authorized by the Director of the Office of Nuclear Material Safety and Safeguards or designee. The request for such alternative should demonstrate that:
1.
The proposed alternatives would provide an acceptable level of quality and safety, or Certificate of Compliance No. 1014 Appendix B 3-2 (continued)
Renewed Amendment No. 2
Design Features 3.0 DESIGN FEATURES 3.3.2 Construction/Fabrication Alternatives to Codes, Standards, and Criteria (cont'd)
- 2.
Compliance with the specified requirements of the ASME Code,Section III, 1995 Edition with Addenda through 1997, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Requests for alternatives shall be submitted in accordance with 10 CFR 72.4.
(continued)
I Certificate of Compliance No. 1014 Appendix B 3-3 Renewed Amendment No. 2
DESIGN FEATURES Design Features 3.0 Table 3-1 (page 1 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement ASME Code Section/ Article MPC,MP
Subsection NCA General basket Requirements.
assembly, HI-Requires preparation STORM of a Design OVERPACK Specification, Design steel Report, Overpressure structure, and Protection Report, HI-TRAC Certification of TRANSFER Construction Report, CASK steel Data Report, and structure r
other administrative controls for an ASME Code stamped vessel.
MPC NB-1100 Statement of requirements for Code stamping of components.
Certificate of Compliance No. 1014 Appendix B 3-4 Alternative, Justification & Compensatory Measures Because the MPC, OVERPACK, and TRANSFER CASK are not ASME Code stamped vessels, none of the specifications, reports, certificates, or other general requirements specified by NCA are required. In lieu of a Design Specification and Design Report, the HI-STORM FSAR includes the design criteria, service conditions, and load combinations for the design and operation of the HI-STORM 100 System as well as the results of the stress analyses to demonstrate that applicable Code stress limits are met. Additionally, the fabricator is not required to have an ASME-certified QA program. All important-to-safety activities are governed by the NRG-approved Holtec QA program.
Because the cask components are not certified to the Code, the terms "Certificate Holder" and "Inspector" are not germane to the manufacturing of NRG-certified cask components. To eliminate ambiguity, the responsibilities assigned to the Certificate Holder in the various articles of Subsections NB, NG, and NF of the Code, as applicable, shall be interpreted to apply to the NRC Certificate of Compliance (CoC) holder (and by extension, to the component fabricator) if the requirement must be fulfilled. The Code term "Inspector" means the QNQC personnel of the Coe holder and its vendors assigned to oversee and inspect the manufacturing process.
MPC enclosure vessel is designed and will be fabricated in accordance with ASME Code, Section Ill, Subsection NB to the maximum practical extent, but Code stamping is not required.
I Renewed Amendment No. 2
Design Features 3.0 Table 3-1 (page 2 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory ASME Code Measures Section/Article MPC basket NB-1130 NB-1132.2(d)
The MPC basket supports (nonpressure-retaining supports and requires that the first structural attachments)and lift lugs (nonstructural lift lugs connecting weld of a attachments (relative to the function of lifting a loaded nonpressure-MPC) that are used exclusively for lifting an empty retaining structural MPC) are welded to the inside of the pressure-retaining attachment to a MPC shell, but are not designed in accordance with component shall be Subsection NB. The basket supports and associated considered part of attachment welds are designed to satisfy the stress the component limits of Subsection NG and the lift lugs and associated unless the weld is attachment welds are designed to satisfy the stress more than 2t from the limits of Subsection NF, as a minimum. These pressure-retaining attachments and their welds are shown by analysis to portion of the meet the respective stress limits for their service component, where t conditions. Likewise, non-structural items, such as is the nominal shield plugs, spacers, etc. if used, can be attached to thickness of the pressure-retaining parts in the same manner.
pressure-retaining material.
NB-1 132.2(e) requires that the first connecting weld of a welded nonstructural attachment to a component shall conform to NB-4430 if the connecting weld is within 2t from the pressure-retaining portion of the component.
MPC NB-2000 Requires materials to' Materials will be supplied by Holtec-approved suppliers be supplied by with Certified Material Test Reports (CMTRs) in ASME-approved accordance with NB-2000 requirements.
material supplier.
Certificate of Compliance No. 1014 Appendix B 3-5 Renewed Amendment No. 2
Design Features 3.0 Table 3-1 (page 3 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory ASME Code Measures Section/Article MPC, MPC NB-3100 Provides These requirements are not applicable. The HI-basket NG-31 00 requirements for STORM FSAR, serving as the Design Specification, assembly, HI-NF-3100 determining design establishes the service conditions and load STORM loading conditions, combinations for the storage system.
OVERPACK such as pressure, and HI-TRAC temperature, and TRANSFER mechanical loads.
CASK MPC NB-3350 NB-3352.3 requires, Due to MPC basket-to-shell interface requirements, the for Category C joints, MPC shell-to-baseplate weld joint design (designated that the minimum Category C) does not include a reinforcing fillet weld or dimensions of the a bevel in the MPC baseplate, which makes it different welds and throat than any of the representative configurations depicted in thickness shall be as Figure NB-4243-1. The transverse thickness of this weld shown in Figure NB-is equal to the thickness of the adjoining shell (1/2 inch).
4243-1.
The weld is designed as a full penetration weld that receives VT and RT or UT, as well as final surface PT examinations. Because the MPC shell design thickness is considerably larger than the minimum thickness required by the Code, a reinforcing fillet weld that would intrude into the MPC cavity space is not included. Not including this fillet weld provides for a higher quality radiographic examination of the full penetration weld.
From the standpoint of stress analysis, the fillet weld serves to reduce the local bending stress (secondary stress) produced by the gross structural discontinuity defined by the flat plate/shell junction. In the MPC design, the shell and baseplate thicknesses are well beyond that required to meet their respective membrane stress intensity limits.
I Certificate of Compliance No. 1014 Appendix B 3-6 Renewed Amendment No. 2
Design Features 3.0 Table 3-1 (page 4 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement ASME Code Section/ Article MPC,MPC NB-4120 NB-4121.2, NG-Basket NG-4120 4121.2, and NF-Assembly, HI-NF-4120 4121.2 provide STORM requirements for OVERPACK repetition of tensile or steel impact tests for structure, and material subjected to HI-TRAC heat treatment during TRANSFER fabrication or CASK steel installation.
structure MPC,MPC NB-4220 Requires certain basket NF-4220 forming tolerances to assembly, HI-be met for cylindrical, STORM conical, or spherical OVERPACK shells of a vessel.
steel structure, and HI-TRAC TRANSFER CASK steel structure MPC Lid and NB-4243 Full penetration Closure Ring welds required for Welds Category C Joints (flat head to main shell per NB-3352.3).
Certificate of Compliance No. 1014 Appendix B 3-7 Alternative, Justification & Compensatory Measures In-shop operations of short duration that apply heat to a component, such as plasma cutting of plate stock, welding, machining, coating, and pouring of lead are not, unless explicitly stated by the Code, defined as heat treatment operations.
For the steel parts* in the HI-STORM 100 System components, the duration for which a part exceeds the off-normal temperature limit defined in Chapter 2 of the FSAR shall be limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a particular manufacturing process (such as the HI-TRAC lead pouring process).
The cylindricity measurements on the rolled shells are not specifically recorded in the shop travelers, as would be the case for a Code-stamped pressure vessel.
Rather, the requirements on inter-component clearances (such as the MPG-to-TRANSFER CASK) are guaranteed through fixture-controlled manufacturing. The fabrication specification and shop procedures ensure that all dimensional design objectives, including inter-component annular clearances are satisfied. The dimensions required to be met in fabrication are chosen to meet the functional requirements of the dry storage components. Thus, although the post-forming Code cylindricity requirements are not evaluated for compliance (directly, they are indirectly satisfied (actually exceeded) in the final manufactured components.
MPC lid and closure ring are not full penetration welds.
They are welded independently to provide a redundant seal. Additionally, a weld efficiency factor of 0.45 has been applied to the analyses of these welds.
Renewed Amendment No. 2
Design Features 3.0 Table 3-1 (page 5 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory ASME Code Measures Section/Article MPC Lid to NB-5230 Radiographic (RT) or Only UT or multi-layer liquid penetrant (PT)
Shell Weld ultrasonic (UT) examination is permitted. If PT alone is used, at a examination required minimum, it will include the root and final weld layers and each approximately 3/8 inch of weld depth.
MPC Closure NB-5230 Radiographic (RT) or Root (if more than one weld pass is required) and final Ring, Vent ultrasonic (UT) liquid penetrant examination to be performed in and Drain examination required accordance with NB-5245. The closure ring provides Cover Plate independent redundant closure for vent and drain cover Welds plates.
MPC NB-6111 All completed The MPC enclosure vessel is seal welded in the field Enclosure pressure retaining following fuel assembly loading. The MPC enclosure Vessel and systems shall be vessel shall then be pressure tested as defined in Lid pressure tested.
Chapter 9. Accessibility for leakage inspections preclude a Code compliant pressure test. All MPC enclosure vessel welds (except closure ring and vent/drain cover plate) are inspected by volumetric examination, except the MPC lid-to-shell weld shall be verified by volumetric or multi-layer.PT examination. If PT alone is used, at a minimum, it must include the root and final layers and each approximately 3/8 inch of weld depth. For either UT or PT, the maximum undetectable flaw size must be demonstrated to be less than the critical flaw size. The critical flaw size must be determined in accordance with ASME Section Xl methods. The critical flaw size shall not cause the primary stress limits of NB-3000 to be exceeded.
The inspection results, including relevant findings (indications), shall be made a permanent part of the user's records by video, photographic, or other means which provide an equivalent retrievable record of weld integrity. The video or photographic records should be taken during the final interpretation period described in ASME Section V, Article 6, T-676. The vent/drain cover plate and the closure ring welds are confirmed by liquid penetrant examination. The inspection of the weld must be performed by qualified personnel and shall meet the acceptance requirements of ASME Code Section III, NB-5350 for PT or NB-5332 for UT.
I I
I Certificate of Compliance No. 1014 Appendix B 3-8 Renewed Amendment No. 2
Design Features 3.0 Table 3-1 (page 6 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory ASME Code Measures Section/Article MPC NB-7000 Vessels are required No overpressure protection is provided. The function Enclosure to have overpressure of the MPC enclosure vessel is to contain the Vessel protection radioactive contents under normal, off-normal, and accident conditions. The MPC vessel is designed to withstand maximum internal pressure considering 100% fuel rod failure and maximum accident temperatures.
MPC NB-8000 States requirements The HI-STORM100 System is to be marked and Enclosure for nameplates, identified in accordance with 1 OCFR71 and 1 OCFR72 Vessel stamping and reports requirements. Code stamping is not required. QA data per NCA-8000.
package to be in accordance with Holtec approved QA program.
MPC Basket NG-2000 Requires materials to Materials will be supplied by Holtec-approved supplier Assembly be supplied by with CMTRs in accordance with NG-2000 ASME-approved requirements.
material supplier.
Certificate of Compliance No. 1014 Appendix B 3-9 Renewed Amendment No. 2
Design Features 3.0 Table 3-1 (page 6 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory ASME Code Measures Section/Article MPC NB-7000 Vessels are required No overpressure protection is provided. The function Enclosure to have overpressure of the MPC enclosure vessel is to contain the Vessel protection radioactive contents under normal, off-normal, and accident conditions. The MPC vessel is designed to withstand maximum internal pressure considering 100% fuel rod failure and maximum accident temperatures.
MPC NB-8000 States requirements The HI-STORM100 System is to be marked and Enclosure for nameplates, identified in accordance with 10CFR71 and 10CFR72 Vessel stamping and reports requirements. Code stamping is not required. QA data per NCA-8000.
package to be in accordance with Holtec approved QA program.
MPC Basket NG-2000 Requires materials to Materials will be supplied by Holtec-approved supplier Assembly be supplied by with CMTRs in accordance with NG-2000 ASME-approved requirements.
material supplier.
Certificate of Compliance No. 1014 Appendix B 3-9 Renewed Amendment No. 2
Design Features 3.0 Table 3-1 (page 7 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory ASME Code Measures Section/Article MPC basket NG-4420 NG-4427(a) allows a Modify the Code requirement (intended for core support assembly fillet weld in any structures) with the following text prepared to accord with single continuous the geometry and stress analysis imperatives for the fuel weld to be less than basket: For the longitudinal MPC basket fillet welds, the the specified fillet following criteria apply: 1) The specified fillet weld throat weld dimension by dimension must be maintained over at least 92 percent not more than 1/16 of the total weld length. All regions of undersized weld inch, provided that must be less than 3 inches long and separated from each the total undersize other by at least 9 inches. 2) Areas of undercuts and portion of the weld porosity beyond that allowed by the applicable ASME does not exceed 10 Code shall not exceed 1/2 inch in weld length. The total percent of the length length of undercut and porosity over any 1-foot length of the weld. Individual shall not exceed 2 inches. 3) The total weld length in undersize weld which items (1) and (2) apply shall not exceed a total of portions shall not 10 percent of the overall weld length. The limited access exceed 2 inches in of the MPC basket panel longitudinal fillet welds makes length.
it difficult to perform effective repairs of these welds and creates the potential for causing additional damage to the basket assembly (e.g., to the neutron absorber and its sheathing) if repairs are attempted. The acceptance criteria provided in the foregoing have been established to comport with the objectives of the basket design and preserve the margins demonstrated in the supporting stress analysis.
From the structural standpoint, the weld acceptance criteria are established to ensure that any departure from the ideal, continuous fillet weld seam would not alter the primary bending stresses on which the design of the fuel baskets is predicated. Stated differently, the permitted weld discontinuities are limited in size to ensure that they remain classifiable as local stress elevators ("peak stress", F, in the ASME Code for which specific stress intensity limits do not apply).
MPC Basket NG-8000 States requirements The HI-STORM100 System is to be marked and Assembly for nameplates, identified in accordance with 1 OCFR71 and 1 OCFR72 stamping and reports requirements. Code stamping is not required. The per NCA-8000.
MPC basket data package to be in accordance with Holtec approved QA program.
OVERPACK NF-2000 Requires materials to Materials will be supplied by Holtec-approved supplier Steel be supplied by with CMTRs in accordance with NF-2000 Structure ASME-approved requirements.
material supplier.
Certificate of Compliance No. 1014 Appendix B 3-10 Renewed Amendment No. 2
Design Features 3.0 Table 3-1 (page 8 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory ASME Code Measures Section/Article TRANSFER NF-2000 Requires materials to Materials will be supplied by Holtec-approved supplier CASK Steel be supplied by with CMTRs in accordance with NF-2000 Structure ASME-approved requirements.
material supplier.
OVERPACK NF-4441 Requires special The margins of safety in these welds under loads Baseplate and examinations or experienced during lifting operations or accident Lid Top Plate requirements for conditions are quite large. The OVERPACK baseplate welds where a welds to the inner shell, pedestal shell, and radial primary member of plates are only loaded during lifting conditions and have thickness 1 inch or large safety factors during lifting. Likewise, the top lid greater is loaded to plate to lid shell weld has a large structural margin transmit loads in the under the inertia loads imposed during a non-through thickness mechanistic tipover event.
direction.
OVERPACK NF-3256 Provides Welds for which no structural credit is taken are Steel NF-3266 requirements for identified as "Non-NF" welds in the design drawings.
Structure welded joints.
These non-structural welds are specified in accordance with the pre-qualified welds of AWS D1.1. These welds shall be made by welders and weld procedures.
qualified in accordance with AWS D1.1 or ASME Section IX.
Welds for which structural credit is taken in the safety analyses shall meet the stress limits for NF-3256.2, but are not required to meet the joint configuration requirements specified in these Code articles. The geometry of the joint designs in the cask structures are based on the fabricability and accessibility of the joint, not generally contemplated by this Code section governing supports.
I I
I Certificate of Compliance No. 1014 Appendix B 3-11 Renewed Amendment No. 2
Design Features 3.0 Table 3-1 (page 9 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory ASME Code Measures Section/Article HI-STORM NF-3320 NF-3324.6 and NF-These Code requirements are applicable to linear OVERPACK NF-4720 4720 provide structures wherein bolted joints carry axial, shear, as well and HI-TRAC requirements for as rotational (torsional) loads. The OVERPACK and TRANSFER bolting TRANSFER CASK bolted connections in the structural CASK load path are qualified by design based on the design loadings defined in the FSAR.
Bolted joints in these components see no shear or torsional loads under normal storage conditions. Larger clearances between bolts and holes may be necessary to ensure shear interfaces located elsewhere in the structure engage prior to the bolts experiencing shear loadings (which occur only during side impact scenarios).
Bolted joints that are subject to shear loads in accident conditions are qualified by appropriate stress analysis.
Larger bolt-to-hole clearances help ensure more efficient operations in making these bolted connections, thereby minimizing time spent by operations personnel in a radiation area. Additionally, larger bolt-to-hole clearances allow interchangeability of the lids from one particular fabricated cask to another.
I Certificate of Compliance No. 1014 Appendix B 3-12 Renewed Amendment No. 2
DESIGN FEATURES (continued) 3.4 Site-Specific Parameters and Analyses Design Features 3.0 Site-specific parameters and analyses that will require verification by the system user are, as a minimum, as follows:
1.
The temperature of 80° F is the maximum average yearly temperature.
2.
The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40° F and less than 125° F.
3.
- a.
The resultant horizontal acceleration (vectorial sum of two horizontal Zero Period Accelerations (ZPAs) at a three-dimensional seismic site), GH, and vertical ZPA, Gv, on the top surface of the ISFSI pad, expressed as fractions of 'g', shall satisfy the following inequality:
whereµ is either the Coulomb friction coefficient for the cask/lSFSI pad interface or the ratio r/h, where 'r' is the radius of the cask and 'h' is the height of the cask center-of-gravity above the ISFSI pad surface. The above inequality must be met for both definitions ofµ, but only applies to ISFSls where the casks are deployed in a freestanding configuration. Unless demonstrated by appropriate testing that a higher coefficient of friction value is appropriate for a specific ISFSI, the value used shall be 0.53. If acceleration time-histories on the ISFSI pad surface are available, GH and Gv may be the coincident values of the instantaneous net horizontal and vertical accelerations. If instantaneous accelerations are used, the inequality shall be evaluated at each time step in the acceleration time history over the total duration of the seismic event.
If this static equilibrium based inequality cannot be met, a dynamic analysis of the cask/lSFSI pad assemblage with appropriate recognition of soil/structure interaction effects shall be performed to ensure that the casks will not tip over or undergo excessive sliding under the site's Design Basis Earthquake.
Certificate of Compliance No. 1014 Appendix B Table 3-2 (not used) 3-13 (continued)
Renewed Amendment No. 2
DESIGN FEATURES 3.4 Site-Specific Parameters and Analyses (continued)
Design Features 3.0 b.
For free-standing casks, under environmental conditions that may degrade the pad/cask interface friction (such as due to icing) the response of the casks under the site's Design Basis Earthquake shall be established using the best estimate of the friction coefficient in an appropriate analysis model. The analysis should demonstrate that the earthquake will not result in cask tipover or cause a cask to fall off the pad. In addition, impact between casks should be precluded, or should be considered an accident for which the maximum g-load experienced by the stored fuel shall be limited to 45 g's.
c.
For those ISFSI sites with design basis seismic acceleration values higher than those allowed for free-standing casks, the HI-STORM 100 System shall be anchored to the ISFSI pad. The site seismic characteristics and the anchorage system shall meet the following requirements:
i.
The site acceleration response spectra at the top of the ISFSI pad shall have ZPAs that meet the following inequalities:
AND Gv.$1.5 Where:
GH is the vectorial sum of the two horizontal ZPAs at a three-dimensional seismic site ( or the horizontal ZPA at a two-dimensional site) and Gv is the vertical ZPA.
ii.
Each HI-STORM 100 dry storage cask shall be anchored with twenty-eight (28), 2-inch diameter studs and compatible nuts of material suitable for the expected ISFSI environment.
The studs shall meet the following requirements:
Yield Strength at Ambient Temperature:.2:, 80 ksi Ultimate Strength at Ambient Temperature:.2:, 125 ksi Initial Tensile Pre-Stress:.2:, 55 ksi AND.$ 65 ksi NOTE:
The above anchorage specifications are required for the seismic (continued)
Certificate of Compliance No. 1014 Appendix B 3-14 Renewed Amendment No. 2
Design Features 3.0 DESIGN FEATURES 3.4 Site-Specific Parameters and Analyses (continued) spectra defined in item 3.4.3.b.i. Users may use fewer studs or those of different diameter to account for site-specific seismic spectra less severe than those specified above. The embedment design shall comply with Appendix B of ACI-349-97. A later edition of this Code may be used, provided a written reconciliation is performed.
iii.
Embedment Concrete Compressive Strength: > 4,000 psi at 28 days
- 4.
The analyzed flood condition of 15 fps water velocity and a height of 125 feet of water (full submergence of the loaded cask) are not exceeded.
- 5.
The potential for fire and explosion shall be addressed, based on site-specific considerations. This includes the condition that the on-site transporter fuel tank will contain no more than 50 gallons of diesel fuel while handling a loaded OVERPACK or TRANSFER CASK.
- 6.
- a.
For free-standing casks, the ISFSI pad shall be verified by analysis to limit cask deceleration during design basis drop and non-mechanistic tip-over events to
< 45 g's at the top of the MPC fuel basket. Analyses shall be performed using methodologies consistent with those described in the HI-STORM 100 FSAR.
A lift height above the ISFSI pad is not required to be established if the cask is lifted with a device designed in accordance with ANSI N14.6 and having redundant drop protection features.
- b.
For anchored casks, the ISFSI pad shall be designed to meet the embedment requirements of the anchorage design. A cask tip-over event for an anchored cask is not credible. The ISFSI pad shall be verified by analysis to limit cask deceleration during a design basis drop event to < 45 g's at the top of the MPC fuel basket, except as provided for in this paragraph below. Analyses shall be performed using methodologies consistent with those described in the HI-STORM 100 FSAR. A lift height above the ISFSI pad is not required to be established if the cask is lifted with a device design in accordance with ANSI N14.6 and having redundant drop protection features.
- 7.
In cases where engineered features (i.e., berms and shield walls) are used to ensure that the requirements of 1 OCFR72.1 04(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category.
(continued)
Certificate of Compliance No. 1014 Appendix B 3-15 Renewed Amendment No. 2
Design Features 3.0 DESIGN FEATURES 3.4 Site-Specific Parameters and Analyses (continued)
- 8.
LOADING OPERATIONS, TRANSPORT OPERATIONS, and UNLOADING OPERATIONS shall only be conducted with working area ambient temperatures > 00 F.
- 9.
For those users whose site-specific design basis includes an event or events (e.g.,
flood) that result in the blockage of any OVERPACK inlet or outlet air ducts for an extended period of time (i.e, longer than the total Completion Time of LCO 3.1.2), an analysis or evaluation may be 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.
(continued)
Certificate of Compliance No. 1014 Appendix B 3-16 Renewed Amendment No. 2
DESIGN FEATURES Design Features 3.0 3.5 Cask Tran sf er Facility (CTF}
3.5.1 TRANSFER CASK and MPC Lifters Lifting of a loaded TRANSFER CASK and MPG using devices that are not integral to structures governed by 10 CFR Part 50 shall be performed with a CTF that is designed, operated, fabricated, tested, inspected, and maintained in accordance with the guidelines of NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" and the below clarifications. The CTF Structure requirements below do not apply to heavy loads bounded by the regulations of 1 0 CFR Part 50.
3.5.2 CTF Structure Requirements.
3.5.2.1 Cask Transfer Station and Stationary Lifting Devices
- 1.
- 2.
- 3.
- 4.
The metal weldment structure of the CTF structure shall be designed to comply with the stress limits of ASME Section Ill, Subsection NF, Class 3 for linear structures. The applicable loads, load combinations, and associated service condition definitions are provided in Table 3-3. All compression loaded members shall satisfy the buckling criteria of ASME Section Ill, Subsection NF.
If a portion of the CTF structure is constructed of reinforced concrete, then the factored load combinations set forth in ACl-318 (89} for the loads defined in Table 3-3 shall apply.
The TRANSFER CASK and MPG lifting device used with the CTF shall be designed,* fabricated, operated, tested, inspected and maintained in accordance with NUREG-0612, Section 5.1.
The CTF shall be designed, constructed, and evaluated to ensure that if the MPG is dropped during inter-cask transfer operations, its confinement boundary would not be breached. This requirements applies to CTFs with either stationary or mobile lifting devices.
(continued)
Certificate of Compliance No. 1014 Appendix B 3-17 Renewed Amendment No. 2
Design Features 3.0 DESIGN FEATURES 3.5.2.2 Mobile Lift Devices If a mobile lifting device is used as the lifting device, in lieu of a stationary lifting device, is shall meet the guidelines of NUREG- 0612, Section 5.1, with the following clarifications:
- 1. Mobile lifting devices shall have a minimum safety factor of two over the allowable load table for the lifting device in accordance with the guidance of NUREG-0612, Section 5.1.6(1 )(a) and shall be capable of stopping and holding the load during a Design Basis Earthquake (DBE) event.
- 2.
Mobile lifting devices shall conform to meet the requirements of ANSI B30.5, "Mobile and Locomotive Cranes," in lieu of the requirements of ANSI B30.2, "Overhead and Gantry Cranes."
- 3.
Mobile cranes are not required to meet the requirements of NUREG-0612, Section 5.1.6(2) for new cranes.
- 4.
Horizontal movements of the TRANSFER CASK and MPC using a mobile crane are prohibited.
(continued)
Certificate of Compliance No. 1014 Appendix B 3-18 Renewed Amendment No. 2
Design Features 3.0 DESIGN FEATURES Table 3-3 Load Combinations and Service Condition Definitions for the CTF Structure (Note 1)
Load Combination ASME IlIl Service Condition Comment for Definition of Allowable Stress D*
All primary load bearing Level A members must satisfy Level D+S A stress limits D + M + W' Factor of safety against (Note 2) overturning shall be > 1.1 D + F Level D D+E D + Y_
D = Dead load D* = Apparent dead load S = Snow and ice load for the CTF site M = Tornado missile load for the CTF site W' = Tornado wind load for the CTF site F = Flood load for the CTF site E = Seismic load for the CTF site Y = Tsunami load for the CTF site Notes:
- 1. The reinforced concrete portion of the CTF structure shall also meet the factored combinations of loads set forth in ACI-318(89).
- 2.
Tornado missile load may be reduced or eliminated based on a PRA for the CTF site.
Certificate of Compliance No. 1014 Appendix B 3-19 Renewed Amendment No. 2
DESIGN FEATURES 3.6 Forced Helium Dehydration System 3.6.1
System Description
Design Features 3.0 Use of the Forced Helium Dehydration (FHD) system, (a closed-loop system) is an alternative to vacuum drying the MPC for moderate burn up fuelR 45,000 MWD/MTU) and mandatory for drying MPCs containing one or more high burn up fuel assemblies.
The FHD system shall be designed for normal operation (i.e., excluding startup and shutdown ramps) in accordance with the criteria in Section 3.6.2.
3.6.2 Design Criteria 3.6.2.1 The temperature of the helium gas in the MPC shall be at least 15°F higher than the saturation temperature at coincident pressure.
3.6.2.2 The pressure in the MPC cavity space shall be.s 60.3 psig (75 psia).
3.6.2.3 The hourly recirculation rate of helium shall be S 1 0 times the nominal helium mass backfilled into the MPC for fuel storage operations.
3.6.2.4 The partial pressure of the water vapor in the MPC cavity will not exceed 3 torr. The limit is met if the gas temperature at the demoisturizer outlet is verified by measurement to remain.s 21 °F for a period of 30 minutes or if the dew point of the gas exiting the MPC is verified by measurement to remain.s 22.9°F forS 30 minutes.
3.6.2.5 The condensing module shall be designed to de-vaporize the recirculating helium gas to a dew point.s 120°F.
3.6.2.6 The demoisturizing module shall be configured to be introduced into its helium conditioning function after the condensing module has been operated for the required length of time to assure that the bulk moisture vaporization in the MPC (defined as Phase 1 in FSAR Appendix 2.B) has been completed.
3.6.2.7 The helium circulator shall be sized to effect the minimum flow rate of circulation required by these design criteria.
3.6.2.8 The pre-heater module shall be engineered to ensure that the temperature of the helium gas in the MPC meets these design criteria.
Certificate of Compliance No. 1014 Appendix B 3-20 (continued)
Renewed Amendment No. 2
DESIGN FEATURES 3.6 Forced Helium Dehydration System (continued) 3.6.3 Fuel Cladding Temperature Design Features 3.0 A steady-state thermal analysis of the MPC under the forced helium flow scenario shall be performed using the methodology described in HI-STORM 100 FSAR Section 4.4, with due recognition of the forced convection process during FHD system operation. This analysis shall demonstrate that the peak temperature of the fuel cladding under the most adverse condition of FHD system operation, is below the peak cladding temperature limit for normal conditions of storage for the applicable fuel type (PWR or BWR) and cooling time at the start of dry storage.
3.6.4 Pressure Monitoring During FHD Malfunction During an FHD malfunction event, described in HI-STORM 100 FSAR Section 11.1 as a loss of helium circulation, the system pressure must be monitored to ensure that the conditions listed therein are met.
Certificate of Compliance No. 1014 Appendix B
. 3-21 Renewed Amendment No. 2
DESIGN FEATURES 3.7 Supplemental Cooling System
- 3. 7.1
System Description
Design Features 3.0 The SCS is a water circulation system for cooling the MPC inside the HI-TRAC transfer cask during on-site transport. Use of the Supplemental Cooling System (SCS) is required for post-backfill HI-TRAC operations of an MPC containing one or more high burnup (> 45,000 MWD/MTU) fuel assemblies. The SCS shall be designed for normal operation (i.e., excluding startup and shutdown ramps) in accordance with the criteria in Section 3.7.2.
3.7.2 Design Criteria
- 3. 7.2.1 The system shall consist of a skid-mounted coolant pump and an air-cooled heat exchanger.
3.7.2.2 The pump shall be sized to limit the coolant temperature rise (from annulus inlet to outlet) to a reasonably low value (202F) and the air-cooled heat exchanger sized for the design basis heat load at an ambient air temperature of 1002F. The pump and aircooler fan shall be powered by electric motors with a backup power supply for uninterrupted operation.
3.7.2.3 The system shall utilize a contamination-free fluid medium in contact with the external surfaces of the MPC and inside surfaces of the HI -TRAC transfer cask to minimize corrosion.
3.7.2.4 All passive components such as tubular heat exchangers, manually operated valves and fittings shall be designed to applicable standards (TEMA, ANSI).
3.7.2.5 The heat dissipation capacity of the SCS shall be equal to or greater than the minimum necessary to ensure that the peak cladding temperature is below 4002C (7522F). All heat transfer surfaces in heat exchangers shall be assumed to be fouled to the maximum limits specified in a widely used heat exchanger equipment standard such as the Standards of Tubular Exchanger Manufacturers Association.
3.7.2.6 The coolant utilized to extract heat from the MPC shall be high purity water.
Antifreeze may be used to prevent water from freezing if warranted by operating conditions.
Certificate of Compliance No. 1014 Appendix B 3-22 Renewed Amendment No. 2
DESIGN FEATURES 3.7 Supplemental Cooling System (continued)
Design Features 3.0
- 3. 7.2. 7 All pressure boundaries (as defined in the ASME Boiler and Pressure Vessel Code,Section VIII Division 1) shall have pressure ratings that are greater than the maximum system operating pressure by at least 15 psi.
3.7.2.8 All ASME Code components shall comply with Section VIII Division 1 of the ASME Boiler and Pressure Vessel Code.
3.7.2.9 All gasketed and packed joints shall have a mirJimum design pressure rating of the pump shut-off pressure plus 15 psi.
Certificate of Compliance No. 1014 Appendix B 3-23 Renewed Amendment No. 2
Design Features 3.0 DESIGN FEATURES 3.8 Combustible Gas Monitoring During MPC Lid Welding During MPC lid-to-shell welding operations, combustible gas monitoring of the space under the MPC lid is required, to ensure that there is no combustible mixture present in the welding area.
Certificate of Compliance No. 1014 Appendix B 3-24 Renewed Amendment No. 2