ML22098A249
| ML22098A249 | |
| Person / Time | |
|---|---|
| Site: | Holtec |
| Issue date: | 01/31/2023 |
| From: | Division of Fuel Management |
| To: | |
| Kris Banovac NMSS/DFM/STLB 301-415-7116 | |
| Shared Package | |
| ML22098A233 | List:
|
| References | |
| 001028/L-2020-RNW-0007 RIN 3150-AK86, NRC-2022-0109 | |
| Download: ML22098A249 (1) | |
Text
RENEWED CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX B APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STORM 100 CASK SYSTEM AMENDMENT NO. 4
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 . . . . . . . . . . . . . . . . . . 3-1 3.3 Codes and Standards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-2 3.4 Site Specific Parameters and Analyses . . . . . . . . . . . . . . . . . . . . . . . . . 3-8 3.5 Cask Transfer Facility (CTF) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-12 3.6 Forced Helium Dehydration System . . . . . . . . . . . . . . . . . . . . . . . . . . 3-15 Table 3-1 List of ASME Code Alternatives for HI-STORM 100 System . . . . . . . . . 3-3 Table 3-2 Representative DBE Acceleration Values to Prevent HI-STORM 100 Sliding (µ = 0.53) . . . . . . . . . . . . . . . . . . . . . . . . 3-8 Table 3-3 Load Combinations and Service Condition Definitions For the CTF Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-14 Certificate of Compliance No. 1014 Appendix B i
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 The CASK TRANSFER FACILITY includes the following (CTF) components and equipment: (1) a Cask Transfer Structure 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 ASSEMBLY 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, missing structural components such as grid l spacers, whose structural integrity has been impaired such l that geometric rearrangement of fuel or gross failure of the cladding is expected based on engineering evaluations, or l 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.
DAMAGED FUEL CONTAINER DFCs are specially designed enclosures for (DFC) 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
- 5. Holtec Indian Point Unit 1 design FUEL DEBRIS FUEL DEBRIS is ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting these loose fuel assembly parts, or fuel assemblies with known or suspected defects which cannot be handled by normal means due to fuel cladding damage.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 1-1
Definitions 1.0 (continued) 1.0 Definitions (continued)
INTACT FUEL ASSEMBLY 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 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 MPC and end when the OVERPACK or TRANSFER CASK is suspended from or secured on the transporter. LOADING OPERATIONS does not included MPC transfer between the TRANSFER CASK and the OVERPACK.
MINIMUM ENRICHMENT MINIMUM ENRICHMENT is the minimum assembly average enrichment. Natural uranium blankets are not considered in determining minimum enrichment.
MULTI-PURPOSE CANISTER MPCs are the sealed spent nuclear fuel canisters which (MPC) 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 MPC provides the confinement boundary for the contained radioactive materials.
(continued)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 1-2
Definitions 1.0 1.0 Definitions (continued)
NON-FUEL HARDWARE 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), Neutron Source Assemblies (NSAs), water displacement guide tube plugs, orifice rod assemblies, and vibration suppressor inserts.
OVERPACK 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 MPC to the environs. The OVERPACK does not include the TRANSFER CASK.
PLANAR-AVERAGE PLANAR AVERAGE INITIAL ENRICHMENT is the INITIAL ENRICHMENT average of the distributed fuel rod initial enrichments within a given axial plane of the assembly lattice.
SPENT FUEL STORAGE An SFSC is a container approved for the storage of spent CASKS (SFSCs) fuel assemblies at the ISFSI. The HI-STORM 100 SFSC System consists of the OVERPACK and its integral MPC.
TRANSFER CASK TRANSFER CASKs are containers designed to contain the MPC during and after loading of spent fuel assemblies and to transfer the MPC to or from the OVERPACK. The HI-STORM 100 System employs either the 125-Ton or the 100-Ton HI-TRAC TRANSFER CASK, or for Indian Point Unit 1, the 75-Ton HI-TRAC 100D Version IP1.
TRANSPORT OPERATIONS 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 after LOADING OPERATIONS or before UNLOADING OPERATIONS. 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 MPC between the OVERPACK and the TRANSFER CASK.
(continued)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 1-3
Definitions 1.0 1.0 Definitions (continued)
UNLOADING OPERATIONS 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 MPC transfer between the TRANSFER CASK and the OVERPACK.
ZR ZR means any zirconium-based fuel cladding or fuel channel material authorized for use in a commercial nuclear power plant reactor.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 1-4
Approved Contents 2.0 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
- 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.
- a. For MPCs partially loaded with array/class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A fuel assemblies, all remaining ZR clad INTACT FUEL ASSEMBLIES in the MPC shall meet the decay heat generation limits for the 6x6A, 6x6B, 6x6C, 7x7A and 8x8A fuel assemblies.
- b. All BWR fuel assemblies may be stored with or without ZR channels with the exception of array/class 10x10D and 10x10E fuel assemblies, which may be stored with or without ZR or stainless steel channels.
2.1.2 Uniform Fuel Loading Any authorized fuel assembly may be stored in any fuel storage location, subject to other restrictions related to DAMAGED FUEL, FUEL DEBRIS, and NON-FUEL HARDWARE specified in the CoC.
(continued)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-1
Approved Contents 2.0 2.0 Approved Contents 2.1 Fuel Specifications and Loading Conditions (contd) 2.1.3 Regionalized Fuel Loading Users may choose to store fuel using regionalized loading in lieu of uniform loading to allow higher heat emitting fuel assemblies to be stored than would otherwise be able to be stored using uniform loading. Regionalized loading is limited to those fuel assemblies with ZR cladding. Figures 2.1-1 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 Renewed Amendment No. 4 Appendix B 2-2
Approved Contents 2.0 Figure 2.1-1 Fuel Loading Regions - MPC-24 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-3
Approved Contents 2.0 Figure 2.1-2 Fuel Loading Regions - MPC-24E/24EF Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-4
Approved Contents 2.0 Figure 2.1-3 Fuel Loading Regions - MPC-32/32F Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-5
Approved Contents 2.0 Figure 2.1-4 Fuel Loading Regions - MPC-68/68FF Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-6
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: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class.
- b. Initial Enrichment: As specified in Table 2.1-2 for the applicable fuel assembly array/class.
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 14x14D and Cooling time > 8 years and an average 15x15G burnup < 40,000 MWD/MTU.
ii. All Other Array/Classes Cooling time and average burnup as specified in Section 2.4.
iii. NON-FUEL HARDWARE As specified in Table 2.1-8.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-7
Approved Contents 2.0 Table 2.1-1 (page 2 of 39)
Fuel Assembly Limits I. MPC MODEL: MPC-24 (continued)
A. Allowable Contents (continued)
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D < 710 Watts and 15x15G ii All Other Array/Classes As specified in Section 2.4.
- e. Fuel Assembly Length: < 176.8 inches (nominal design)
- f. Fuel Assembly Width: < 8.54 inches (nominal design)
- g. Fuel Assembly Weight: < 1,680 lbs (including NON-FUEL HARDWARE)
B. Quantity per MPC: Up to 24 fuel assemblies.
C. Deleted.
D. DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS are not authorized for loading into the MPC-24.
E. One NSA is authorized for loading into the MPC-24.
Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, APSRs or NSAs 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 Renewed Amendment No. 4 Appendix B 2-8
Approved Contents 2.0 Table 2.1-1 (page 3 of 39)
Fuel Assembly Limits II. MPC 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: ZR or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array/class.
- b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for the applicable INITIAL ENRICHMENT: fuel assembly array/class.
- c. Initial Maximum Rod As specified in Table 2.1-3 for the applicable Enrichment: fuel assembly array/class.
- d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 6x6A, 6x6C, Cooling time > 18 years and an average 7x7A, and 8x8A: burnup < 30,000 MWD/MTU ii. Array/Class 8x8F Cooling time > 10 years and an average burnup < 27,500 MWD/MTU.
iii. Array/Classes 10x10D and Cooling time > 10 years and an average 10x10E burnup < 22,500 MWD/MTU.
iv. All Other Array/Classes As specified in Section 2.4.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-9
Approved Contents 2.0 Table 2.1-1 (page 4 of 39)
Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)
A. Allowable Contents (continued)
- e. Decay Heat Per Assembly:
- i. Array/Classes 6x6A, 6x6C, < 115 Watts 7x7A, and 8x8A ii. Array/Class 8x8F < 183.5 Watts.
iii. Array/Classes 10x10D and < 95 Watts 10x10E iv. All Other Array/Classes As specified in Section 2.4.
- f. Fuel Assembly Length: < 176.5 inches (nominal design)
- g. Fuel Assembly Width: < 5.85 inches (nominal design)
- h. Fuel Assembly Weight: < 700 lbs, including channels Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-10
Approved Contents 2.0 Table 2.1-1 (page 5 of 39)
Fuel Assembly Limits II. 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: ZR or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array/class.
- b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
- i. Array/Classes 6x6A, 6x6C, As specified in Table 2.1-3 for the applicable 7x7A, and 8x8A fuel assembly array/class.
ii. All Other Array/Classes 4.0 wt% 235U specified in Table 2.1-3
- c. Initial Maximum Rod As specified in Table 2.1-3 for the applicable Enrichment: fuel assembly array/class.
- d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 6x6A, 6x6C, Cooling time > 18 years and an average 7x7A,and 8x8A burnup < 30,000 MWD/MTU.
ii. Array/Class 8x8F Cooling time > 10 years and an average burnup < 27,500 MWD/MTU.
iii. Array/Classes 10x10D and Cooling time > 10 years and an average 10x10E burnup < 22,500 MWD/MTU.
iv. All Other Array Classes As specified in Section 2.4.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-11
Approved Contents 2.0 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 10x10D and < 95 Watts 10x10E iv. All Other Array/Classes As specified in Section 2.4.
- f. Fuel Assembly Length:
- 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 Renewed Amendment No. 4 Appendix B 2-12
Approved Contents 2.0 Table 2.1-1 (page 7 of 39)
Fuel Assembly Limits 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 As specified in Table 2.1-3 for fuel Enrichment: assembly array/class 6x6B.
- d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTIHM.
Assembly:
- e. Decay Heat Per Assembly: < 115 Watts
- f. Fuel Assembly Length: < 135.0 inches (nominal design)
- g. Fuel Assembly Width: < 4.70 inches (nominal design)
- h. Fuel Assembly Weight: < 400 lbs, including channels Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-13
Approved Contents 2.0 Table 2.1-1 (page 8 of 39)
Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)
A. Allowable Contents (continued)
- 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 Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTIHM.
Assembly:
- e. Decay Heat Per Assembly: < 115 Watts
- f. Fuel Assembly Length: < 135.0 inches (nominal design)
- g. Fuel Assembly Width: < 4.70 inches (nominal design)
- h. Fuel Assembly Weight: < 550 lbs, including channels and DFC Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-14
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: ZR
- b. Composition: 98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U.
- c. Number of Rods Per Thoria Rod Canister: < 18
- d. Decay Heat Per Thoria Rod Canister: < 115 Watts
- e. Post-irradiation Fuel Cooling Time A fuel post-irradiation cooling time > 18 years and Average Burnup Per Thoria and an average burnup < 16,000 Rod Canister: MWD/MTIHM.
- f. Initial Heavy Metal Weight: < 27 kg/canister
- g. Fuel Cladding O.D.: > 0.412 inches
- h. Fuel Cladding I.D.: < 0.362 inches
- i. Fuel Pellet O.D.: < 0.358 inches
- j. Active Fuel Length: < 111 inches
- k. Canister Weight: < 550 lbs, including fuel Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-15
Approved Contents 2.0 Table 2.1-1 (page 10 of 39)
Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)
B. Quantity per MPC:
- 1. Up to one (1) Dresden Unit 1 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 10x10D and 10x10E fuel assemblies in stainless steel channels must be stored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 - 50.
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 Renewed Amendment No. 4 Appendix B 2-16
Approved Contents 2.0 Table 2.1-1 (page 11 of 39)
Fuel Assembly Limits III. 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, 7x7A or 8x8A, and meet the following specifications:
- a. Cladding Type: ZR b Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for the INITIAL ENRICHMENT: applicable fuel assembly array/class.
- c. Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment: applicable fuel assembly array/class.
- d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTU.
Assembly:
- e. Decay Heat Per Assembly < 115 Watts
- f. Fuel Assembly Length: < 135.0 inches (nominal design)
- g. Fuel Assembly Width: < 4.70 inches (nominal design)
- h. Fuel Assembly Weight: < 400 lbs, including channels Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-17
Approved Contents 2.0 Table 2.1-1 (page 12 of 39)
Fuel Assembly Limits III. 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, 7x7A, or 8x8A, and meet the following specifications:
- a. Cladding Type: ZR
- b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for the INITIAL ENRICHMENT: applicable fuel assembly array/class.
- c. Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment: applicable fuel assembly array/class.
- d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTU.
Assembly:
- e. Decay Heat Per Assembly: < 115 Watts
- f. Fuel Assembly Length: < 135.0 inches (nominal design)
- g. Fuel Assembly Width: < 4.70 inches (nominal design)
- h. Fuel Assembly Weight: < 550 lbs, including channels and DFC Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-18
Approved Contents 2.0 Table 2.1-1 (page 13 of 39)
Fuel Assembly Limits III. 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, 7x7A, or 8x8A, and meet the following specifications:
- a. Cladding Type: ZR
- b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for the INITIAL ENRICHMENT: applicable original fuel assembly array/class.
c Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment: applicable original fuel assembly array/class.
- d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTU for the Assembly original fuel assembly.
- e. Decay Heat Per Assembly < 115 Watts
- f. Original Fuel Assembly Length < 135.0 inches (nominal design)
- g. Original Fuel Assembly Width < 4.70 inches (nominal design)
- h. Fuel Debris Weight < 550 lbs, including channels and DFC Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-19
Approved Contents 2.0 Table 2.1-1 (page 14 of 39)
Fuel Assembly Limits III. 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: ZR
- b. Maximum PLANAR- As specified in Table 2.1-3 for fuel AVERAGE INITIAL assembly array/class 6x6B.
ENRICHMENT:
- c. Initial Maximum Rod As specified in Table 2.1-3 for fuel Enrichment: assembly array/class 6x6B.
- d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTIHM.
Assembly:
- e. Decay Heat Per Assembly < 115 Watts
- f. Fuel Assembly Length: < 135.0 inches (nominal design)
- g. Fuel Assembly Width: < 4.70 inches (nominal design)
- h. Fuel Assembly Weight: < 400 lbs, including channels Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-20
Approved Contents 2.0 Table 2.1-1 (page 15 of 39)
Fuel Assembly Limits III. 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: ZR
- b. Maximum PLANAR- As specified in Table 2.1-3 for fuel AVERAGE INITIAL assembly array/class 6x6B.
ENRICHMENT:
- c. Initial Maximum Rod As specified in Table 2.1-3 for fuel Enrichment: assembly array/class 6x6B.
- d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTIHM.
Assembly:
- e. Decay Heat Per Assembly < 115 Watts
- f. Fuel Assembly Length: < 135.0 inches (nominal design)
- g. Fuel Assembly Width: < 4.70 inches (nominal design)
- h. Fuel Assembly Weight: < 550 lbs, including channels and DFC Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-21
Approved Contents 2.0 Table 2.1-1 (page 16 of 39)
Fuel Assembly Limits III. MPC 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: ZR
- b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for original INITIAL ENRICHMENT: fuel assembly array/class 6x6B.
- c. Initial Maximum Rod As specified in Table 2.1-3 for original Enrichment: fuel assembly array/class 6x6B.
- d. Post-irradiation Cooling Time Cooling time > 18 years and an average and Average Burnup Per burnup < 30,000 MWD/MTIHM for the Assembly: original fuel assembly.
- e. Decay Heat Per Assembly < 115 Watts
- f. Original Fuel Assembly Length: < 135.0 inches (nominal design)
- g. Original Fuel Assembly Width: < 4.70 inches (nominal design)
- h. Fuel Debris Weight: < 550 lbs, including channels and DFC Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-22
Approved Contents 2.0 Table 2.1-1 (page 17 of 39)
Fuel Assembly Limits III. MPC 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: ZR
- b. Composition: 98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U.
- c. Number of Rods Per Thoria Rod Canister: < 18
- d. Decay Heat Per Thoria Rod Canister: < 115 Watts
- e. Post-irradiation Fuel Cooling A fuel post-irradiation cooling time > 18 Time and Average Burnup Per years and an average burnup < 16,000 Thoria Rod Canister: MWD/MTIHM.
- f. Initial Heavy Metal Weight: < 27 kg/canister
- g. Fuel Cladding O.D.: > 0.412 inches
- h. Fuel Cladding I.D.: < 0.362 inches
- i. Fuel Pellet O.D.: < 0.358 inches
- j. Active Fuel Length: < 111 inches
- k. Canister Weight: < 550 lbs, including fuel Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-23
Approved Contents 2.0 Table 2.1-1 (page 18 of 39)
Fuel Assembly Limits III. 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 Renewed Amendment No. 4 Appendix B 2-24
Approved Contents 2.0 Table 2.1-1 (page 19 of 39)
Fuel Assembly Limits IV. MPC MODEL: MPC-24E 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: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class
- b. Initial Enrichment: As specified in Table 2.1-2 for the applicable fuel assembly array/class.
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 14x14D and Cooling time > 8 years and an average 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 Renewed Amendment No. 4 Appendix B 2-25
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 and < 710 Watts.
15x15G ii. All other Array/Classes As specified in Section 2.4.
- e. Fuel Assembly Length: < 176.8 inches (nominal design)
- f. Fuel Assembly Width: < 8.54 inches (nominal design)
- g. Fuel Assembly Weight: < 1,680 lbs (including NON-FUEL HARDWARE)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-26
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: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class
- b. Initial Enrichment: As specified in Table 2.1-2 for the applicable fuel assembly array/class.
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 14x14D and Cooling time > 8 years and an average 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 Renewed Amendment No. 4 Appendix B 2-27
Approved Contents 2.0 Table 2.1-1 (page 22 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 < 710 Watts.
and 15x15G ii. All Other Array/Classes As specified in Section 2.4.
- e. Fuel Assembly Length < 176.8 inches (nominal design)
- f. Fuel Assembly Width < 8.54 inches (nominal design)
- g. Fuel Assembly Weight < 1,680 lbs (including NON-FUEL HARDWARE and DFC)
B. 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. FUEL DEBRIS is not authorized for loading in the MPC-24E.
D. One NSA is 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, APSRs or NSAs 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 Renewed Amendment No. 4 Appendix B 2-28
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: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class
- b. Initial Enrichment: As specified in Table 2.1-2 for the applicable fuel assembly array/class.
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly
- i. Array/Classes 14x14D and Cooling time > 9 years and an average 15x15G burnup < 30,000 MWD/MTU or cooling time > 20 years and an average burnup <
40,000 MWD/MTU.
ii. Array/Class 14x14E Cooling time > 30 years.
An average burnup < 30,000 MWD/MTU with an enrichment > 3.5 wt. % 235U or, an average burnup < 10,000 MWD/MTU with an enrichment > 2.7 wt. % 235U and
< 3.5 wt. % 235U.
iii. All Other Array/Classes As specified in Section 2.4.
iv. NON-FUEL HARDWARE As specified in Table 2.1-8.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-29
Approved Contents 2.0 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 and < 500 Watts 15x15G ii. Array/Class 14x14E < 250 Watts iii. All Other Array/Classes As specified in Section 2.4.
- e. Fuel Assembly Length < 176.8 inches (nominal design)
- f. Fuel Assembly Width < 8.54 inches (nominal design)
- g. Fuel Assembly Weight < 1,680 lbs (including NON-FUEL HARDWARE)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-30
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: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class
- b. Initial Enrichment: As specified in Table 2.1-2 for the applicable fuel assembly array/class.
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 14x14D and Cooling time > 9 years and an average 15x15G burnup < 30,000 MWD/MTU or cooling time > 20 years and an average burnup <
40,000 MWD/MTU.
ii. Array/Class 14x14E Cooling time > 30 years.
An average burnup < 30,000 MWD/MTU with an enrichment > 3.5 wt. % 235U or, an average burnup < 10,000 MWD/MTU with an enrichment > 2.7 wt. % 235U and
< 3.5 wt. % 235U.
iii. All Other Array/Classes As specified in Section 2.4.
iv. NON-FUEL HARDWARE As specified in Table 2.1-8.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-31
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 < 500 Watts.
and 15x15G ii. Array/Class 14x14E < 250 Watts iii. All Other Array/Classes As specified in Section 2.4.
- e. Fuel Assembly Length < 176.8 inches (nominal design)
- f. Fuel Assembly Width < 8.54 inches (nominal design)
- g. Fuel Assembly Weight < 1,680 lbs (including NON-FUEL HARDWARE and DFC)
B. Quantity per MPC: With the exception of array/class 14x14E, up to 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 may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications. For array/class 14x14E, up to 32 INTACT FUEL ASSEMBLIES, and/or DAMAGED FUEL ASSEMBLIES stored in DAMAGED FUEL CONTAINERS.
C. FUEL DEBRIS is not authorized for loading in the MPC-32.
D. With the exception of array/class 14x14E, one NSA is authorized for loading in the MPC-32. For array/class 14x14E, Indian Point Unit 1, fuel assemblies may contain an antimony beryllium secondary source assembly. Up to 32 Indian Point Unit 1 secondary source assemblies may be stored in the MPC-32. Other NON-FUEL HARDWARE is not permitted to be stored with array/class 14x14E.
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, APSRs or NSAs 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 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-32
Approved Contents 2.0 fuel loading.
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: ZR or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array/class
- b. Maximum PLANAR-AVERAGE As specified in Table 2.1-3 for the applicable INITIAL ENRICHMENT: fuel assembly array/class.
- c. Initial Maximum Rod Enrichment As specified in Table 2.1-3 for the applicable fuel assembly array/class.
- e. Post-irradiation Cooling Time and Average Burnup Per Assembly
- i. Array/Classes 6x6A, 6x6B, Cooling time > 18 years and an average 6x6C, 7x7A, and 8x8A burnup < 30,000 MWD/MTU (or MTU/MTIHM).
ii. Array/Class 8x8F Cooling time > 10 years and an average burnup < 27,500 MWD/MTU.
iii. Array/Classes 10x10D and Cooling time > 10 years and an average 10x10E burnup < 22,500 MWD/MTU.
iv. All Other Array/Classes As specified in Section 2.4.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-33
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, < 115 Watts 6x6C, 7x7A, and 8x8A ii. Array/Class 8x8F < 183.5 Watts iii. Array/Classes 10x10D and < 95 Watts 10x10E iv. All Other Array/Classes As specified in Section 2.4.
- f. Fuel Assembly Length
- i. Array/Class 6x6A, 6x6B, < 135.0 inches (nominal design) 6x6C, 7x7A, or 8x8A ii. All Other Array/Classes < 176.5 inches (nominal design)
- g. Fuel Assembly Width
- i. Array/Class 6x6A, 6x6B, 6x6C, < 4.70 inches (nominal design) 7x7A, or 8x8A ii. All Other Array/Classes < 5.85 inches (nominal design)
- h. Fuel Assembly Weight
- i. Array/Class 6x6A, 6x6B, 6x6C, < 550 lbs, including channels 7x7A, or 8x8A ii. All Other Array/Classes < 700 lbs, including channels Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-34
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: ZR or Stainless Steel (SS) in accordance with Table 2.1-3 for the applicable fuel assembly array/class.
- b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT:
- i. Array/Classes 6x6A, 6x6B, As specified in Table 2.1-3 for the applicable 6x6C, 7x7A, and 8x8A. fuel assembly array/class.
ii. All Other Array Classes < 4.0 wt.% 235U.
- c. Initial Maximum Rod Enrichment As specified in Table 2.1-3 for the applicable fuel assembly array/class.
- d. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Class 6x6A, 6x6B, Cooling time > 18 years and an average 6x6C, 7x7A, or 8x8A burnup < 30,000 MWD/MTU (or MWD/MTIHM).
ii. Array/Class 8x8F Cooling time > 10 years and an average burnup < 27,500 MWD/MTU.
iii. Array/Class 10x10D and Cooling time > 10 years and an average 10x10E burnup < 22,500 MWD/MTU.
iv. All Other Array/Classes As specified in Section 2.4.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-35
Approved Contents 2.0 Table 2.1-1 (page 30 of 39)
Fuel Assembly Limits VI. MPC MODEL: MPC-68FF (continued)
A. Allowable Contents (continued)
- e. Decay Heat Per Assembly
- i. Array/Class 6x6A, 6x6B, 6x6C, < 115 Watts 7x7A, or 8x8A ii. Array/Class 8x8F < 183.5 Watts iii. Array/Classes 10x10D and < 95 Watts 10x10E iv. All Other Array/Classes As specified in Section 2.4.
- f. Fuel Assembly Length
- i. Array/Class 6x6A, 6x6B, 6x6C, < 135.0 inches (nominal design) 7x7A, or 8x8A ii. All Other Array/Classes < 176.5 inches (nominal design)
- g. Fuel Assembly Width
- i. Array/Class 6x6A, 6x6B, 6x6C, < 4.70 inches (nominal design) 7x7A, or 8x8A ii. All Other Array/Classes < 5.85 inches (nominal design)
- h. Fuel Assembly Weight
- i. Array/Class 6x6A, 6x6B, 6x6C, < 550 lbs, including channels and DFC 7x7A, or 8x8A ii. All Other Array/Classes < 700 lbs, including channels and DFC Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-36
Approved Contents 2.0 Table 2.1-1 (page 31 of 39)
Fuel Assembly limits 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:
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 10x10D and 10x10E fuel assemblies in stainless steel channels must be stored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 - 50.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-37
Approved Contents 2.0 Table 2.1-1 (page 32 of 39)
Fuel Assembly Limits VII. MPC 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: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class
- b. Initial Enrichment: As specified in Table 2.1-2 for the applicable fuel assembly array/class.
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 14x14D and Cooling time > 8 years and an average 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 Renewed Amendment No. 4 Appendix B 2-38
Approved Contents 2.0 Table 2.1-1 (page 33 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 and < 710 Watts.
15x15G ii. All other Array/Classes As specified in Section 2.4.
- e. Fuel Assembly Length: < 176.8 inches (nominal design)
- f. Fuel Assembly Width: < 8.54 inches (nominal design)
- g. Fuel Assembly Weight: < 1,680 lbs (including NON-FUEL HARDWARE)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-39
Approved Contents 2.0 Table 2.1-1 (page 34 of 39)
Fuel Assembly Limits VII. MPC 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: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class
- b. Initial Enrichment: As specified in Table 2.1-2 for the applicable fuel assembly array/class.
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 14x14D and Cooling time > 8 years and an average 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 Renewed Amendment No. 4 Appendix B 2-40
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 < 710 Watts.
and 15x15G ii. All Other Array/Classes As specified in Section 2.4.
- e. Fuel Assembly Length < 176.8 inches (nominal design)
- f. Fuel Assembly Width < 8.54 inches (nominal design)
- g. Fuel Assembly Weight < 1,680 lbs (including NON-FUEL HARDWARE and DFC)
B. 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. One NSA is 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, APSRs or NSAs 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 Renewed Amendment No. 4 Appendix B 2-41
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 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: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class
- b. Initial Enrichment: As specified in Table 2.1-2 for the applicable fuel assembly array/class.
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 14x14D and Cooling time > 9 years and an average 15x15G burnup < 30,000 MWD/MTU or cooling time > 20 years and an average burnup <
40,000 MWD/MTU.
ii. Array/Class 14x14E Cooling time > 30 years.
An average burnup < 30,000 MWD/MTU with an enrichment > 3.5 wt. % 235U or, an average burnup < 10,000 MWD/MTU with an enrichment > 2.7 wt. % 235U and
< 3.5 wt. % 235U.
iii. All Other Array/Classes As specified in Section 2.4.
iv. NON-FUEL HARDWARE As specified in Table 2.1-8.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-42
Approved Contents 2.0 Table 2.1-1 (page 37 of 39)
Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (contd)
A. Allowable Contents (contd)
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D < 500 Watts.
and 15x15G ii. Array/Class 14x14E < 250 Watts iii. All Other Array/Classes As specified in Section 2.4.
- e. Fuel Assembly Length < 176.8 inches (nominal design)
- f. Fuel Assembly Width < 8.54 inches (nominal design)
- g. Fuel Assembly Weight < 1,680 lbs (including NON-FUEL HARDWARE)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-43
Approved Contents 2.0 Table 2.1-1 (page 38 of 39)
Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (contd)
A. Allowable Contents (contd)
- 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: ZR or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array/class
- b. Initial Enrichment: As specified in Table 2.1-2 for the applicable fuel assembly array/class.
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Array/Classes 14x14D and Cooling time > 9 years and an average 15x15G burnup < 30,000 MWD/MTU or cooling time > 20 years and an average burnup <
40,000 MWD/MTU.
ii. Array/Class 14x14E Cooling time > 30 years.
An average burnup < 30,000 MWD/MTU with an enrichment > 3.5 wt. % 235U or, an average burnup < 10,000 MWD/MTU with an enrichment > 2.7 wt. % 235U and < 3.5 wt. % 235U.
iii. All Other Array/Classes As specified in Section 2.4.
iv. NON-FUEL HARDWARE As specified in Table 2.1-8.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-44
Approved Contents 2.0 Table 2.1-1 (page 39 of 39)
Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (contd)
A. Allowable Contents (contd)
- d. Decay Heat Per Fuel Storage Location:
- i. Array/Classes 14x14D < 500 Watts.
and 15x15G ii. Array/Class 14x14E < 250 Watts iii. All Other Array/Classes As specified in Section 2.3.
- e. Fuel Assembly Length < 176.8 inches (nominal design)
- f. Fuel Assembly Width < 8.54 inches (nominal design)
- g. Fuel Assembly Weight < 1,680 lbs (including NON-FUEL HARDWARE and DFC)
B. Quantity per MPC: With the exception of array/class 14x14E, 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. For array/class 14x14E, up to 32 INTACT FUEL ASSEMBLIES and/or DAMAGED FUEL ASSEMBLIES stored in DAMAGED FUEL CONTAINERS. FUEL DEBRIS from array/class 14x14E is not authorized for loading in the MPC-32F.
C. With the exception of array/class 14x14E, one NSA is permitted for loading in the MPC-32F. For array/class 14x14E, Indian Point Unit 1, fuel assemblies may contain an antimony beryllium secondary source assembly. Up to 32 Indian Point Unit 1 secondary source assemblies may be stored in the MPC-32F. Other NON-FUEL HARDWARE is not permitted to be stored with array/class 14x14E.
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, APSRs or NSAs 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 Renewed Amendment No. 4 Appendix B 2-45
Approved Contents 2.0 Table 2.1-2 (page 1 of 4)
PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 14x14A 14x14B 14x14C 14x14D 14x14E Array/Class Clad Material ZR ZR ZR SS SS Design Initial U
< 365 < 412 < 438 < 400 < 206 (kg/assy.) (Note 3)
Initial Enrichment (MPC-24, 24E and N/A
< 4.6 (24) < 4.6 (24) < 4.6 (24) < 4.0 (24) 24EF without soluble boron
< 5.0 < 5.0 < 5.0 < 5.0 credit) N/A (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF)
(wt % 235U)
(Note 7)
Initial Enrichment (MPC-24, 24E,
< 4.5 24EF, 32, or 32F
< 5.0 < 5.0 < 5.0 < 5.0 (MPC-32/32F with soluble boron only, Note 9) credit - see Note 5)
(wt % 235U)
No. of Fuel Rod 179 179 176 180 173 Locations Fuel Rod Clad O.D.
> 0.400 > 0.417 > 0.440 > 0.422 > 0.3415 (in.)
Fuel Rod Clad I.D.
< 0.3514 < 0.3734 < 0.3880 < 0.3890 < 0.3175 (in.)
Fuel Pellet Dia.
(in.) < 0.3444 < 0.3659 < 0.3805 < 0.3835 < 0.3130 (Note 8)
Fuel Rod Pitch (in.) < 0.556 < 0.556 < 0.580 < 0.556 Note 6 Active Fuel Length
< 150 < 150 < 150 < 144 < 102 (in.)
No. of Guide and/or 17 17 5 (Note 4) 16 0 Instrument Tubes Guide/Instrument Tube > 0.017 > 0.017 > 0.038 > 0.0145 N/A Thickness (in.)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-46
Approved Contents 2.0 Table 2.1-2 (page 2 of 4)
PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 15x15A 15x15B 15x15C 15x15D 15x15E 15x15F Array/Class Clad Material ZR ZR ZR ZR ZR ZR Design Initial U (kg/assy.) < 473 < 473 < 473 < 495 < 495 < 495 (Note 3)
Initial Enrichment (MPC-24, 24E and < 4.1 (24) < 4.1 (24) < 4.1 (24) < 4.1 (24) < 4.1 (24) < 4.1 (24) 24EF without soluble boron credit) < 4.5 < 4.5 < 4.5 < 4.5 < 4.5 < 4.5 (wt % 235U) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF)
(Note 7)
Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F
< 5.0 < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 with soluble boron credit - see Note 5)
(wt % 235U)
No. of Fuel Rod 204 204 204 208 208 208 Locations Fuel Rod Clad O.D.
> 0.418 > 0.420 > 0.417 > 0.430 > 0.428 > 0.428 (in.)
Fuel Rod Clad I.D.
< 0.3660 < 0.3736 < 0.3640 < 0.3800 < 0.3790 < 0.3820 (in.)
Fuel Pellet Dia. (in.)
< 0.3580 < 0.3671 < 0.3570 < 0.3735 < 0.3707 < 0.3742 (Note 8)
Fuel Rod Pitch (in.) < 0.550 < 0.563 < 0.563 < 0.568 < 0.568 < 0.568 Active Fuel Length
< 150 < 150 < 150 < 150 < 150 < 150 (in.)
No. of Guide and/or 21 21 21 17 17 17 Instrument Tubes Guide/Instrument Tube Thickness (in.) > 0.0165 > 0.015 > 0.0165 > 0.0150 > 0.0140 > 0.0140 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-47
Approved Contents 2.0 Table 2.1-2 (page 3 of 4)
PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 15x15G 15x15H 16x16A 17x17A 17x17B 17x17C Array/ Class Clad Material SS ZR ZR ZR ZR ZR Design Initial U (kg/assy.) < 420 < 495 < 448 < 433 < 474 < 480 (Note 3)
Initial Enrichment (MPC-24, 24E, and
< 4.0 (24) < 3.8 (24) < 4.6 (24) < 4.0 (24) < 4.0 (24) < 4.0 (24) 24EF without soluble boron
< 4.5 < 4.2 < 5.0 < 4.4 < 4.4 < 4.4 credit)
(24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF) (24E/24EF)
(wt % 235U)
(Note 7)
Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F
< 5.0 < 5.0 < 5.0 < 5.0 < 5.0 < 5.0 with soluble boron credit - see Note 5)
(wt % 235U)
No. of Fuel Rod 204 208 236 264 264 264 Locations Fuel Rod Clad O.D.
> 0.422 > 0.414 > 0.382 > 0.360 > 0.372 > 0.377 (in.)
Fuel Rod Clad I.D.
< 0.3890 < 0.3700 < 0.3320 < 0.3150 < 0.3310 < 0.3330 (in.)
Fuel Pellet Dia.
(in.) < 0.3825 < 0.3622 < 0.3255 < 0.3088 < 0.3232 < 0.3252 (Note 8)
Fuel Rod Pitch (in.) < 0.563 < 0.568 < 0.506 < 0.496 < 0.496 < 0.502 Active Fuel Length
< 144 < 150 < 150 < 150 < 150 < 150 (in.)
No. of Guide and/or 21 17 5 (Note 4) 25 25 25 Instrument Tubes Guide/Instrument Tube > 0.0145 > 0.0140 > 0.0400 > 0.016 > 0.014 > 0.020 Thickness (in.)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-48
Approved Contents 2.0 Table 2.1-2 (page 4 of 4)
PWR FUEL ASSEMBLY CHARACTERISTICS Notes:
- 1. All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
- 2. Deleted.
- 3. Design initial uranium weight is the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each PWR fuel assembly, the total uranium weight limit specified in this table may be increased up to 2.0 percent for comparison with users fuel records to account for manufacturers tolerances.
- 4. Each guide tube replaces four fuel rods.
- 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 4.0 wt.% 235U.
- 8. Annular fuel pellets are allowed in the top and bottom 12" of the active fuel length.
- 9. This fuel assembly array/class includes only the Indian Point Unit 1 fuel assembly. This assembly class has been analyzed in all PWR MPCs, however, it is only to be loaded in the MPC-32/32F.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-49
Approved Contents 2.0 Table 2.1-3 (page 1 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 6x6A 6x6B 6x6C 7x7A 7x7B 8x8A Array/Class Clad Material ZR ZR ZR ZR ZR ZR Design Initial U
< 110 < 110 < 110 < 100 < 198 < 120 (kg/assy.) (Note 3)
Maximum PLANAR- < 2.7 for the AVERAGE INITIAL UO2 rods.
ENRICHMENT < 2.7 See Note 4 < 2.7 < 2.7 < 4.2 < 2.7 (wt.% 235U) for MOX (Note 14) rods Initial Maximum Rod Enrichment < 4.0 < 4.0 < 4.0 < 5.5 < 5.0 < 4.0 (wt.% 235U)
No. of Fuel Rod 35 or 36 (up Locations 35 or 36 to 9 MOX 36 49 49 63 or 64 rods)
Fuel Rod Clad O.D.
> 0.5550 > 0.5625 > 0.5630 > 0.4860 > 0.5630 > 0.4120 (in.)
Fuel Rod Clad I.D.
< 0.5105 < 0.4945 < 0.4990 < 0.4204 < 0.4990 < 0.3620 (in.)
Fuel Pellet Dia. (in.) < 0.4980 < 0.4820 < 0.4880 < 0.4110 < 0.4910 < 0.3580 Fuel Rod Pitch (in.) < 0.710 < 0.710 < 0.740 < 0.631 < 0.738 < 0.523 Active Fuel Length
< 120 < 120 < 77.5 < 80 < 150 < 120 (in.)
No. of Water Rods 1 or 0 1 or 0 0 0 0 1 or 0 (Note 11)
>0 >0 N/A N/A N/A >0 Thickness (in.)
Channel Thickness
< 0.060 < 0.060 < 0.060 < 0.060 < 0.120 < 0.100 (in.)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-50
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 Design Initial U
< 192 < 190 < 190 < 190 < 191 < 180 (kg/assy.) (Note 3)
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.% 235U)
No. of Fuel Rod 74/66 63 or 64 62 60 or 61 59 64 Locations (Note 5)
Fuel Rod Clad O.D.
> 0.4840 > 0.4830 > 0.4830 > 0.4930 > 0.4576 > 0.4400 (in.)
Fuel Rod Clad I.D.
< 0.4295 < 0.4250 < 0.4230 < 0.4250 < 0.3996 < 0.3840 (in.)
Fuel Pellet Dia. (in.) < 0.4195 < 0.4160 < 0.4140 < 0.4160 < 0.3913 < 0.3760 Fuel Rod Pitch (in.) < 0.642 < 0.641 < 0.640 < 0.640 < 0.609 < 0.566 Design Active Fuel
< 150 < 150 < 150 < 150 < 150 < 150 Length (in.)
No. of Water Rods 1-4 N/A 1 or 0 2 5 2 (Note 11) (Note 7) (Note 12)
Water Rod Thickness
> 0.034 > 0.00 > 0.00 > 0.034 > 0.0315 > 0.00 (in.)
Channel Thickness (in.) < 0.120 < 0.120 < 0.120 < 0.100 < 0.055 < 0.120 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-51
Approved Contents 2.0 Table 2.1-3 (page 3 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 9x9E 9x9F 9x9B 9x9C 9x9D 9x9G Array/Class (Note 13) (Note 13)
Clad Material ZR ZR ZR ZR ZR ZR Design Initial U
< 180 < 182 < 182 < 183 < 183 < 164 (kg/assy.) (Note 3)
Maximum PLANAR-AVERAGE INITIAL ENRICHMENT < 4.2 < 4.2 < 4.2 < 4.0 < 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.% 235U)
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 (in.)
Fuel Rod Clad I.D.
< 0.3810 < 0.3640 < 0.3640 < 0.3640 < 0.3860 < 0.3640 (in.)
Fuel Pellet Dia. (in.) < 0.3740 < 0.3565 < 0.3565 < 0.3530 < 0.3745 < 0.3565 Fuel Rod Pitch (in.) < 0.572 < 0.572 < 0.572 < 0.572 < 0.572 < 0.572 Design Active Fuel
< 150 < 150 < 150 < 150 < 150 < 150 Length (in.)
No. of Water Rods 1 1 (Note 6) 1 2 5 5 (Note 11) (Note 6)
Water Rod Thickness
> 0.00 > 0.020 > 0.0300 > 0.0120 > 0.0120 > 0.0320 (in.)
Channel Thickness (in.) < 0.120 < 0.100 < 0.100 < 0.120 < 0.120 < 0.120 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-52
Approved Contents 2.0 Table 2.1-3 (page 4 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly Array/Class 10x10A 10x10B 10x10C 10x10D 10x10E Clad Material ZR ZR ZR SS SS Design Initial U (kg/assy.) (Note 3)
< 188 < 188 < 179 < 125 < 125 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT
< 4.2 < 4.2 < 4.2 < 4.0 < 4.0 (wt.% 235U)
(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 I.D. (in.) < 0.3520 < 0.3480 < 0.3294 < 0.3560 < 0.3500 Fuel Pellet Dia. (in.) < 0.3455 < 0.3420 < 0.3224 < 0.3500 < 0.3430 Fuel Rod Pitch (in.) < 0.510 < 0.510 < 0.488 < 0.565 < 0.557 Design Active Fuel Length (in.) < 150 < 150 < 150 < 83 < 83 No. of Water Rods (Note 11) 2 1 (Note 6) 5 (Note 10) 0 4 Water Rod Thickness (in.) > 0.0300 > 0.00 > 0.031 N/A > 0.022 Channel Thickness (in.) < 0.120 < 0.120 < 0.055 < 0.080 < 0.080 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-53
Approved Contents 2.0 Table 2.1-3 (page 5 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS Notes:
- 1. All dimensions are design nominal values. Maximum and minimum dimensions are specified to bound variations in design nominal values among fuel assemblies within a given array/class.
- 2. Deleted.
- 3. Design initial uranium weight is the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each BWR fuel assembly, the total uranium weight limit specified in this table may be increased up to 1.5 percent for comparison with users fuel records to account for manufacturer tolerances.
- 4. < 0.635 wt. % 235U and < 1.578 wt. % total fissile plutonium (239Pu and 241 Pu), (wt. % of total fuel weight, i.e., UO2 plus PuO2).
- 5. This assembly class contains 74 total rods; 66 full length rods and 8 partial length rods.
- 6. Square, replacing nine fuel rods.
- 7. Variable.
- 8. This assembly contains 92 total fuel rods; 78 full length rods and 14 partial length rods.
- 9. This assembly class contains 91 total fuel rods; 83 full length rods and 8 partial length rods.
- 10. One diamond-shaped water rod replacing the four center fuel rods and four rectangular water rods dividing the assembly into four quadrants.
- 11. These rods may also be sealed at both ends and contain Zr material in lieu of water.
- 12. This assembly is known as QUAD+. It has four rectangular water cross segments dividing the assembly into four quadrants.
- 13. For the SPC 9x9-5 fuel assembly, each fuel rod must meet either the 9x9E or the 9x9F set of limits for clad O.D., clad I.D., and pellet diameter.
- 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 Renewed Amendment No. 4 Appendix B 2-54
Approved Contents 2.0 Table 2.1-4 TABLE DELETED Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-55
Approved Contents 2.0 Table 2.1-5 TABLE DELETED Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-56
Approved Contents 2.0 Table 2.1-6 (page 1 of 2)
TABLE DELETED Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-57
Approved Contents 2.0 Table 2.1-6 (page 2 of 2)
TABLE DELETED Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-58
Approved Contents 2.0 Table 2.1-7 (page 1 of 2)
TABLE DELETED Certificate of Compliance No. 1014 Appendix B 2-59 Renewed Amendment No. 4
Approved Contents 2.0 Table 2.1-7 (page 2 of 2)
TABLE DELETED Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 2-60
Approved Contents 2.0 Table 2.1-8 NON-FUEL HARDWARE COOLING AND AVERAGE BURNUP (Notes 1, 2, and 3)
Post-irradiation INSERTS NSA or GUIDE CONTROL APSR Cooling Time (Note 4) TUBE HARDWARE COMPONENT BURNUP (years) BURNUP (Note 5) (Note 6) (MWD/MTU)
(MWD/MTU) BURNUP BURNUP (MWD/MTU) (MWD/MTU)
>3 < 24,635 NA (Note 7) NA NA
>4 < 30,000 < 20,000 NA NA
>5 < 36,748 < 25,000 < 630,000 < 45,000
>6 < 44,102 < 30,000 - < 54,500
>7 < 52,900 < 40,000 - < 68,000
>8 < 60,000 < 45,000 - < 83,000
>9 - < 50,000 - < 111,000
> 10 - < 60,000 - < 180,000
> 11 - < 75,000 - < 630,000
> 12 - < 90,000 - -
> 13 - < 180,000 - -
> 14 - < 630,000 - -
Notes: 1. Burnups for NON-FUEL HARDWARE are to be determined based on the burnup and uranium mass of the fuel assemblies in which the component was inserted during reactor operation.
- 2. Linear interpolation between points is permitted, except that NSA or Guide Tube Hardware and APSR burnups > 180,000 MWD/MTU and < 630,000 MWD/MTU must be cooled > 14 years and > 11 years, respectively.
- 3. Applicable to uniform loading and regionalized loading.
- 4. Includes Burnable Poison Rod Assemblies (BPRAs), Wet Annular Burnable Absorbers (WABAs), and vibration suppressor inserts..
- 5. Includes Thimble Plug Devices (TPDs), water displacement guide tube plugs, and orifice rod assemblies.
- 6. Includes Control Rod Assemblies (CRAs), Control Element Assemblies (CEAs), and Rod Cluster Control Assemblies (RCCAs).
- 7. NA means not authorized for loading at this cooling time.
2-61 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 2.4 Decay Heat, Burnup, and Cooling Time Limits for ZR-Clad Fuel This section provides the limits on ZR-clad fuel assembly decay heat, burnup, and cooling time for storage in the HI-STORM 100 System. 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)
Decay Heat per Fuel Storage Location MPC Model (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 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 2.4.2 Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel (contd)
Table 2.4-2 Fuel Storage Regions and Maximum Decay Heat per MPC Number of Fuel Inner Region Outer Region Storage Locations Maximum Decay Maximum Decay MPC Model in Inner and Outer Heat per Assembly Heat per Assembly Regions (kW) (kW)
MPC-24 4 and 20 1.470 0.900 MPC-24E/24EF 4 and 20 1.540 0.900 MPC-32/32F 12 and 20 1.131 0.600 MPC-68/68FF 32 and 36 0.500 0.275 2.4.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel 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 heat 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, E235.
2.4.3.2 Calculate the maximum allowable fuel assembly average burnup for a minimum cooling time between 3 and 20 years using the equation below.
Bu = (A x q) + (B x q2) + (C x q3) + [D x (E235)2] + (E x q x E235) + (F x q2 x E235) + G Equation 2.4.3 Where:
Bu = Maximum allowable average burnup per fuel assembly (MWD/MTU) 2-63 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 2.4.3 Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel (contd) 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 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-3 (Page 1 of 8)
PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 14x14A Time (years) A B C D E F G
>3 20277.1 303.592 -68.329 -139.41 2993.67 -498.159 -615.411
>4 35560.1 -6034.67 985.415 -132.734 3578.92 -723.721 -609.84
>5 48917.9 -14499.5 2976.09 -150.707 4072.55 -892.691 -54.8362
>6 59110.3 -22507 5255.61 -177.017 4517.03 -1024.01 613.36
>7 67595.6 -30158.1 7746.6 -200.128 4898.71 -1123.21 716.004
>8 74424.9 -36871.1 10169.4 -218.676 5203.64 -1190.24 741.163
>9 81405.8 -44093.1 12910.8 -227.916 5405.34 -1223.27 250.224
> 10 86184.3 -49211.7 15063.4 -237.641 5607.96 -1266.21 134.435
> 11 92024.9 -55666.8 17779.6 -240.973 5732.25 -1282.12 -401.456
> 12 94775.8 -58559.7 19249.9 -246.369 5896.27 -1345.42 -295.435
> 13 100163 -64813.8 22045.1 -242.572 5861.86 -1261.66 -842.159
> 14 103971 -69171 24207 -242.651 5933.96 -1277.48 -1108.99
> 15 108919 -75171.1 27152.4 -243.154 6000.2 -1301.19 -1620.63
> 16 110622 -76715.2 28210.2 -240.235 6028.33 -1307.74 -1425.5
> 17 115582 -82929.7 31411.9 -235.234 5982.3 -1244.11 -1948.05
> 18 119195 -87323.5 33881.4 -233.28 6002.43 -1245.95 -2199.41
> 19 121882 -90270.6 35713.7 -231.873 6044.42 -1284.55 -2264.05
> 20 124649 -93573.5 37853.1 -230.22 6075.82 -1306.57 -2319.63 2-65 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-3 (Page 2 of 8)
PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 14x14B Time (years) A B C D E F G
>3 18937.9 70.2997 -28.6224 -130.732 2572.36 -383.393 -858.17
>4 32058.7 -4960.63 745.224 -125.978 3048.98 -551.656 -549.108
>5 42626.3 -10804.1 1965.09 -139.722 3433.49 -676.643 321.88
>6 51209.6 -16782.3 3490.45 -158.929 3751.01 -761.524 847.282
>7 57829.9 -21982 5009.12 -180.026 4066.65 -846.272 1200.45
>8 62758 -26055.3 6330.88 -196.804 4340.18 -928.336 1413.17
>9 68161.4 -30827.6 7943.87 -204.454 4500.52 -966.347 1084.69
> 10 71996.8 -34224.3 9197.25 -210.433 4638.94 -1001.83 1016.38
> 11 75567.3 -37486.1 10466.9 -214.95 4759.55 -1040.85 848.169
> 12 79296.7 -40900.3 11799.6 -212.898 4794.13 -1040.51 576.242
> 13 82257.3 -43594 12935 -212.8 4845.81 -1056.01 410.807
> 14 83941.2 -44915.2 13641 -215.389 4953.19 -1121.71 552.724
> 15 87228.5 -48130 15056.9 -212.545 4951.12 -1112.5 260.194
> 16 90321.7 -50918.3 16285.5 -206.094 4923.36 -1106.35 -38.7487
> 17 92836.2 -53314.5 17481.7 -203.139 4924.61 -1109.32 -159.673
> 18 93872.8 -53721.4 17865.1 -202.573 4956.21 -1136.9 30.0594
> 19 96361.6 -56019.1 19075.9 -199.068 4954.59 -1156.07 -125.917
> 20 98647.5 -57795.1 19961.8 -191.502 4869.59 -1108.74 -217.603 2-66 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-3 (Page 3 of 8)
PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 14x14C Time (years) A B C D E F G
>3 19176.9 192.012 -66.7595 -138.112 2666.73 -407.664 -1372.41
>4 32040.3 -4731.4 651.014 -124.944 3012.63 -530.456 -890.059
>5 43276.7 -11292.8 2009.76 -142.172 3313.91 -594.917 -200.195
>6 51315.5 -16920.5 3414.76 -164.287 3610.77 -652.118 463.041
>7 57594.7 -21897.6 4848.49 -189.606 3940.67 -729.367 781.46
>8 63252.3 -26562.8 6273.01 -199.974 4088.41 -732.054 693.879
>9 67657.5 -30350.9 7533.4 -211.77 4283.39 -772.916 588.456
> 10 71834.4 -34113.7 8857.32 -216.408 4383.45 -774.982 380.243
> 11 75464.1 -37382.1 10063 -218.813 4460.69 -776.665 160.668
> 12 77811.1 -39425.1 10934.3 -225.193 4604.68 -833.459 182.463
> 13 81438.3 -42785.4 12239.9 -220.943 4597.28 -803.32 -191.636
> 14 84222.1 -45291.6 13287.9 -218.366 4608.13 -791.655 -354.59
> 15 86700.1 -47582.6 14331.2 -218.206 4655.34 -807.366 -487.316
> 16 88104.7 -48601.1 14927.9 -219.498 4729.97 -849.446 -373.196
> 17 91103.3 -51332.5 16129 -212.138 4679.91 -822.896 -654.296
> 18 93850.4 -53915.8 17336.9 -207.666 4652.65 -799.697 -866.307
> 19 96192.9 -55955.8 18359.3 -203.462 4642.65 -800.315 -1007.75
> 20 97790.4 -57058.1 19027.7 -200.963 4635.88 -799.721 -951.122 2-67 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-3 (Page 4 of 8)
PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 15x15A/B/C Time (years) A B C D E F G
>3 15789.2 119.829 -21.8071 -127.422 2152.53 -267.717 -580.768
>4 26803.8 -3312.93 415.027 -116.279 2550.15 -386.33 -367.168
>5 36403.6 -7831.93 1219.66 -126.065 2858.32 -471.785 326.863
>6 44046.1 -12375.9 2213.52 -145.727 3153.45 -539.715 851.971
>7 49753.5 -16172.6 3163.61 -166.946 3428.38 -603.598 1186.31
>8 55095.4 -20182.5 4287.03 -183.047 3650.42 -652.92 1052.4
>9 58974.4 -23071.6 5156.53 -191.718 3805.41 -687.18 1025
> 10 62591.8 -25800.8 5995.95 -195.105 3884.14 -690.659 868.556
> 11 65133.1 -27747.4 6689 -203.095 4036.91 -744.034 894.607
> 12 68448.4 -30456 7624.9 -202.201 4083.52 -753.391 577.914
> 13 71084.4 -32536.4 8381.78 -201.624 4117.93 -757.16 379.105
> 14 73459.5 -34352.3 9068.86 -197.988 4113.16 -747.015 266.536
> 15 75950.7 -36469.4 9920.52 -199.791 4184.91 -779.222 57.9429
> 16 76929.1 -36845.6 10171.3 -197.88 4206.24 -794.541 256.099
> 17 79730 -39134.8 11069.4 -190.865 4160.42 -773.448 -42.6853
> 18 81649.2 -40583 11736.1 -187.604 4163.36 -785.838 -113.614
> 19 83459 -41771.8 12265.9 -181.461 4107.51 -758.496 -193.442
> 20 86165.4 -44208.8 13361.2 -178.89 4107.62 -768.671 -479.778 2-68 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-3 (Page 5 of 8)
PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 15x15D/E/F/H Time (years) A B C D E F G
>3 15192.5 50.5722 -12.3042 -126.906 2009.71 -235.879 -561.574
>4 25782.5 -3096.5 369.096 -113.289 2357.75 -334.695 -254.964
>5 35026.5 -7299.87 1091.93 -124.619 2664 -414.527 470.916
>6 42234.9 -11438.4 1967.63 -145.948 2945.81 -474.981 1016.84
>7 47818.4 -15047 2839.22 -167.273 3208.95 -531.296 1321.12
>8 52730.7 -18387.2 3702.43 -175.057 3335.58 -543.232 1223.61
>9 56254.6 -20999.9 4485.93 -190.489 3547.98 -600.64 1261.55
> 10 59874.6 -23706.5 5303.88 -193.807 3633.01 -611.892 1028.63
> 11 62811 -25848.4 5979.64 -194.997 3694.14 -618.968 862.738
> 12 65557.6 -27952.4 6686.74 -198.224 3767.28 -635.126 645.139
> 13 67379.4 -29239.2 7197.49 -200.164 3858.53 -677.958 652.601
> 14 69599.2 -30823.8 7768.51 -196.788 3868.2 -679.88 504.443
> 15 71806.7 -32425 8360.38 -191.935 3851.65 -669.917 321.146
> 16 73662.6 -33703.5 8870.78 -187.366 3831.59 -658.419 232.335
> 17 76219.8 -35898.1 9754.72 -189.111 3892.07 -694.244 -46.924
> 18 76594.4 -35518.2 9719.78 -185.11 3897.04 -712.82 236.047
> 19 78592.7 -36920.8 10316.5 -179.54 3865.84 -709.551 82.478
> 20 80770.5 -38599.9 11051.3 -175.106 3858.67 -723.211 -116.014 2-69 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-3 (Page 6 of 8)
PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 16X16A Time (years) A B C D E F G
>3 17038.2 158.445 -37.6008 -136.707 2368.1 -321.58 -700.033
>4 29166.3 -3919.95 508.439 -125.131 2782.53 -455.722 -344.199
>5 40285 -9762.36 1629.72 -139.652 3111.83 -539.804 139.67
>6 48335.7 -15002.6 2864.09 -164.702 3444.97 -614.756 851.706
>7 55274.9 -20190 4258.03 -185.909 3728.11 -670.841 920.035
>8 60646.6 -24402.4 5483.54 -199.014 3903.29 -682.26 944.913
>9 64663.2 -27753.1 6588.21 -215.318 4145.34 -746.822 967.914
> 10 69306.9 -31739.1 7892.13 -218.898 4237.04 -746.815 589.277
> 11 72725.8 -34676.6 8942.26 -220.836 4312.93 -750.85 407.133
> 12 76573.8 -38238.7 10248.1 -224.934 4395.85 -757.914 23.7549
> 13 78569 -39794.3 10914.9 -224.584 4457 -776.876 69.428
> 14 81559.4 -42453.6 11969.6 -222.704 4485.28 -778.427 -203.031
> 15 84108.6 -44680.4 12897.8 -218.387 4460 -746.756 -329.078
> 16 86512.2 -46766.8 13822.8 -216.278 4487.79 -759.882 -479.729
> 17 87526.7 -47326.2 14221 -218.894 4567.68 -805.659 -273.692
> 18 90340.3 -49888.6 15349.8 -212.139 4506.29 -762.236 -513.316
> 19 93218.2 -52436.7 16482.4 -207.653 4504.12 -776.489 -837.1
> 20 95533.9 -54474.1 17484.2 -203.094 4476.21 -760.482 -955.662 2-70 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-3 (Page 7 of 8)
PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 17x17A Time (years) A B C D E F G
>3 16784.4 3.90244 -10.476 -128.835 2256.98 -287.108 -263.081
>4 28859 -3824.72 491.016 -120.108 2737.65 -432.361 -113.457
>5 40315.9 -9724 1622.89 -140.459 3170.28 -547.749 425.136
>6 49378.5 -15653.1 3029.25 -164.712 3532.55 -628.93 842.73
>7 56759.5 -21320.4 4598.78 -190.58 3873.21 -698.143 975.46
>8 63153.4 -26463.8 6102.47 -201.262 4021.84 -685.431 848.497
>9 67874.9 -30519.2 7442.84 -218.184 4287.23 -754.597 723.305
> 10 72676.8 -34855.2 8928.27 -222.423 4382.07 -741.243 387.877
> 11 75623 -37457.1 9927.65 -232.962 4564.55 -792.051 388.402
> 12 80141.8 -41736.5 11509.8 -232.944 4624.72 -787.134 -164.727
> 13 83587.5 -45016.4 12800.9 -230.643 4623.2 -745.177 -428.635
> 14 86311.3 -47443.4 13815.2 -228.162 4638.89 -729.425 -561.758
> 15 87839.2 -48704.1 14500.3 -231.979 4747.67 -775.801 -441.959
> 16 91190.5 -51877.4 15813.2 -225.768 4692.45 -719.311 -756.537
> 17 94512 -55201.2 17306.1 -224.328 4740.86 -747.11 -1129.15
> 18 96959 -57459.9 18403.8 -220.038 4721.02 -726.928 -1272.47
> 19 99061.1 -59172.1 19253.1 -214.045 4663.37 -679.362 -1309.88
> 20 100305 -59997.5 19841.1 -216.112 4721.71 -705.463 -1148.45 2-71 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-3 (Page 8 of 8)
PWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 17x17B/C Time (years) A B C D E F G
>3 15526.8 18.0364 -9.36581 -128.415 2050.81 -243.915 -426.07
>4 26595.4 -3345.47 409.264 -115.394 2429.48 -350.883 -243.477
>5 36190.4 -7783.2 1186.37 -130.008 2769.53 -438.716 519.95
>6 44159 -12517.5 2209.54 -150.234 3042.25 -489.858 924.151
>7 50399.6 -16780.6 3277.26 -173.223 3336.58 -555.743 1129.66
>8 55453.9 -20420 4259.68 -189.355 3531.65 -581.917 1105.62
>9 59469.3 -23459.8 5176.62 -199.63 3709.99 -626.667 1028.74
> 10 63200.5 -26319.6 6047.8 -203.233 3783.02 -619.949 805.311
> 11 65636.3 -28258.3 6757.23 -214.247 3972.8 -688.56 843.457
> 12 68989.7 -30904.4 7626.53 -212.539 3995.62 -678.037 495.032
> 13 71616.6 -32962.2 8360.45 -210.386 4009.11 -666.542 317.009
> 14 73923.9 -34748 9037.75 -207.668 4020.13 -662.692 183.086
> 15 76131.8 -36422.3 9692.32 -203.428 4014.55 -655.981 47.5234
> 16 77376.5 -37224.7 10111.4 -207.581 4110.76 -703.37 161.128
> 17 80294.9 -39675.9 11065.9 -201.194 4079.24 -691.636 -173.782
> 18 82219.8 -41064.8 11672.1 -195.431 4043.83 -675.432 -286.059
> 19 84168.9 -42503.6 12309.4 -190.602 4008.19 -656.192 -372.411
> 20 86074.2 -43854.4 12935.9 -185.767 3985.57 -656.72 -475.953 2-72 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-4 (Page 1 of 10)
BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 7x7B Time (years) A B C D E F G
>3 26409.1 28347.5 -16858 -147.076 5636.32 -1606.75 1177.88
>4 61967.8 -6618.31 -4131.96 -113.949 6122.77 -2042.85 -96.7439
>5 91601.1 -49298.3 17826.5 -132.045 6823.14 -2418.49 -185.189
>6 111369 -80890.1 35713.8 -150.262 7288.51 -2471.1 86.6363
>7 126904 -108669 53338.1 -167.764 7650.57 -2340.78 150.403
>8 139181 -132294 69852.5 -187.317 8098.66 -2336.13 97.5285
>9 150334 -154490 86148.1 -193.899 8232.84 -2040.37 -123.029
> 10 159897 -173614 100819 -194.156 8254.99 -1708.32 -373.605
> 11 166931 -186860 111502 -193.776 8251.55 -1393.91 -543.677
> 12 173691 -201687 125166 -202.578 8626.84 -1642.3 -650.814
> 13 180312 -215406 137518 -201.041 8642.19 -1469.45 -810.024
> 14 185927 -227005 148721 -197.938 8607.6 -1225.95 -892.876
> 15 191151 -236120 156781 -191.625 8451.86 -846.27 -1019.4
> 16 195761 -244598 165372 -187.043 8359.19 -572.561 -1068.19
> 17 200791 -256573 179816 -197.26 8914.28 -1393.37 -1218.63
> 18 206068 -266136 188841 -187.191 8569.56 -730.898 -1363.79
> 19 210187 -273609 197794 -182.151 8488.23 -584.727 -1335.59
> 20 213731 -278120 203074 -175.864 8395.63 -457.304 -1364.38 2-73 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-4 (Page 2 of 10)
BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 8x8B Time (years) A B C D E F G
>3 28219.6 28963.7 -17616.2 -147.68 5887.41 -1730.96 1048.21
>4 66061.8 -10742.4 -1961.82 -123.066 6565.54 -2356.05 -298.005
>5 95790.7 -53401.7 19836.7 -134.584 7145.41 -2637.09 -298.858
>6 117477 -90055.9 41383.9 -154.758 7613.43 -2612.69 -64.9921
>7 134090 -120643 60983 -168.675 7809 -2183.3 -40.8885
>8 148186 -149181 81418.7 -185.726 8190.07 -2040.31 -260.773
>9 159082 -172081 99175.2 -197.185 8450.86 -1792.04 -381.705
> 10 168816 -191389 113810 -195.613 8359.87 -1244.22 -613.594
> 11 177221 -210599 131099 -208.3 8810 -1466.49 -819.773
> 12 183929 -224384 143405 -207.497 8841.33 -1227.71 -929.708
> 13 191093 -240384 158327 -204.95 8760.17 -811.708 -1154.76
> 14 196787 -252211 169664 -204.574 8810.95 -610.928 -1208.97
> 15 203345 -267656 186057 -208.962 9078.41 -828.954 -1383.76
> 16 207973 -276838 196071 -204.592 9024.17 -640.808 -1436.43
> 17 213891 -290411 211145 -202.169 9024.19 -482.1 -1595.28
> 18 217483 -294066 214600 -194.243 8859.35 -244.684 -1529.61
> 19 220504 -297897 219704 -190.161 8794.97 -10.9863 -1433.86
> 20 227821 -318395 245322 -194.682 9060.96 -350.308 -1741.16 2-74 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-4 (Page 3 of 10)
BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 8x8C/D/E Time (years) A B C D E F G
>3 28592.7 28691.5 -17773.6 -149.418 5969.45 -1746.07 1063.62
>4 66720.8 -12115.7 -1154 -128.444 6787.16 -2529.99 -302.155
>5 96929.1 -55827.5 21140.3 -136.228 7259.19 -2685.06 -334.328
>6 118190 -92000.2 42602.5 -162.204 7907.46 -2853.42 -47.5465
>7 135120 -123437 62827.1 -172.397 8059.72 -2385.81 -75.0053
>8 149162 -152986 84543.1 -195.458 8559.11 -2306.54 -183.595
>9 161041 -177511 103020 -200.087 8632.84 -1864.4 -433.081
> 10 171754 -201468 122929 -209.799 8952.06 -1802.86 -755.742
> 11 179364 -217723 137000 -215.803 9142.37 -1664.82 -847.268
> 12 186090 -232150 150255 -216.033 9218.36 -1441.92 -975.817
> 13 193571 -249160 165997 -213.204 9146.99 -1011.13 -1119.47
> 14 200034 -263671 180359 -210.559 9107.54 -694.626 -1312.55
> 15 205581 -275904 193585 -216.242 9446.57 -1040.65 -1428.13
> 16 212015 -290101 207594 -210.036 9212.93 -428.321 -1590.7
> 17 216775 -299399 218278 -204.611 9187.86 -398.353 -1657.6
> 18 220653 -306719 227133 -202.498 9186.34 -181.672 -1611.86
> 19 224859 -314004 235956 -193.902 8990.14 145.151 -1604.71
> 20 228541 -320787 245449 -200.727 9310.87 -230.252 -1570.18 2-75 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-4 (Page 4 of 10)
BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 9x9A Time (years) A B C D E F G
>3 30538.7 28463.2 -18105.5 -150.039 6226.92 -1876.69 1034.06
>4 71040.1 -16692.2 1164.15 -128.241 7105.27 -2728.58 -414.09
>5 100888 -60277.7 24150.1 -142.541 7896.11 -3272.86 -232.197
>6 124846 -102954 50350.8 -161.849 8350.16 -3163.44 -91.1396
>7 143516 -140615 76456.5 -185.538 8833.04 -2949.38 -104.802
>8 158218 -171718 99788.2 -196.315 9048.88 -2529.26 -259.929
>9 172226 -204312 126620 -214.214 9511.56 -2459.19 -624.954
> 10 182700 -227938 146736 -215.793 9555.41 -1959.92 -830.943
> 11 190734 -246174 163557 -218.071 9649.43 -1647.5 -935.021
> 12 199997 -269577 186406 -223.975 9884.92 -1534.34 -1235.27
> 13 207414 -287446 204723 -228.808 10131.7 -1614.49 -1358.61
> 14 215263 -306131 223440 -220.919 9928.27 -988.276 -1638.05
> 15 221920 -321612 239503 -217.949 9839.02 -554.709 -1784.04
> 16 226532 -331778 252234 -216.189 9893.43 -442.149 -1754.72
> 17 232959 -348593 272609 -219.907 10126.3 -663.84 -1915.3
> 18 240810 -369085 296809 -219.729 10294.6 -859.302 -2218.87
> 19 244637 -375057 304456 -210.997 10077.8 -425.446 -2127.83
> 20 248112 -379262 309391 -204.191 9863.67 100.27 -2059.39 2-76 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-4 (Page 5 of 10)
BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 9x9B Time (years) A B C D E F G
>3 30613.2 28985.3 -18371 -151.117 6321.55 -1881.28 988.92
>4 71346.6 -15922.9 631.132 -128.876 7232.47 -2810.64 -471.737
>5 102131 -60654.1 23762.7 -140.748 7881.6 -3156.38 -417.979
>6 127187 -105842 51525.2 -162.228 8307.4 -2913.08 -342.13
>7 146853 -145834 79146.5 -185.192 8718.74 -2529.57 -484.885
>8 162013 -178244 103205 -197.825 8896.39 -1921.58 -584.013
>9 176764 -212856 131577 -215.41 9328.18 -1737.12 -1041.11
> 10 186900 -235819 151238 -218.98 9388.08 -1179.87 -1202.83
> 11 196178 -257688 171031 -220.323 9408.47 -638.53 -1385.16
> 12 205366 -280266 192775 -223.715 9592.12 -472.261 -1661.6
> 13 215012 -306103 218866 -231.821 9853.37 -361.449 -1985.56
> 14 222368 -324558 238655 -228.062 9834.57 3.47358 -2178.84
> 15 226705 -332738 247316 -224.659 9696.59 632.172 -2090.75
> 16 233846 -349835 265676 -221.533 9649.93 913.747 -2243.34
> 17 243979 -379622 300077 -222.351 9792.17 1011.04 -2753.36
> 18 247774 -386203 308873 -220.306 9791.37 1164.58 -2612.25
> 19 254041 -401906 327901 -213.96 9645.47 1664.94 -2786.2
> 20 256003 -402034 330566 -215.242 9850.42 1359.46 -2550.06 2-77 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-4 (Page 6 of 10)
BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 9x9C/D Time (years) A B C D E F G
>3 30051.6 29548.7 -18614.2 -148.276 6148.44 -1810.34 1006
>4 70472.7 -14696.6 -233.567 -127.728 7008.69 -2634.22 -444.373
>5 101298 -59638.9 23065.2 -138.523 7627.57 -2958.03 -377.965
>6 125546 -102740 49217.4 -160.811 8096.34 -2798.88 -259.767
>7 143887 -139261 74100.4 -184.302 8550.86 -2517.19 -275.151
>8 159633 -172741 98641.4 -194.351 8636.89 -1838.81 -486.731
>9 173517 -204709 124803 -212.604 9151.98 -1853.27 -887.137
> 10 182895 -225481 142362 -218.251 9262.59 -1408.25 -978.356
> 11 192530 -247839 162173 -217.381 9213.58 -818.676 -1222.12
> 12 201127 -268201 181030 -215.552 9147.44 -232.221 -1481.55
> 13 209538 -289761 203291 -225.092 9588.12 -574.227 -1749.35
> 14 216798 -306958 220468 -222.578 9518.22 -69.9307 -1919.71
> 15 223515 -323254 237933 -217.398 9366.52 475.506 -2012.93
> 16 228796 -334529 250541 -215.004 9369.33 662.325 -2122.75
> 17 237256 -356311 273419 -206.483 9029.55 1551.3 -2367.96
> 18 242778 -369493 290354 -215.557 9600.71 659.297 -2589.32
> 19 246704 -377971 302630 -210.768 9509.41 1025.34 -2476.06
> 20 249944 -382059 308281 -205.495 9362.63 1389.71 -2350.49 2-78 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-4 (Page 7 of 10)
BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 9x9E/F Time (years) A B C D E F G
>3 30284.3 26949.5 -16926.4 -147.914 6017.02 -1854.81 1026.15
>4 69727.4 -17117.2 1982.33 -127.983 6874.68 -2673.01 -359.962
>5 98438.9 -58492 23382.2 -138.712 7513.55 -3038.23 -112.641
>6 119765 -95024.1 45261 -159.669 8074.25 -3129.49 221.182
>7 136740 -128219 67940.1 -182.439 8595.68 -3098.17 315.544
>8 150745 -156607 88691.5 -193.941 8908.73 -2947.64 142.072
>9 162915 -182667 109134 -198.37 8999.11 -2531 -93.4908
> 10 174000 -208668 131543 -210.777 9365.52 -2511.74 -445.876
> 11 181524 -224252 145280 -212.407 9489.67 -2387.49 -544.123
> 12 188946 -240952 160787 -210.65 9478.1 -2029.94 -652.339
> 13 193762 -250900 171363 -215.798 9742.31 -2179.24 -608.636
> 14 203288 -275191 196115 -218.113 9992.5 -2437.71 -1065.92
> 15 208108 -284395 205221 -213.956 9857.25 -1970.65 -1082.94
> 16 215093 -301828 224757 -209.736 9789.58 -1718.37 -1303.35
> 17 220056 -310906 234180 -201.494 9541.73 -1230.42 -1284.15
> 18 224545 -320969 247724 -206.807 9892.97 -1790.61 -1381.9
> 19 226901 -322168 250395 -204.073 9902.14 -1748.78 -1253.22
> 20 235561 -345414 276856 -198.306 9720.78 -1284.14 -1569.18 2-79 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-4 (Page 8 of 10)
BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 9x9G Time (years) A B C D E F G
>3 35158.5 26918.5 -17976.7 -149.915 6787.19 -2154.29 836.894
>4 77137.2 -19760.1 2371.28 -130.934 8015.43 -3512.38 -455.424
>5 113405 -77931.2 35511.2 -150.637 8932.55 -4099.48 -629.806
>6 139938 -128700 68698.3 -173.799 9451.22 -3847.83 -455.905
>7 164267 -183309 109526 -193.952 9737.91 -3046.84 -737.992
>8 182646 -227630 146275 -210.936 10092.3 -2489.3 -1066.96
>9 199309 -270496 184230 -218.617 10124.3 -1453.81 -1381.41
> 10 213186 -308612 221699 -235.828 10703.2 -1483.31 -1821.73
> 11 225587 -342892 256242 -236.112 10658.5 -612.076 -2134.65
> 12 235725 -370471 285195 -234.378 10604.9 118.591 -2417.89
> 13 247043 -404028 323049 -245.79 11158.2 -281.813 -2869.82
> 14 253649 -421134 342682 -243.142 11082.3 400.019 -2903.88
> 15 262750 -448593 376340 -245.435 11241.2 581.355 -3125.07
> 16 270816 -470846 402249 -236.294 10845.4 1791.46 -3293.07
> 17 279840 -500272 441964 -241.324 11222.6 1455.84 -3528.25
> 18 284533 -511287 458538 -240.905 11367.2 1459.68 -3520.94
> 19 295787 -545885 501824 -235.685 11188.2 2082.21 -3954.2
> 20 300209 -556936 519174 -229.539 10956 2942.09 -3872.87 2-80 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-4 (Page 9 of 10)
BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 10x10A/B Time (years) A B C D E F G
>3 29285.4 27562.2 -16985 -148.415 5960.56 -1810.79 1001.45
>4 67844.9 -14383 395.619 -127.723 6754.56 -2547.96 -369.267
>5 96660.5 -55383.8 21180.4 -137.17 7296.6 -2793.58 -192.85
>6 118098 -91995 42958 -162.985 7931.44 -2940.84 60.9197
>7 135115 -123721 63588.9 -171.747 8060.23 -2485.59 73.6219
>8 148721 -151690 84143.9 -190.26 8515.81 -2444.25 -63.4649
>9 160770 -177397 104069 -197.534 8673.6 -2101.25 -331.046
> 10 170331 -198419 121817 -213.692 9178.33 -2351.54 -472.844
> 11 179130 -217799 138652 -209.75 9095.43 -1842.88 -705.254
> 12 186070 -232389 151792 -208.946 9104.52 -1565.11 -822.73
> 13 192407 -246005 164928 -209.696 9234.7 -1541.54 -979.245
> 14 200493 -265596 183851 -207.639 9159.83 -1095.72 -1240.61
> 15 205594 -276161 195760 -213.491 9564.23 -1672.22 -1333.64
> 16 209386 -282942 204110 -209.322 9515.83 -1506.86 -1286.82
> 17 214972 -295149 217095 -202.445 9292.34 -893.6 -1364.97
> 18 219312 -302748 225826 -198.667 9272.27 -878.536 -1379.58
> 19 223481 -310663 235908 -194.825 9252.9 -785.066 -1379.62
> 20 227628 -319115 247597 -199.194 9509.02 -1135.23 -1386.19 2-81 Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B
Approved Contents 2.0 Table 2.4-4 (Page 10 of 10)
BWR Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling Array/Class 10x10C Time (years) A B C D E F G
>3 31425.3 27358.9 -17413.3 -152.096 6367.53 -1967.91 925.763
>4 71804 -16964.1 1000.4 -129.299 7227.18 -2806.44 -416.92
>5 102685 -62383.3 24971.2 -142.316 7961 -3290.98 -354.784
>6 126962 -105802 51444.6 -164.283 8421.44 -3104.21 -186.615
>7 146284 -145608 79275.5 -188.967 8927.23 -2859.08 -251.163
>8 162748 -181259 105859 -199.122 9052.91 -2206.31 -554.124
>9 176612 -214183 133261 -217.56 9492.17 -1999.28 -860.669
> 10 187756 -239944 155315 -219.56 9532.45 -1470.9 -1113.42
> 11 196580 -260941 174536 -222.457 9591.64 -944.473 -1225.79
> 12 208017 -291492 204805 -233.488 10058.3 -1217.01 -1749.84
> 13 214920 -307772 221158 -234.747 10137.1 -897.23 -1868.04
> 14 222562 -326471 240234 -228.569 9929.34 -183.47 -2016.12
> 15 228844 -342382 258347 -226.944 9936.76 117.061 -2106.05
> 16 233907 -353008 270390 -223.179 9910.72 360.39 -2105.23
> 17 244153 -383017 304819 -227.266 10103.2 380.393 -2633.23
> 18 249240 -395456 321452 -226.989 10284.1 169.947 -2623.67
> 19 254343 -406555 335240 -220.569 10070.5 764.689 -2640.2
> 20 260202 -421069 354249 -216.255 10069.9 854.497 -2732.77 2-82 Certificate of Compliance No. 1014 Renewed Amendment No. 4 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 10 CFR 72, Subpart K.
3.2 Design Features Important for Criticality Control 3.2.1 MPC-24
- 1. Flux trap size: > 1.09 in.
10
- 2. B 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.
10
- 2. B 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.
10
- 2. B 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 10
- 2. B loading in the neutron absorbers: > 0.0372 g/cm2 (Boral) and > 0.0310 g/cm2 (METAMIC) 3.2.5 MPC-32 and MPC-32F
- 1. Fuel cell pitch: > 9.158 inches 10
- 2. B loading in the neutron absorbers: > 0.0372 g/cm2 (Boral) and > 0.0310 g/cm2 (METAMIC)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-1
Design Features 3.0 DESIGN FEATURES 3.2 Design features Important for Criticality Control (contd) 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 B4C 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 10B 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 III, 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 (continued)
DESIGN FEATURES Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-2
Design Features 3.0 3.3.2 Construction/Fabrication Alternatives to Codes, Standards, and Criteria (contd)
- 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)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-3
Design Features 3.0 DESIGN FEATURES Table 3-1 (page 1 of 9)
LIST OF ASME CODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component Reference Code Requirement Alternative, Justification & Compensatory Measures ASME Code Section/Article MPC, MPC Subsection NCA General Because the MPC, OVERPACK, and TRANSFER CASK basket Requirements. are not ASME Code stamped vessels, none of the assembly, HI- Requires preparation specifications, reports, certificates, or other general STORM of a Design requirements specified by NCA are required. In lieu of a OVERPACK Specification, Design Design Specification and Design Report, the HI-STORM steel Report, Overpressure FSAR includes the design criteria, service conditions, and structure, and Protection Report, load combinations for the design and operation of the HI-HI-TRAC Certification of STORM 100 System as well as the results of the stress TRANSFER Construction Report, analyses to demonstrate that applicable Code stress limits CASK steel Data Report, and are met. Additionally, the fabricator is not required to have structure other administrative an ASME-certified QA program. All important-to-safety controls for an ASME activities are governed by the NRC-approved Holtec QA Code stamped program.
vessel.
Because the cask components are not certified to the Code, the terms Certificate Holder and Inspector are not germane to the manufacturing of NRC-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 QA/QC personnel of the CoC holder and its vendors assigned to oversee and inspect the manufacturing process.
MPC NB-1100 Statement of MPC enclosure vessel is designed and will be fabricated requirements for in accordance with ASME Code,Section III, Subsection Code stamping of NB to the maximum practical extent, but Code stamping components. is not required.
Certificate of Compliance No. 1014 Appendix B Renewed Amendment No. 4 3-4
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 Measures ASME Code 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 MPC) retaining structural are welded to the inside of the pressure-retaining MPC attachment to a 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 limits the component of Subsection NG and the lift lugs and associated unless the weld is attachment welds are designed to satisfy the stress limits more than 2t from the of Subsection NF, as a minimum. These attachments pressure-retaining and their welds are shown by analysis to meet the portion of the respective stress limits for their service conditions.
component, where t Likewise, non-structural items, such as shield plugs, is the nominal spacers, etc. if used, can be attached to pressure-thickness of the retaining parts in the same manner.
pressure-retaining material.
NB-1132.2(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 Renewed Amendment No. 4 Appendix B 3-5
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 Measures ASME Code Section/Article MPC, MPC NB-3100 Provides These requirements are not applicable. The HI-STORM basket NG-3100 requirements for FSAR, serving as the Design Specification, establishes assembly, HI- NF-3100 determining design the service conditions and load combinations for the STORM loading conditions, 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 a dimensions of the bevel in the MPC baseplate, which makes it different than welds and throat any of the representative configurations depicted in Figure thickness shall be as NB-4243-1. The transverse thickness of this weld is equal shown in Figure NB- to the thickness of the adjoining shell (1/2 inch). The weld 4243-1. 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.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-6
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 Alternative, Justification & Compensatory Measures ASME Code Section/Article MPC, MPC NB-4120 NB-4121.2, NG- In-shop operations of short duration that apply heat to a Basket NG-4120 4121.2, and NF- component, such as plasma cutting of plate stock, welding, Assembly, HI- NF-4120 4121.2 provide machining, coating, and pouring of lead are not, unless STORM requirements for explicitly stated by the Code, defined as heat treatment OVERPACK repetition of tensile or operations.
steel impact tests for structure, and material subjected to For the steel parts in the HI-STORM 100 System HI-TRAC heat treatment during components, the duration for which a part exceeds the TRANSFER fabrication or off-normal temperature limit defined in Chapter 2 of the CASK steel installation. 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 structure manufacturing process (such as the HI-TRAC lead pouring process).
MPC, MPC NB-4220 Requires certain The cylindricity measurements on the rolled shells are not basket NF-4220 forming tolerances to specifically recorded in the shop travelers, as would be assembly, HI- be met for cylindrical, the case for a Code-stamped pressure vessel. Rather, STORM conical, or spherical the requirements on inter-component clearances (such OVERPACK shells of a vessel. as the MPC-to-TRANSFER CASK) are guaranteed steel through fixture-controlled manufacturing. The fabrication structure, and specification and shop procedures ensure that all HI-TRAC dimensional design objectives, including inter-component TRANSFER annular clearances are satisfied. The dimensions CASK steel required to be met in fabrication are chosen to meet the structure 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 NB-4243 Full penetration MPC lid and closure ring are not full penetration welds.
Closure Ring welds required for They are welded independently to provide a redundant Welds Category C Joints seal. Additionally, a weld efficiency factor of 0.45 has (flat head to main been applied to the analyses of these welds.
shell per NB-3352.3).
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-7
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 Measures ASME Code Section/Article MPC Lid to NB-5230 Radiographic (RT) or Only UT or multi-layer liquid penetrant (PT) examination Shell Weld ultrasonic (UT) is permitted. If PT alone is used, at a minimum, it will examination required 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 following Enclosure pressure retaining fuel assembly loading. The MPC enclosure vessel shall then Vessel and systems shall be be pressure tested as defined in Chapter 9. Accessibility for Lid pressure tested. 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 XI 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 users 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.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-8
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 Measures ASME Code Section/Article MPC NB-7000 Vessels are required No overpressure protection is provided. The function of Enclosure to have overpressure the MPC enclosure vessel is to contain the radioactive Vessel protection 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 requirements.
ASME-approved material supplier.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-9
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 Measures ASME Code 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 the single continuous geometry and stress analysis imperatives for the fuel basket: For weld to be less than the longitudinal MPC basket fillet welds, the following criteria apply: 1) The specified fillet weld throat dimension must be the specified fillet maintained over at least 92 percent of the total weld length. All weld dimension by regions of undersized weld must be less than 3 inches long and not more than 1/16 separated from each other by at least 9 inches. 2) Areas of inch, provided that undercuts and porosity beyond that allowed by the applicable the total undersize ASME Code shall not exceed 1/2 inch in weld length. The total portion of the weld length of undercut and porosity over any 1-foot length shall not does not exceed 10 exceed 2 inches. 3) The total weld length in which items (1) and percent of the length (2) apply shall not exceed a total of 10 percent of the overall weld of the weld. Individual length. The limited access of the MPC basket panel longitudinal fillet welds makes it difficult to perform effective repairs of these undersize weld welds and creates the potential for causing additional damage to portions shall not the basket assembly (e.g., to the neutron absorber and its exceed 2 inches in sheathing) if repairs are attempted. The acceptance criteria length. 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 10CFR71 and 10CFR72 stamping and reports requirements. Code stamping is not required. The MPC per NCA-8000. 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 requirements.
Structure ASME-approved material supplier.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-10
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 Measures ASME Code 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 requirements.
Structure ASME-approved 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 plates primary member of are only loaded during lifting conditions and have large thickness 1 inch or safety factors during lifting. Likewise, the top lid plate to greater is loaded to lid shell weld has a large structural margin under the transmit loads in the inertia loads imposed during a non-mechanistic tipover through thickness event.
direction.
OVERPACK NF-3256 Provides Welds for which no structural credit is taken are identified Steel NF-3266 requirements for as Non-NF welds in the design drawings. These non-Structure welded joints. 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.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-11
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 Measures ASME Code 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 load CASK 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.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-12
Design Features 3.0 DESIGN FEATURES (continued) 3.4 Site-Specific Parameters and Analyses Site-specific parameters and analyses that will require verification by the system user are, as a minimum, as follows:
- 1. The temperature of 80o F is the maximum average yearly temperature.
- 2. The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40o F and less than 125o 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:
GH + : GV < :
where : is either the Coulomb friction coefficient for the cask/ISFSI 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 of :, but only applies to ISFSIs 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/ISFSI 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 sites Design Basis Earthquake.
Table 3-2 (not used)
(continued)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-13
Design Features 3.0 DESIGN FEATURES 3.4 Site-Specific Parameters and Analyses (continued)
- 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 sites 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 gs.
- 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:
GH < 2.12 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: > 80 ksi Ultimate Strength at Ambient Temperature: > 125 ksi Initial Tensile Pre-Stress: > 55 ksi AND < 65 ksi NOTE: The above anchorage specifications are required for the seismic (continued)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-14
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 gs 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 gs 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 10CFR72.104(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category.
(continued)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-15
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 > 0o 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.
- 10. Users shall establish procedural and/or mechanical barriers to ensure that during LOADING OPERATIONS and UNLOADING OPERATIONS, either the fuel cladding is covered by water, or the MPC is filled with an inert gas.
(continued)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-16
Design Features 3.0 DESIGN FEATURES 3.5 Cask Transfer Facility (CTF) 3.5.1 TRANSFER CASK and MPC Lifters Lifting of a loaded TRANSFER CASK and MPC 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 10 CFR Part 50.
3.5.2 CTF Structure Requirements 3.5.2.1 Cask Transfer Station and Stationary Lifting Devices
- 1. The metal weldment structure of the CTF structure shall be designed to comply with the stress limits of ASME Section III, 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 III, Subsection NF.
- 2. If a portion of the CTF structure is constructed of reinforced concrete, then the factored load combinations set forth in ACI-318 (89) for the loads defined in Table 3-3 shall apply.
- 3. The TRANSFER CASK and MPC lifting device used with the CTF shall be designed, fabricated, operated, tested, inspected and maintained in accordance with NUREG-0612, Section 5.1.
- 4. The CTF shall be designed, constructed, and evaluated to ensure that if the MPC 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 Renewed Amendment No. 4 Appendix B 3-17
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, it 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 Renewed Amendment No. 4 Appendix B 3-18
Design Features 3.0 DESIGN FEATURES Table 3-3 Load Combinations and Service Condition Definitions for the CTF Structure (Note 1)
Load Combination ASME III Service Condition Comment for Definition of Allowable Stress D* All primary load bearing Level A members must satisfy Level A D+S 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 Renewed Amendment No. 4 Appendix B 3-19
Design Features 3.0 DESIGN FEATURES 3.6 Forced Helium Dehydration System 3.6.1 System Description Use of the Forced Helium Dehydration (FHD) system, (a closed-loop system) is an alternative to vacuum drying the MPC for moderate burnup fuel (< 45,000 MWD/MTU) and mandatory for drying MPCs containing one or more high burnup 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 15oF higher than the saturation temperature at coincident pressure.
3.6.2.2 The pressure in the MPC cavity space shall be < 60.3 psig (75 psia).
3.6.2.3 The hourly recirculation rate of helium shall be > 10 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 < 21oF for a period of 30 minutes or if the dew point of the gas exiting the MPC is verified by measurement to remain
< 22.9oF for > 30 minutes.
3.6.2.5 The condensing module shall be designed to de-vaporize the recirculating helium gas to a dew point < 120oF.
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.
(continued)
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-20
Design Features 3.0 DESIGN FEATURES 3.6 Forced Helium Dehydration System (continued) 3.6.3 Fuel Cladding Temperature 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 Renewed Amendment No. 4 Appendix B 3-21
Design Features 3.0 DESIGN FEATURES 3.7 Supplemental Cooling System 3.7.1 System Description 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 (20ºF) and the air-cooled heat exchanger sized for the design basis heat load at an ambient air temperature of 100ºF. 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 400ºC (752ºF). All heat transfer surfaces in heat exchangers shall be assumed to be fouled to the maximum limits specified in a widely used heat exchange 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 Renewed Amendment No. 4 Appendix B 3-22
Design Features 3.0 DESIGN FEATURES 3.7 Supplemental Cooling System (continued) 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 minimum design pressure rating of the pump shut-off pressure plus 15 psi.
Certificate of Compliance No. 1014 Renewed Amendment No. 4 Appendix B 3-23
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 Renewed Amendment No. 4 Appendix B 3-24