ML22098A246: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
Line 20: Line 20:


=Text=
=Text=
{{#Wiki_filter:RENEWED CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX 13 APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STORM 100 GASK SYSTEM AMENDMENT NO. 3
{{#Wiki_filter:}}
 
TABLE OF CONTENTS 1.0      DEFIN ITIO NS .................................................                        1-1 2.0      APPROVED CONTENTS ......................................                                2-1 3.0      DESIGN FEATURES ............................................                            3-1 3.1            S ite    ..................................................                      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 (p = 0.53) .......................                  3-8 Table 3-3      Load Combinations and Service Condition Definitions For the CTF Structure ................................                3-20 3-14 Certificate of Compliance No. 1014 Renewed Amendment No. 3 Appendix B                                                  i
 
Definitions 1.0 1.0 Definitions
  ---------------------------------------------------------NOT E------------------------------------------------------------
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, whose structural integrity has been impaired such that geometric rearrangement of fuel or gross failure of the cladding is expected, or 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 Certificate of Compliance No. 1014                                                          Renewed Amendment No. 3 Appendix B                                                  1-1
 
Definitions 1.0
: 1. 0 Definitions (continued)
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.
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.
MULTl-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.
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.
Certificate of Compliance No. 1014                                      Renewed Amendment No. 3 Appendix B                                    1-2
 
Definitions 1.0 1.0 Definitions (continued)
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.
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 to and from the ISFSI. TRANSPORT OPERATIONS begin when the OVERPACK or TRANSFER CASK is first suspended from or secured on the transporter and end when the OVERPACK or TRANSFER CASK is at its destination and no longer secured on or suspended from the transporter.
TRANSPORT OPERATIONS include transfer of the MPC between the OVERPACK and the TRANSFER CASK.
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.
Certificate of Compliance No. 1014                                    Renewed Amendment No. 3 Appendix B                                    1-3
 
Definitions 1.0 1.0 Definitions (continued)
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. 3 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 10xi0D and 10xl OE fuel assemblies, which may be stored with or without ZR or stainless steel channels.
2.1.2  Uniform Fuel Loadinq 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. 3 Appendix B                                          2-1
 
Approved Contents 2.0 2.0 Approved Contents 2.1      Fuel Specifications and Loading Conditions (cont'd) 2.1.3    Reqionalized Fuel Loadinq 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, respectively 1 . 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 hours, 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.
        '    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. 3 Appendix B                                            2-2
 
Approved Contents
 
==2.0 LEGEND==
REGION 1:
REGION 2:    [ I Figure 2.1-1 Fuel Loading Regions - MPC-24 Certificate of Compliance No. 1014                            Renewed Amendment No. 3 Appendix 8                                    2-3
 
Approved Contents 2.0 LE]GEND:
REGION 1:
REGION 2:      I    ,
91, Ll Figure 2.1-2 Fuel Loading Regions - MPC-24E/24EF Certificate of Compliance No. 1014 Appendix B                                  2-4                Renewed Amendment No. 3
 
Approved Contents
 
==2.0 LEGEND==
REGION 1:
REGION 2:
193
                                                    ....          I    J  .......
                                                        . . ..  . I  . .    . .    .  . . . . . . . . . *. . .    .    .
                                                          . .... . I  I  I I I I        ... t . . . . . . I. . . . . . ..
                                              . . . . . . . . . . . . . . . .I J. . . . . . . . . . . . . . . . . . . ..
Figure 2.1-3 Fuel Loading Regions - MPC-32/32F Certificate of Compliance No. 1014                                                          Renewed Amendment No. 3 Appendix B                                  2-5
 
Approved Contents
 
==2.0 LEGEND==
REGION 1:
90' REGION 2-:
1        2 a*zNK A            3  4            6      7  8 I
45 0  4                        59      50 XV ~    F      ~  Y    U      NPfl            I '7,J
                                  . 61              Ill a
95i V U6    J 68 270' Figure 2.1-4 Fuel Loading Regions - MPC-68/68FF Renewed Amendment No. 3 Certificate of Compliance No. 1014 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                    Cooling time > 8 years and an average 14x14D,14x14E, and              burnup < 40,000 MWD/MTU.
15x1 5G Cooling time and average burnup as ii. All Other Array/Classes specified in Section 2.4.
iii. NON-FUEL HARDWARE              As specified in Table 2.1-8.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                      2-7
 
Approved Contents 2.0 Table 2.1-1 (page 2 of 39)
Fuel Assembly Limits I. MPG MODEL: MPC-24 (continued)
A. Allowable Contents (continued)
: d. Decay Heat Per Fuel Storage Location:
: i. Array/Classes 14x14D,          710 Watts 14x14E, 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 MPG: 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.
Renewed Amendment No. 3 Certificate of. Compliance No. 1014 Appendix B                                        2-8
 
Approved Contents 2.0 Table 2.1-1 (page 3 of 39)
Fuel Assembly Limits 11.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 10xlOD and        Cooling time > 10 years and an average 10xl0E                          burnup < 22,500 MWD/MTU.
iv. All Other Array/Classes          As specified in Section 2.4.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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 10xlOD and      < 95 Watts 1Oxl OE 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 Ibs, including channels Renewed Amendment No. 3 Certificate of Compliance No. 1014 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 orwithout 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.
4.0 wt%  2-U ii. All Other Array/Classes 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 10x1 OD and                Cooling time > 10 years and an average 10x1 OE                                burnup _ 22,500 MWD/MTU.
iv. All Other Array Classes                    As specified in Section 2.4.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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 10x1 OD and          < 95 Watts 10xl0E iv. All Other Array/Classes            As specified ir Section 2.4.
: f. Fuel Assembly Length:
: i. Array/Class 6x6A, 6x6C, 7x7A,      < 135.0 inche, s (nominal design) or8x8A ii. All Other Array/Classes            < 176.5 inchec (nominal design)
: g. Fuel Assembly Width:
: i. Array/Class 6x6A, 6x6C, 7x7A,      < 4.70 inches (nominal design) or8x8A ii. All Other Array/Classes            < 5.85 inches nominal-design)
: h. Fuel Assembly Weight:
: i. Array/Class 6x6A, 6x6C, 7x7A,      < 550 Ibs, inclLiding channels and DFC or 8x8A ii. All Other Array/Classes            < 700 Ibs, inclu ding channels and DFC Renewed Amendment No. 3 Certificate of Compliance No. 1014 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 Ibs, including channels Renewed Amendment No. 3 Certificate of Compliance No. 1014 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 Ibs, including channels and DFC Renewed Amendment No. 3 Certificate of Compliance No. 1014 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 (ThO 2 and U0 2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:
: a. Cladding Type:                          ZR
: b. Composition:                              98.2 wt.% ThO 2 , 1.8 wt. % UO 2 with an enrichment of 93.5 wt. % 23U.
: 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 Ibs, including fuel Renewed Amendment No. 3 Certificate of Compliance No. 1014 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 10xi0D and 10xl0E 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.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                        2-16
 
Approved Contents 2.0 Table 2.1-1 (page 11 of 39)
Fuel Assembly Limits II1. 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 Ibs, including channels Certificate of Compliance No. 1014                                          Renewed Amendment No. 3 Appendix B                                        2-17
 
Approved Contents 2.0 Table 2.1-1 (page 12 of 39)
Fuel Assembly Limits II1. 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 Ibs, including channels and DFC Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                      2.-18
 
Approved Contents 2.0 Table 2.1-1 (page 13 of 39)
Fuel Assembly Limits I1l. 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 Ibs, including channels and DFC Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                    ?-1 9
 
Approved Contents 2.0 Table 2.1-1 (page 14 of 39)
Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
: 4. Mixed oxide (MOX), BWR INTACT FUEL ASSEMBLIES, with or without ZR channels. MOX BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
: a. Cladding Type:                        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 Ibs, including channels Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                    2 -20
 
Approved Contents 2.0 Table 2.1-1 (page 15 of 39)
Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
: 5. Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without ZR channels, placed in DAMAGED FUEL CONTAINERS. MOX BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
: a. Cladding Type:                      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 Ibs, including channels and DFC Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                    2-21
 
Approved Contents 2.0 Table 2.1-1 (page 16 of 39)
Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
: 6. Mixed Oxide (MOX), BWR FUEL DEBRIS, with orwithoutZR 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. OriginalFuel Assembly Width:          < 4.70 inches (nominal design)
: h. Fuel Debris Weight:                  < 550 Ibs, including channels and DFC Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix 8                                    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 (ThO 2 and U0 2 ) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:
: a. Cladding Type:                        ZR
: b. Composition:                          98.2 wt.% ThO 2, 1.8-wt. % U0 2 with an 5
enrichment of 93.5 wt. %  23  U.
: 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 Ibs, including fuel Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                      2-23
 
Approved Contents 2.0 Table 2.1-1 (page 18 of 39)
Fuel Assembly Limits Ill. MPC MODEL: MPC-68F (continued)
B. Quantity per MPC (up to a total of 68 assemblies):
(All fuel assemblies must be array/class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A):
Up to four (4) DFCs containing uranium oxide BWR FUEL DEBRIS or MOX BWR FUEL DEBRIS. The remaining MPC-68F fuel storage locations may be filled with fuel assemblies of the following type, as applicable:
: 1. Uranium oxide BWR INTACT FUEL ASSEMBLIES;
: 2. MOX BWR INTACT FUEL ASSEMBLIES;
: 3. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES placed in DFCs;
: 4. MOX BWR DAMAGED FUEL ASSEMBLIES placed in DFCs; or
: 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.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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, 14x14E,          Cooling time > 8 years and an average and 15x15G                          burnup < 40,000 MWD/MTU.
ii. All Other Array/Classes              As specified in Section 2.4.
iii. NON-FUEL HARDWARE                    As specified in Table 2.1-8.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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,            < 710 Watts.
14x14E, 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)
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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,            Cooling time > 8 years and an average 14x14E, and 15x15G              burnup < 40,000 MWD/MTU.
ii. All Other Array/Classes          As specified in Section 2.4.
iii. NON-FUEL HARDWARE                As specified in Table 2.1-8.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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.
14x14E, 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)
: 8. Quantity per MPC: Up to four (4) DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 3, 6, 19 and/or 22. The remaining MPC-24E fuel storage locations may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.
C.      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.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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,            Cooling time > 9 years and an average 14x14E, and 15x15G              burnup < 30,000 MWD/MTU or cooling time > 20 years and an average burnup <
40,000 MWD/MTU.
ii. All Other Array/Classes          As specified-in-Section 2.4.
As specified in Table 2.1-8.
iii. NON-FUEL HARDWARE Renewed Amendment No. 3 Certificate of Compliance No. 1014 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:
                                                    < 500 Watts
: i. Array/Classes 14x14D, 14x14E, and 15x15G As specified in Section 2.4.
ii. All Other Array/Classes
: 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. 3 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 th-e-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,              Cooling time > 9 years and an average 14x14E, and 15x15G              burnup <30,000 MWD/MTU or cooling time > 20 years and an average 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. 3 Appendix B                                      2-31
 
Approved Contents 2.0 Table 2.1-1 (page 26 of 39)
Fuel Assembly Limits V. MPG MODEL: MPC-32 (continued)
A. Allowable Contents (continued)
: d. Decay Heat Per Fuel Storage Location:
L Array/Classes 14x14D,          500 Watts.
14x14E, 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)
: 8. . Quantity per MPG: 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.
C. FUEL DEBRIS is not authorized for loading in the MPC-32.
D. One NSA is authorized for loading in the MPC-32.
Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, 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.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                      2-32
 
Approved Contents 2.0 Table 2.1-1 (page 27 of 39)
Fuel Assembly Limits VI. MPC MODEL: MPC-68FF A. Allowable Contents
: 1. Uranium oxide or MOX BWR INTACT FUEL ASSEMBLIES listed in Table 2.1-3, with or without channels and meeting the following specifications:
: a. Cladding Type:                          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 10xlOD and        Cooling time > 10 years and an average 10x1 OE                          burnup < 22,500 MWD/MTU.
iv. All Other Array/Classes          As specified in Section 2.4.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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 Wattc S iii. Array/Classes 1OxIOD and          < 95 Watts 10xl0E iv. All Other Array/Classes          As specified iin Section 2.4.
: f. Fuel Assembly Length
: i. Array/Class 6x6A, 6x6B,            < 135.0 inche s (nominal design) 6x6C, 7x7A, or 8x8A ii. All Other Array/Classes            < 176.5 inche.s (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, inchuding channels 7x7A, or 8x8A ii. All Other Array/Classes            < 700 lbs, incl uding channels Renewed Amendment No. 3 Certificate of Compliance No. 1014 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-6applicable 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.
                                                        < 4.0 wt.%  23 ii. All Other Array Classes                            U.
: 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 Bumup 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 1 0x1 OD 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.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                          2-35
 
Approved Contents 2.0 Table 2.1-1 (page 30 of 39)
Fuel Assembly Limits Vl. 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    10xl0D 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 Ibs, including channels and DFC 7x7A, or 8x8A ii. All Other Array/Classes            < 700 lbs, including channels and DFC Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                            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:
: i. Uranium Oxide BWR INTACT FUEL ASSEMBLIES; or ii. MOX BWR INTACT FUEL ASSEMBLIES.
C. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC-68FF. The Antimony-Beryllium source material shall be in a water rod location.
D. Array/Class 10x1 OD and 10x1 OE fuel assemblies in stainless steel channels must be stored in fuel storage locations 19 - 22, 28 - 31, 38 -41, and/or 47 - 50.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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, 14x14E,      Cooling time > 8 years and an average and 15x15G                        burnup < 40,000 MWD/MTU.
ii. All Other Array/Classes            As specified in Section 2.4.
As specified in Table 2.1-8.
iii. NON-FUEL HARDWARE Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                        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,              < 710 Watts.
14x14E, 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)
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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,                Cooling time > 8 years and an average 14x14E, and 15x15G                burnup < 40,000 MWD/MTU.
ii. All Other Array/Classes            As specified in Section 2.4.
iii. NON-FUEL HARDWARE                  As specified in Table 2.1-8.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                        2-40
 
Approved Contents 2.0 Table 2.1-1 (page 35 of 39)
Fuel Assembly Limits VII. MPG MODEL: MPC-24EF (continued)
A. Allowable Contents (continued)
: d. Decay Heat Per Fuel Storage Location:
                                                    .=:: 710 Watts.
: i. Array/Classes 14x14D, 14x14E, and 15x15G As specified in Section 2.4.
ii. All Other Array/Classes
: 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)
: 8. Quantity per MPG: 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, 1 O, 15, and/or
: 16. These requirements are in addition to any other requirements specified for uniform or regionalized fuel loading.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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 FUELASSEMBLIES 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,            Cooling time_> 9 years and an average 14x14E, and 15x15G              burnup <30,000 MWD/MTU or cooling time > 20 years and an average 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.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                    2-42
 
Approved Contents 2.0 Table 2.1-1 (page 37 of 39)
Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (cont'd)
A. Allowable Contents (cont'd)
: d. Decay Heat Per Fuel Storage Location:
: i. Array/Classes 14x14D,
                                                    < 500 Watts.
14x14E, 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)
Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                      2-43
 
Approved Contents 2.0 Table 2.1-1 (page 38 of 39)
Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (cont'd)
A. Allowabe Contents (c-nt'd) ...
: 2. Uranium oxide, PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS, with or without NON-FUEL HARDWARE, placed in DAMAGED FUEL CONTAINERS. Uranium oxide PWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS shall meet the criteria specified in Table 2.1-2 and meet the following specifications (Note 1):
: a. CladdingType"....                      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,              Cooling time > 9 years and an average 14x14E, and 15x15G              burnup <30,000 MWD/MTU or cooling time > 20 years and an average 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.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 Appendix B                                      2-44
 
Approved Contents 2.0 Table 2.1-1 (page 39 of 39)
Fuel Assembly Limits VIII. MPC MODEL: MPC-32F (cont'd)
A. Allowable Contents (cont'd)
: d. Decay Heat Per Fuel Storage Location:
: i. Array/Classes 14x14D,          .s 500 Watts.
14x14E, and 15x15G ii. All Other Array/Classes      As specified in Section 2.3.
: e. Fuel Assembly Length              .s 176.8 inches (nominal design)
: f. Fuel Assembly Width              .s 8.54 inches (nominal design)
: g. Fuel Assembly Weight                .s 1,680 lbs (including NON-FUEL HARDWARE and DFC)
B. Quantity per MPC: Up to eight (8) DAMAGED FUEL ASSEMBLIES and/or FUEL DEBRIS in DAMAGED FUEL CONTAINERS, stored in fuel storage locations 1, 4, 5, 10, 23, 28, 29, and/or 32. The remaining MPC-32F fuel storage locations may be filled with PWR INTACT FUEL ASSEMBLIES meeting the applicable specifications.
C. One NSA is permitted for loading in the MPC-32F.
Note 1: Fuel assemblies containing BPRAs, TPDs, WABAs, water displacement guide tube plugs, orifice rod assemblies, or vibration suppressor inserts may be stored in any fuel storage location. Fuel assemblies containing CRAs, RCCAs, CEAs, 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.
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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 (kg/assy.) (Note 3)        s 365            S 412            .:5.438        .:5.400          .:5.206 Initial Enrichment (MPC-24, 24E and 24EF without S 4.6 (24)    s 4.6 (24)        s 4.6 (24)      .:5.4.0 (24)      s5.0 (24) soluble boron s5.0            s5.o              s5.0          s5.o              sS.O credit)
(24E/24EF)      (24E/24EF)        (24E/24EF)    (24E/24EF)        (24E/24EF)
(wt% 235U)
(Note 7)
Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F s5.o            s5.o              s5.0          sS.O              ss.o with soluble boron credit - see Note 5)
(wt% 23sU)
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 1.D.
_s 0.3514      _s 0.3734        s0.3880        .s0.3890          .s 0.3175 (in.)
Fuel Pellet Dia.
(in.)                    _s 0.3444      s0.3659          s0.3805        .s0.3835          s0.3130 (Note 8)
Fuel Rod Pitch (in.)        .s0.556        .s 0.556          .s0.580        s0.556              Note 6 Active Fuel Length (in.)
                              .s 150          .s 150            .s 150        .s 144            .s 102 No. of Guide and/or Instrument Tubes 17              17        5 (Note 4)            16                0 Guide/lnstrument Tube                      .:! 0.017      .:! 0.017        .:! 0.038    .:! 0.0145              NIA Thickness (in.}
Renewed Amendment No. 3 Certificate of Compliance No. 1014 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.)                ,:s 473          !S473                !S473        !S495          ,:s 495          !S495 (Note 3)
Initial Enrichment (MPC-24, 24E and        ,:s 4.1 (24)    ,:s 4.1 (24)        ,:s 4.1 (24)  !S4.1 (24)    !S4.1 (24)      ,:s 4.1 (24)
* 24EF without soluble boron credit)        ,:s 4.5          ,:s 4.5              !S4.5        !S4.5            ,:s 4.5        !S4.5
- (wt% 23su)            (24E/24EF)        (24E/24EF)        _ (24E/24EF)      (24E/24EF)    (24E/24EF)        (24E/24EF)
(Note 7)
Initial Enrichment (MPC-24, 24E, 24EF, 32, or 32F with soluble boron
                              ,:s 5.0          !S5.0                !S5.0        !S5.0            ,:s 5.0          !S5,0 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.
(in.)
                          ,:s 0.3660        !S0.3736            ,:s 0.3640      !S0.3800      !S0.3790          !S0.3820 Fuel Pellet Dia. (in.)
                        !S0.3580          !S0.3671            !S0.3570        !:0.3735      !S 0.3707        !S0.3742 (Note 8)
Fuel Rod Pitch {in.)      !S0.550          !S0.563              !S0.563        !S0.568        ,:s 0.568        ,:s 0.568 Active Fuel Length (in.)
                            ,:s 150          ,:s 150              ,:s 150      !S150          ,:s 150          !S150 No. of Guide and/or 21              21                  21          17                17              17 Instrument Tubes Guide/Instrument 0.0165            0.015            0.0165        0.0150        0.0140          0.0140 Tube Thickness (in.)
Certificate of Compliance No. 1014 Appendix B                                                    2-47                      Renewed Amendment No. 3
 
Approved Contents 2.0 Table 2.1-2 (page 3 of 4)
PW R FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 15x15G          15x15H            16x16A          17x17A          17x178            17x17C Array/ Class Clad Material                ss              ZR                ZR            ZR              ZR                ZR Design Initial U (kg/assy.)                  .s 420          .s 495          .s 448          .s 433          .s 474            .5480 (Note 3)
Initial Enrichment (MPC-24, 24E, and 24EF without
                          .s 4.0 (24)    S 3.8 (24)        .s 4.6 (24)    .s 4.0 (24)    .s 4.0 (24)        .s 4.0 (24) soluble boron credit)
                              .54.5            <4.2              .s 5.0        .54.4          .s 4.4            .s 4.4 (24E/24EF)      (24E/24EF)        (24E/24EF)      (24E/24EF)      (24E/24EF)        (24E/24EF)
(wt% 2JsU)
(Note-7)            ,,
Initial Enrichment (MPC-24, 24E, 24EF,32,or32F with soluble boron
                              .55.0          .s 5.0            .s 5.0        s 5.0            .s 5.0            .55.0 credit - see Note 5)
(wt% 23sU)
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.
(in.)
                          .s 0.3890      _:s0.3700        .s 0.3320      .s 0.3150      .s 0.3310        .s 0.3330 Fuel Pellet Dia.
(in.)                    .s 0.3825      .S 0.3622          .s 0.3255      .s 0.3088      .S 0.3232          .s 0.3252 (Note 8)
Fuel Rod Pitch (in.)      .s 0.563        .50.568            .50.506        .s 0.496        .s 0.496          .s 0.502 Active Fuel Length (in.)
                            .s 144          .:s 150          .:s 150        .:s 150          .:s 150          .s 150 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 Appendix B                                              2-48                          Renewed Amendment No. 3
 
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 i$ the nominal uranium weight specified for each assembly by the fuel manufacturer or reactor user. For each PWR fuel assembly, the total uranium weight limit specified in this table may be increased up to 2.0 percent for comparison with users' fuel records to account for manufacturer's tolerances.
: 4. Each guide tube replaces four fuel rods.
: 5. Soluble boron concentration per LCO 3.3.1.
: 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.
Certificate of Compliance No. 1014 Appendix B                                  2-49                    Renewed Amendment No. 3
 
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 (kg/assy.) (Note 3)        <110            <110            <110            <100          <198        <120 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 (Nbtdf4)-                                  rods Initial Maximum Rod Enrichment                < 4.0          < 4.0          < 4.0            < 5.5          < 5.0        < 4.0 2
(wt.%    -U)
No. of Fuel Rod                      35 or 36 (up Locations                35 or 36      to 9 MOX            36              49              49    63 or 64 rods)
(in.) Rod Clad O.D.
Fuel
                          > 0.5550        > 0.5625        > 0.5630        > 0.4860        > 0.5630  > 0.4120 Fuel Rod Clad 1.0.
(in.)                    < 0.5105        < 0.4945        < 0.4990        < 0.4204        < 0.4990  < 0.3620 Fuel Pellet Dia. (in.)  < 0.4980        < 0.4820        < 0.4880        < 0.4110        < 0.4910  < 0.3580 Fuel Rod Pitch (in.)    < 0.710          < 0.710        < 0.740        < 0.631        < 0.738    < 0.523 ActiveFuelLength          < 120          < 120          < 77.5            < 80          < 150      < 120 (in.)                  _ _  _  _ _ _ _  _  _  _  _ _  _  _  _ _  _ _ _ _  _  _ _ _ __              _  _  _ _
No. of Water Rods          1orO            1 orO            0                0              0        1 orO (Note 11)                                              __r__1or0_              0              0        1_or_0 Water    Rod Thickness      (in.)        >0              >0              N/A              N/A            N/A          >0 Channel Thickness (in.)                    < 0.060        < 0.060        < 0.060          < 0.060        <0.120    < 0.100 Certificate of Compliance No. 1014 Appendix B                                            2-50                              Renewed Amendment No. 3
 
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 (kg/assy.) (Note 3)          <192      < 190          <190      <190          <191          <180 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT                    < 4.2    < 4 .2        < 4.2    < 4.2          < 4.0        < 4.2 (wt.% 2-U)
(Note 14)
Initial Maximum Rod Enrichment                    < 5.0    < 5.0          < 5.0    < 5.0        < 5.0        < 5.0 (wt.% 2U)
No. of Fuel Rod                                                                              74/66 No.tof                      63 or 64      62          60 or 61      59            64          74/66 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.
(in.)                      < 0.4295  <0.4250        < 0.4230  < 0.4250      < 0.3996      < 0.3840 Fuel Pellet Dia. (in.)      < 0.4195  < 0.4160      < 0.4140  < 0.4160      < 0.3913      < 0.3760 Fuel Rod Pitch (in.)        <0.642    < 0.641        < 0.640  < 0.640      < 0.609      < 0.566 Design Active Fuel Length (in.)                  <150      <150            <150      <150          <150          <150 No. of Water Rods              1orO        2            1-4                    N/A            2 (Note 11)                      1_or 0_2                (Note 7)                (Note 12)          2 (in.) Rod Thickness Water
                            > 0.034    > 0.00        > 0.00    > 0.034      > 0.0315        > 0.00 Channel Thickness (in.)      < 0.120    < 0.120        < 0.120  < 0.100      < 0.055      < 0.120 Certificate of Compliance No. 1014 Appendix B                                        2-51                    Renewed Amendment No. 3
 
Approved Contents 2.0 Table 2.1-3 (page 3 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly              9x9B          9x9C          9x9D            9x9E        9x9F        9x9G Array/Class                                                          (Note 13)    (Note 13)
Clad Material                ZR            ZR            ZR              ZR          ZR          ZR Design Initial U            <1                                          <183        <183        <164 (kg/assy.) (Note 3)        <180          <182          <182            _            _
Maximum PLANAR-AVERAGE INITIAL
  -ENRICHMENT                  < 4.2          < 4.2          < 4.2          < 4.0        < 4.0        <4.2 (wt.% 2U)
(Note 14)
Initial Maximum Rod Enrichment                  < 5.0          < 5.0        < 5.0            < 5.0        < 5.0        < 5.0 (wt.% 2U)
No. of Fuel Rod              72            80            79              76          76          72 Locations Fuel Rod Clad O.D.
(in.)                    > 0.4330      > 0.4230      > 0.4240        > 0.4170    > 0.4430    > 0.4240 Fuel Rod Clad I.D.
(in.)                    <0.3810        < 0.3640      <0.3640        <0.3640      <0.3860      <0.3640 Fuel Pellet Dia. (in.)    <0.3740        < 0.3565      < 0.3565        < 0.3530    < 0.3745    < 0.3565 Fuel Rod Pitch (in.)      < 0.572        < 0.572      < 0.572          < 0.572      < 0.572      < 0.572 Design Active Fuel          <        150                <150            <150        <150        <150 Length (in.)                <_5__5__5__5                                              <_150_<_150 No. of Water Rods        1 (Note 6)          1              2                5                    (    1 (Note 11)                1_(Noe__)_                        2    _(Note                                  6) water Rod Thickness (in.)                      > 0.00        > 0.020      > 0.0300        > 0.0120    > 0.0120    > 0.0320 (in.)
Channel Thickness (in.)    _< 0.120  -T  < 0.100      _< 0.100        _< 0.120    _< 0.120    _< 0.120 Certificate of Compliance No. 1014 Appendix B                                          2-52                        Renewed Amendment No. 3
 
Approved Contents 2.0 Table 2.1-3 (page 4 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly Array/Class              1OxlOA        10x10B        1Oxl0C        lOxIOD      1Oxl0E Clad Material                              ZR            ZR          ZR            SS          SS Design Initial U (kglassy.) (Note 3)    <188          <188        <179          <125        <125 Maximum PLANAR-AVERAGE INITIAL ENRICHMENT                              <4.2          <4.2          <4.2          <4.0        <4.0 (wt.% MiU)
(Note 14)
Initial-Maximum Rod Enrichment (wt.% -SU)                              < 5.0          .5.0    _<    5.0          _<
: 5.        < 5.
No. of Fuel Rod Locations                92178        91/83 (Note 8)      (Note 9)        96            100        96 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  1    < 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      <50.055      < 0.080      < 0.080 Certificate of Compliance No. 1014 Appendix B                                                                  Renewed Amendment No. 3 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. % 2 5U and < 1.578 wt. % total fissile plutonium (239Pu and 241Pu), (wt. % of total fuel weight, i.e., U0 2 plus PuO 2).
: 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.
11i      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.% 21U, as applicable.
Certificate of Compliance No. 1014                                            Renewed Amendment No. 3 Appendix B                                            2-54
 
Approved Contents 2.0 Table 2.1-4 TABLE DELETED Certificate of Compliance No. 1014 Appendix B                                      Renewed Amendment No. 3 2-55
 
Approved Contents 2.0 Table 2.1-5 TABLE DELETED Certificate of Compliance No. 1014 Appendix B                                      Renewed Amendment No. 3 2-56
 
Approved Contents 2.0 Table 2.1-6 (page 1 of 2)
TABLE DELETED Certificate of Compliance No. 1014 Renewed Amendment No. 3 Appendix B                                  2-57
 
Approved Contents 2.0 Table 2.1-6 (page 2 of 2)
TABLE DELETED Certificate of Compliance No. 1014 Appendix B                                  2-58            Renewed Amendment No. 3
 
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. 3
 
Approved Contents 2.0 Table 2.1-7 (page 2 of 2)
TABLE DELETED Certificate of Compliance No. 1014 Appendix B                                                  Renewed Amendment No. 3 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            NSAorGUIDE                CONTROL                  APSR Cooling Time                  (Note 4)        TUBE HARDWARE            COMPONENT                BURNUP (years)                  BURNUP                  (Note 5)              (Note 6)            (MWD/MTU)
(MWO/MTU)              BURNUP                BURNUP (MWD/MTU)              (MWD/MTU)
            ?:.3                  s24,635              NA (Note 7)                NA                      NA
            ?:.4                  s3o,ooo                s20,ooo                  NA                      NA
            ?:.5                  S 36,748              s25,ooo              s63o,ooo                !: 45,000
            ?:.6                  S 44,102              s30,000                                      s54,500
            ?:.7                  s52,900                s4o,ooo                                      s68,000
            ?:.8                  S 60,000              s 45,000                                    s83,000
            ?:.9                                        s50,000
* s111,000
          ?:,.10                                        s60,000                                      S 180,000
          ?:.11                                          s 75,000                                    s630,000
          ?:,.12                                          S 90,000
          ?:.13                                          !: 180,000
        ?:.14                                          s630,000 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 ands 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 Renewed Amendment No. 3 Certificate of Compliance No. 1014 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)
MPC Mode II                      Decay Heat per Fuel Storage Location I_                (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. 3 Appendix B
 
Approved Contents 2.0 2.4.2      Regionalized Fuel Loading Decay Heat Limits for ZR-Clad Fuel (cont'd)
Table 2.4-2 Fuel Storage Regions and Maximum Decay Heat per MPC Number of Fuel          Inner Region          Outer Region MPC Model            Storage Locations        Maximum Decay          Maximum Decay 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:
0    Minimum fuel assembly cooling time 0    Maximum fuel assembly decay heat 0    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, F_2.
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 q1) + (C x q3) + [D x (E) 21+ (E x q x E) + (F x q2 x E) + 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. 3 Appendix B
 
Approved Contents 2.0 2.4.3    Burnup Limits as a Function of Cooling Time for ZR-Clad Fuel (cont'd) q      Maximum allowable decay heat per fuel storage location determined in Section 2.4.1 or 2.4.2 (kW)
E23 = Minimum fuel assembly average enrichment (wt. %        23U)
(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 burnuplimits 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. 3 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
                                        . - - ---        -150707 407255
                                                                    ------    -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        74.424.9    -3687j.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      11779.6          -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. 3 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. 3 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 14x1 4C 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. 3 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 2!3        1&sect;.789.2      119.829          .8071          * -27.422            2152.53            -267.117              -5803-68 2!4        26803.8      -3312.93          415.027              -116.279          2550.15            -386.33              -367.168 2!5        36403.6      -7831.93          1219.66            -126.065            2858.32            -471.785              326.863 2!6          44046.1      -12375.9          2213.52            -145.727            3153.45            -539.715              851.971 2!7          49753.5      -16172.6          3163.61            -166.946            3428.38          -603.598              1186.31 2!8          55095.4      -20182.5          4287.03              -183.047            3650.42            -652.92              1052.4 2!9          58974.4      -23071.6          5156.53            -191.718            3805.41            -687.18                1025 2!10          62591.8      -25800.8          5995.95              -195.105          3884.14            -690.659              868.556 2!11          65133.1      -27747.4              6689              -203.095          4036.91            -744.034              894.607 2! 12        68448.4        -30456            7624.9            -202.201            4083.52            -753.391              577.914 2! 13        71084.4      -32536.4          8381.78            -201.624            4117.93            -757.16              379.105 2!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          -TT9.222                57.9429 2!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 2!18          81649.2        -40583            11736.1            -187.604            4163.36          -785.838              -113.614 19            83459      -41TT1.8          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. 3 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 1Sx15D/E/F/H Time (years)            A                B            C                  D          E            F              G 3          15192.5          &sect;0.5722    2.3042          -26.906      2009.71    -235.879    1.574 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 2:10        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 2:12        65557.6        -27952.4      6686.74            -198.224      3767.28    -635.126    645.139 13          67379.4        -29239.2      719_7.49          -200.164        3858.53    -677.958      652.601 14          69599.2        -30823.8      7768.51          -196.788        3868.2      -679.88    504.443 2: 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. 3 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      -1 36.707  -2368-1      1.58  -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. 3 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    425.1,36
  >  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 a>20          100305    -59997.5    19841.1      -216.112    4721.71    -705.463    -1148.45 2-71 Certificate of Compliance No. 1014                                Renewed Amendment No. 3 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    4_7.5234
>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. 3 Appendix B
 
Approved Contents 2.0 Table 2.4-4 (Page 1 of 10)
BWA Fuel Assembly Cooling Time-Dependent Coefficients (ZR-Clad Fuel)
Cooling                                                  Array/Class 7x78 Time (years)                A              B            C              D          E              F              G
      ?_3          26409.1            28347.5    --16858      -47.076      5636.32      -1606.75      17788 4          61967.8          -6618.31    -4131.96      -113.949      6122.77      -2042.85    -96.7439 5            91601.1          -49298.3      17826.5      -132.045      8_4.14      -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. 3 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            2821-9.6      28963.7  7616,2      -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    714.41    -2637.09        -298.858 2.6            117477      -90055.9    41383.9      -154.758    7613.43    -2612.69      . -64.9921
  >7            134090        -120643    60983        -168.675    7809        -2183.3        -40.8885 2.8            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 2.10            168816      -191389    113810      -195.613    8359.87    -1244.22        -613.594 2.11          177221        -210599    131099        -208.3      8810      -1466.49        -819.773 12          183929        -224384    143405        -207.497    8841.33    -1227.71        -929.708 2.13          191093        -240384    158327        -204.95    8760.17    -811.708        -1154.76 2.14          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
: 2. 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. 3 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 k 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. 3 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                2-8463.2  -18105,5      -50.039          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  .. -
76.11                -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
?.-1-6--'      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. 3 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    --8371        -61.1-17  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. 3 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          30051i6      29548.7  --18614.2      -148.276  6148.44    -1810.34      t1006-
  >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. 3 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. 3 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. 3 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 10x1A0B 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. 3 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 10xiOC 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. 3 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 general use by 10 CFR Part 50 license holders at various site locations under the 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.
: 2.        10B loading in the neutron absorbers: > 0.0267 g/cm 2 (Boral) and > 0.0223 g/cm2 (METAMIC) 3.2.2    MPC-68 and MPC-68FF
: 1.      Fuel cell pitch: > 6.43 in.
: 2.        '1B loading in the neutron absorbers: > 0.0372 g/cm 2 (Boral) and > 0.0310 g/cm2 (METAMIC) 3.2.3    MPC-68F
: 1.        Fuel cell pitch: > 6.43 in.
: 2.      '11 loading in the Boral neutron absorbers: > 0.01 g/cm2 3.2.4    MPC-24E and MPC-24EF
: 1.      Flux trap size:
: i. Cells 3, 6, 19, and 22: > 0.776 inch ii. All Other Cells: > 1.076 inches
: 2.      10B  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
: 2.      '0 B loading in the neutron absorbers: > 0.0372 g/cm 2 (Boral) and > 0.0310 g/cm 2 (METAMIC)
Certificate of Compliance No. 1014 Appendix B                                                                    Renewed Amendment No. 3 3-1
 
Design Features 3.0 DESIGN FEATURES 3.2    Design features important for Criticality Control (cont'd) 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)
Certificate of Compliance No. 1014                                        Renewed Amendment No. 3 Appendix B 3-2
 
Design Features 3.0 DESIGN FEATURES 3.3.2  Construction/Fabrication Alternatives to Codes, Standards, and Criteria (cont'd)
: 2. Compliance with the specified requirements of the ASME Code, Section III, 1995 Edition with Addenda through 1997, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Requests for alternatives shall be submitted in accordance with 10 CFR 72.4.
(continued)
Certificate of Compliance No. 1014 Appendix B                                                                Renewed Amendment No. 3 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-1 100          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. 3 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-1 130            NB-1 132.2(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. ifused, can be attached to pressure-thickness of the          retaining parts in the same manner.
pressure-retaining material.
NB-1 132.2(e) requires that the first connecting weld of a welded nonstructural attachment to a component shall conform to NB-4430 ifthe connecting weld is within 2t from the pressure-retaining portion of the component.
MPC                  NB-2000            Requires materials to    Materials will be supplied by Holtec-approved suppliers be supplied by            with Certified Material Test Reports (CMTRs) in ASME-approved              accordance with NB-2000 requirements.
material supplier.
Certificate of Compliance No. 1014 Appendix B                                                                          Renewed Amendment No. 3 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, MPG          NB-31 00            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 .      .CategoryC) 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 Appendix B                                                                        Renewed Amendment No. 3 3-6
 
Design Features 3.0 Table 3-1 (page 4 of 9)
LIST OF ASME CODE ALTEA NATIVES FOR HI-STORM 100 CASK SYSTEM Component            - -Reference        - Code Requarement        - Alternative-, JustJficatlon & 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, sue:h 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 oarts in the HI-STORM 10(LSystern___
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 hours 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 basket                NF-4220            forming tolerances to      not specifically recorded in the shop travelers, as would assembly, HI-                            be met for cylindrical,    be the case for a Code-stamped pressure vessel.
STORM                                    conical, or spherical    Rather, the requirements on inter-component clearances QVERPACK                                  shells of a vessel.        (such as he M_PC-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 Appendix B                                                                            Renewed Amendment No. 3 3-7
 
Design Features 3.0 Table 3-1 (page 5 of 9)
LIST OF ASMECODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Reference          Code Requirement            Alternative, Justification &Compensatory Measures ASMECode Section/Article MPG 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 (AT) or      Root (if more than one weld pass is required) and final Ring, Vent                              ultrasonic (UT)          liquid penetrant examination to be performed in ana-main                                examrnation-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 vessaj  atwelded in the field-following
-Enclosure                        -- -- pressure reta1n1ng    -fijel assembly loading. The MPC enclosure vessel shall then Vessel and                              systems shall be        be pressure tested as defined in Chapter 9. Accessibility for pressure tested.        leakage Inspections preclude a Code compliant pressure test. -
Lid 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 critii:;al _flaw size shall npt cause the primary stress limits of NB-3000 to be exceeded.
The Inspection results, Including relevant findings (indications),
shall be made a permanent part of the user's records by video, photographic, or other means which provide an equivalent retrievable record of weld Integrity. The video or photographic records should be taken during the final interpretation period described In ASME Section V, Article 6, T-676. The venVdrain cover plate and the closure ring welds are confirmed by liquicf -
penetrant examination. The inspection of the weld must be performed by qualified personnel and shall meet the acceptance requirements of ASME Code Section Ill, NB-5350 for PT or NB-5332 for UT.
Certificate of Compliance No. 1014 Appendix B                                                                            Renewed Amendment No. 3 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. 3 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 MPG 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 length.The limited-access of-lhe*MPC basket panel lon-gituaina.I-
                                            - oftheweld.-lndividua1-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 fo 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 10CFA72 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                                  AS ME-approved material supplier.
Certificate of Compliance No. 1014 Renewed Amendment No. 3 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 Requfrement        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                        reqi.mements- for -*      conartions are quiiefarge. *The OVERPACK hasepiate 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__l!n_dJ:lr the
-                                    transmit-loads in-the  - inertia loads impos-ed 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 uNon-NF" welds in the design drawings. These non-Structure                            welded joints.            structural welds are -specified in accorcfan-ce with tlie pre-qualified welds of AWS D1.1. These welds shall be made by welders and weld procedures qualified in accordance with AWS 01.1 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 f abricability and accessibility of the joint, not generally contemplated by this Code section governing supports.
Certificate of Compliance No. 1014                                                  Renewed Amendment No. 3 Appendix B 3-11
 
Design Features 3.0 Table 3-1 (page 9 of 9)
LIST OF ASMECODE ALTERNATIVES FOR HI-STORM 100 CASK SYSTEM Component          Reference        Code Requirement        Alternative, Justification & Compensatory Measures ASMECode 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).
Boltedjoinls 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 Appendix B                                                                    Renewed Amendment No. 3 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 80&deg; F is the maximum average yearly temperature.
: 2.      The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40&deg; F and less than 125&deg; 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:
where &#xb5; is either the Coulomb friction coefficient for the cask/1SFSI 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 &#xb5;, but only applies to ISFSls where the casks are deployed in a freestanding configuration. Unless demonstrated by appropriate testing that a higher coefficient of friction value is appropriate for a specific ISFSI, the value used shall be 0.53. If acceleration time-histories on the ISFSI pad surface are available, GH and Gv may be the coincident values of the instantaneous net horizontal and vertical accelerations. If instantaneous accelerations are used, the inequality shall be evaluated at each time step in the acceleration time history over the total duration of the seismic event.
If this static equilibrium based inequality cannot be met, a dynamic analysis of the cask/lSFSI pad assemblage with appropriate recognition of soil/structure interaction effects shall be performed to ensure that the casks will not tip over or undergo excessive sliding under the site's Design Basis Earthquake.
Table 3-2 (not used)
(continued}
Certificate of Compliance No. 1014                                                Renewed Amendment No. 3 Appendix B 3-13
 
Design Features 3.0 DESIGN FEATURES 3.4      Site-Specific Paraeters 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 site's Design Basis Earthquake shall be established using the best estimate of the friction coefficient in an appropriate analysis model. The analysis should demonstrate that the earthquake will not result in cask tipover or cause a cask to fall off the pad. In addition, impact between casks st1ould be precluded, or should be considered an accident for which the maximum g-load experienced by the stored fuel shall be limited to 45 g's.
: c. For those ISFSI sites with design basis seismic acceleration values higher than those allowed for free-standing casks, the HI-STORM 100 System shall be anchored to the ISFSI pad. The site seismic characteristics and the anchorage system shall meet the following requirements:
: i.          The site acceleration response spectra at the top of the ISFSI pad shall have ZPAs that meet the following inequalities:
AND Where:
G H 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 ,=s 65 ksi NOTE:        The above anchorage specifications are required for the seismic (continued)
Certificate of Compliance No. 1014 Appendix B                                                                      Renewed Amendment No. 3 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 ACl-349-97. A later edition of this Code may be used, provided a written reconciliation is performed.
iii. Embedment Concrete Compressive Strength:  4,000 psi at 28 days
: 4.        The analyzed flood condition of 15 fps water velocity and a height of 125 feet of water (full submergence of the loaded cask) are not exceeded.
: 5.        The potential for fire and explosion shall be addressed, based on site-specific considerations. This includes the condition that the on-site transporter fuel tank will contain no more than 50 gallons of diesel fuel while handling a loaded OVERPACK or TRANSFER CASK.
: 6.        a.      For free-standing casks, the ISFSI pad shall be verified by analysis to limit cask deceleration during design basis drop and non-mechanistic tip-over events to
                        !: 45 g's at the top of the MPC fuel basket. Analyses shall be performed using methodologies consistent with those described in the HI-STORM 100 FSAR.
A lift height above the ISFSI pad is not required to be established if the cask is lifted with a device designed in accordance with ANSI N14.6 and having redundant drop protection features.
: b.      For anchored casks, the ISFSI pad shall be designed to meet the embedment requirements of the anchorage design. A cask tip-over event for an anchored cask is not credible. The ISFSI pad shall be verified by analysis to limit cask.
deceleration during a design basis drop event to _s 45 g's at the top of the MPC fuel basket, except as provided for in this paragraph below. Analyses shall be performed using methodologies consistent with those described in the HI STORM 100 FSAR. A lift height above the ISFSI pad is not required to be established if the cask is lifted with a device design in accordance with ANSI N14.6 and having redundant drop protection features.
: 7.        In cases where engineered features (i.e., berms and shield walls) are used to ensure that the requirements of 10CFR72.104(a) ae met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category.
(continued)
Certificate of Compliance No. 1014 Appendix B                                                                      Renewed Amendment No. 3 3-15
 
Design Features 3.0 Certificate of Compliance No. 1014 Appendix B                              Renewed Amendment No. 3 3-16
 
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 0&deg; 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 perlormed 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 shorf 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 Appendix B                                                                  Renewed Amendment No. 3 3-17
 
Design Features 3.0 DESIGN FEATURES 3.5    Cask Tran sf er 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- err structure shall be designed to comply with the stress limits of ASME Section Ill, Subsection NF, Class 3 for linear structures. The applicable loads, load combinations, and associated service condition definitions are provided in Table 3-3. All compression loaded members shall satisfy the buckling criteria of ASME Section JII, Subsection NF.
: 2. If a portion of the CTF structure is constructed of reinforced concrete, then the factored load combinations set forth in ACl-318 (89) for the loads defined in Table 3-3 shall apply.
: 3. The TRANSFER CASK and MPG lifting device used with the CTF shall be designed, fabricated, operated, tested, inspected and maintained in accordance with NUREG-0612, Section 5.1.
: 4. The CTF shall be designed, constructed, and evaluated to ensure that if the MPG is dropped during inter-cask transfer operations, its confinement boundar.y_would not be breached. This requirements applies to CTFs with either stationary or mobile lifting devices.
(continued)
Certificate of Compliance No. 1014 Appendix B                                                                    Renewed Amendment No. 3 3-18
 
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 830.5, "Mobile and Locomotive Cranes," in lieu of the requirements of ANSI 830.2, "Overhead and Gantry Cranes."
: 3. Mobile cranes are not required to meet the requirements of NUAEG-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. 3 Appendix B 3-19
 
Design Features 3.0 DESIGN FEATURES Table 3-3 Load Combinations and Service Condition Definitions for the CTF Structure {Note 1)
Load Combination            ASME Ill Service Condition                Comment for Definition of Allowable Stress D*                                                All primary load bearing Level A            members must satisfy Level D+S                                                A stress limits D+M+W'                                                Factor of safety against (Note 2)                                            overturning shall be  1.1 D+F                            LevelD 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 ACl-318(89).
: 2. Tornado missile load may be reduced or eliminated based on a PAA for the CTF site.
Certificate of Compliance No. 1014 Renewed Amendment No. 3 Appendix B 3-20
 
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 MPG for moderat 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 MPG shall be at least 15&deg;F higher than the saturation temperature at coincident pressure.
3.6.2.2 The.pressure in-the MPG cavity space shall-bes 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 MPG for fuel storage operations.
3.6.2.4 The partial pressure of the water vapor in the MPG cavity will not exceed 3 torr. The limit is met if the gas temperature at the demoisturizer outlet is verified by measurement to remains 21&deg;F for a period of 30 minutes or if the dew point of the gas exiting the MPG is verified by measurement to remain s 22.9&deg;F for 30 minutes.
3.6.2.5 The condensing module shall be designed to de-vaporize the recirculating helium gas to a dew point s 120&deg;F.
3.6.2.6 The demoisturizing module shall be configured to be introduced into its helium conditioning function after the condensing module has been operated for the required length of time to assure that the bulk moisture vaporization in the MPC (defined as Phase 1 in FSAR Appendix 2.B) has been-completed.
3.6.2.7 The helium circulator shall be sized to effect the minimum flow rate of circulation required by these design criteria.
3.6.2.8 The pre-heater module shall be engineered to ensure that the temperature of the helium gas in the MPG meets these design criteria.
(continued)
Certificate of Compliance No. 1014 Renewed Amendment No. 3 Appendix B 3-21
 
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. 3 Appendix B 3-22
 
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 MPG containing one or more high burnup (> 45,000 MWD/MTU) fuel assemblies. The SGS 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 (202 F) and the air-cooled heat exchanger sized for the design basis heat load at an ambient air*
temperature of 1002 F. 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-tree fluid medium in contact with the external surfaces of the MPC and inside surfaces of the HI -TRAC transfer cask to minimize corrosion.
3.7.2.4 All passive components such as tubular heat exchangers, manually operated valves and fittings shall be designed to applicable standards (TEMA, ANSI).
3.7.2.5 The heat dissipation capacity of the SCS shall be equal to or greater than the minimum necessary to ensure that the peak cladding temperature is below 4002C (7522 F). 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 MPG.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. 3 Appendix B 3-23
 
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. 3 Appendix B 3-24
 
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. 3 Appendix B 3-25}}

Revision as of 07:05, 18 November 2024

Proposed Renewed Certificate of Compliance No. 1014, Appendix B: Technical Specifications for the HI-STORM 100 Cask System Amendment No. 3
ML22098A246
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: ... further results
References
001028/L-2020-RNW-0007 NRC-2022-0109, RIN 3150-AK86
Download: ML22098A246 (1)
v • d • e


Text

Retrieved from "https://kanterella.com/w/index.php?title=ML22098A246&oldid=3730620"