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{{#Wiki_filter:RENEWED CERTIFICATE OF COMPLIANCE NO. 1008 APPENDIX B APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STAR 100 CASK SYSTEM AMENDMENT 3
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TABLE OF CONTENTS 1.0    Definitions ................................................................................................................... 1 1.1    Fuel Specifications....................................................................................................... 2 1.2    Functional and Operating Limits Violations ................................................................... 2 1.3    Codes and Standards .................................................................................................. 3 1.4    Site Specific Parameters and Analyses ........................................................................ 3 1.5    Design Specifications .................................................................................................. 5 Table 1.1-1      Fuel Assembly Limits ........................................................................................ 6 Table 1.1-2      PWR Fuel Assembly Characteristics................................................................ 23 Table 1.1-3      BWR Fuel Assembly Characteristics................................................................ 27 Table 1.1-4      Fuel Assembly Cooling and Decay Heat Generation ........................................ 32 Table 1.1-5      Fuel Assembly Cooling and Average Burnup ................................................... 33 Table 1.1-6      Non-Fuel Hardware Cooling and Average Burnup ............................................ 34 Table 1.3-1      List of ASME Code Exceptions for the HI-STAR 100 Cask System .................. 35 Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                        i
 
APPENDIX B                  DESIGN FEATURES 1.0 Definitions Refer to Appendix A for Definitions Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                      1
 
1.1 Fuel Specifications 1.1.1  Fuel To Be Stored In The HI-STAR 100
: 1.      INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, FUEL DEBRIS, and certain non-fuel hardware meeting the limits specified in Table 1.1-1 (which refers to Tables 1.1-2 through 1.1-6) may be stored in the HI-STAR 100 System.
: 2.      For MPCs partially loaded with stainless steel clad fuel assemblies, all remaining fuel assemblies in the MPC shall meet the maximum decay heat generation limit for the stainless steel clad fuel assemblies.
: 3.      For MPCs partially loaded with DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS, all remaining Zircaloy clad INTACT FUEL ASSEMBLIES in the MPC shall meet the maximum decay heat generation limits for the DAMAGED FUEL ASSEMBLIES.
: 4.      For MPC-68's partially loaded with array/class 6x6A, 6x6B, 6x6C, or 8x8A fuel assemblies, all remaining Zircaloy clad INTACT FUEL ASSEMBLIES in the MPC shall meet the maximum decay heat generation limits for the 6x6A, 6x6B, 6x6C, and 8x8A fuel assemblies.
1.2    Functional and Operating Limits Violations If any Fuel Specifications defined in Section 1.1 are violated, the following actions shall be completed:
: 1.      The affected fuel assemblies shall be placed in a safe condition without delay and in a controlled manner.
: 2.      Within 24 hours, notify the NRC Operations Center.
: 3.      Within 30 days, submit a special report which describes the cause of the violation, and actions taken to restore compliance and prevent recurrence.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            2
 
1.3    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-STAR 100 Cask System, as clarified in Specification 1.3.1 below.
1.3.1  Exceptions to Codes, Standards, and Criteria Table 1.3-1 lists approved exceptions to the ASME Code for the design of the HI-STAR 100 Cask System.
1.3.2  Construction/Fabrication Exceptions to Codes, Standards, and Criteria Proposed alternatives to the ASME Code, Sections II and III, 1995 Edition with Addenda through 1997 including exceptions allowed by Specification 1.3.1 may be used 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
: 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 exceptions shall be submitted in accordance with 10 CFR 72.4 1.4    Site Specific Parameters and Analyses Site-specific parameters and analyses that need verification by the system user are, as a minimum, as follows:
: 1.      The temperature of 80o F is the maximum allowed average yearly temperature.
: 2.      The allowed temperature extremes, averaged over a three day period, shall be greater than -40o F and less than 125o F.
: 3.      The horizontal and vertical seismic acceleration levels are bounded by the values listed below in Table 1-4.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                        3
 
Table 1-4 Design-Basis Earthquake Input on the Top Surface of an ISFSI Pad Horizontal g-Level in Horizontal g-Level          Corresponding Vertical Each of Two Vector Sum                  g-Level (Upward)
Orthogonal Directions 0.222 g                  0.314 g              1.00 x 0.222 g = 0.222 g 0.235 g                  0.332 g              0.75 x 0.235 g = 0.176 g 0.24 g                  0.339 g              0.667 x 0.24 g = 0.160 g 0.25 g                  0.354 g              0.500 x 0.25 g = 0.125 g
: 4.      For HI-STAR 100 casks stored horizontally, the following inequality shall be satisfied:
1 2
where HCGH is the center of gravity height of the horizontal cask above the ISFSI pad, B is the width of the supporting structure, G is the zero period acceleration seismic amplifier in horizontal direction, and  is ratio of the vertical acceleration multiplier.
If the above inequality cannot be satisfied for a particular site, then a 3-D time history analysis may be performed to demonstrate stability of HI-STAR 100 overpack in horizontal storage configuration.
In all cases, HCGH must not exceed 72 inches.
: 5.      The analyzed flood condition of 13 fps water velocity and a height of 656 feet of water (full submergence of the loaded cask) are not exceeded.
: 6.      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 combustible transporter fuel.
: 7.      The cask storage pads shall be verified by analysis to limit cask deceleration during both the design basis drop and the non-mechanistic tipover event to 60 gs at the top of the MPC fuel basket. Analyses shall be performed using methodologies consistent with those described in the HI-STAR FSAR.
: 8.      In cases where engineered features (i.e., berms, shield walls) are used to ensure that the requirements of 10CFR72.104(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            4
 
1.5    Design Specifications 1.5.1  Specifications Important for Criticality Control 1.5.1.1    MPC-24
: 1. Minimum flux trap size: 1.09 in.
: 2. Minimum 10B loading in the neutron absorbers: 0.0267 g/cm2 (Boral) and 0.0223 g/cm2 (METAMIC) 1.5.1.2    MPC-68 and MPC-68F
: 1. Minimum fuel cell pitch: 6.43 in.
: 2. Minimum 10B loading in the neutron absorbers: 0.0372 g/cm2 (Boral) and 0.0310 g/cm2 (METAMIC) in the MPC-68, and 0.01 g/cm2 (Boral) in the MPC-68F.
1.5.1.3    MPC-32
: 1. Minimum fuel cell pitch: 9.158 in
: 2. Minimum 10B loading in the neutron absorbers: 0.0372 g/cm2 (Boral) and 0.0310 g/cm2 (Metamic) 1.5.2  Specifications Important for Thermal Performance 1.5.2.1    OVERPACK The paint used on the HI-STAR 100 OVERPACK must have an emissivity no less than 0.85.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                          5
 
Table 1.1-1 (Page 1 of 17)
Fuel Assembly Limits I. MPC MODEL: MPC-24 A. Allowable Contents
: 1. Uranium oxide, PWR INTACT FUEL ASSEMBLIES, with or without Burnable Poison Rods (BPRAs) or Thimble Plug Devices (TPDs) listed in Table 1.1-2, and meeting the following specifications:
: a. Cladding type:                        Zircaloy (Zr) or stainless steel (SS) as specified in Table 1.1-2 for the applicable fuel assembly array/class
: b. Initial enrichment:                    As specified in Table 1.1-2 for the applicable fuel assembly array/class.
: c. Decay heat per assembly
: i. Zr Clad:                        An assembly decay heat as specified in Table 1.1-4 for the applicable post-irradiation cooling time.
                                                        <575 watts ii. SS Clad
: d. Post-irradiation cooling time and average burnup per assembly
: i. Zr clad:                        An assembly post-irradiation cooling time and average burnup as specified in Table 1.1-5.
BPRA and TPD post-irradiation cooling time and average burnup as specified in Table 1.1.6.
ii. SS clad:                          An assembly post-irradiation cooling time
                                                        >9 years and an average burnup
                                                        <30,000 MWD/MTU.
OR An assembly post-irradiation cooling time
                                                        >15 years and an average burnup
                                                        <40,000 MWD/MTU.
: e. Nominal fuel assembly length:          <176.8 inches
: f. Nominal fuel assembly width:          <8.54 inches
: g. Fuel assembly weight:                  <1,680 lbs (including non-fuel hardware)
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                              6
 
Table 1.1-1 (Page 2 of 17)
Fuel Assembly Limits I. MPC MODEL: MPC-24 (continued)
B. Quantity per MPC: Up to 24 PWR fuel assemblies.
C. Fuel assemblies shall not contain control components except as specifically authorized by this certificate of compliance. BPRAs and TPDs are authorized for loading in the HI-STAR 100 System with their associated fuel assemblies provided the burnup and cooling time limits specified in Table 1.1-6 are met.
D. DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS are not authorized for loading into the MPC-24.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                              7
 
Table 1.1-1 (Page 3 of 17)
Fuel Assembly Limits II. MPC MODEL: MPC-68 A. Allowable Contents
: 1. Uranium oxide, BWR INTACT FUEL ASSEMBLIES listed in Table 1.1-3, with or without Zircaloy channels, and meeting the following specifications:
: a. Cladding type:                      Zircaloy (Zr) or stainless steel (SS) as specified in Table 1.1-3 for the applicable fuel assembly array/class.
: b. Maximum PLANAR-AVERAGE              As specified in Table 1.1-3 for the applicable fuel INITIAL ENRICHMENT:                assembly array/class.
: c. Initial maximum rod                As specified in Table 1.1-3 for the applicable fuel enrichment:                        assembly array/class.
: d. Decay heat per assembly
: i. Zr clad                      An assembly decay heat as specified in Table 1.1-4 for the applicable post-irradiation cooling time, except for (1) array/class 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A fuel assemblies, which shall have a decay heat <115 watts and (2) array/class 8x8F fuel assemblies, which shall have a decay heat
                                                      <183.5 watts.
ii. SS clad
                                                      <95 watts
: e. Post-irradiation cooling time, average burnup per assembly:
: i. Zr clad:                      An assembly post-irradiation cooling time and average burnup as specified in Table 1.1-5, except for (1) array/class 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A fuel assemblies, which shall have a cooling time
                                                      >18 years, an average burnup <30,000 MWD/MTU, and (2) array/class 8x8F fuel assemblies, which shall have a cooling time >10 years, an average burnup
                                                      <27,500 MWD/MTU.
ii. SS clad:                      An assembly cooling time after discharge >10 years, an average burnup <22,500 MWD/MTU.
: e. Nominal fuel assembly length:      <176.2 inches
: f. Nominal fuel assembly width:      <5.85 inches
: g. Fuel assembly weight                < 700 lbs, including channels Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                              8
 
Table 1.1-1 (Page 4 of 17)
Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)
A. Allowable Contents (continued)
: 2. Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 1.1-3 for fuel assembly array/class 6x6A, 6x6B, 6x6C, 7x7A, or 8x8A, and meet the following specifications:
: a. Cladding type:                        Zircaloy (Zr)
: b. Maximum PLANAR-AVERAGE                As specified in Table 1.1-3 for the applicable fuel INITIAL ENRICHMENT:                  assembly array/class.
: c. Initial maximum rod enrichment:        As specified in Table 1.1-3 for the applicable fuel assembly array/class.
: d. Decay heat per assembly                <115 watts
: e. Post-irradiation cooling time and      An assembly post-irradiation cooling time average burnup per assembly:          >18 years and an average burnup
                                                        <30,000 MWD/MTU.
: f. Nominal fuel assembly length:        <135.0 inches
: g. Nominal fuel assembly width:          <4.70 inches
: h. Fuel assembly weight                  <400 lbs, including channels Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                              9
 
Table 1.1-1 (Page 5 of 17)
Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)
A. Allowable Contents (continued)
: 3. Mixed oxide (MOX), BWR INTACT FUEL ASSEMBLIES, with or without Zircaloy channels.
MOX BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 1.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
: a. Cladding type:                          Zircaloy (Zr)
: b. Maximum PLANAR-AVERAGE                  As specified in Table 1.1-3 for fuel assembly INITIAL ENRICHMENT:                    array/class 6x6B.
: c. Initial maximum rod enrichment:        As specified in Table 1.1-3 for fuel assembly array/class 6x6B.
: d. Decay heat per assembly                <115 watts
: e. Post-irradiation cooling time and      An assembly post-irradiation cooling time average burnup per assembly:          >18 years and an average burnup
                                                          <30,000 MWD/MTIHM.
: f. Nominal fuel assembly length:          <135.0 inches
: g. Nominal fuel assembly width:            <4.70 inches
: h. Fuel assembly weight                    <400 lbs, including channels Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                              10
 
Table 1.1-1 (Page 6 of 17)
Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)
A. Allowable Contents (continued)
: 4. Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. MOX BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 1.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
: a. Cladding type:                          Zircaloy (Zr)
: b. Maximum PLANAR-AVERAGE                  As specified in Table 1.1-3 for array/class 6x6B.
INITIAL ENRICHMENT:
: c. Initial maximum rod enrichment:        As specified in Table 1.1-3 for array/class 6x6B.
: d. Decay heat per assembly                <115 watts
: e. Post-irradiation cooling time and      An assembly post-irradiation cooling time average burnup per assembly:          >18 years and an average burnup
                                                          <30,000 MWD/MTIHM.
: f. Nominal fuel assembly length:          <135.0 inches
: g. Nominal fuel assembly width:            <4.70 inches
: h. Fuel assembly weight                    <400 lbs, including channels Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                              11
 
Table 1.1-1 (Page 7 of 17)
Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)
A. Allowable Contents (continued)
: 5. Thoria rods (ThO2 and UO2) placed in Dresden Unit 1 Thoria Rod Canisters (as shown in Figure 2.1.2A of the SAR) and meeting the following specifications:
: a. Cladding type:                          Zircaloy (Zr)
: b. Composition:                            98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U.
: c. Number of rods per Thoria Rod          <18 Canister:
: d. Decay heat per Thoria Rod              <115 Watts Canister:
: 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 MWD/MTIHM.
Rod Canister:
: f. Initial heavy metal weight:            <27 kg/canister
: g. Nominal fuel cladding O.D.:            >0.412 inches
: h. Nominal fuel cladding I.D.:            <0.362 inches
: i. Nominal fuel pellet O.D.:              <0.358 inches
: j. Nominal active fuel length:            <111 inches
: k. Canister weight:                        <550 lbs, including fuel Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                              12
 
Table 1.1-1 (Page 8 of 17)
Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)
B. Quantity per MPC: Up to one (1) Dresden Unit 1 Thoria Rod Canister loaded toward the basket periphery (i.e., away from the hot central core of the fuel basket) plus any combination of DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS and INTACT FUEL ASSEMBLIES, up to a total of 68.
C. Fuel assemblies with stainless steel channels are not authorized for loading in the MPC-68.
D. Dresden Unit 1 fuel assemblies (fuel assembly array/class 6x6A, 6x6B, 6x6C, or 8x8A) 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.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                              13
 
Table 1.1-1 (Page 9 of 17)
Fuel Assembly Limits III. MPC MODEL: MPC-68F A. Allowable Contents
: 1. Uranium oxide, BWR INTACT FUEL ASSEMBLIES, with or without Zircaloy channels.
BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 1.1-3 for fuel assembly array/class 6x6A, 6x6C, 7x7A, or 8x8A and meet the following specifications:
: a. Cladding type:                          Zircaloy (Zr)
: b. Maximum PLANAR-AVERAGE                  As specified in Table 1.1-3 for the applicable fuel INITIAL ENRICHMENT:                    assembly array/class.
: c. Initial maximum rod enrichment:        As specified in Table 1.1-3 for the applicable fuel assembly array/class.
: d. Decay heat per assembly                <115 watts
: e. Post-irradiation cooling time and      An assembly post-irradiation cooling time average burnup per assembly:          >18 years and an average burnup
                                                          <30,000 MWD/MTU.
: f. Nominal fuel assembly length:          <176.2 inches
: g. Nominal fuel assembly width:            <5.85 inches
: h. Fuel assembly weight                    <700 lbs, including channels Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                              14
 
Table 1.1-1 (Page 10 of 17)
Fuel Assembly Limits III. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
: 2. Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 1.1-3 for fuel assembly array/class 6x6A, 6x6C, 7x7A, or 8x8A, and meet the following specifications:
: a. Cladding type:                          Zircaloy (Zr)
: b. Maximum PLANAR-AVERAGE                  As specified in Table 1.1-3 for the applicable fuel INITIAL ENRICHMENT:                    assembly array/class.
: c. Initial maximum rod enrichment:          As specified in Table 1.1-3 for the applicable fuel assembly array/class.
: d. Decay heat per assembly                  <115 watts
: e. Post-irradiation cooling time and        A post-irradiation cooling time after discharge average burnup per assembly:            >18 years and an average burnup
                                                          <30,000 MWD/MTU.
: f. Nominal fuel assembly length:          <135.0 inches
: g. Nominal fuel assembly width:            <4.70 inches
: h. Fuel assembly weight                    <400 lbs, including channels Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                15
 
Table 1.1-1 (Page 11 of 17)
Fuel Assembly Limits III. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
: 3. Uranium oxide, BWR FUEL DEBRIS, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the uranium oxide BWR FUEL DEBRIS shall meet the criteria specified in Table 1.1-3 for fuel assembly array/class 6x6A, 6x6C, 7x7A, or 8x8A, and meet the following specifications:
: a. Cladding type:                          Zircaloy (Zr)
: b. Maximum PLANAR-AVERAGE                  As specified in Table 1.1-3 for the applicable INITIAL ENRICHMENT:                    original fuel assembly array/class.
: c. Initial maximum rod enrichment:          As specified in Table 1.1-3 for the applicable original fuel assembly array/class.
: d. Decay heat per DFC:                      <115 watts
: e. Post-irradiation cooling time and        A post-irradiation cooling time after discharge average burnup per assembly:            >18 years and an average burnup
                                                          <30,000 MWD/MTU for the original fuel assembly.
: f. Nominal original fuel assembly          <135.0 inches length:
: g. Nominal original fuel assembly          <4.70 inches width:
: h. Fuel debris weight                      <400 lbs, including channels Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                16
 
Table 1.1-1 (Page 12 of 17)
Fuel Assembly Limits III. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
: 4. Mixed oxide(MOX), BWR INTACT FUEL ASSEMBLIES, with or without Zircaloy channels.
MOX BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 1.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
: a. Cladding type:                          Zircaloy (Zr)
: b. Maximum PLANAR-AVERAGE                  As specified in Table 1.1-3 for fuel assembly INITIAL ENRICHMENT:                    array/class 6x6B.
: c. Initial maximum rod enrichment:          As specified in Table 1.1-3 for fuel assembly array/class 6x6B.
: d. Decay heat per assembly                  <115 watts
: e. Post-irradiation cooling time and        An assembly post-irradiation cooling time after average burnup per assembly:            discharge >18 years and an average burnup
                                                          <30,000 MWD/MTIHM.
: f. Nominal fuel assembly length:          <135.0 inches
: g. Nominal fuel assembly width:            <4.70 inches
: h. Fuel assembly weight                    <400 lbs, including channels Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                17
 
Table 1.1-1 (Page 13 of 17)
Fuel Assembly Limits III. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
: 5. Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. MOX BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 1.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
: a. Cladding type:                          Zircaloy (Zr)
: b. Maximum PLANAR-AVERAGE                  As specified in Table 1.1-3 for array/class 6x6B.
INITIAL ENRICHMENT:
: c. Initial maximum rod enrichment:          As specified in Table 1.1-3 for array/class 6x6B.
: d. Decay heat per assembly                  <115 watts
: e. Post-irradiation cooling time and        A post-irradiation cooling time after discharge average burnup per assembly:            >18 years and an average burnup
                                                          <30,000 MWD/MTIHM.
: f. Nominal fuel assembly length:          <135.0 inches
: g. Nominal fuel assembly width:            <4.70 inches
: h. Fuel assembly weight                    <400 lbs, including channels Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                18
 
Table 1.1-1 (Page 14 of 17)
Fuel Assembly Limits III. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
: 6. Mixed oxide (MOX), BWR FUEL DEBRIS, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the MOX BWR FUEL DEBRIS shall meet the criteria specified in Table 1.1-3 for fuel assembly array/class 6x6B, and meet the following specifications:
: a. Cladding type:                          Zircaloy (Zr)
: b. Maximum PLANAR-AVERAGE                  As specified in Table 1.1-3 for original fuel INITIAL ENRICHMENT:                    assembly array/class 6x6B.
: c. Initial maximum rod enrichment:          As specified in Table 1.1-3 for original fuel assembly array/class 6x6B.
: d. Decay heat per DFC                      <115 watts
: e. Post-irradiation cooling time and        A post-irradiation cooling time after discharge average burnup per assembly:            > 18 years and an average burnup
                                                          < 30,000 MWD/MTIHM for the original fuel assembly.
: f. Nominal original fuel assembly          <135.0 inches length:
: g. Nominal original fuel assembly          <4.70 inches width:
: h. Fuel debris weight                      <400 lbs, including channels Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                19
 
Table 1.1-1 (Page 15 of 17)
Fuel Assembly Limits III. MPC MODEL: MPC-68F (continued)
A. Allowable Contents (continued)
: 7. Thoria rods (ThO2 and UO2) placed in Dresden Unit 1 Thoria Rod Canisters (as shown in Figure 2.1.2A of the SAR) and meeting the following specifications:
: a. Cladding type:                          Zircaloy (Zr)
: b. Composition:                            98.2 wt.% ThO2, 1.8 wt. % UO2 with an enrichment of 93.5 wt. % 235U.
: c. Number of rods per Thoria Rod            <18 Canister:
: d. Decay heat per Thoria Rod                <115 Watts Canister:
: 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 MWD/MTIHM.
Rod Canister:
: f. Initial heavy metal weight:            <27 kg/canister
: g. Nominal fuel cladding O.D.:              >0.412 inches
: h. Nominal fuel cladding I.D.:              <0.362 inches
: i. Nominal fuel pellet O.D.:              <0.358 inches
: j. Nominal active fuel length:            <111 inches
: k. Canister weight:                        <550 lbs, including fuel Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                20
 
Table 1.1-1 (Page 16 of 17)
Fuel Assembly Limits III. MPC MODEL: MPC-68F (continued)
B. Quantity per MPC:
Up to four (4) DFCs containing uranium oxide or MOX BWR FUEL DEBRIS. The remaining MPC-68F fuel storage locations may be filled with array/class 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A 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 DAMAGED FUEL CONTAINERS; or
: 5. Up to one (1) Dresden Unit 1 Thoria Rod Canister loaded toward the basket periphery (i.e.,
away from the hot central core of the fuel basket).
C. Fuel assemblies with stainless steel channels are not authorized for loading in the MPC-68F.
D. Dresden Unit 1 fuel assemblies (fuel assembly array/class 6x6A, 6x6B, 6x6C or 8x8A) with one Antimony-Beryllium neutron source are authorized for loading in the MPC-68F. The antimony-Beryllium neutron source material shall be in a water rod location.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            21
 
Table 1.1-1 (Page 17 of 17)
Fuel Assembly Limits IV. MPC MODEL MPC-32 A. Allowable Contents
: 1. Uranium oxide, PWR INTACT FUEL ASSEMBLIES, listed in Table 1.1-2, and meeting the following specifications:
: a. Cladding type:                          Zircaloy (Zr) as specified in Table 1.1-2 for the applicable fuel assembly array/class. SS clad assemblies are not allowed for storage in the MPC-32
: b. Initial enrichment:                      As specified in Table 1.1-2 for the applicable fuel assembly array/class.
: c. Decay heat per assembly                An assembly decay heat as specified in Table 1.1-4 for the applicable post-irradiation cooling time.
: d. Post-irradiation cooling time        An assembly post-irradiation cooling time and average burnup per assembly              average burnup as specified in Table 1.1-5.
: e. Nominal fuel assembly length:            < 176.8 inches
: f. Nominal fuel assembly width:            < 8.54 inches
: g. Fuel assembly weight:                    < 1,680 lbs (including non-fuel hardware)
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            22
 
Table 1.1-2 (Page 1 of 4)
PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 14x14A          14x14B        14x14C    14x14D  15x15A Array/Class Clad Material Zr              Zr            Zr      SS        Zr (Note 2)
Design Initial U
                            < 407            < 407          < 425    < 400    < 464 (kg/assy.) (Note 3)
Initial Enrichment
                            < 4.6            < 4.6          < 4.6    < 4.0    < 4.1 (MPC-24 without soluble boron credit)
(wt % 235U)
Initial Enrichment (MPC-24 and MPC-          < 5.0            < 5.0          < 5.0    < 5.0    < 5.0 32 with soluble boron credit, Note 6)
(wt % 235U)
No. of Fuel Rods 179              179            176      180      204 (Note 5)
Clad O.D. (in.)          > 0.400          > 0.417        > 0.440  > 0.422  > 0.418 Clad I.D. (in.)          < 0.3514        < 0.3734      < 0.3880  < 0.3890 < 0.3660 Pellet Dia. (in.)        < 0.3444        < 0.3659      < 0.3805  < 0.3835 < 0.3580 (Note 7)
Fuel Rod Pitch (in.)    < 0.556          < 0.556        < 0.580  < 0.556  < 0.550 Active Fuel
                            < 150            < 150          < 150    < 144    < 150 Length (in.)
No. of Guide Tubes          17              17        5 (Note 4)    16        21 Guide Tube
                          > 0.017          > 0.017        > 0.038  > 0.0145 > 0.0165 Thickness (in.)
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            23
 
Table 1.1-2 (Page 2 of 4)
PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 15x15B          15x15C        15x15D  15x15E  15x15F Array/Class Clad Material Zr              Zr            Zr      Zr      Zr (Note 2)
Design Initial U
                            < 464            < 464          < 475    < 475    < 475 (kg/assy.) (Note 3)
Initial Enrichment
                            < 4.1            < 4.1          < 4.1    < 4.1    < 4.1 (MPC-24 without soluble boron credit)
(wt % 235U)
Initial Enrichment (MPC-24 and MPC-          < 5.0            < 5.0          < 5.0    < 5.0    < 5.0 32 with soluble boron credit, Note 6)
(wt % 235U)
No. of Fuel Rods 204              204            208      208      208 (Note 5)
Clad O.D. (in.)          > 0.420          > 0.417        > 0.430  > 0.428  > 0.428 Clad I.D. (in.)          < 0.3736        < 0.3640      < 0.3800 < 0.3790 < 0.3820 Pellet Dia. (in.)        < 0.3671        < 0.3570      < 0.3735 < 0.3707 < 0.3742 (Note 7)
Fuel Rod Pitch (in.)    < 0.563          < 0.563        < 0.568  < 0.568  < 0.568 Active Fuel
                            < 150            < 150          < 150    < 150    < 150 Length (in.)
No. of Guide Tubes          21              21            17      17        17 Guide Tube
                          > 0.015          > 0.0165      > 0.0150 > 0.0140 > 0.0140 Thickness (in.)
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            24
 
Table 1.1-2 (Page 3 of 4)
PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 15x15G        15x15H      16x16A      17x17A  17x17B  17x17C Array/ Class Clad Material SS              Zr          Zr          Zr      Zr      Zr (Note 2)
Design Initial U
                          < 420          < 475        < 443        < 467  < 467    < 474 (kg/assy.) (Note 3)
Initial Enrichment
                          < 4.0          < 3.8        < 4.6        < 4.0    < 4.0    < 4.0 (MPC-24 without soluble boron credit)
(wt % 235U)
Initial Enrichment (MPC-24 and MPC-          < 5.0          < 5.0        < 5.0        < 5.0    < 5.0    < 5.0 32 with soluble boron credit, Note 6)
(wt % 235U)
No. of Fuel Rods 204            208          236          264      264      264 (Note 5)
Clad O.D. (in.)        > 0.422        > 0.414      > 0.382      > 0.360 > 0.372  > 0.377 Clad I.D. (in.)        < 0.3890      < 0.3700    < 0.3350    < 0.3150  < 0.3310 < 0.3330 Pellet Dia. (in.)      < 0.3825      < 0.3622    < 0.3255    < 0.3088  < 0.3232 < 0.3252 (Note 7)
Fuel Rod Pitch (in.)    < 0.563        < 0.568      < 0.506      < 0.496 < 0.496  < 0.502 Active Fuel
                          < 144          < 150        < 150        < 150  < 150    < 150 Length (in.)
No. of Guide Tubes          21            17      5 (Note 4)        25      25      25 Guide Tube
                        > 0.0145      > 0.0140    > 0.0350      > 0.016 > 0.014  > 0.020 Thickness (in.)
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            25
 
Table 1.1-2 (Page 4 of 4)
PWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
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. Zr. Designates cladding material made of Zirconium or Zirconium alloys.
: 3. Design initial uranium weight is the 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 tolerances.
: 4. Each guide tube replaces four fuel rods.
: 5. Missing fuel rods must be replaced with dummy fuel rods that displace an equal or greater amount of water as the original fuel rods.
: 6. Soluble boron concentration per LCO 2.3.1, as applicable
: 7. Annular fuel pellets are allowed in the top and bottom 12 of the active fuel length.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                          26
 
Table 1.1-3 (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 (Note 2)
Design Initial U
                          < 110          < 110        < 110        < 100  < 195    < 120 (kg/assy.) (Note 3)
                                      < 2.7 for the Maximum PLANAR-UO2 rods.
AVERAGE INITIAL
                          < 2.7      See Note 4      < 2.7        < 2.7    < 4.2    < 2.7 ENRICHMENT for MOX (wt.% 235U) rods Initial Maximum Rod Enrichment                < 4.0          < 4.0        < 4.0        < 5.5    < 5.0    < 4.0 (wt.% 235U) 35 or 36 No. of Fuel Rods 35 or 36        (up to 9        36          49      49    63 or 64 (Note 14)
MOX rods)
Clad O.D. (in.)        > 0.5550      > 0.5625    > 0.5630    > 0.4860  > 0.5630 > 0.4120 Clad I.D. (in.)        < 0.5105      < 0.4945    < 0.4990    < 0.4204  < 0.4990 < 0.3620 Pellet Dia. (in.)      < 0.4980      < 0.4820    < 0.4880    < 0.4110  < 0.4910 < 0.3580 Fuel Rod Pitch (in.)    < 0.710        < 0.710      < 0.740      < 0.631 < 0.738  < 0.523 Active Fuel
                          < 120          < 120      < 77.5        < 80  < 150    < 120 Length (in.)
No. of Water Rods 1 or 0          1 or 0          0            0      0    1 or 0 (Note 11)
Water Rod
                            >0              >0          N/A          N/A      N/A      >0 Thickness (in.)
Channel
                        < 0.060        < 0.060      < 0.060      < 0.060 < 0.120  < 0.100 Thickness (in.)
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            27
 
Table 1.1-3 (Page 2 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 8x8B        8x8C        8x8D      8x8E    8x8F      9x9A    9x9B Array/Class Clad Material Zr          Zr          Zr        Zr      Zr      Zr      Zr (Note 2)
Design Initial U
                          < 185      < 185      < 185    < 185    < 185    < 177    < 177 (kg/assy.) (Note 3)
Maximum PLANAR-AVERAGE INITIAL
                          < 4.2      < 4.2      < 4.2    < 4.2    < 3.6    < 4.2    < 4.2 ENRICHMENT (wt.% 235U)
Initial Maximum Rod Enrichment              < 5.0      < 5.0      < 5.0    < 5.0    < 5.0    < 5.0    < 5.0 (wt.% 235U)
No. of Fuel Rods                                                            74/66 63 or 64      62      60 or 61      59      64                72 (Note 14)                                                                  (Note 5)
Clad O.D. (in.)        > 0.4840    > 0.4830    > 0.4830  > 0.4930 > 0.4576  > 0.4400 > 0.4330 Clad I.D. (in.)        < 0.4295    < 0.4250    0.4230  < 0.4250 < 0.3996  < 0.3840 < 0.3810 Pellet Dia. (in.)      < 0.4195    < 0.4160    < 0.4140  < 0.4160 < 0.3913  < 0.3760 < 0.3740 Fuel Rod Pitch (in.)    < 0.642    < 0.641    < 0.640  < 0.640  < 0.609  < 0.566  < 0.572 Design Active Fuel
                          < 150      < 150      < 150    < 150    < 150    < 150    < 150 Length (in.)
No. of Water Rods                                1-4                N/A                1 1 or 0        2                    5                2 (Note 11)                                      (Note 7)          (Note 12)          (Note 6)
Water Rod
                        > 0.034      > 0.00    > 0.00    > 0.034 > 0.0315  > 0.00  > 0.00 Thickness (in.)
Channel
                        < 0.120    < 0.120    < 0.120  < 0.100  < 0.055  < 0.120  < 0.120 Thickness (in.)
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            28
 
Table 1.1-3 (Page 3 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly                                              9x9E      9x9F 9x9C            9x9D                            10x10A Array/Class                                            (Note 13) (Note 13)
Clad Material Zr              Zr            Zr        Zr      Zr (Note 2)
Design Initial U
                            < 177            < 177          < 177    < 177    < 186 (kg/assy.) (Note 3)
Maximum PLANAR-AVERAGE INITIAL
                            < 4.2            < 4.2          < 4.1    < 4.1    < 4.2 ENRICHMENT (wt.% 235U)
Initial Maximum Rod Enrichment                < 5.0            < 5.0          < 5.0    < 5.0    < 5.0 (wt.% 235U)
No. of Fuel Rods                                                            92/78 80              79            76        76 (Note 14)                                                                  (Note 8)
Clad O.D. (in.)          > 0.4230        > 0.4240      > 0.4170  > 0.4430 > 0.4040 Clad I.D. (in.)          < 0.3640        < 0.3640      < 0.3640  < 0.3860 < 0.3520 Pellet Dia. (in.)        < 0.3565        < 0.3565      < 0.3530  < 0.3745 < 0.3455 Fuel Rod Pitch (in.)    < 0.572          < 0.572        < 0.572  < 0.572  < 0.510 Design Active Fuel
                            < 150            < 150          < 150    < 150    < 150 Length (in.)
No. of Water Rods 1              2              5        5        2 (Note 11)
Water Rod
                          > 0.020          > 0.0300      > 0.0120  > 0.0120 > 0.0300 Thickness (in.)
Channel
                          < 0.100          < 0.100        < 0.120  < 0.120  < 0.120 Thickness (in.)
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            29
 
Table 1.1-3 (Page 4 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
Fuel Assembly 10x10B          10x10C    10x10D  10x10E Array/Class Clad Material (Note 2)                      Zr              Zr        SS      SS Design Initial U (kg/assy.) (Note 3)      < 186          < 186      < 125    < 125 Maximum PLANAR-AVERAGE
                                          < 4.2          < 4.2      < 4.0    < 4.0 INITIAL ENRICHMENT (wt% 235U)
Initial Maximum Rod
                                          < 5.0          < 5.0      < 5.0    <5 Enrichment (wt.% 235U)
No. of Fuel Rods (Note 14)          91/83 (Note 9)        96        100      96 Clad O.D. (in.)                        > 0.3957        > 0.3780  > 0.3960 > 0.3940 Clad I.D. (in.)                        < 0.3480        < 0.3294  < 0.3560 < 0.3500 Pellet Dia. (in.)                      < 0.3420        < 0.3224  < 0.3500 < 0.3430 Fuel Rod Pitch (in.)                    < 0.510          < 0.488  < 0.565  < 0.557 Design Active Fuel Length (in.)          < 150          < 150      < 83    < 83 No. of Water Rods (Note 11)            1 (Note 6)      5 (Note 10)    0        4 Water Rod Thickness (in.)                > 0.00          > 0.031      N/A  > 0.022 Channel Thickness (in.)                < 0.120          < 0.055  < 0.080  < 0.080 Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                            30
 
Table 1.1-3 (Page 5 of 5)
BWR FUEL ASSEMBLY CHARACTERISTICS (Note 1)
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. Zr designates cladding material made from Zirconium or Zirconium alloys.
: 3. Design initial uranium weight is the 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% for comparison with users fuel records to account for manufacturers tolerances.
: 4.  < 0.635 wt. % 235U and < 1.578 wt. % total fissile plutonium (239Pu and 241Pu), (wt. % of total fuel weight, i.e., UO2 plus PuO2).
: 5. This assembly class contains 74 total fuel rods; 66 full length rods and 8 partial length rods.
: 6. Square, replacing nine fuel rods.
: 7. Variable
: 8. This assembly class contains 92 total fuel rods; 78 full length rods and 14 partial length rods.
: 9. This assembly class contains 91 total fuel rods, 83 full length rods and 8 partial length rods.
: 10. One diamond-shaped water rod replacing the four center fuel rods and four rectangular water rods dividing the assembly into four quadrants.
: 11. These rods may be sealed at both ends and contain Zr material in lieu of water.
: 12. This assembly is known as QUAD+ and 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 9x9F set of limits for clad O.D., clad I.D., and pellet diameter.
: 14. Missing fuel rods must be replaced with dummy fuel rods that displace an equal or greater amount of water as the original fuel rods. Storage of 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A fuel assemblies with missing fuel rods are permitted provided the assemblies are stored as DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                          31
 
Table 1.1-4 FUEL ASSEMBLY COOLING AND DECAY HEAT GENERATION Post-Irradiation                MPC-24                MPC-68            MPC-32 Cooling Time          PWR Assembly With or      BWR Assembly Decay  PWR Assembly (years)          Without BPRAs or TPDs          Heat (Watts)  Decay Heat (Watts)
Decay Heat (Watts) 5                    792 (Vertical)              272          578 (Vertical) 833 (Horizontal)                          625 (Horizontal)
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                              32
 
Table 1.1-5 FUEL ASSEMBLY COOLING AND AVERAGE BURNUP (Note 1)
Post-          MPC-24              MPC-24          MPC-68    MPC-32    MPC-32 PWR Irradiation  PWR Assembly PWR Assembly                BWR    PWR Assembly  Assembly Cooling          Burnup              Burnup        Assembly    Burnup      Burnup Time            (Without        (With BPRAs)        Burnup  (MWD/MTU)  (Non-Zircaloy (years)        BPRAs and          (MWD/MTU) (MWD/MTU)                    Grid Spacers)
With or Without                                              (MWD/MTU)
TPDs)
(MWD/MTU) 5            28,700            28,300        26,000      -            -
6            32,700            32,300        29,100      -            -
7            33,300            32,700        29,600      -            -
8            35,500            35,000        31,400    24,500        -
9            37,000            36,500        32,800    29,500        -
10            38,200            37,600        33,800    31,100        -
11            39,300            38,700        34,800    32,800        -
12            40,100            39,500        35,500    34,500      24,500 13            40,800            40,200        36,200    37,000      27,000 14            41,500            40,800        36,900    39,500      29,500 15            42,100            41,400        37,600    40,300      32,000 16                                                          41,100      34,500 17                                                          42,000      36,100 18                                                          42,800      39,500 19                                                          43,600      39,500 20                                                          44,500      42,500 Note: 1. Linear interpolation between points permitted.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                          33
 
Table 1.1-6 NON-FUEL HARDWARE COOLING AND AVERAGE BURNUP (Note 1)
Post-Irradiation                  MPC-24                            MPC-24 Cooling Time (years)              BPRA Burnup                      TPD Burnup (MWD/MTU)                      (MWD/MTU) 3                        20,000                        NC (Note 2) 4                            NC                            20,000 5                        30,000                            NC 6                        40,000                          30,000 7                            NC                            40,000 8                        50,000                            NC 9                        60,000                          50,000 10                          NC                            60,000 11                          NC                              NC 12                          NC                            90,000 13                          NC                          180,000 14                          NC                          630,000 Notes:      1. Linear interpolation between points is permitted, except that TPD burnups >180,000 MWD/MTU and 630,000 MWD/MTU must be cooled 14 years.
: 2. Not Calculated Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                      34
 
Table 1.3-1 (Page 1 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component                  Reference          Code Requirement            Exception, Justification & Compensatory Measures ASME Code Section/Article MPC, MPC              Subsection NCA        General Requirements.        Because the MPC and overpack are not ASME Code stamped basket assembly,                            Requires preparation of      vessels, none of the specifications, reports, certificates, or other and HI-STAR                                  a Design Specification,      general requirements specified by NCA are required. The HI-overpack steel                              Design Report,              STAR FSAR includes the design criteria, service conditions, and structure                                    Overpressure                load combinations for the design and operation of the HI-STAR Protection Report,          100 System as well as the results of the stress analyses to Certification of            demonstrate that applicable Code stress limits are met.
Construction Report,        Additionally the fabricator is not required to have an ASME-Data Report, and other      certified QA program. All important-to-safety activities are administrative controls      governed by the NRC approved Holtec QA program.
for an ASME Code stamped vessel              Because the cask components are not certified to the Code, the terms Certificate Holder and Inspector are not germane to the manufacturing of NRC-certified cask components. To eliminate ambiguity, the responsibilities assigned to the Certificate Holder in the various articles of Subsections NB, NG, and NF of the Code, as applicable, shall be interpreted to apply to the NRC Certificate of Compliance (CoC) holder (and by extension, to the component fabricator) if the requirement must be fulfilled. The Code term Inspector means the QA/QC personnel of the CoC holder and its vendors assigned to oversee and inspect the manufacturing process.
MPC                  NB-1100                Statement of requirements MPC enclosure vessel is designed and will be fabricated in for Code stamping of        accordance with ASME Code, Section III, Subsection NB to the components.                  maximum practical extent, but Code stamping is not required.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                        35
 
Table 1.3-1 (Page 2 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component                  Reference          Code Requirement              Exception, Justification & Compensatory Measures ASME Code Section/Article MPC                  NB-2000                Requires materials to be      Materials will be supplied by Holtec-approved suppliers with supplied by ASME-            Certified Material Test Reports (CMTRs) in accordance with approved material            NB-2000 requirements.
supplier.
MPC basket            NB-1130                NB-1132.2(d) requires that The MPC basket supports (nonpressure-retaining structural supports and lift                            the first connecting weld of attachments) and lift lugs (nonstructural attachments used lugs                                        a nonpressure-retaining      exclusively for lifting an empty MPC) are welded to the inside of the structural attachment to a pressure-retaining MPC shell, but are not designed in accordance component shall be            with Subsection NB. The basket supports and associated considered part of the        attachment welds are designed to satisfy the stress limits of component unless the weld Subsection NG and the lift lugs and associated attachment welds is more than 2t from the      are designed to satisfy the stress limits of Subsection NF, as a pressure-retaining portion of minimum. These attachments and their welds are shown by the component, where t is analysis to meet the respective stress limits for their service the nominal thickness of the conditions.
pressure-retaining material. Likewise, non-structural items, such as shield plugs, spacers, etc., if used, can be attached to pressure-retaining parts in the same NB-1132.2(e) requires that manner.
the first connecting weld of a welded nonstructural attachment to a component shall conform to NB-4430 if the connecting weld is within 2t from the pressure-retaining portion of the component.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                          36
 
Table 1.3-1 (Page 3 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component            Reference          Code Requirement              Exception, Justification & Compensatory Measures ASME Code Section/Article MPC, MPC basket NB-3100                  Provides requirements for      These requirements are not applicable. The HI-STAR FSAR assembly, and HI- NG-3100                determining design loading    serving as the Design Specification, establishes the service STAR overpack        NF-3100            conditions, such as pressure,  conditions and load combinations for the storage system.
steel structure                          temperature, and mechanical loads.
MPC                  NB-3350            NB-3352.3 requires, for        The MPC shell-to-baseplate weld joint design (designated Category Category C joints, that the    C) may not include a reinforcing fillet weld or a bevel in the MPC minimum dimensions of the      baseplate, which makes it different than any of the representative welds and throat thickness    configurations depicted in Figure NB-4243-1. The transverse shall be as shown in Figure    thickness of this weld is equal to the thickness of the adjoining NB-4243-1.                    shell. The weld is designed as a full penetration weld that receives VT and RT or UT, as well as final surface PT examinations.
Because the MPC shell design thickness is considerably larger than the minimum thickness required by the Code, a reinforcing fillet weld that would intrude into the MPC cavity space is not included.
Not including this fillet weld provides for a higher quality radiographic examination of the full penetration weld.
From the standpoint of stress analysis, the fillet weld serves to reduce the local bending stress (secondary stress) produced by the gross structural discontinuity defined by the flat plate / shell junction. In the MPC design, the shell and baseplate thicknesses are well beyond that required to meet their respective membrane stress intensity limits.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                        37
 
Table 1.3-1 (Page 4 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component            Reference          Code Requirement                  Exception, Justification & Compensatory Measures ASME Code Section/Article MPC. MPC basket NB-4120                  NB-4121.2, NG-4121.2, and          In-shop operations of short duration that apply heat to a assembly, and HI- NG-4120                NF-4121.2 provide                  component, such as plasma cutting of plate stock, welding, STAR overpack        NF-4120            requirements for repetition of    machining, coating, and pouring of Holtite are not, unless explicitly steel structure                          tensile or impact tests for        stated by the Code, defined as heat treatment operations material subjected to heat treatment during fabrication or    For the steel parts in the HI-STAR 100 System components, the installation                      duration for which a part exceeds the off-normal temperature limit shall be limited to 24 hours in a particular manufacturing process (such as the Holtite pouring process).
MPC and HI-STAR NB-4220                  Requires certain forming          The cylindricity measurements on the rolled shells are not overpack steel        NF-4220            tolerance to be met for            specifically recorded in the shop travelers, as would be the case for structure                                cylindrical, conical, or spherical a Code-stamped pressure vessel. Rather, the requirements on shells of a vessel.                inter-component clearances (such as the MPC-to-overpack) are guaranteed through fixture-controlled manufacturing. The fabrication specification and shop procedures ensure that all dimensional design objectives, including inter-component annular clearances are satisfied.
The dimensions required to be met in fabrication are chose to meet the functional requirements of the dry storage components. Thus, although the post-forming Code cylindricity requirements are not evaluated for compliance directly, they are indirectly satisfied (actually exceeded) in the final manufactured components.
MPC Lid and          NB-4243              Full penetration welds            MPC lid and closure ring are not full penetration welds. They Closure      Ring                          required for Category C          are welded independently to provide a redundant seal.
Welds                                      Joints (flat head to main        Additionally, a weld efficiency factor of 0.45 has been applied shell per NB-3352.3).            to the analyses of these welds.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                          38
 
Table 1.3-1 (Page 5 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component            Reference          Code Requirement              Exception, Justification & Compensatory Measures ASME Code Section/Article MPC Lid to          NB-5230            Radiographic (RT) or          Only UT or multi-layer liquid penetrant (PT) examination is Shell Weld                              ultrasonic (UT)                permitted. If PT alone is used, at a minimum, it will include the examination required          root and final weld layers and each approximately 3/8 inch of weld depth.
MPC Closure          NB-5230            Radiographic (RT) or          Root (if more than one weld pass is required) and final liquid Ring, Vent and                          ultrasonic (UT)                penetrant examination to be performed in accordance with NB-Drain Cover                              examination required          5245. The MPC vent and drain cover plate welds are leak Plate Welds                                                            tested. The closure ring provides independent redundant closure for vent and drain cover plates.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                      39
 
Table 1.3-1 (Page 6 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component            Reference            Code Requirement          Exception, Justification & Compensatory Measures ASME Code Section/Article MPC                NB-6111                All completed pressure    The MPC enclosure vessel is seal welded in the field following Enclosure                                retaining systems shall    fuel assembly loading. The MPC enclosure vessel shall then be Vessel and                                be pressure tested.        hydrostatically tested as defined in Chapter 9. Accessibility for Lid                                                                  leakage inspections preclude a Code compliant hydrostatic test.
All MPC enclosure vessel welds (except the closure ring and vent/drain cover plate) are inspected by volumetric examination, except the MPC lid-to-shell weld shall be verified by volumetric or multi-layer PT examination. If PT alone is used, at a minimum, it must include the root and final layers and each approximately 3/8 inch of weld depth. For either UT or PT, the maximum undetectable flaw size must be demonstrated to be less than the critical flaw size. The critical flaw size must be determined in accordance with ASME Section XI methods. The critical flaw size shall not cause the primary stress limits of NB-3000 to be exceeded. The vent/drain cover plate weld is confirmed by liquid penetrant examination and the closure ring weld is confirmed by liquid penetrant examination. The inspection process, including findings, (indications) shall be made a permanent part of the certificate holders 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 inspection of the weld must be performed by qualified personnel and shall meet the acceptance requirements of ASME Code Section III, NB-5350 for PT or NB-5332 for UT.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                      40
 
Table 1.3-1 (Page 7 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component            Reference            Code Requirement            Exception, Justification & Compensatory Measures ASME Code Section/Article MPC                NB-7000                Vessels are required to    No overpressure protection is provided. The function of the Enclosure                                have overpressure          MPC enclosure vessel is to contain the radioactive contents Vessel                                    protection                  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 for    The HI-STAR 100 Cask System is to be marked and identified Enclosure                                nameplates, stamping        in accordance with 10CFR71 and 10CFR72 requirements.
Vessel                                    and reports per NCA-        Code stamping is not required. QA data package to be in 8000.                      accordance with Holtec approved QA program.
Overpack          NB-1100                Statement of                Overpack helium retention boundary is designed, and will be Helium                                    requirements for Code      fabricated in accordance with ASME Code, Section III, Subsection Retention                                stamping of components      NB to the maximum practical extent, but Code stamping is not Boundary                                                              required.
Overpack          NB-2000                Requires materials to be    Material will be supplied by Holtec approved suppliers with Helium                                    supplied by ASME            CMTRs per NB-2000.
Retention                                approved Material Boundary                                  Supplier Overpack          NB-7000                Vessels are required to    No overpressure protection is provided. Function of overpack Helium                                    have overpressure          vessel is to contain helium contents under normal, off-normal, Retention                                protection                  and accident conditions. Overpack Boundary                                                              vessel is designed to withstand maximum internal pressure and maximum accident temperatures.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3 41
 
Table 1.3-1 (Page 8 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component            Reference            Code Requirement            Exception, Justification & Compensatory Measures ASME Code Section/Article Overpack          NB-8000                Statement of                The HI-STAR 100 Cask System is to be marked and identified Helium                                    requirements for            in accordance with 10CFR71 and 10CFR72 requirements.
Retention                                nameplates, stamping        Code stamping is not required. QA data package to be in Boundary                                  and reports per NCA-        accordance with Holtec approved QA program.
8000 MPC Basket        NG-2000                Requires materials to be    Materials will be supplied by Holtec-approved supplier with Assembly                                  supplied by ASME-          CMTRs per NG-2000 requirements.
approved material supplier.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                      42
 
Table 1.3-1 (Page 9 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component          Reference          Code Requirement                Exception, Justification & Compensatory Measures ASME Code Section/Article MPC Basket        NG-4420            NG-4427(a) allows a fillet weld Modify the Code requirement (intended for core support structures)
Assembly                              in any single continuous weld with the following text prepared to accord with the geometry and to be less than the specified    stress analysis imperatives for the fuel basket: For the longitudinal fillet weld dimension by not    MPC basket fillet welds, the following criteria apply: 1) The more than 1/16 inch, provided specified fillet weld throat dimension must be maintained over at that the total undersize portion least 92 percent of the total weld length. All regions of undersized of the weld does not exceed 10 weld must be less than 3 inches long and separated from each percent of the length of the    other by at least 9 inches. 2) Areas of undercuts and porosity weld. Individual undersize      beyond that allowed by the applicable ASME Code shall not exceed weld portions shall not exceed 1/2 inch in weld length. The total length of undercut and porosity 2 inches in length              over any 1-foot length shall not exceed 2 inches. 3) The total weld length in which items (1) and (2) apply shall not exceed a total of 10 percent of the overall weld length. The limited access of the MPC basket panel longitudinal fillet welds makes it difficult to perform effective repairs of these welds and creates the potential for causing additional damage to the basket assembly (e.g., to the neutron absorber and its sheathing) if repairs are attempted. The acceptance criteria provided in the foregoing have been established to comport with the objectives of the basket design and preserve the margins demonstrated in the supporting stress analysis. From the structural standpoint, the weld acceptance criteria are established to ensure that any departure from the ideal, continuous fillet weld seam would not alter the primary bending stresses on which the design of the fuel baskets is predicated. Stated differently, the permitted weld discontinuities are limited in size to ensure that they remain classifiable as local stress elevators (peak stress, F, in the ASME Code for which specific stress intensity limits do not apply).
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                        43
 
Table 1.3-1 (Page 10 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component        Reference          Code Requirement                Exception, Justification & Compensatory Measures ASME Code Section/Article MPC Basket        NG-8000            States requirements for          The HI-STAR 100 Cask System will be marked and identified in Assembly                              nameplates, stamping and        accordance with 10CFR71 and 10CFR72 requirements. No reports per                      code stamping is required. The MPC basket data package will NCA-8000.                        be in conformance with Holtecs QA program.
Overpack          NF-4622            All welds, including repair      Intermediate shell-to-top flange welds and intermediate shell-to-Intermediate                          welds, shall be post-weld        bottom plate welds do not require PWHT. These welds attach Shells                                heat treated (PWHT).            non-pressure retaining parts to pressure retaining parts. The pressure retaining parts are >7 inches thick. Localized PWHT will cause material away from the weld to experience elevated temperatures which will have an adverse effect on the material properties.
Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                        44
 
Table 1.3-1 (Page 11 of 11)
LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component            Reference            Code Requirement              Exception, Justification & Compensatory Measures ASME Code Section/Article Overpack          NG-2000                Perform radiographic          Radiography of helium retention boundary welds after Helium                                    examination after post-      PWHT is not required. All welds (including repairs) will Retention                                weld heat treatment          have passed radiographic examination prior to PWHT of Boundary                                  (PWHT)                        the entire containment boundary. Confirmatory radiographic examination after PWHT is not necessary because PWHT is not known to introduce new weld defects in nickel steels.
Overpack          NF-2000                Requires materials to be      Materials will be supplied by Holtec-approved supplier with Intermediate                              supplied by ASME approved    CMTRs in accordance with NF-2000 requirements.
Shells                                    Material Supplier Overpack          NB-2330                Defines the methods for      TNDT shall be defined in accordance with Regulatory Guides Helium                                    determining the TNDT for      7.11 and 7.12 for the helium retention boundary Retention                                impact testing of materials  components.
Boundary Renewed Certificate of Compliance No. 1008 Appendix B  Amendment 3                                    45}}

Revision as of 08:15, 17 January 2022

Proposed Technical Specifications (Appendix B) for CoC No. 1008, Renewed Amendment No. 3
ML21168A364
Person / Time
Site: 07201008
Issue date: 09/09/2021
From:
Office of Nuclear Material Safety and Safeguards
To:
Holtec
KLBanovac NMSS/DFM/STL 301.415.7116
Shared Package
ML21168A351 List:
References
CAC 001208, EPID L-2018-RNW-0030
Download: ML21168A364 (47)
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