ML21168A361

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Proposed Technical Specifications (Appendix B) for CoC No. 1008, Renewed Amendment No. 2
ML21168A361
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
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ML21168A351 List:
References
CAC 001208, EPID L-2018-RNW-0030
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RENEWED CERTIFICATE OF COMPLIANCE NO. 1008 APPENDIX B APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STAR 100 CASK SYSTEM AMENDMENT 2

TABLE OF CONTENTS REVISION HISTORY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iii 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 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 Table 1.1-3 BWR Fuel Assembly Characteristics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 Table 1.1-4 Fuel Assembly Cooling and Decay Heat Generation . . . . . . . . . . . . . . . . . . . . 31 Table 1.1-5 Fuel Assembly Cooling and Average Burnup . . . . . . . . . . . . . . . . . . . . . . . . . . 32 Table 1.1-6 Non-Fuel Hardware Cooling and Average Burnup . . . . . . . . . . . . . . . . . . . . . . 33 Table 1.3-1 List of ASME Code Exceptions for the HI-STAR 100 Cask System . . . . . . . . . 34 Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 i

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Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 ii

REVISION HISTORY Amendment Section Change Description 1 Throughout Editorial changes and typographical corrections.

1.0 Revised definitions of DAMAGED FUEL ASSEMBLY, DAMAGED FUEL CONTAINER, and PLANAR-AVERAGE INITIAL ENRICHMENT.

1.1 Revised Section 1.1.1 to permit storage of certain non-fuel hardware.

1.4 Revised Item 6 to clarify the requirements for cask storage pad.

1.5 Revised Section 1.5.2 to replace the term painted surface of with paint used on.

Table 1.1-1 Added limits for non-fuel hardware (BPRAs and TPDs ),

array class 8x8F, and Thoria Rods.

Table 1.1-2 Revised certain fuel assembly parameters, added array/class 15x15H fuel assembly, and added clarifying notes.

Table 1.1-3 Revised certain fuel assembly parameters, added array/class 8x8F fuel assembly, and added clarifying notes.

Tables 1.1-4 Revised to clarify limits, reflect addition of BPRAs and and 1.1-5 TPDs, and permit linear interpolation between points.

Table 1.1-6 Added table specifying cooling and average burnup limits for non-fuel hardware.

Table 1.3-1 Added exception to ASME Code NB-5230 for the MPC lid-to-shell weld and added clarifying text.

2 1.4 Revised Item 6 to clarify the requirements for cask storage pad.

Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 iii

APPENDIX B DESIGN FEATURES 1.0 Definitions

Note -----------------------------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout this Appendix.

Term Definition 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, missing fuel rods that are not replaced with dummy fuel rods, or those that cannot be handled by normal means. Fuel assemblies which 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-STAR 100 design are shown in Figures 2.1.1 and 2.1.2 of the Final Safety Analysis Report (SAR) for the HI-STAR 100 Cask System.

FUEL DEBRIS FUEL DEBRIS is ruptured fuel rods, severed rods, loose fuel pellets or fuel assemblies with known or suspected defects which cannot be handled by normal means due to fuel cladding damage.

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. Partial fuel assemblies, that is fuel assemblies from which fuel rods are missing, 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 original fuel rod(s).

PLANAR-AVERAGE PLANAR-AVERAGE INITIAL ENRICHMENT is INITIAL ENRICHMENT the average of the distributed fuel rod initial enrichments within a given axial plane of the assembly lattice.

Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 1

1.1 Fuel Specifications 1.1.1 Fuel To Be Stored In The HI-STAR 100 SFSC

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 SFSC 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.

1.1.2 Preferential Fuel Loading Preferential fuel loading shall be used whenever fuel assemblies with significantly different post-irradiation cooling times (equal to or greater than one year) are to be loaded in the same MPC. That is, fuel assemblies with the longest post-irradiation cooling times shall be loaded into fuel storage locations at the periphery of the basket.

Fuel assemblies with shorter post-irradiation cooling times shall be placed toward the center of the basket.

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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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.

The above actions are not a substitute for the reporting requirements ontained in 10 CFR 72.75.

Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 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 Table1.3-1 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,Section 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 2 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. 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.
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 combustible transporter fuel.
6. 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.

7. 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 2 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 Boral neutron absorbers: 0.0267 g/cm2 1.5.1.2 MPC-68 and MPC-68F
1. Minimum fuel cell pitch: 6.43 in.
2. Minimum 10B loading in the Boral neutron absorbers: 0.0372 g/cm2 in the MPC-68, and 0.01 g/cm2 in the MPC-68F.

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 2 5

Table 1.1-1 (Page 1 of 16)

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.

ii. SS Clad < 575 watts

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 2 6

Table 1.1-1 (Page 2 of 16)

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 2 7

Table 1.1-1 (Page 3 of 16)

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, 6x6C, 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, 6x6C, 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 2 8

Table 1.1-1 (Page 4 of 16)

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, 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 > 18 average burnup per assembly: 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 2 9

Table 1.1-1 (Page 5 of 16)

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 > 18 average burnup per assembly: 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 2 10

Table 1.1-1 (Page 6 of 16)

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 > 18 average burnup per assembly: 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 2 11

Table 1.1-1 (Page 7 of 16)

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 and average burnup per Thoria > 18 years and an average burnup Rod Canister: < 16,000 MWD/MTIHM.
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 2 12

Table 1.1-1 (Page 8 of 16)

Fuel Assembly Limits II. MPC MODEL: MPC-68 (continued)

B. Quantity per MPC: Up to one (1) Dresden Unit 1 Thoria Rod Canister 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 2 13

Table 1.1-1 (Page 9 of 16)

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 > 18 average burnup per assembly: 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 2 14

Table 1.1-1 (Page 10 of 16)

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 2 15

Table 1.1-1 (Page 11 of 16)

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 2 16

Table 1.1-1 (Page 12 of 16)

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 2 17

Table 1.1-1 (Page 13 of 16)

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 2 18

Table 1.1-1 (Page 14 of 16)

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 2 19

Table 1.1-1 (Page 15 of 16)

Fuel Assembly Limits III. MPC MODEL: MPC-68F (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 and average burnup per Thoria > 18 years and an average burnup Rod Canister: < 16,000 MWD/MTIHM.
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 2 20

Table 1.1-1 (Page 16 of 16)

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.

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 2 21

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 (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 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 2 22

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 (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 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 2 23

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 (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 < 0.3320 < 0.3150 < 0.3310 < 0.3330 Pellet Dia. (in.) < 0.3825 < 0.3622 < 0.3255 < 0.3088 < 0.3232 < 0.3252 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 > 0.0400 > 0.016 > 0.014 > 0.020 Thickness (in.)

Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 24

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.

Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 25

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 2 26

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 2 27

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 2 28

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 2 29

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 2 30

Table 1.1-4 FUEL ASSEMBLY COOLING AND DECAY HEAT GENERATION (Note 1)

MPC-24 PWR Assembly MPC-68 Post-Irradiation With or Without BWR Assembly Cooling Time BPRAs or TPDs Decay Heat (years)

Decay Heat (Watts)

(Watts)

 5 792 272

 6 773 261

 7 703 238

 8 698 236

 9 692 234

10 687 232

11 683 231

12 678 229

13 674 228

14 669 227

15 665 226 Note: 1. Linear interpolation between points permitted.

Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 31

Table 1.1-5 FUEL ASSEMBLY COOLING AND AVERAGE BURNUP (Note 1)

MPC-24 PWR Assembly MPC-24 MPC-68 Post-Irradiation Burnup PWR Assembly BWR Assembly Cooling Time (Without BPRAs Burnup Burnup (years) and With or (With BPRAs)

(MWD/MTU)

Without TPDs) (MWD/MTU)

(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

 9 37,000 36,500 32,800

10 38,200 37,600 33,800

11 39,300 38,700 34,800

12 40,100 39,500 35,500

13 40,800 40,200 36,200

14 41,500 40,800 36,900

15 42,100 41,400 37,600 Note: 1. Linear interpolation between points permitted.

Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 32

Table 1.1-6 NON-FUEL HARDWARE COOLING AND AVERAGE BURNUP (Note 1)

Post-Irradiation MPC-24 MPC-24 Cooling Time BPRA Burnup TPD Burnup (years) (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 2 33

Table 1.3-1 (Page 1 of 5)

LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component Reference ASME Code Requirement Exception, Justification & Compensatory Measures Code Section/Article MPC NB-1100 Statement of MPC enclosure vessel is designed and will be fabricated in requirements for Code accordance with ASME Code,Section III, Subsection NB to stamping of the maximum practical extent, but Code stamping is not components. required.

MPC NB-2000 Requires materials to be Materials will be supplied by Holtec-approved suppliers supplied by ASME- with Certified Material Test Reports (CMTRs) in approved material accordance with NB-2000 requirements.

supplier.

MPC Lid and NB-4243 Full penetration welds MPC lid and closure ring are not full penetration welds.

Closure Ring required for Category C They are welded independently to provide a redundant Welds Joints (flat head to main seal. Additionally, a weld efficiency factor of 0.45 has been shell per NB-3352.3). applied to the analyses of these welds.

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 examination required the root and final weld layers and each approximately 3/8 inch of weld depth.

MPC Closure NB-5230 Radiographic (RT) or Root (if more than one weld pass is required) and final Ring, Vent ultrasonic (UT) liquid penetrant examination to be performed in and Drain examination required accordance with NB-5245. The MPC vent and drain cover Cover Plate plate welds are leak tested. The closure ring provides Welds independent redundant closure for vent and drain cover plates.

Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 34

Table 1.3-1 (Page 2 of 5)

LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component Reference ASME Code Requirement Exception, Justification & Compensatory Measures Code Section/Article MPC NB-6111 All completed pressure The MPC enclosure vessel is seal welded in the field Enclosure retaining systems shall following fuel assembly loading. The MPC enclosure Vessel and be pressure tested. vessel shall then be hydrostatically tested as defined in Lid Chapter 9. Accessibility for 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 2 35

Table 1.3-1 (Page 3 of 5)

LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component Reference ASME Code Requirement Exception, Justification & Compensatory Measures Code Section/Article MPC NB-7000 Vessels are required to No overpressure protection is provided. The function of Enclosure 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 for The HI-STAR 100 Cask System is to be marked and Enclosure nameplates, stamping identified in accordance with 10CFR71 and 10CFR72 Vessel and reports per NCA- requirements. Code stamping is not required. QA data 8000. package to be in accordance with Holtec approved QA program.

Overpack NB-1100 Statement of Overpack helium retention boundary is designed, and will Helium requirements for Code be fabricated in accordance with ASME Code,Section III, Retention stamping of components Subsection NB to the maximum practical extent, but Code Boundary stamping is not 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 Helium have overpressure overpack vessel is to contain helium contents under Retention protection normal, off-normal, 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 2 36

Table 1.3-1 (Page 4 of 5)

LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component Reference ASME Code Requirement Exception, Justification & Compensatory Measures Code Section/Article Overpack NB-8000 Statement of The HI-STAR 100 Cask System is to be marked and Helium requirements for identified in accordance with 10CFR71 and 10CFR72 Retention nameplates, stamping requirements. Code stamping is not required. QA data Boundary and reports per NCA- package to be in accordance with Holtec approved QA 8000 program.

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.

MPC Basket NG-8000 States requirements for The HI-STAR 100 Cask System will be marked and Assembly nameplates, stamping identified in accordance with 10CFR71 and 10CFR72 and reports per requirements. No code stamping is required. The MPC NCA-8000. basket data package will be in conformance with Holtecs QA program.

Overpack NF-4622 All welds, including Intermediate shell-to-top flange welds and intermediate Intermediate repair welds, shall be shell-to-bottom plate welds do not require PWHT. These Shells post-weld heat treated welds attach non-pressure retaining parts to pressure (PWHT). 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 2 37

Table 1.3-1 (Page 5 of 5)

LIST OF ASME CODE EXCEPTIONS FOR THE HI-STAR 100 CASK SYSTEM Component Reference ASME Code Requirement Exception, Justification & Compensatory Measures 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 CMTRs in accordance with NF-2000 requirements.

Shells approved 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 components.

Boundary materials Renewed Certificate of Compliance No. 1008 Appendix B Amendment 2 38

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