ML21168A355

From kanterella
Revision as of 21:38, 18 January 2022 by StriderTol (talk | contribs) (StriderTol Bot change)
Jump to navigation Jump to search

Proposed Technical Specifications (Appendix B) for CoC No. 1008, Renewed Amendment No. 0
ML21168A355
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: ML21168A355 (34)
v • d • e


Text

RENEWED CERTIFICATE OF COMPLIANCE NO. 1008 APPENDIX B APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STAR 100 CASK SYSTEM AMENDMENT 0

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 DAMAGED FUEL ASSEMBLIES are fuel assemblies with ASSEMBLY known or suspected cladding defects 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. A DAMAGED FUEL ASSEMBLY's inability to be handled by normal means must be due to mechanical damage and must not be due to fuel rod cladding damage.

DAMAGED FUEL DFCs are specially designed enclosures for DAMAGED CONTAINER (DFC) FUEL ASSEMBLIES or FUEL DEBRIS which permit gaseous and liquid media to escape while minimizing dispersal of gross particulates.

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 INTACT FUEL ASSEMBLIES are fuel assemblies without ASSEMBLY 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 the simple INITIAL ENRICHMENT average of the distributed fuel rod enrichments within a given axial plane of the assembly lattice.

Renewed Certificate of Compliance No. 1008 1 Appendix B - Amendment 0

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

a. INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, and FUEL DEBRIS meeting the limits specified in Table 1.1-1 (which refers to Tables 1.1-2 through 1.1-5) may be stored in the HI-STAR 100 SFSC System.
b. 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.
c. 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.
c. For MPC-68's partially loaded with array/class 6x6A, 6x6B, 6x6C, or BxBA fuel assemblies, all remaining Zircaloy clad INTACT FUEL ASSEMBLIES in the MPC shall meet the maximum decay heat generation limits for the 6x6A, 6x68, 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:

a. The affected fuel assemblies shall be placed in a safe conditior, without delay and in a controlled manner.
b. 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.

Renewed Certificate of Compliance No. 1008 2 Appendix B - Amendment 0

c. 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 contained in 10 CFR 72.75 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, Section Ill, 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 Ill, 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 will need verification by the system user, as a minimum. are as follows:

1. The temperature of 80°F is the maximum allowed average yearly temperature.

Renewed Certificate of Compliance No. 1008 3 Appendix B - Amendment 0

2. The allowed temperature extremes, averaged over a three day period, shall be greater than -40°F, and less than 125 °F.
3. The horizontal and vertical seismic acceleration levels are bounded by the values listed below in Table 1-4.

Table 1-4 Design-Basis Earthquake Input on the Top Surface of an ISFSI Pad Horizontal g-level in Horizontal g-level Corresponding each of two orthogonal Vector Sum Vertical g-level directions (upward}

0.222 g 0.314 g 1.00 X 0.222 Q =0.222 9 0.235 g 0.332 g 0.75 X 0.235 Q =0.176 g 0.24 g 0.339 g 0.667 0.24 Q =0.160 9 X

0.25g 0.354 g 0.500 0.25 Q =0.125 g X

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 taflk will contain no more than 50 gallons of combustible transporter fuel.
6. In addition to the requirement of 10 CFR 72.212(b)(2)(ii), the cask storage pads and foundation shall include the following characteristics as applicable to the drop and tipover analyses:
a. Concrete thickness: ~ 36 inches
b. Concrete compressive strength: ~ 4,200 psi
c. Reinforcement top and bottom (Both Directions):

Reinforcement area and spacing determined by analysis Reinforcement yield strength: ~ 60,000 psi

d. Soil effective modulus of elasticity: ,:: 28,000 psi An acceptable method of defining the soil effective modulus of elasticity applicable to the drop and tipover analyses is provided Renewed Certificate of Compliance No. 1008 4 Appendix B - Amendment 0

in Table 13 of NUREG/CR-6608 with soil classification in accordance with ASTM-D2487-93, Standard Classification of Soils for Engineering Purposes (Unified Soil Classification System USCS} and density determination in accordance with ASTM-D1586-84, Standard Test Method for Penetration Test and Split/Barrel Sampling of Soils.

7. In cases where engineered features (i.e., berms, shield walls) are used to ensure that the requirements of 10 CFR 72.104(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category.

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 Bora! 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 Baral neutron absorbers: 0.0372 g/cm2 in the MPC 68, and 0.01g/cm2 in the MPC-68F.

1.5.2. Specifications Important for Thermal Performance 1.5.2.1 OVERPACK The painted surface of the HI-STAR 100 OVERPACK must have an emissivity no less than 0.85.

Renewed Certificate of Compliance No. 1008 5 Appendix B - Amendment 0

Table 1.1-1 Fuel Assembly Limits I. MPC MODEL: MPC-24 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) 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. ZrClad: An assembly post-irradiation cooling time and average burnup as specified in Table 1.1-5.

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.

Renewed Certificate of Compliance No. 1008 6 Appendix B - Amendment 0

~ 176.8 inches

e. Nominal Fuel Assembly Length:
f. Nominal Fuel Assembly ~ 8.54 inches Width:
g. Fuel Assembly Weight: ~ 1,680 lbs B. Quantity per MPC: Up to 24 fuel assemblies.

C. Fuel assemblies shall not contain control components.

D. DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS are not authorized for loading into the MPC-24.

Renewed Certificate of Compliance No. 1008 7 Appendix B - Amendment 0

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- As specified in Table 1.1-3 for the AVERAGE INITIAL applicable fuel assembly array/class.

ENRICHMENT:

c. Initial Maximum Rod As.specified in Table 1.1-3 for the Enrichment: applicable fuel 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 array/class 6x6A, 6x6C,and 8x8A fuel assemblies, which shall have a decay heat !:. 115 Watts.

ii. SS Clad: ~ 95 Watts lj Renewed Certificate of Compliance No. 1008 8 Appendix B - Amendment 0

e. 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, except for array/class 6x6A, 6x6C, and 8x8A fuel assemblies, which shall have a cooling time~ 18 years and an average burnup ~ 30,000 MWD/MTU.

ii. SS Clad: An assembly cooling time after discharge

~ 10 years and an ~verage burn up~

22,500 MWD/MTU.

f. Nominal Fuel Assembly ~ 176.2 inches Length:
g. Nominal Fuel Assembly ~ 5.85 inches Width:
h. Fuel Assembly Weight: ~ 700 lbs, including channels Renewed Certificate of Compliance No. 1008 9 Appendix B - Amendment 0

V

. Uranium ox 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 As specified in Table 1.1-3 for the AVERAGE INITIAL applicable fuel assembly array/class.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 1.1-3 for the Enrichment: applicable fuel assembly array/class.
d. Decay Heat Per 115 Watts Assembly:
e. Post-irradiation An assembly post-irradiation cooling time Cooling Time and 18 years and an average burnup Average Burnup Per 30,000 MWD/MTU.

Assembly:

f. Nominal Fuel Assembly 135.0 inches Length:
g. Nominal Fuel Assembly 4.70 inches Width:
h. Fuel Assembly Weight: 400 lbs, including channels 10 Renewed Certificate of Compliance No. 1008 Appendix B - Amendment 0
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- As specified in Table 1.1-3 for fuel AVERAGE INITIAL assembly array/class 6x68.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 1.1-3 for fuel Enrichment: assembly array/class 6x68.
d. Decay Heat Per ~ 115 Watts Assembly:
e. Post-irradiation An assembly post-irradiation cooling time Cooling Time and  ::. 18 years and an average burnup ~

Average Burnup Per 30,000 MWD/MTIHM.

Assembly:

f. Nominal Fuel Assembly ~ 135.0 inches Length:
g. Nominal Fuel Assembly ~ 4.70 inches Width:
h. Fuel Assembly Weight: ~ 400 lbs, including channels Renewed Certificate of Compliance No. 1008 11 Appendix B - Amendment 0
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- As specified in Table 1.1-3 for AVERAGE INITIAL array/class 6x68.

ENRICHMENT:

C. Initial Maximum Rod As specified in Table 1.1-3 for Enrichment: array/class 6x68.

d. Decay Heat Per ~ 115 Watts Assembly:
e. Post-irradiation An assembly post-irradiation Cooling Time and cooling time ~ 18 years and an Average Burnup Per average burnup ~ 30,000 Assembly: MWD/MTIHM.
f. Nominal Fuel Assembly ~ 135.0 inches Length:
g. Nominal Fuel Assembly ~ 4.70 inches Width
h. Fuel Assembly Weight: ~ 400 lbs, including channels B. Quantity per MPC: 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.

Renewed Certificate of Compliance No. 1008 12 Appendix B - Amendment 0

Ill. 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 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- As specified in Table 1.1-3 for the AVERAGE INITIAL applicable fuel assembly array/class.

ENRICHMENT:

C. Initial Maximum Rod As specified in Table 1.1-3 for the Enrichment: applicable fuel assembly array/class.

d. Decay Heat Per ~ 115 Watts.

Assembly:

e. Post-irradiation An assembly post-irradiation cooling Cooling Time and time ~ 18 years and an average burnup Average Burnup Per ~ 30,000 MWD/MTU.

Assembly:

f. Nominal Fuel Assembly ~ 176.2 inches Length:
g. Nominal Fuel Assembly ~ 5.85 inches Width:
h. Fuel Assembly Weight: ~ 700 lbs, including channels Renewed Certificate of Compliance No. 1008 13 Appendix B - Amendment 0
2. Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, piaced 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- As specified in Table 1.1-3 for the AVERAGE INITIAL applicable fuel assembly array/class.

ENRICHMENT:

C. Initial Maximum Rod As specified in Table 1.1-3 for the Enrichment: applicable fuel assembly array/class.

d. Decay Heat Per ~ 115 Watts Assembly:
e. Post-irradiation A post-irradiation cooling time after Cooling Time and discharge :::. 18 years and an average Average Burnup Per burnup ~ 30,000 MWD/MTU.

Assembly:

f. Nominal Fuel Assembly ~ 135.0 inches Length:
g. Nominal Fuel Assembly ~ 4.70 inches Width:
h. Fuel Assembly Weight: ~ 400 lbs, including channels Renewed Certificate of Compliance No. 1008 14 Appendix B - Amendment 0
3. Uranium oxide, BWR FUEL DEBRIS, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the 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- As specified in Table 1.1-3 for the AVERAGE INITIAL applicable original fuel assembly ENRICHMENT: array/class.
c. Initial Maximum Rod As specified in Table 1.1-3 for the Enrichment: applicable original fuel assembly array/class.
d. Decay Heat Per  !: 115 Watts DFC:
e. Post-irradiation A post-irradiation cooling time after Cooling Time and discharge ~ 18 years and an average Average Burnup Per burnup:: 30,000 MWD/MTU for the Assembly: original fuel assembly.
f. Nominal Original Fuel < 135.0 inches Assembly Length:
g. Nominal Original Fuel  !: 4.70 inches Assembly Width:
h. Fuel Debris Weight:  !: 400 lbs, including channels Renewed Certificate of Compliance No. 1008 15 Appendix B - Amendment 0
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- As specified in Table 1.1-3 for fuel AVERAGE INITIAL assembly array/class 6x68.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 1.1-3 for fuel Enrichment: assembly array/class 6x68 .
d. Decay Heat Per ~ 115 Watts Assembly:
e. Post-irradiation An assembly post-irradiation cooling Cooling Time and time after discharge ~ 18 years and an Average Burnup Per average burnup ~ 30,000 Assembly: MWD/MTIHM.
f. Nominal Fuel Assembly ~ 135.0 inches Length:
g. Nominal Fuel Assembly ~ 4.70 inches Width:
h. Fuel Assembly Weight: ~ 400 lbs, including channels Renewed Certificate of Compliance No. 1008 16 Appendix B - Amendment 0
5. 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- As specified in Table 1.1-3 for fuel AVERAGE INITIAL assembly array/class 6x6B.

ENRICHMENT:

c. Initial Maximum Rod As specified in Table 1.1-3 for fuel Enrichment: assembly array/class 6x68.
d. Decay Heat Per ~ 115 Watts Assembly:
e. Post-irradiation A post-irradiation cooling time after Cooling Time and discharge ~ 18 years and an average
  • Average Burnup Per burnup:: 30,000 MWD/MTIHM.

Assembly:

f. Nominal Fuel Assembly  :: 135.0 inches Length:
g. Nominal Fuel Assembly  :: 4.70 inches Width:
h. Fuel Assembly Weight: ~ 400 lbs, including channels Renewed Certificate of Compliance No. 1008 17 Appendix B - Amendment 0
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- As specified in Table 1.1-3 for original AVERAGE INITIAL fuel assembly array/class 6x6B.

ENRICHMENT:

C. Initial Maximum Rod As specified in Table 1.1-3 for original Enrichment: fuel assembly array/class 6x6B.

d. Decay Heat Per ~ 115 Watts DFC:
e. Post-irradiation A post-irradiation cooling time after Cooling Time and discharge ~ 18 years and an average Average Burnup Per burnup ~ 30,000 MWD/MTIHM for the Assembly: original fuel assembly.
f. Nominal Original Fuel ~ 135.0 inches Assembly Length:
g. Nominal Original Fuel ~ 4.70 inches Assembly Width:
h. Fuel Debris Weight: ~ 400 lbs, including channels Renewed Certificate of Compliance No. 1008 18 Appendix B - Amendment 0

B. Quantity per MPG:

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, 6x68, 6x6C, 7x7A, and 8x8A fuel assemblies of the following type, as applicable:

a. Uranium oxide BWR INTACT FUEL ASSEMBLIES;
b. MOX BWR INTACT FUEL ASSEMBLIES;
c. Uranium oxide BWR DAMAGED FUEL ASSEMBLIES placed in DFCs; or
d. MOX BWR DAMAGED FUEL ASSEMBLIES placed in DFCs.

C. Fuel assemblies with stainless steel channels are not authorized for loading in the MPC-68F.

Renewed Certificate of Compliance No. 1008 19 Appendix B - Amendment 0

Table 1.1-2 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 ~402  ;:402  ;:410 ~400 ~420 (kg/assy.)

Initial Enrichment (wt . ~4.6  ;: 4.6  ;: 4.6  ;:4.0  ;:4.1

%235U)

No. of Fuel Rods 179 179 176 180 204 Clad 0.0. (in.)  :: 0.400  :: 0.417  :: 0.440 ~0.422 ~0.418 Clad 1.0. (in.) ~0.3514 ~0.3734  ;: 0.3840  ;:0.3890  ;: 0.3660 Pellet Oja. (in.)  ;: 0.3444  ;: 0.3659  ;: 0.3770  ;: 0.3835 ;: 0.3580 Fuel Rod Pitch (in.)  ;: 0.556  ;: 0.556  ;: 0.580  ;: 0.556  ;: 0.550 Active Fuel Length ~ 150  ;: 150  ;: 150  ;: 144  ;: 150 (in.)

No. of Guide Tubes 17 17 5(note 3) 16 21 Guide Tube ~0.017  :: 0.017 ~0.040 ~0.0145 ~0.0165 Thickness (in.)

Renewed Certificate of Compliance No. 1008 20 Appendix B - Amendment 0

Table 1.1-2 (continued) .

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.)

Initial Enrichment (wt .::4.1 .::4.1 !4.1 .:: 4.1 .:: 4.1

% 2l5U)

No. of Fuel Rods 204 204 208 208 208 Clad 0.0. (in.) ==.0.420 ==.0.417 ==. 0.430 ==. 0.428 ==.0.428 Clad 1.0. (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 Length .:: 150 .:: 150  ! 150 .:: 150 .:: 150 (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 21 Appendix B - Amendment 0

Table 1.1-2 (continued)

PWR FUEL ASS EMBLY CHARACTERISTICS (note 1)

Fuel Assembly 15x15G 16x16A 17x17A 17x178 17x17C Array/ Class Clad Material ss Zr Zr Zr Zr (note 2)

Design Initial U !420 !430 !450 !464 !460 (kg/assy.)

Initial Enrichment (wt !4,0  ;:: 4.6  !:4,0  :!: 4.0 !4,0

% 235U)

No. of Fuel Rods 204 236 264 264 264 Clad O.D. (in.) ~0.422 ~ 0.382 ~ 0.360 ~0.372 ?0.377 Clad I.D. (in.) !0.3890 !0,3320 ~0.3150 ~0.3310

.~0.3330 Pellet Dia. (in.) ~0.3825 ~0.3255 !0,3088 !0,3232 ~0.3252 Fuel Rod Pitch~ (in.) ~0.563 ~0.506 =:0.496  ! 0.496  :!:0,502 Active Fuel Length ~ 144  !: 150  !: 150  !: 150  !: 150 (in.)

No. of Guide Tubes 21 5 (note 3) 25

- 25 25 Guide Tube ~0.0145 ~0.0400 ~ 0.016 ~ 0.014 ~0.020 Thickness (in.)

Notes: 1. Initial Uranium weights and all dimensions are design nominal values. Actual uranium weights may be up to 2.0% higher, within the manufacturers tolerance. 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. Each guide tube replaces four fuel rods.

Renewed Certificate of Compliance No. 1008 22 Appendix B - Amendment 0

Table 1.1-3 BWR FUEL ASSEMBLY CHARACTERISTICS (note 1)

Fuel Assembly 6x6A 6x6B 6x6C 7x7A 7x7B SxSA Array/Class Clad Material Zr Zr Zr Zr Zr Zr (note 2)

Design Initial U .:: 108 .:: 108 ~108 ~ 100 .:: 195 .:: 120 (kg/assy.)

Maximum PLANAR- .::2.7 .::2.7 for the .::2.7 ,::2.7 .::4.2 .::2.7 AVERAGE INITIAL U02 rods.

ENRICHMENT See Note 3 (wt.% 235U) for MOX rods Initial Maximum .:: 4.0 .:: 4.0 .:: 4.0 .:: 4.0 .:: 5.0 .:: 4.0 Rod Enrichment (wt.% 23sU)

No. of Fuel Rods 36 36 (upto 9 36 49 49 64 MOX rods)

Clad 0.0. (in.) .::,0.5550 .::,0.5625 .::,0.5630 .::, 0.4860 :: 0.5630 .::,0.4120 Clad 1.0. (in.) .:: 0.4945 .:: 0.4945 .:: 0.4990 .:: 0.4200 .::'0.4990 .:: 0.3620 Pellet Dia. (in.)  ::, 0.4940  ::, 0.4820  ::, 0.4880 .=: 0.4110 .:: 0.4880  ::, 0.3580 Fuel Rod Pitch (in.)  ::, 0.694 .:: 0.694 ~0.740 .:: 0.631  ::, 0.738 .:: 0.523 Active Fuel Length .:: 110 .:: 110 .:: 77.5 ,::79 .:: 150 .::110 (in.)

No. of Water Rods 0 0 0 0 0 0 Water Rod NIA NIA N/A N/A NIA N/A Thickness (in.)

Channel Thickness  ::, 0.060 .:: 0.060 .:: 0.060  ::, 0.060  ::,0.120  ::,0.100 (in.)

Renewed Certificate of Compliance No. 1008 23 Appendix B - Amendment 0

. Table 1.1-3 (continued) . ..

BWR FUEL ASSEMBLY CHARACTERISTICS (note 1)

Fuel Assembly 8x88 8x8C 8x8D 8x8E .9x9A 9x9B Array/Class Clad Material Zr Zr Zr Zr Zr Zr (Note 2)

Design Initial U  !: 185  !: 185  !: 185  :: 180  !: 173  :: 173

{kg/assy.)

Maximum PLANAR-  !: 4.2  :: 4.2  ::4.2  :: 4.2  ::4.2  ::4.2 AVERAGE INITIAL ENRICHMENT (wt.% 235U)

Initial Maximum Rod  ::5.0  ::5.0  ::5.0  ::5.0  ::5.0  ::5.0 Enrichment (wt.% 235U)

No. of Fuel Rods 63 62 60 59 74/66 72 (Note 4)

Clad 0.0. (in.) ~0.4840 ~ 0.4830 ~0.4830 ~ 0.4930 ~ 0.4400 ~0.4330 Clad I.D. (in.)  ::0.4250  !: 0.4250  !: 0.4190  !: 0.4250 !: 0.3840 !:0,3810 Pellet Dia. (in.)  :: 0.4160  !: 0.4160  ::0.4110  !: 0.4160 !: 0.3760 !: 0.3740 Fuel Rod Pitch (in.)  !: 0.641  ::0.641  !: 0.640  ::0.640  :: 0.566  !: 0.569 Design Active Fuel  !: 150  :: 150  !: 150  !: 150  !: 150  !: 150 Length (in.)

No. of Water Rods 1 2 1-4 5 2 1 (Note 5)

(Note 6)

Water Rod Thickness ~ 0.034 > 0.00 > 0.00  ? 0.034 >0.00 >0.00 (in.)

Channel Thickness  !: 0.120  !: 0.120  !: 0.120  !: 0.100  !: 0.120  !: 0.120 (in.)

Renewed Certificate of Compliance No. 1008 24 Appendix B - Amendment 0

Table 1.1-3 (continued)

BWR FUEL ASSEMBLY CHARACTERISTICS (note 1)

Fuel Assembly 9x9C 9x9D 9x9E 9x9F 10x10A Array/Class Clad Material Zr Zr Zr Zr Zr Design Initial U ,:: 173 ,:: 170 ,:: 170 ,:: 170 ,:: 182 (kg/assy.)

Maximum PLANAR- ,::4.2 ,::4.2 ,::4.2 ,::4.2 ,::4.2 AVERAGE INITIAL ENRICHMENT (wt.% 235 U)

Initial Maximum Rod ,::5.0 ,::5.0 ,::5.0 ,::5.0 ,::5.0 Enrichment (wt.% 235 U)

No. of Fuel Rods 80 79 76 76 92/78 (Note 7)

Clad O.D. (in.) ~0.4230 ~ 0.4240 ~ 0.4170 ~ 0.4430 ~0.4040 Clad 1.D. (in.) ~0.3640 ~0.3640 ~0.3590 ,::0.3810 ~0.3520 Pellet Dia. On.) ,:: 0.3565 ,:: 0.3565 ~ 0.3525 ~ 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 Water Rod Thickness > 0.020 ~0.0305 ~0.0305 ~0.0305 ~0.0300 (in.)

Channel Thickness (in.) !0,100 ~0.100 !0,100 ~ 0.100 ~0.120 Renewed Certificate of Compliance No. 1008 25 Appendix B - Amendment 0

Table 1.1-3 (continued)

BWR FUEL ASSEMBLY CHARACTERISTICS (note 1)

Fuel Assembly Array/Class 10x10B 10x10C 10x10D 10x10E Clad Material (note 2) Zr Zr ss ss Design Initial U (kg/assy.)  ! 182  ! 180  ! 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 !5,0 Enrichment (wt.% 235U)

No.of Fuel Rods 91/83 (note 8) 96 100 96 Clad 0.0. {in.) ~0.3957 ~0.3790 ~0--3960 ~0.3940 Clad 1.0. (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 1 (Note 5) 5 (Note 9) 0 4 Water Rod Thickness (in.) > 0.00 ~ 0.034 NIA ~0.022 Channel Thickness (in.) ~0.120  ::0.055  :: 0.080 ~0.080

1. Initial uranium we*ights and all dimensions are design nominal values. Actual uranium weights may be up to 1.5% higher, within the manufacturer's tolerance. 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.  :: 0.612 wt.% 235 U and:: 1.578 wt,% total fuel fissile plutonium {239Pu and 2 ~ 1Pu).
4. This assembly class contains 74 rods; 66 full length rods and 8 partial length rods.
5. Square, replacing nine fuel rods.
6. Variable
7. This assembly class contains 92 total fuel rods; -78 full length rods and 14 partial length rods.
8. This assembly class contains 91 total fuel rods; 83 full length rods and 8 partial length rods.
9. One diamond shaped water rod replacing the four center fuel rods and four rectangualr water rods dividing the assembly into four quadrants.

Renewed Certificate of Compliance No. 1008 26 Appendix B - Amendment 0

Table 1.1-4 FUEL ASSEMBLY COOLING AND DECAY HEAT GENERATION Post-irradiation MPC-24 MPC-68 Cooling Time PWR Assembly BWR Assembly (years) Decay Heat 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

> 14 ~665 ~226 Renewed Certificate of Compliance No. 1008 27 Appendix B - Amendment 0

Table 1.1-5 FUEL ASSEMBLY COOLING AND AVERAGE BURNUP Post-irradiation MPC-24 MPC-68 Cooling Time PWR Assembly BWR Assembly (years) Burnup Burnup (MWD/MTU) (MWD/MTU)

?.5 ~28,700 ~ 26,000

?.6 ~32,800 ~ 29,100

?. 7 ~33,300 ~29,600

?. 8 ~35,600 ~ 31,400

?.9 ~37,000 ~ 32,800

?. 10 ~ 38,300 ~ 33,800

?. 11 ~39,300 ~ 34,800

?. 12 ~40,200 ~ 35,500

?. 13 ~40,900 ~ 36,200

?. 14 ~41,500 ~ 36,900

?. 15 ~42,100 ~37,600 Renewed Certificate of Compliance No. 1008 28 Appendix B - Amendment 0

LIST OF ASME CODE EXCEPTIONS FOR HI-STAR 100 SYSTEM Table 1.3-1 Component Reference ASME Code Code Requirement Exception, Justification &

Section/Article Compensatory Measures MPC NB-1100 Statement of requirements for Code MPC enclosure vessel is designed and will be stamping of components. fabricated In accordance with ASME Code, Section Ill, Subsection NB to the maximum practical extent, but Code stamping is not required.

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

MPC Lid and Closure NB-4243 Full penetration welds required for Category MPC lid and closure ring are not full penetration Ring Welds C Joints (flat head to main shell per NB- welds. They are welded independently to provide a 3352.3) redundant seal. Additionally, a weld efficiency factor of 0.45 has been applied to the analyses of these welds.

MP.C Closure Ring, NB-5230 Radiographic (RT) or ultrasonic (UT) Root and final liquid penetrant examination to be Vent and Drain Cover examination required. performed in accordance with NB-5245. The MPC Plate Welds vent and drain cover plate welds are leak tested.

The closure ring provides Independent redundant closure for vent and drain cover plates.

Renewed Certificate of Compliance No. 1008 29 Appendix B - Amendment 0

Component Reference ASME Code Code Requirement Exception, Justification &

Sectfon/ArtJcre Compensatory Measures MPG Enclosure NB-6111 All completed pressure retaining systems The MPC enclosure vessel is seat welded in Vessel and Lid shall be pressure tested. the field following fuel assembly loading. The MPG enclosure vessel shall then be hydrostatically tested as defined in Chapter 9.

Accessibility for leakage inspections preclude a Code compliant hydrostatic test. All MPG enclosure vessel welds (except the lid-to-shell and closure ring and venVdrain cover plate) are inspected by RT or UT. The MPG lid-to-shell root and final weld layers are PT examined and the entire weld is either UT examined or multilayer PT examined. The vent/drain cover plate weld is confirmed by leakage testing and 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 holder's records by video, photographic, or other means which provide an equivalent retrievable record of weld integrity.

The video or photographic records should be taken during the final interpretation period described in ASME Section V, Article 6, T~676.

The inspection of the weld must be performed by qualified personnel and shall meet the acceptance requirements of ASME Code Section Ill, NB-5350 for PT or NB-5332 for UT.

Renewed Certificate of Compliance No. 1008 30 Appendix B - Amendment 0

Component Reference ASME Code Code Requirement Exception, Justification &

Section/Article Compensatory Measures MPC Enclosure NB-7000 Vessels are required to have No overpressure protection is provided.

Vessel overpressure protection. Function of MPC enclosure vessel is to contain radioactive contents under normal, off-normal, and accident conditions of storage. MPC vessel is designed to withstand maximum internal pressure considering 100% fuel rod failure and maximum accident temperatures.

MPC Enclosure NB-8000 States requirements for nameplates, HI-STAR 100 System to be marked and Vessel stamping and reports per NCA-8000. identified in accordance with 10CFR71 and 10CFR72 requirements. Code stamping is not

  • required. QA data package to be in accordance with Holtec approved QA program.

Overpack Helium NB-1100 Statement of requirements for Code Overpack helium retention boundary is Retention Boundary stamping of components. designed, and will be fabricated in accordance with ASME Code, Section Ill, Subsection NB to the maximum practical extent, but Code stamping is not required.

Overpack Helium NB-2000 Requires materials to be supplied by Materials will be supplied by Holtec approved Retention Boundary ASME approved Material Supplier. suppliers with CMTRs per NB-2000.

Overpack Helium NB-7000 Vessels are required to have No overpressure protection is provided.

Retention Boundary overpressure protection. Function of overpack vessel is to contain helium contents under normal, off-normal, and accident conditions. Overpack vessel is designed to withstand maximum internal pressure and maximum accident temperatures.

n Renewed Certificate of Compliance No. 1008 31 Appendix B - Amendment 0

Component Reference ASME Code Code Requirement Exception, Justification &

Section/Article Compensatory Measures Overpack Helium NB-8000 Statement of Requirements for HI-STAR 100 System to be marked and Retention nameplates, stamping and reports per identified in accordance with 10CFR71 and Boundary NCA-8000. 10CFR72 requirements. Code stamping is not required. QA data package to be in.

accordance with Holtec's approved QA program.

MPC Basket NG-2000 Requires materials to be supplied by Materials will be supplied by Holtec approved Assembly ASME approved Material Supplier. supplier with CMTRs in accordance with NG-2000 requirements.

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

Overpack NF-4622 All welds, including repair welds, shall rntermediate shell-to-top flange welds and r ntermediate Shells be post-weld heat treated (PWHT). intermediate shell-to-bottom plate welds do not require PWHT. These welds attach 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.

Overpack Helium NG-2000 Perform radiographic examination after Radiography of the helium retention boundary Retention Boundary post-weld heat treatment (PWHn welds after PWHT is not required. All welds (including repairs) will have passed radiographic examination prior to PWHT of the entire containment boundary. Conrmatory radiographic examination after PWHT is not necessary because PWHT is not known to introduce new weld defects in nickel steels.

Renewed Certificate of Compliance No. 1008 32 Appendix B - Amendment 0

Component Reference ASME Code Code Requirement Exception, Justification &

Section/Article Compensatory Measures Overpack NF-2000 Requires materials to be supplied by Materials will be supplied by Holtec approved Intermediate Shells ASME approved Material Supplier.

  • supplier with CMTRs in accordance with NF-2000 requirements.

Overpack Helium NB-2330 Defines the methods for determining the T NOT shall be defined in accordance with Retention Boundary T NOT for impact testing of materials. Regulatory Guides 7.11 and 7.12 for the helium retention boundary components.

Renewed Certificate of Compliance No. 1008 33 Appendix B - Amendment 0

Retrieved from "https://kanterella.com/w/index.php?title=ML21168A355&oldid=3409030"