ML19282C369
| ML19282C369 | |
| Person / Time | |
|---|---|
| Site: | 07201032 |
| Issue date: | 10/02/2019 |
| From: | Holtec |
| To: | Division of Spent Fuel Management |
| Shared Package | |
| ML19282C357 | List: |
| References | |
| 5018071 | |
| Download: ML19282C369 (9) | |
Text
CERTIFICATE OF COMPLIANCE NO. 1032 APPENDIX B APPROVED CONTENTS AND DESIGN FEATURES FOR THE HI-STORM FW MPC STORAGE SYSTEM ATTACHMENT 4 TO HOLTEC LETTER 5018071 1 of 9
Approved Contents 2.0 Certificate of Compliance No.1032 Amendment No. 65 Appendix B 2-5 Table 2.1-1 (page 1 of 6)
Fuel Assembly Limits I. MPC MODEL: MPC-37 A. Allowable Contents
- 1. Uranium oxide PWR UNDAMAGED FUEL ASSEMBLIES and, DAMAGED FUEL ASSEMBLIES meeting the criteria in Table 2.1-2, and/or FUEL DEBRIS meeting the criteria in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):
- a. Cladding Type:
ZR
- b. Maximum Initial Enrichment:
5.0 wt. % U-235 with soluble boron credit per LCO 3.3.1 OR burnup credit per Section 2.4
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
Cooling Time 2 years Assembly Average Burnup 68.2 GWD/MTU
- d. Decay Heat Per Fuel Storage Location:
As specified in Section 2.3
- e. Fuel Assembly Length:
199.2 inches (nominal design including NON-FUEL HARDWARE and DFC)
- f. Fuel Assembly Width:
8.54 inches (nominal design)
- g. Fuel Assembly Weight:
2050 lbs (including NON-FUEL HARDWARE and DFC)
ATTACHMENT 4 TO HOLTEC LETTER 5018071 2 of 9
Approved Contents 2.0 Certificate of Compliance No.1032 Amendment No. 65 Appendix B 2-7 Table 2.1-1 (page 3 of 6)
Fuel Assembly Limits II. MPC MODEL: MPC-89 A. Allowable Contents
- 1. Uranium oxide BWR UNDAMAGED FUEL ASSEMBLIES and, DAMAGED FUEL ASSEMBLIES meeting the criteria in Table 2.1-3, and/or FUEL DEBRIS meeting the criteria in Table 2.1-3, with or without channels and meeting the following specifications:
- a. Cladding Type:
ZR
- b. Maximum PLANAR-AVERAGE INITIAL ENRICHMENT(Note 1):
As specified in Table 2.1-3 for the applicable fuel assembly array/class.
- c. Initial Maximum Rod Enrichment 5.0 wt. % U-235
- d. Post-irradiation Cooling Time and Average Burnup Per Assembly
- i. Array/Class 8x8F Cooling time 10 years and an assembly average burnup 27.5 GWD/MTU.
ii. All Other Array Classes Cooling Time 1.2 years and an assembly average burnup 65 GWD/MTU
- e. Decay Heat Per Assembly
- i. Array/Class 8x8F 183.5 Watts ii. All Other Array Classes As specified in Section 2.3
- f. Fuel Assembly Length 176.5 inches (nominal design)
- g. Fuel Assembly Width 5.95 inches (nominal design)
- h. Fuel Assembly Weight 850 lbs, including a DFC as well as a channel ATTACHMENT 4 TO HOLTEC LETTER 5018071 3 of 9
Approved Contents 2.0 Certificate of Compliance No.1032 Amendment No. 65 Appendix B 2-9 Table 2.1-1 (page 5 of 6)
Fuel Assembly Limits III. MPC MODEL: MPC-32ML A. Allowable Contents
- 1. Uranium oxide PWR UNDAMAGED FUEL ASSEMBLIES and, DAMAGED FUEL ASSEMBLIES meeting the criteria for array/class 16x16D in Table 2.1-2, and/or FUEL DEBRIS meeting the criteria for array/class 16x16D in Table 2.1-2, with or without NON-FUEL HARDWARE and meeting the following specifications (Note 1):
- a. Cladding Type:
ZR
- b. Maximum Initial Enrichment:
5.0 wt. % U-235 with soluble boron credit per LCO 3.3.1
- c. Post-irradiation Cooling Time and Average Burnup Per Assembly:
Cooling Time 3 years Assembly Average Burnup 68.2 GWD/MTU
- d. Decay Heat Per Fuel Storage Location:
As specified in Section 2.3
- e. Fuel Assembly Length:
193 inches (nominal design including NON-FUEL HARDWARE and DFC)
- f. Fuel Assembly Width:
9.04 inches (nominal design)
- g. Fuel Assembly Weight:
1858 lbs (including NON-FUEL HARDWARE and DFC)
ATTACHMENT 4 TO HOLTEC LETTER 5018071 4 of 9
Design Features 3.0 Certificate of Compliance No. 1032 Amendment No. 65 Appendix B 3-1 3.0 DESIGN FEATURES 3.1 Site 3.1.1 Site Location The HI-STORM FW Cask System is authorized for general use by 10 CFR Part 50 license holders at various site locations under the provisions of 10 CFR 72, Subpart K.
3.2 Design Features Important for Criticality Control 3.2.1 MPC-37
- 1.
Minimum Bbasket cell ID: 8.92 in. (min.nominal)
- 2.
Minimum Bbasket cell wall thickness: 0.57 in. (min.nominal)
- 3.
B4C in the Metamic-HT: 10.0 wt % (min.)
3.2.2 MPC-89
- 1.
Minimum Bbasket cell ID: 5.99 in. (min.nominal)
- 2.
Minimum Bbasket cell wall thickness: 0.38 in. (min.nominal)
- 3.
B4C in the Metamic-HT: 10.0 wt % (min.)
3.2.3 Neutron Absorber Tests
- 1.
The weight percentage of the boron carbide must be confirmed to be greater than or equal to 10% in each lot of Al/B4C powder.
- 2.
The areal density of the B-10 isotope corresponding to the 10% min.
weight density in the manufactured Metamic HT panels shall be independently confirmed by the neutron attenuation test method by testing at least one coupon from a randomly selected panel in each lot.
- 3.
If the B-10 areal density criterion in the tested panels fails to meet the specific minimum, then the manufacturer has the option to reject the entire lot or to test a statistically significant number of panels and perform statistical analysis for acceptance.
- 4.
All test procedures used in demonstrating compliance with the above requirements shall conform to the cask designers QA program which has been approved by the USNRC under docket number 71-0784.
ATTACHMENT 4 TO HOLTEC LETTER 5018071 5 of 9
Design Features 3.0 Certificate of Compliance No. 1032 Amendment No. 65 Appendix B 3-2 3.2.4 MPC-32ML
- 1.
Minimum Bbasket cell ID: 9.53 (min.nominal)
- 2.
Minimum Bbasket cell wall thickness: 0.57 in (min.nominal)
- 3.
B4C in the Metamic-HT: 10.0wt% (min.)
3.3 Codes and Standards The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2007 Edition, is the governing Code for the HI-STORM FW System MPC as clarified in Specification 3.3.1 below, except for Code Sections V and IX. The ASME Code paragraphs applicable to the HI-STORM FW OVERPACK and TRANSFER CASK are listed in Table 3-2. The latest effective editions of ASME Code Sections V and IX, including addenda, may be used for activities governed by those sections, provided a written reconciliation of the later edition against the 2007 Edition, including any addenda, is performed by the certificate holder. American Concrete Institute (ACI) 349-85 is the governing Code for plain concrete as clarified in Appendix 1.D of the Final Safety Analysis Report for the HI-STORM 100 Cask System.
ATTACHMENT 4 TO HOLTEC LETTER 5018071 6 of 9
Design Features 3.0 Certificate of Compliance No. 1032 Amendment No. 65 Appendix B 3-11 3.0 DESIGN FEATURES (continued) 3.4 Site-Specific Parameters and Analyses Site-specific parameters and analyses that will require verification by the system user are, as a minimum, as follows:
- 1.
The temperature of 80o F is the maximum average yearly temperature. A Sites yearly average ambient temperature may be used for site-specific analysis.
- 2.
The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40o F and less than 125o F.
- 3.
- a.
For storage in a free-standing OVERPACK, Tthe resultant horizontal acceleration (vectorial sum of two horizontal Zero Period Accelerations (ZPAs) at a three-dimensional seismic site), aH, and vertical ZPA, aV, on the top surface of the ISFSI pad, expressed as fractions of a, shall satisfy the following inequalities:
aH f (1 - aV); and aH r (1 - aV) / h where f is the Coulomb friction coefficient for the cask/ISFSI pad interface, r is the radius of the cask, and h is the height of the cask center-of-gravity above the ISFSI pad surface. Unless demonstrated by appropriate testing that a higher coefficient of friction value is appropriate for a specific ISFSI, the value used shall be 0.53. If acceleration time-histories on the ISFSI pad surface are available, aH and aV may be the coincident values of the instantaneous net horizontal and vertical accelerations. If instantaneous accelerations are used, the inequalities shall be evaluated at each time step in the acceleration time history over the total duration of the seismic event.
If this static equilibrium based inequality cannot be met, a dynamic analysis of the cask/ISFSI pad assemblage with appropriate recognition of soil/structure interaction effects shall be performed to ensure that the casks will not tip over or undergo excessive sliding under the sites Design Basis Earthquake.
ATTACHMENT 4 TO HOLTEC LETTER 5018071 7 of 9
Design Features 3.0 Certificate of Compliance No. 1032 Amendment No. 65 Appendix B 3-12
- b. For a free-standing OVERPACK Uunder environmental conditions that may degrade the pad/cask interface friction (such as due to icing) the response of the casks under the sites Design Basis Earthquake shall be established using the best estimate of the friction coefficient in an appropriate analysis model. The analysis should demonstrate that the earthquake will not result in cask tipover or cause excessive sliding such that impact between casks could occur. Any impact between casks should be considered an accident for which the maximum total deflection, d, in the active fuel region of the basket panels shall be limited by the following inequality: d 0.005 l, where I is the basket cell inside dimension.
- c.
For those ISFSI sites with design basis seismic acceleration values that may overturn or cause excessive sliding of free-standing casks, the anchored HI-STORM FW OVERPACK shall be utilized. Each OVERPACK shall be anchored with studs and compatible nuts of material suitable for the expected ISFSI environment. The embedment design shall comply with Appendix B of ACI-349-97. A later edition of this Code may be used, provided a written reconciliation is performed.
- 4.
The maximum permitted depth of submergence under water shall not exceed 125 feet.
- 5.
The maximum permissible velocity of floodwater, V, for a flood of height, h, shall be the lesser of V1 or V2, where:
V1 = (1.876 W*)1/2 / h V2 = (1.876 f W*/ D h)1/2 and W* is the apparent (buoyant weight) of the loaded overpack (in pounds force), D is the diameter of the overpack (in feet), and f is the interface coefficient of friction between the ISFSI pad and the overpack, as used in step 3.a above. Use the height of the overpack, H, if h>H.
- 6.
The potential for fire and explosion while handling a loaded OVERPACK or TRANSFER CASK shall be addressed, based on site-specific considerations. The user shall demonstrate that the site-specific potential for fire is bounded by the fire conditions analyzed by the Certificate Holder, or an analysis of the site-specific fire considerations shall be performed.
ATTACHMENT 4 TO HOLTEC LETTER 5018071 8 of 9
Design Features 3.0 Certificate of Compliance No. 1032 Amendment No. 65 Appendix B 3-13 7.
a.
For storage in a free-standing OVERPACK, Tthe user shall demonstrate that the ISFSI pad parameters used in the non-mechanistic tipover analysis are bounding for the site or a site specific non-mechanistic tipover analysis shall be performed using the dynamic model described in FSAR Section 3.4. The maximum total deflection, d, in the active fuel region of the basket panels shall be limited by the following inequality: d 0.005 l, where l is basket cell inside dimension.
b.
For storage in an anchored OVERPACK, a tipover event is not credible. However, the ISFSI pad shall be designed to meet the embedment requirements of the anchored design.
8.
In cases where engineered features (i.e., berms and shield walls) are used to ensure that the requirements of 10CFR72.104(a) are met, such features are to be considered important-to-safety and must be evaluated to determine the applicable quality assurance category.
9.
LOADING OPERATIONS, TRANSPORT OPERATIONS, and UNLOADING OPERATIONS shall only be conducted with working area ambient temperatures 0o F.
10.
For those users whose site-specific design basis includes an event or events (e.g., flood) that result in the blockage of any OVERPACK inlet or outlet air ducts for an extended period of time (i.e, longer than the total Completion Time of LCO 3.1.2), an analysis or evaluation may be performed to demonstrate adequate heat removal is available for the duration of the event. Adequate heat removal is defined as fuel cladding temperatures remaining below the short term temperature limit. If the analysis or evaluation is not performed, or if fuel cladding temperature limits are unable to be demonstrated by analysis or evaluation to remain below the short term temperature limit for the duration of the event, provisions shall be established to provide alternate means of cooling to accomplish this objective.
11.
Users shall establish procedural and/or mechanical barriers to ensure that during LOADING OPERATIONS and UNLOADING OPERATIONS, either the fuel cladding is covered by water, or the MPC is filled with an inert gas.
12.
The entire haul route shall be evaluated to ensure that the route can support the weight of the loaded system and its conveyance.
13.
The loaded system and its conveyance shall be evaluated to ensure under the site specific Design Basis Earthquake the system does not tipover or slide off the haul route.
14.
The HI-STORM FW/HI-TRAC VW stack which occurs during MPC TRANSFER shall be evaluated to ensure under the site specific Design Basis Earthquake the system does not tipover. A probabilistic risk ATTACHMENT 4 TO HOLTEC LETTER 5018071 9 of 9