NLS2012134, Independent Spent Fuel Storage Installation Decommissioning Funding Plan
| ML12354A216 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/17/2012 |
| From: | Vanderkamp D Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, NRC/NMSS/SFST |
| References | |
| NLS2012134 | |
| Download: ML12354A216 (16) | |
Text
H Nebraska Public Power District Always there-when you need us NLS2012134 December 17, 2012 ATTN: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Subject:
Independent Spent Fuel Storage Installation Decommissioning Funding Plan Cooper Nuclear Station, Docket No. 50-298, DPR-46 Cooper Nuclear Station ISFSI, Docket No. 72-66
Dear Sir or Madam:
The purpose of this correspondence is to provide Nebraska Public Power District's Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Funding Plan for Cooper Nuclear Station (CNS) in accordance with 10 CFR 72.30, Financial Assurance and Recordkeeping for Decommissioning. The enclosure to this letter provides a detailed cost estimate for decommissioning the ISFSI at CNS in an amount reflecting the work is performed by an independent contractor, an adequate contingency factor, and release of the facility and the dry storage system for unrestricted use, as specified in 10 CFR Part 20.1402.
Additionally, the enclosure provides identification of the key assumptions contained in the cost estimate and also the volume of onsite subsurface material containing residual radioactivity, if any, that will require remediation to meet the criteria for license termination.
The enclosure also presents information related to demonstrating the adequacy of decommissioning funding for ultimate ISFSI decommissioning.
Finally, attached is the certification required pursuant to 10 CFR 72.3 0(b)(6) that financial assurance for decommissioning has been provided in the amount of the cost estimate for decommissioning.
This letter contains no new regulatory commitments.
COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68327-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 w
.nppd.com
NLS2012134 Page 2 of 2 Should you have any questions concerning this matter, please contact me at (402) 825-2904.
Sincerely, pavid W. Van Der Kta Licensing Manager
/jo
Attachment:
Certification of Financial Assurance
Enclosure:
10 CFR ISFSI Decommissioning Cost Estimate cc:
Regional Administrator w/ attachment and enclosure USNRC - Region IV Cooper Project Manager w/ attachment and enclosure USNRC - NRR Project Directorate IV-1 Senior Resident Inspector w/ attachment and enclosure USNRC - CNS NPG Distribution w/o attachment and enclosure CNS Records w/ attachment and enclosure
NLS2012134 Attachment Page 1 of 2 Attachment Certification of Financial Assurance
CERTIFICATION OF FINANCIAL ASSURANCE NRC License: DPR-46 Nebraska Public Power District Cooper Nuclear Station P.O. Box 98 72676 648 A Brownville NE 68321 Issued to: U.S. Nuclear Regulatory Commission
Subject:
Independent Spent Fuel Storage Installation Certification:
I hereby certify that Nebraska Public Power District is the licensee Independent Spent Fuel Storage Installation (Cooper ISFSI), and that provide this Certification of Financial Assurance with respect to the ISFSI.
for the Cooper Nuclear Station the undersigned is authorized to decommissioning of the Cooper During the operation of this ISFSI spent nuclear fuel will be stored in storage casks licensed under 10 CFR Part 72.
Pursuant to contracts with the Department of Energy the spent fuel and casks will ultimately be removed from the ISFSI location, at which time the ISFSI will be decommissioned in accordance with NRC regulations.
I further certify that financial assurance in an amount sufficient to fund ISFSI decommissioning at the time of such decommissioning exists, as described in the Enclosure to the letter to which this Certification is attached. That amount is premised on a site-specific decommissioning cost estimate provided in that Enclosure.
Cooper Nuclear Station ISFSI
$ 3,702,000 (inclusive of contingency)
Corporate Seal Name "-Td L.
Title:
Vice President & Chief Financial Officer Date
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NLS2012134 Enclosure Page 1 of 12 Enclosure Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Funding Plan Cooper Nuclear Station, Docket No. 50-298, DPR-46 Cooper Nuclear Station ISFSI, Docket No. 72-66 10 CFR 72.30 ISFSI Decommissioning Cost Estimate
10 CFR 72.30 ISFSI Decommissioning Funding Plan Background and Introduction The Nuclear Regulatory Commission (NRC) issued its final rule on Decommissioning Planning on June 17, 201 1,1 with the rule becoming effective on December 17, 2012.
Subpart 72.30, "Financial assurance and recordkeeping for decommissioning," requires that each holder of, or applicant for, a license under this part must submit for NRC review and approval a decommissioning funding plan that contains information on how reasonable assurance will be provided that funds will be available to decommission the Independent Spent Fuel Storage Installation (ISFSI).
In accordance with the rule, this enclosure provides a detailed cost estimate for decommissioning the ISFSI at Cooper Nuclear Station (CNS) in an amount reflecting:
- 1. The work is performed by an independent contractor;
- 2. An adequate contingency factor; and
- 3. Release of the facility and dry storage systems for unrestricted use, as specified in 10 CFR Part 20.1402 This enclosure also provides:
- 1. Identification of the key assumptions contained in the cost estimate; and
- 2. The volume of onsite subsurface material containing residual radioactivity, if any, that will require remediation to meet the criteria for license termination.
Finally, in Section 7 of this enclosure, Nebraska Public Power District (NPPD) provides a description of the method of assuring funds for decommissioning the ISFSI, including means for adjusting the cost estimate and associated funding levels over the life of the plant.
The material in Sections 1 - 6, and Tables 1 and 2, herein, were prepared based on evaluations conducted by TLG Services, Inc. Section 7, containing the financial assurance information, was prepared by NPPD.
- 2.
Spent Fuel Management Strategy The operating license for CNS is currently set to expire on January 18, 2034. With the anticipation of an extended power uprate, approximately 6,114 spent fuel assemblies are currently projected to be generated over the life of the plant. Because of the breach by the U.S. Code of Federal Regulations, Title 10, Parts 20, 30, 40, 50, 70 and 72 "Decommissioning Planning,"
Nuclear Regulatory Commission, Federal Register Volume 76, Number 117 (p 35512 et seq.), June 17, 2011 1
Department of Energy (DOE) of its contract to remove fuel from the site, an ISFSI has been constructed and spent fuel transferred to dry storage modules located on the ISFSI, to support continued plant operations. Based upon the current projection of the DOE's ability to remove spent fuel from the site, this estimate assumes that the current ISFSI will be expanded after shutdown to store the used fuel that remained in the spent fuel pool in order to support plant decommissioning. The ISFSI is operated under a Part 50 General License (in accordance with 10 CFR 72, Subpart K[2I).
Because of the DOE's breach, it is envisioned that the spent fuel pool will contain a significant number of spent fuel assemblies at the time of expiration of the current operating license in 2034, assuming the plant operates to that date, including assemblies off-loaded from the reactor vessel. To facilitate immediate dismantling operations or safe-storage operations, the fuel that cannot be transferred directly to the DOE from the pool is assumed to be packaged in dry storage modules for interim storage at the ISFSI.
Once the spent fuel pool is emptied, the spent fuel pool systems and fuel pool areas can be either decontaminated and dismantled or prepared for long-term storage.
Completion of the ISFSI decommissioning process is dependent upon the DOE's ability to remove spent fuel from the site. DOE's repository program assumes that spent fuel allocations will be accepted for disposal from the nation's commercial nuclear plants, with limited exceptions, in the order (the "queue") in which it was discharged from the reactor. [3] NPPD's current spent fuel management plan for the CNS spent fuel is based in general upon: 1) a 2020 start date for DOE initiating transfer of commercial spent fuel to a federal facility (not necessarily a final repository), and 2) expectations for spent fuel receipt by the DOE for the CNS fuel. The DOE's generator allocation/receipt schedules are based upon the oldest fuel receiving the highest priority. Assuming a maximum rate of transfer of 3,000 metric tons of uranium/year,[4] the spent fuel is projected to be fully removed from the CNS site in 2063. This also assumes that the 1,054 spent fuel assemblies NPPD has in storage at General Electric's wet-pool ISFSI in Morris, Illinois are shipped first, starting in 2022.
NPPD believes that one or more monitored retrievable storage facilities could be put into place within a reasonable time. In a report delivered to Congress in 2009,E51 DOE presented a six-year timeline for siting and constructing an interim storage facility (pending legislation eliminating the linkage in the Nuclear Waste Policy Act of 1982, as U.S. Code of Federal Regulations, Title 10, Part 72, Subpart K, "General License for Storage of Spent Fuel at Power Reactor Sites."
U.S. Code of Federal Regulations, Title 10, Part 961.11, Article IV - Responsibilities of the Parties, B. DOE Responsibilities, 5.(a)... DOE shall issue an annual acceptance priority ranking for receipt of SNF and/or HLW at the DOE repository. This priority ranking shall be based on the age of SNF and/or HLW as calculated from the date of discharge of such materials from the civilian nuclear power reactor. The oldest fuel or waste will have the highest priority for acceptance, except as... "
4 "Acceptance Priority Ranking & Annual Capacity Report," DOE/RW-0567, July 2004 5
"Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites," DOE/RW-0596, U.S. Department of Energy Office of Civilian Radioactive Waste Management, December 2008 2
amended, between interim storage and the opening of the Yucca Mountain repository).
The six-year time span would allow fuel receipt by the 2020 date.
NPPD's position is that the DOE has a contractual obligation to accept the spent fuel earlier than the projections set out above consistent with its contract commitments. No assumption made in this study should be interpreted to be inconsistent with this claim.
- 3.
ISFSI Decommissioning Strategy At the conclusion of the spent fuel transfer process the ISFSI will be promptly decommissioned (similar to the power reactor DECON alternative).
For purposes of providing an estimate for a funding plan, financial assurance is expected to be provided on the basis of a prompt ISFSI decommissioning scenario. In this estimate the ISFSI decommissioning is considered an independent project, regardless of the decommissioning alternative identified for the nuclear power plant.
- 4.
ISFSI Description The design and capacity of the CNS ISFSI is based upon a NUHOMS-61BT dry storage system. The NUHOMS system is comprised of a dry storage canister (DSC) with 61 spent fuel assembly capacity and a horizontal storage module (HSM), Model 202. The DSCs are assumed to be transferred directly to the DOE and not returned to the station. Some of the remaining HSMs are assumed to have residual radioactivity due to some minor level of neutron-induced activation as a result of the long-term storage of the spent fuel. The cost to dispose of residual radioactivity, and verify that the remaining facility and surrounding environs meet the NRC's radiological limits established for unrestricted use, form the basis of the ISFSI decommissioning estimate.
NPPD's current spent fuel management plan for the CNS spent fuel would result in 55 HSMs being placed on an expanded storage pad at the site. This represents 54% of the total spent fuel projected to be generated during the currently licensed operating period.
This projected configuration is based upon the 2020 DOE spent fuel program start with a 2027 DOE start date for the fuel at the CNS site, a 3,000 MTU / year pickup rate, and a 52 module capacity for the ISFSI pad built to support plant operations. This scenario would allow the spent fuel storage pool to be emptied within approximately five and one-half years following the permanent cessation of operations.
Table 1 provides the significant quantities and physical dimensions used as the basis in developing the ISFSI decommissioning estimate.
- 5.
Key Assumptions / Estimating Approach The decommissioning estimate is based on the configuration of the ISFSI expected after all spent fuel and GTCC material has been removed from the site. The configuration of the ISFSI is based on the station operating until the end of its current license (2034) and 3
the DOE's spent fuel acceptance assumptions, as previously described. For purposes of this analysis the current pad (265 feet by 42 feet) will be expanded to accommodate the 55 modules.
The dry storage vendor, Transnuclear, Inc., does not expect the horizontal storage modules to have any interior or exterior radioactive surface contamination.E6] It is expected that this assumption would be confirmed as a result of good radiological practice of surveying potentially impacted areas after each spent fuel transfer campaign.
Any neutron activation of the steel and concrete is expected to be extremely small. 7]
This assumption is adopted for this analysis.
The decommissioning estimate is based on the premise that the DSC support structure within some of the HSMs will contain low levels of neutron-induced residual radioactivity that would necessitate remediation at the time of decommissioning. As an allowance, nine of the 55 HSMs are assumed to be affected, i.e., contain residual radioactivity. The allowance quantity is based upon the number of DSCs required for the final core off-load (i.e., 548 offloaded assemblies/unit, 61 assemblies per DSC) which results in a total of nine HSMs that contain residual radioactivity. It is assumed that these are the final HSMs offloaded; consequently they have the least time for radioactive decay of the neutron activation products.
It is not expected that there will be any residual contamination left on the concrete ISFSI pad. It is expected that this assumption would be confirmed as a result of good radiological practice of surveying potentially impacted areas after each spent fuel transfer campaign. Therefore, it is assumed for this analysis that the ISFSI pad will not be contaminated. As such, only verification surveys are included for the pad in the decommissioning estimate.
There is no known subsurface material in the proximity of the ISFSI containing residual radioactivity that will require remediation to meet the criteria for license termination.
Decommissioning is assumed to be performed by an independent contractor. As such, essentially all labor, equipment, and material costs are based on national averages, i.e.,
costs from national publications such as R.S. Means' Building Construction Cost Data (adjusted for regional variations), and laboratory service costs are based on vendor price lists. Those craft labor positions that are expected to be provided locally, are consistent with fully burdened contractor labor rates used in the most recently developed CNS decommissioning cost estimate, escalated to 2012 dollars. NPPD, as licensee, will oversee the site activities; the estimate includes NPPD's labor and overhead costs.
6 Updated Final Safety Analysis Report for the Standardized NIUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Transnuclear Inc., NUH-003, Rev. 12, at page 3.5-1 dated February 1, 2012,
[ML12037A013]
7 Ibid. at page 9.6-1 4
Low-level radioactive waste packaging, transport and disposal costs are based on rates consistent with the most recently developed decommissioning cost estimate (year 2008 dollars), escalated to 2012 dollars.
Contingency has been added at an overall rate of 25%. This is consistent with the contingency evaluation criteria referenced by the NRC in NUREG-1757.J81 Costs are reported in 2012 dollars and based upon a decommissioning analysis prepared for CNS in 2008. Activity costs originally reported in 2008 dollars have been escalated to 2012 dollars using the Consumer Price Index, Services.J9' The estimate is limited to costs necessary to terminate the ISFSI's NRC license and meet the 10 CFR §20.1402 criteria for unrestricted use. Disposition of released material and structures is outside the scope of the estimate.
- 6.
Cost Estimate The estimated cost to decommission the ISFSI and release the facility for unrestricted use is provided in Table 2. The cost has been organized into three phases, including:
" An initial planning phase - empty HSMs are characterized and the specifications and work procedures for the decontamination (DSC support structure removal) developed.
" The remediation phase - residual radioactivity is removed, packaged in certified waste containers, transported to the low-level waste site, and disposed of at low-level waste.
" The final phase - license termination surveys, independent surveys are completed, and an application for license termination submitted.
In addition to the direct costs associated with a contractor providing the decommissioning services, the estimate also contains costs for the NRC (and NRC contractor to perform the verification survey), NPPD's oversight staff, site security (industrial), and other site operating costs.
For estimating purposes it should be conservatively assumed that all expenditures will be incurred following plant decommissioning and all spent fuel removal. Based on best available information, NPPD expects that the DOE will complete the pickup of spent fuel at CNS by 2064.
8 "Consolidated Decommissioning Guidance, Financial Assurance, Recordkeeping, and Timeliness," U.S.
Nuclear Regulatory Commission's Office of Nuclear Material Safety and Safeguards, NUREG-1757, Volume 3, Revision 1, February 2012 Bureau of Labor Statistics, Consumer Price Index - All Urban Consumers, Services, Series ID: CUUR0000SAS 5
- 7.
Financial Assurance ISFSI operations at CNS are in response to the DOE's failure to remove spent nuclear fuel from the site in a timely manner. The costs for management of the spent fuel are costs for which the DOE is responsible under federal law and the Standard Contract. It is therefore expected that, once the ISFSI is no longer needed, the cost to decommission the ISFSI would be a DOE-reimbursable expense. Until such time that the costs can be recovered from the DOE, NPPD will rely upon the money available in its decommissioning trust fund to terminate the ISFSI license and release the facility for unrestricted use.
Using the decommissioning trust fund is reasonable based on the following:
Although the decommissioning trust fund is for radiological decommissioning (i.e.,
post-shutdown) costs only, the ISFSI decommissioning is a radiological cost. Also, to the extent that the trust fund balance exceeds costs required for Part 50 radiological decommissioning, these funds would be available to address costs incurred by NPPD, including ISFSI decommissioning costs.
The projected minimum certification amount, calculated pursuant to 10 CFR 50.75(c) required to demonstrate reasonable assurance of funds for decommissioning CNS is
$574,906,000 (2010 dollars), based upon the NRC's latest figures for calculating that value. [10]
" Based upon CNS's decommissioning trust fund balance as of December 31, 2010 as reported in Nebraska Public Power District's March 29, 2011 Decommissioning Funding Seventh Biennial Report and considering a 2.5% real rate of return[l 11 on the fund between December 31, 2010 and the start of CNS decommissioning the trust fund would contain a $829,041,114 surplus (refer to Table 3) beyond the NRC minimum funding formula provided in 10CFR50.75(c). This surplus is more than sufficient to complete the future decommissioning of the ISFSI (estimated cost provided in Table 2).
NPPD will continue to assess the decommissioning fund status in accordance with the NRC requirements (e.g. 10CFR 50.75(b)(2), 10CFR 50.75(f)(1), 10CFR72.30(c)) and projected surplus, to account for the continued assurance of adequate funds for ISFSI decommissioning. Any adjustments to the cost estimate and funding levels will be made in connection with the triennial filing required pursuant to 1 OCFR72.30(c). To the extent any specific regulatory actions are necessary at the time of withdrawal from the trust fund of the amount necessary for ISFSI decommissioning, NPPD will pursue such actions.
10 "Report on Waste Burial Charges," U.S. Nuclear Regulatory Commission's Office of Nuclear Reactor Regulation, NUREG-1307, Rev. 14, November 2010 11 The assumed annual real rate of return is 2.50 percent. The District's Board of Directors (as the licensee's rate setting authority) has approved this assumption for the decommissioning funding plan for Cooper Nuclear Station through the adoption of a Board Resolution, dated June 13, 2008, as part of its official business.
6
In addition to the projected excess in decommissioning funds that would be available for the diminimus level of funding required for ISFSI decommissioning, NPPD could additionally rely on its available cash and investments that total over $1 billion (including $346.5 million in liquid assets). This information was provided to the NRC with NPPD's guarantee of deferred premiums, pursuant to 10 CFR 140.21, submitted by letter dated July 3, 2012, "Licensee Guarantees of Payment of Deferred Premiums, Cooper Nuclear Station, Docket No. 50.298, DPR-46.
NPPD provides this information because it further demonstrates the availability of funding to pay for ISFSI decommissioning. NPPD is not here submitting this information in the form of a guarantee under 10 CFR 72.30(e)(2), but may do so in the future.
7
Table 1 Significant Quantities and Physical Dimensions ISFSI Pad Item Length (ft)
Width (ft)
Residual Radioactivity Current ISFSI Pad 265 42 No ISFSI Horizontal Storage Module - Model 202 Item Value Notes (all dimensions are nominal)
Outside Height (inches) 222 Without vent cover Outside Length (inches) 248 Without shield walls Outside Width (inches) 116 Without shield walls Quantity (total) 55 Spent Fuel Equivalent to the number of HSMs used to store last Quantity (with residual radioactivity) 9 complete core offload)
DSC Internal Steel with Residual Radioactivity (pounds) 44,000 Low-Level Radioactive Waste (cubic feet) 1,011 Low-Level Radioactive Waste (packaged density) 46 Average weight density 8
Table 2 ISFSI Decommissioning Costs and Waste Volumes Waste Volume (thousands, 2012 dollars)
Person-Hours NRC / NRC Removal Packaging Transport Disposal Other Total (ft3)
Contractor Licensee Contractor Decommissioning Contractor Planning (characterization, specs and procedures) 178 178 16,646 Remediation (activated metal removal) 187 5
7 220 127 545 1,011 License Termination (radiological surveys) 1,456 1,456 15,734 Subtotal 187 5
7 220 1,761 2,180 1,011 32,381 Supporting Costs NRC and NRC Contractor Fees and Costs 243 243 776 Insurance 94 94 Security (industrial) 168 168 4,996 NPPD Oversight Staff 277 277 3,790 Subtotal 782 782 8,786 776 Total (w/o contingency) 187 5
7 220 2,543 2,962 1,011 41,167 776 Total (w/25% contingency) 234 7
8 275 3,179 3,702 9
Table 3 Financial Assurance' 10 CFR 50.75(b) & (c) Decommissioning Estimate (2010 Dollars): $574,906,0002 Decommissioning Fund3 Total as of 12/31/2010: $484,130,065 Schedule of Future Annual Fund Earnings and Decommissioning Cost Escalation: 4 Funding Requirement NRC Beginning Funding Year-Beginning Fund Ending Minimum Year Balance Contribution 2034 $
Interest Balance Escalated 2011
$484,130,065
$26,627,154
$510,757,219
$574,906,000 2012
$510,757,219
$28,091,647
$538,848,866
$592,153,180 2013
$538,848,866
$29,636,688
$568,485,553
$609,917,775 2014
$568,485,553
$31,266,705
$599,752,259
$628,215,309 2015
$599,752,259
$32,986,374
$632,738,633
$647,061,768 2016
$632,738,633
$34,800,625
$667,539,258
$666,473,621 2017
$667,539,258
$36,714,659
$704,253,917
$686,467,830 2018
$704,253,917
$38,733,965
$742,987,882
$707,061,864 2019
$742,987,882
$40,864,334
$783,852,216
$728,273,720 2020
$783,852,216
$43,111,872
$826,964,088
$750,121,932 2021
$872,447,112
$772,625,590 1 The following table is excerpted from Nebraska Public Power District's March 29, 2011 seventh Biennial Report on Financial Assurance for Cooper Nuclear Station in accordance with 10 CFR 50.75(f)(1) Reporting and Recordkeeping for Decommissioning Planning and is provided for illustrative purposes. Please also reference related NPPD correspondence to the NRC (NLS2008098 dated December 15, 2008) that provided various decommissioning planning scenarios for Cooper Nuclear Station that considered both delayed DECON and SAFSTOR alternatives. Either of those scenarios provides deferred dates for the decommissioning of Cooper Nuclear Station. With those later dates, NPPD would expect to accrue additional earnings consistent with the assumed real rate of return for the decommissioning trust fund.
2 This estimate is based upon NRC decommissioning minimum certification escalation requirements in 10 CFR 50.75(c)(1) and (2) and guidance per NUREG 1307 for a BWR the size of Cooper Nuclear Station. The calculation utilizes the vendor waste burial factor in Revision 14 of NUREG 1307 and Labor and Energy escalation factors derived from December 2010 regional data of the U.S. Department of Labor Bureau of Labor Statistics.
3 This is the total amount (Market Value) in the external sinking fund (as described in 10 CFR 50.75) to cover the costs of NRC-defined decommissioning.
The current (November 30, 2012) Market Value of the external sinking fund is
$544,060,055.
4 These figures will be recalculated on an annual basis in accordance with 10 CFR 50.75 (b) and (c). The above amounts reflect the anticipated annual contributions (none presently anticipated), and annual fund earnings that demonstrate full funding of the decommissioning trust by the end of the operating license (license expiration January 18, 2034), and taking into account a pro rata credit during the dismantlement period (recognizing both cash expenditures and earnings) over the first seven years after shutdown assuming immediate decommissioning (see 10 CFR 50.75(e)(1)(ii)).
10
Year Beginning Balance
$826,964,088 Funding Contribution Funding Requirement Year-Beginning 2034 $
Fund Interest
$45,483,025 Ending Balance NRC Minimum Escalated 2022 2023 2024 2025 2026 2027 2028 2029 2030 2031 2032 2033 2034 2035 2036 2037 2038 2039 2040
$872,447,112
$920,431,704
$971,055,447
$1,024,463,497
$1,080,808,989
$1,140,253,484
$1,202,967,425
$1,269,130,634
$1,338,932,819
$1,412,574,124
$1,490,265,700
$1,572,230,314
$1,658,702,981
$1,573797,056
$1,478,937,265
$1,373,417,627
$1,256,488,575
$1,127,354,412
$985,170,642
$47,984,591
$50,623,744
$53,408,050
$56,345,492
$59,444,494
$62,713,942
$66,163,208
$69,802,185
$73,641,305
$77,691,577
$81,964,614
$86,472,667
$82,046,292
$77,100,995
$71,599,971
$65,504,144
$58,772,031
$51,359,607
$43,220,153
$920,431,704
$971,055,447
$1,024,463,497
$1,080,808,989
$1,140,253,484
$1,202,967,425
$1,269,130,634
$1,338,932,819
$1,412,574,124
$1,490,265,700
$1,572,230,314
$1,658,702,981
$1,573,797,056
$1,478,937,265
$1,373,417,627
$1,256,488,575
$1,127,354,412
$985,170,642
$829,041,114
$795,804,358
$819,678,488
$844,268,843
$869,596,908
$895,684,816
$922,555,360
$950,232,021
$978,738,982
$1,008,101,151
$1,038,344,185
$1,069,494,511
$1,101,579,346
$166,952,217
$171,960,786
$177,119,609
$182,433,195
$187,906,194
$193,543,377
$199,349,681 11