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MONTHYEARML0627202212006-10-13013 October 2006 Staff'S Review of the Revision to Technical Specification Surveillance Requirements 3.3.1.2 & 3.3.1.3, Reactor Trip System Instrumentation (RTS) Project stage: Approval L-PI-08-062, Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates2008-08-0808 August 2008 Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates Project stage: Request ML0831109182008-11-18018 November 2008 Request for Additional Information Related to Review of Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate (Tac Nos. MD9492, MD9493, MD9494, and MD9495) Project stage: RAI L-PI-09-008, Supplement to Irradiated Fuel Management Plan and Preliminary/ Decommissioning Cost Estimates for Prairie Island Nuclear Generations Plant (PINGP) (TAC MD9492, MD9493, MD9494, and MD9495)2009-01-19019 January 2009 Supplement to Irradiated Fuel Management Plan and Preliminary/ Decommissioning Cost Estimates for Prairie Island Nuclear Generations Plant (PINGP) (TAC MD9492, MD9493, MD9494, and MD9495) Project stage: Supplement ML0904400352009-02-24024 February 2009 Draft Request for Additional Information Regarding the Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates Project stage: Draft RAI L-PI-09-031, Supplement to Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates2009-03-12012 March 2009 Supplement to Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates Project stage: Supplement ML0909100822009-03-31031 March 2009 ISFSI, and Monticello, Decommissioning Funding Status Reports Project stage: Request ML0912005412009-06-0101 June 2009 Safety Evaluation Spent Fuel Management Program and Preliminary Decommissioning Cost Estimate (Tac Nos. MD9492, MD9493, MD9494 and MD9495) Project stage: Approval L-PI-09-117, Prairie Lsland, Unit 2, Lrradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates2009-10-28028 October 2009 Prairie Lsland, Unit 2, Lrradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates Project stage: Other 2009-10-28
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Category:Letter type:L
MONTHYEARL-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report2019-09-19019 September 2019 Submittal of Revised Pressure and Temperature Limits Report L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)2019-08-27027 August 2019 Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP) 2024-06-05
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L-PI-09-117 OCT 9 8 2W 10 CFR 50.54 10 CFR 50.75 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie lsland Nuclear Generating Plant, Unit 2 Docket 50-306 License No. DPR-60 lrradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates for Prairie Island Nuclear Generating Plant (PINGP)
References:
- 1. Nuclear Management Company, LLC (NMC) letter to US Nuclear Regulatory Commission (NRC), "Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates for Prairie lsland Nuclear Generating Plant (PINGP)", dated August 8, 2008, Accession Number ML082260425.
- 2. Northern States Power Company - Minnesota (NSPM) letter to the NRC, "Supplement to lrradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates for Prairie lsland Nuclear Generating Plant (PINGP) (TAC Nos. MD9492, MD9493, MD9494, and MD9495)", dated January 19, 2009, Accession Number ML090210156.
- 3. NRC letter to NSPM, "Prairie lsland Nuclear Generating Plant, Units 1 and 2 -Safety Evaluation RE: Spent Fuel Management Program and Preliminary Decommissioning Cost Estimate (TAC Nos. MD9492, MD9493, MD9494, and MD9495)", dated June I, 2009, Accession Number ML091200541.
- 4. NSPM letter to the NRC, "Supplement to lrradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates for Prairie lsland Nuclear Generating Plant (PINGP) (TAC Nos. MD9492, MD9493, MD9494, and MD9495)", dated March 12,2009, Accession Number ML090760499.
1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1 121
Document Control Desk Page 2 References (continued)
- 5. Northern States Power Company - Minnesota (NSPM) letter to the NRC, "Decommissioning Funding Status Reports", dated March 31, 2009, Accession Number ML090910082.
Pursuant to 10 CFR 50.54(bb), a licensee shall "submit written notification to the Commission for its review and preliminary approval of the program by which the licensee intends to manage and provide funding for the management of all irradiated fuel at the reactor following permanent cessation of operation of the reactor until title to the irradiated fuel and possession of the fuel is transferred to the Secretary of Energy for its ultimate disposal in a repository." Additionally, 10 CFR 50.75(f)(3), "Reporting and Recordkeeping for Decommissioning Planning" states, "each power reactor licensee shall at or about 5 years prior to the projected end of operations submit a preliminary decommissioning cost estimate which includes an up-to-date assessment of the major factors that could affect the cost to decommission." In Reference 1, as supplemented by References 2 and 4, NMC* submitted the Irradiated Fuel Management Plan and the PlNGP Preliminary Decommissioning Cost Estimate for PlNGP Units 1 and 2.
The NRC safety evaluation (Reference 3) stated, "Although the licensee provided cost information for both Unit 1 and Unit 2, the expiration of the operating license for PlNGP Unit 2 is not until October 29, 2014. Therefore, due to possible significant changes in cost and the decommissioning trust fund (DTF) balance by the time Unit 2 reaches 5 years before expiration of its license, the NRC staffs assessment is based on and covers only Unit 1." NSPM fulfillment of the requirements of 10 CFR 50.54(bb) and 10 CFR 50.75(f)(3) for PlNGP Unit 2 is provided by Attachment 1 to Reference 1, entitled, "Decommissioning Cost Analysis for Prairie Island Nuclear Generating Plant, August 2008, by TLG Services, Inc", as supplemented by Reference 2, Reference 4, and this letter and enclosure. This cost analysis is the most recently completed and remains a valid estimate of future decommissioning costs for Unit 2.
Enclosure 1 reviews the Trust Fund Balance which includes a biennial comparison and an update of the Trust Fund Balance in Reference 5, current as of July 31, 2009 for both Unit 1 and Unit 2. In addition Enclosure 1 reviews changes to the Annual Contribution. Finally, Enclosure 1 provides a review of changes to the real rate of return and includes a sufficiency of funds analysis for Unit 2 to update Reference 2, current as of July 31, 2009.
If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1121.
- On September 22, 2008, NMC transferred its operating authority to Northern States Power Company, a Minnesota Corporation (NSPM), doing business as Xcel Energy. By letter dated September 3, 2008, NSPM assumed responsibility for actions and commitments previously submitted by NMC.
Document Control Desk Page 3 Summaw of Commitments This letter contains no new commitments and no revisions to existing commitments.
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Mark A. Schimmel Site Vice President Prairie Island Nuclear Generating Plant, Units 1 and 2 Northern States Power Company - Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC
Enclosure 1
- 1. Nuclear Regulatory Commission (NRC) Minimum and Funding Status The NRC minimum decommissioning financial assurance requirement for the Prairie Island Nuclear Generating Plant (PINGP) as reported in Reference 1 of this Enclosure and set forth in 10 CFR 50.75 (c) is approximately $345.7 million for Unit 1 and $345.7 million for Unit 2. As of July 31, 2009, the PINGP decommissioning trust funds balances were $333.7 million for Unit 1 and $357.8 for Unit 2. The trust fund monies will be used for radiological decommissioning and irradiated fuel management.
However, inclusion of irradiated fuel costs in this submittal is not intended to acknowledge that these costs will ultimately be borne by Northern States Power Company, a Minnesota corporation (NSPM, doing business as Xcel Energy, since some (or all) are expected to be the responsibility of the U.S. Department of Energy as a result of the breach of the Standard Contract of Disposal of Spent Nuclear Fuel andlor High-Level Radioactive Waste.
The following table, Table 1, includes comparisons of the radiological decommissioning, spent fuel management, and site restoration segmentation of the trust fund balances for PINGP Unit 1 and Unit 2 calculated for the beginning of 2008 and 2009. The current funding status ending in July of 2009 shows a significant improvement of the funds that exceeds the NRC minimum for Unit 2.
Table 1: Trust Fund Balances PlNGP Unit 1 2008 2009 July 2009 Radiological Decommissioning 370,245,731 305,379,191 333,676,530 Spent Fuel Management 24,146,461 19,916,034 21,761,513 Site Restoration 8,048,820 6,638,678 7,253,837 Total 402,441,012 331,933,903 362,691,880 PlNGP Unit 2 2008 2009 July 2009 Radiological Decommissioning 387,142,205 327,830,502 357,804,725 Spent Fuel Management 30,111,059 25,497,927 27,829,257 Site Restoration 12,904,741 10,927,684 11,926,824 Total 430,158,005 364,256,113 397,560,806 Page 1 of 4 NSPM
- 2. Annual Contributions In 2009, based on a ruling by the Minnesota Public Utilities Commission, these funds are not being supplemented with any annual Company contributions for radiological decommissioning. Adjustments to the annual contribution require approval of multiple state public utilities commissions and will be pursued to recover any projected shortfall.
The following annual contributions table, Table 2, shows the approximate accrual segmentation for radiological decommissioning, spent fuel management, and site restoration for PlNGP Unit 1 and Unit 2.
Table 2: Annual Contributions PlNGP Unit 1 Radiological Decommissioning Spent Fuel Management Site Restoration Total PlNGP Unit 2 Radiological Decommissioning Spent Fuel Management Site Restoration Total
- 3. Sufficiency of Funds Analysis Although the Minnesota Public Utilities Commission discontinued the annual supplement, the Commission approved a decommissioning plan that included a 2.89 percent cost escalation rate and a 6.30 percent earnings rate on external funds. The table below, Table 3, demonstrates that the approved 3.41 percent rate of return applied to the current balance reconcile when contributions and earnings are added and the annual costs are subtracted. The projected balance at the end of decommissioning is more than adequate to cover the costs of radiological decommissioning. The 3.41 percent rate of return begins with the 2010 projection.
Table 3: Funds Analysis PlNGP Unit 2 Beginning Balance Before Assumed Balance Payment Annuity Interest Interest Ending Balance 2009 357,804,725 357,804,725 5,083,809 362,888,534 201 0 362,888,534 362,888,534 12,374,499 375,263,033 201 1 375,263,033 375,263,033 12,796,469 388,059,502 2012 388,059,502 10,415,560 398,475,062 13,588,000 412,063,062 Page 2 of 4 NSPM PlNGP Unit 2 Beginning Balance Before Assumed Balance Payment Annuity Interest lnterest Ending Balance 2013 412,063,062 10,415,560 422,478,622 14,406,521 436,885,143 2014 436,885,143 8,332,448 435,832,591 14,861,891 450,694,482 2015 450,694,482 392,676,482 13,390,268 406,066,750 2016 406,066,750 306,023,750 10,435,410 316,459,160 2017 316,459,160 223,603,160 7,624,868 231,228,028 2018 231,228,028 162,145,028 5,529,145 167,674,173 2019 167,674,173 124,136,173 4,233,044 128,369,217 2020 128,369,217 118,648,217 4,045,904 122,694,121 2021 122,694,121 113,000,121 3,853,304 116,853,425 2022 116,853,425 107,159,425 3,654,136 110,813,562 101,119,562 3,448,177 104,567,739 94,846,739 3,234,274 98,081,013 88,387,013 3,013,997 91,401,010 81,707,010 2,786,209 84,493,219 74,799,219 2,550,653 77,349,872 67,628,872 2,306,145 69,935,017 53,653,017 1,829,568 55,482,585 14,100,585 480,830 14,581,414 5,082,414 173,310 5,255,725 5,219,725 177,993 5,397,717 5,376,717 183,346 5,560,063 5,560,063 189,598 5,749,662 5,749,662 196,063 5,945,725 5,945,725 202,749 6,148,474 6,148,474 209,663 6,358,137 6,358,137 216,812 6,574,950 6,574,950 224,206 6,799,156 6,799,156 231,851 7,031,007 7,031,007 239,757 7,270,764 7,270,764 247,933 7,518,697 7,518,697 256,388 7,775,085 7,775,085 265,130 8,040,215 8,040,215 274,171 8,314,386 8,314,386 283,521 8,597,907 8,597,907 293,189 8,891,096 8,891,096 303,186 9,194,282 9,194,282 313,525 9,507,807 Page 3 of 4 NSPM PlNGP Unit 2 Beginning Balance Before Assumed Balance Payment Annuity Interest Interest Ending Balance 2050 9,507,807 9,507,807 324,216 9,832,023 2051 9,832,023 9,832,023 335,272 10,167,295 2052 10,167,295 10,167,295 346,705 10,514,000 2053 10,514,000 10,514,000 Total 537,984,000
- 4. References
- 1. Northern States Power Company - Minnesota (NSPM) letter to the NRC, "Decommissioning Funding Status Reports", dated March 31, 2009, Accession Number ML090910082.
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