|
|
Line 2: |
Line 2: |
| | number = ML061110095 | | | number = ML061110095 |
| | issue date = 05/11/2006 | | | issue date = 05/11/2006 |
| | title = and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Environmental Assessment and Finding of No Significant Impact for Exemptions to 10 CFR 50.71(e)(4) | | | title = Environmental Assessment and Finding of No Significant Impact for Exemptions to 10 CFR 50.71(e)(4) |
| | author name = Lyon C F | | | author name = Lyon C |
| | author affiliation = NRC/NRR/ADRO/DORL | | | author affiliation = NRC/NRR/ADRO/DORL |
| | addressee name = Koehl D L, Palmisano T J | | | addressee name = Koehl D, Palmisano T |
| | addressee affiliation = Nuclear Management Co, LLC | | | addressee affiliation = Nuclear Management Co, LLC |
| | docket = 05000266, 05000282, 05000301, 05000306 | | | docket = 05000266, 05000282, 05000301, 05000306 |
Letter Sequence Other |
---|
|
|
MONTHYEARML0519203602005-07-0101 July 2005 R. E. Ginna Nuclear Power Plant - Transmittal of Revised Analysis Associated with the License Amendment Request Regarding Main Feedwater Isolation Valves Project stage: Request ML0606004242006-03-16016 March 2006 R. E. Ginna, License Amendment, Main Feedwater Isolation Valves Project stage: Acceptance Review ML0608202122006-03-16016 March 2006 R. E. Ginna - Tech Spec Pages for Amendment 95 Main Feedwater Isolation Valves Project stage: Other ML0611100952006-05-11011 May 2006 Environmental Assessment and Finding of No Significant Impact for Exemptions to 10 CFR 50.71(e)(4) Project stage: Other ML0611100322006-05-22022 May 2006 Exemption to 10 CFR 50.71(e)(4) Project stage: Other 2006-03-16
[Table View] |
|
---|
Category:Environmental Assessment
MONTHYEARML21062A0712021-04-21021 April 2021 Final Environmental Assessment and Finding of No Significant Impact of 2012 and 2015 Decommissioning Funding Plans for Point Beach Units 1 and 2 Independent Spent Fuel Storage Installation ML20275A3422020-10-0101 October 2020 Environmental Assessment for the Proposed Amendment of the U.S. Nuclear Regulatory Commission License Number SNM-2506 for the Prairie Island Independent Spent Fuel Storage Installation in Goodhue County, Minnesota ML20265A1042020-09-30030 September 2020 Environmental Assessment for the Proposed Amendment of the U.S. Nuclear Regulatory Commission License Number SNM-2506 for the Prairie Island Independent Spent Fuel Storage Installation in Goodhue County, Minnesota ML15320A2762015-12-0808 December 2015 Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests NRC-2015-0246, Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests2015-12-0808 December 2015 Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests ML15182A0172015-10-22022 October 2015 Draft Environmental Assessment (TAC Nos. MF2603-MF2605 and MF2637 - MF2639) ML13205A1202013-11-0707 November 2013 Draft Environmental Assessment for the Proposed Renewal of the Prairie Island Independent Spent Fuel Storage Installation ML1017202402010-09-27027 September 2010 Environmental Assessment and Finding of No Significant Impact ML1017201962010-09-27027 September 2010 Environmental Assessment and Finding of No Significant Impact NRC-2010-0324, Environmental Assessment and Finding of No Significant Impact2010-09-27027 September 2010 Environmental Assessment and Finding of No Significant Impact ML1011805392010-04-29029 April 2010 Environmental Assessment for the Proposed Amendment to Change Licensee Name ML0932900262010-02-0202 February 2010 Environmental Assessment ML0932900222010-02-0202 February 2010 Letter - Environmental Assessment and Finding of No Significant Impact (Tac Nos. ME2529 and ME2540) ML0611100952006-05-11011 May 2006 Environmental Assessment and Finding of No Significant Impact for Exemptions to 10 CFR 50.71(e)(4) ML0218300892002-07-15015 July 2002 Environmental Assessment and Finding No Significant Impact for the Proposed Conversion to the Improved TSs 2021-04-21
[Table view] Category:Finding of No Significant Impact
MONTHYEARML21055A5982021-03-25025 March 2021 Final Environmental Assessment and Finding of No Significant Impact for the Northern States Power Company'S Initial and Updated Decommissioning Funding Plans Submitted in Accordance with 10 CFR 72.30(B) and (C) ML15320A2762015-12-0808 December 2015 Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests NRC-2015-0246, Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests2015-12-0808 December 2015 Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests ML15182A0172015-10-22022 October 2015 Draft Environmental Assessment (TAC Nos. MF2603-MF2605 and MF2637 - MF2639) ML1105303992011-02-23023 February 2011 FRN: General Notice: Prairie Island Nuclear Generating Plant, Unit 1 - Correction to Notice of Consideration of Issuance of Amendments to Facility Operating Licenses Involving No Significant Hazards Consideration; Correction ML1017202402010-09-27027 September 2010 Environmental Assessment and Finding of No Significant Impact ML0932900262010-02-0202 February 2010 Environmental Assessment ML0932900222010-02-0202 February 2010 Letter - Environmental Assessment and Finding of No Significant Impact (Tac Nos. ME2529 and ME2540) ML0611100952006-05-11011 May 2006 Environmental Assessment and Finding of No Significant Impact for Exemptions to 10 CFR 50.71(e)(4) ML0218300892002-07-15015 July 2002 Environmental Assessment and Finding No Significant Impact for the Proposed Conversion to the Improved TSs 2021-03-25
[Table view] Category:Letter
MONTHYEARL-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report 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) IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 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 ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24155A1952024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information 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 ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter 2024-09-09
[Table view] |
Text
May 11, 2006Mr. Dennis L. KoehlSite Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516 andMr. Thomas J. PalmisanoSite Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, AND PRAIRIE ISLANDNUCLEAR GENERATING PLANT, UNITS 1 AND 2 - ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT FOR EXEMPTIONS TO 10 CFR 50.71(e)(4) (TAC NOS. MC8654, MC8655, MC8656, AND MC8657)
Dear Mr. Koehl and Mr. Palmisano:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impactrelated to your application for exemptions dated October 12, 2005. The proposed exemptionsfrom the requirements of 10 CFR 50.71(e)(4) would allow periodic updates of the Point Beach Nuclear Plant (PBNP), Units 1 and 2, and Prairie Island Nuclear Generating Plant (PINGP),
Units 1 and 2, updated final safety analysis reports once per fuel cycle, within 6 monthsfollowing completion of each PBNP, Unit 1, refueling outage and within 6 months of each PINGP, Unit 2, refueling outage, respectively, not to exceed 24 months from the last submittal for either site.
D. Koehl and T. Palmisano-2-The assessment is being forwarded to the Office of the Federal Register for publication.Sincerely,/RA/Carl F. Lyon, Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-266, 50-301, 50-282, and 50-306
Enclosure:
Environmental Assessmentcc w/encl: See next page D. Koehl and T. Palmisano-2-The assessment is being forwarded to the Office of the Federal Register for publication.Sincerely,/RA/Carl F. Lyon, Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-266, 50-301, 50-282, and 50-306
Enclosure:
Environmental Assessmentcc w/encl: See next page DISTRIBUTION
- PUBLICLPL3-1 R/FRidsNrrPMFLyonRidsNrrPMMChawla RidsNrrDorlLpl3-1RidsNrrLADClarkeRidsOgcRpRidsAcrsAcnwMailCenter RidsRgn3MailCanterRidsNrrDrlRebb ADAMS Accession Number: ML061110095OFFICENRR/LPL3-1/PMNRR/LPL3-1/LAREBB/BCOGCNRR/LPL3-1/BCNAMEFlyon:rsa, caDClarkeRFranovichPMouldingLRaghavanDATE5/4/065/4/065/8/065/10/065/11/06OFFICIAL RECORD COPY 7590-01-PUNITED STATES NUCLEAR REGULATORY COMMISSIONNUCLEAR MANAGEMENT COMPANY, LLCDOCKET NOS. 50-266, 50-301, 50-282, AND 50-306POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2ENVIRONMENTAL ASSESSMENT AND FINDING OFNO SIGNIFICANT IMPACTThe U.S. Nuclear Regulatory Commission (NRC) is considering issuance of exemptionsfrom Title 10 of the Code of Federal Regulations (10 CFR), Section 50.71(e)(4), for FacilityOperating License Nos. DPR-24, DPR-27, DPR-42, and DPR-60, issued to Nuclear Management Company, LLC (NMC, the licensee), for operation of the Point Beach Nuclear Plant (PBNP), Units 1 and 2, located in Manitowoc County, Wisconsin, and the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, located in Goodhue County, Minnesota. Therefore, as required by 10 CFR 51.21, the NRC is issuing this environmental assessmentand finding of no significant impact.
ENVIRONMENTAL ASSESSMENTIdentification of the Proposed Action
- The proposed actions would exempt the licensee from the requirements of 10 CFR50.71(e)(4) regarding submission of revisions to the updated Final Safety Analysis Report (FSAR). The updated FSAR at PINGP is called the Updated Safety Analysis Report (USAR).
Under the proposed exemptions, the licensee would submit updates to the updated FSARsonce per fuel cycle, within 6 months following completion of each PBNP, Unit 1, refueling outage and within 6 months of each PINGP, Unit 2, refueling outage, respectively, not to exceed 24 months from the last submittal for either site. PBNP and PINGP are two-unit sites,each site sharing a common updated FSAR.The proposed actions are in accordance with the licensee's application dated October 12, 2005.
The Need for the Proposed Action
- Section 50.71(e)(4) requires licensees to submit updates to their FSARs annually orwithin 6 months after each refueling outage provided that the interval between successiveupdates does not exceed 24 months. Since the units for each site share a common FSAR, the licensee must update the same document annually or within 6 months after a refueling outage for each unit. The underlying purpose of the rule was to relieve licensees of the burden of filingannual FSAR revisions while ensuring that such revisions are made at least every 24 months.
The NRC reduced the burden, in part, by permitting a licensee to submit its FSAR revisions 6 months after refueling outages for its facility, but it did not provide in the rule for multiple-unitfacilities sharing a common FSAR. Rather, the NRC stated, "[w]ith respect to the concern about multiple facilities sharing a common FSAR, licensees will have maximum flexibility forscheduling updates on a case-by-case basis" (57 FR 39355). Allowing the exemptions would keep the updated FSARs current within 24 months of the last revision, while reducing the burden on the licensee.
Environmental Impacts of the Proposed Action
- The NRC has completed its evaluation of the proposed actions and concludes that theyinvolve administrative activities unrelated to plant operation, and therefore there would be nosignificant environmental impacts associated with the proposed actions.The proposed actions will not significantly increase the pr obability or consequences ofaccidents. No changes are being made in the types of effluents that may be released off site. There is no significant increase in the amount of any effluent released off site. There is nosignificant increase in occupational or public radiation exposure. Therefore, there are nosignificant radiological environmental impacts associated with the proposed actions.With regard to potential non-radiological impacts, the proposed actions do not have apotential to affect any historic sites. They do not affect non-radiological plant effluents and have no other environmental impact. Therefore, there are no significant non-radiological environmental impacts associated with the proposed actions.Accordingly, the NRC concludes that there are no significant environmental impactsassociated with the proposed actions.
Environmental Impacts of the Alternatives to the Proposed Action
- As an alternative to the proposed actions, the NRC staff considered denial of theproposed actions (i.e., the "no-action" alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed actions and the alternative action are similar.
Alternative Use of Resources
- The proposed actions do not involve the use of any different resources than thosepreviously considered in the Final Environmental Statement for PBNP, dated May 1972; inNUREG-1437, Supplement 23, "Generic Environmental Impact Statement for License Renewalof Nuclear Plants [regarding PBNP]," dated August 2005; and in the Final Environmental Statement for PINGP, dated May 1973.
Agencies and Persons Consulted
- In accordance with its stated policy, the staff consulted with the Wisconsin State official,Mr. J. Kitsembel of the Public Service Commission, on April 24, 2006, and with the Minnesota State official, Ms. D. Pile of the Commerce Department, on April 26, 2006, regarding the environmental impact of the proposed actions. The State officials had no comments. FINDING OF NO SIGNIFICANT IMPACTOn the basis of the environmental assessment, the NRC concludes that the proposedactions will not have a significant effect on the quality of the human environment. Accordingly,the NRC has determined not to prepare an environmental impact statement for the proposedactions.For further details with respect to the proposed actions, see the licensee's letter datedOctober 12, 2005. Documents may be examined, and/or copied for a fee, at the NRC's PublicDocument Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will beaccessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site,http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS orwho encounter problems in accessing the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or send an e-mail to pdr@nrc.gov. Dated at Rockville, Maryland, this 11th day of May 2006.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Carl F. Lyon, Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, EsquireVice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016Mr. F. D. KuesterPresident & Chief Executive Officer WE Generation 231 West Michigan Street Milwaukee, WI 53201Regulatory Affairs ManagerPoint Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241Mr. Ken DuveneckTown Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, WI 54228ChairmanPublic Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville RoadLisle, IL 60532-4351Resident Inspector's OfficeU.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241Mr. Jeffery KitsembelElectric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854Nuclear Asset ManagerWisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201Michael B. SellmanPresident and Chief Executive Officer Nuclear Management Company, LLC 700 First Street Hudson, MI 54016Douglas E. CooperSenior Vice President - Group Operations Palisades Nuclear Plant Nuclear Management Company, LLC 27780 Blue Star Memorial Highway Covert, MI 49043Site Director of OperationsNuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241 Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:
Jonathan Rogoff, EsquireVice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016Manager, Regulatory AffairsPrairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089Manager - Environmental Protection DivisionMinnesota Attorney General's Office 445 Minnesota St., Suite 900 St. Paul, MN 55101-2127U.S. Nuclear Regulatory CommissionResident Inspector's Office 1719 Wakonade Drive East Welch, MN 55089-9642Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville RoadLisle, IL 60532-4351AdministratorGoodhue County Courthouse Box 408 Red Wing, MN 55066-0408CommissionerMinnesota Department of Commerce 85 7th Place East, Suite 500 St. Paul, MN 55101-2198Tribal CouncilPrairie Island Indian Community ATTN: Environmental Department 5636 Sturgeon Lake Road Welch, MN 55089Nuclear Asset ManagerXcel Energy, Inc.
414 Nicollet Mall, R.S. 8 Minneapolis, MN 55401Michael B. SellmanPresident and Chief Executive Officer Nuclear Management Company, LLC 700 First Street Hudson, MI 54016Craig G. AndersonSenior Vice President, Group Operations Nuclear Management Company, LLC 700 First Street Hudson, WI 54016