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Category:Environmental Assessment
MONTHYEARML20275A3422020-10-0101 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 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 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 2020-09-30
[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) 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
MONTHYEARIR 05000282/20240032024-11-13013 November 2024 Integrated Inspection Report 05000282/2024003, 05000306/2024003 & 07200010/2024001 ML24310A1682024-11-0505 November 2024 Core Operating Limits Report (COLR) for Cycle 34, Revision 0 ML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 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 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 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 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 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) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations 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) 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 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 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 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 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 April 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report 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) ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 To Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables ML24262A1512024-03-15015 March 2024 L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam ML24010A0582024-03-0505 March 2024 Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 2024-09-27
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 February 2, 2010 Mr. Mark A. Schimmel Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota 1717 Wakonade Drive East Welch, Minnesota 55089-9642 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT (TAC NOS. ME2529 AND ME2540)
Dear Mr. Schimmel:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for exemption dated November 5,2009, as supplemented on November 30 and December 17, 2009. The proposed exemption from specific requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 73, for the Prairie Island Nuclear Generating Plant, Units 1 and 2, would extend the deadline from March 31, 2010, until June 30, 2011, for the implementation of certain measures in 10 CFR Part 73.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and Environmental cc w/encl:
Distribution via
[7590-01-P] NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY -MINNESOTA DOCKET NOS. 50-282 AND 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNITS 1 AND 2 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an Exemption, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 73.5, "Specific exemptions," from the implementation date for certain new requirements of 10 CFR Part 73, "Physical protection of plants and materials," for Facility Operating License Nos. 42 and DPR-60, issued to Northern States Power Company -Minnesota (NSPM, the licensee), for operation of the Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP), located in Goodhue County, Minnesota.
In accordance with 10 CFR 51.21, the NRC prepared an environmental assessment documenting its finding. The NRC concluded that the proposed actions will have no significant environmental impact. ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action: The proposed action would exempt PINGP from the required implementation date of March 31, 2010, for several new requirements of 10 CFR Part 73.
Specifically, PINGP would be granted an exemption from being in full compliance with certain new requirements contained in 10 CFR 73.55 by the March 31,2010, deadline. NSPM has proposed an alternate full compliance implementation date of June 30, 2011, approximately 15 months beyond the date required by 10 CFR Part 73. The proposed action, an extension of the schedule for completion
-2of certain actions required by the revised 10 CFR Part 73, does not involve any physical changes to the reactor, fuel, plant structures, support structures, water, or land at the PINGP site. The proposed action is in accordance with the licensee's application dated November 5,2009, as supplemented by letters dated November 30,2009 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML 100050096) and December 17, 2009. The Need for the Proposed Action: The proposed action is needed to provide the licensee with additional time to perform the required upgrades to the PINGP security system considering the time typically required to design and construct modifications of this scope, and the impediments to construction such as the planned refueling outages at both Units 1 and 2 and weather-related issues. Environmental Impacts of the Proposed Action: The NRC has completed its environmental assessment of the proposed exemption. The staff has concluded that the proposed action to extend the implementation deadline would not significantly affect plant safety and would not have a significant adverse effect on the probability of an accident occurring.
The proposed action would not result in an increased radiological hazard beyond those previously analyzed in the environmental assessment and finding of no significant impact made by the Commission in promulgating its revisions to 10 CFR Part 73, as discussed in a Federal Register notice dated March 27, 2009 (74 FR 13967). There will be no change to radioactive effluents that affect radiation exposures to plant workers and members of the public. Therefore, no changes or different types of radiological impacts are expected as a result of the proposed exemption.
-3The proposed action does not result in changes to land use or water use, or result in changes to the quality or quantity of non-radiological effluents. No changes to the National Pollution Discharge Elimination System permit are needed. No effects on the aquatic or terrestrial habitat in the vicinity of the plant, or to threatened, endangered, or protected species under the Endangered Species Act, or impacts to essential fish habitat covered by the Magnuson-Steven's Act are expected. There are no impacts to the air or ambient air quality. There are no impacts to historical and cultural resources. There would be no impact to socioeconomic resources.
Therefore, no changes to or different types of non-radiological environmental impacts are expected as a result of the proposed exemption. Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action. In addition, in promulgating its revisions to 10 CFR Part 73, the Commission prepared an environmental assessment and published a finding of no significant impact [Part 73, Power Reactor Security Requirements, 74 FR 13926, 13967 (March 27, 2009)]. The licensee currently maintains a security system acceptable to the NRC and will continue to provide acceptable physical protection of PINGP.
Therefore, the extension of the implementation date of the new requirements of 10 CFR Part 73 to June 30, 2011, would not have any significant environmental impacts. The NRC staff's safety evaluation will be provided in the exemption that will be issued as part of the letter to the licensee approving the exemption to the regulation, if granted.
Environmental Impacts of the Alternatives to the Proposed Action: As an alternative to the proposed action, the NRC staff considered denial of the proposed action (Le., the "no-action" alternative). Denial of the exemption request would result in no change in current environmental impacts. If the proposed action was denied, the licensee
-4would have to comply with the March 31,2010, implementation deadline. The environmental impacts of the proposed exemption and the "no action" alternative are similar.
Alternative Use of Resources: The action does not involve the use of any different resources than those considered in the Final Environmental Statement for the Prairie Island Nuclear Generating Plant, Units 1 and 2, dated May 1973. Agencies and Persons Consulted:
In accordance with its stated policy, on January 8, 2010, the NRC staff consulted with the Minnesota State official, Mr.
Stephen Rakow of the Minnesota Department of Commerce, Office of Energy Security, regarding the environmental impact of the proposed action. The State official had no comments. FINDING OF NO SIGNIFICANT IMPACT On the basis of the environmental assessment, the NRC concludes that the proposed action 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 proposed action. For further details with respect to the proposed action, see the licensee's letter dated November 5,2009, as supplemented by letters dated November 30, and December 17,2009. The November 5 and December 17, 2009, letters and portions of the November 30, 2009, submittal contain security-related information and, accordingly, are not available to the public. Other parts of the November 30, 2009, letter, may be examined, and/or copied for a fee, at the NRC's Public Document Room (PDR), located at One White Flint North, Public File Area 0-1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. Publicly available records will be accessible electronically from the Agencywide Documents Access and
-5 Management System (ADAMS) Public Electronic Reading Room on the Internet at the NRC Website: http://www.nrc.gov/reading-rm/adams.html.
Persons who do not have access to ADAMS or who 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.resource@nrc.gov. Dated at Rockville, Maryland, this 2nd day of February 2010. FOR THE NUCLEAR REGULATORY COMMISSION Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Letter (NRR-106) ML093290022 EA FRN (NRR-044) ML093290026 OFFICE DORLlLPL3-1/PM DORLlLPL3-1/LA NRRlDLR/RERB/BC OGC DORLlLPL3-lIBC DORLlLP3-1/PM NAME TWengert THarris Almboden CBoote RPascarelli TWengert DATE 01/12/10 01/12/10 01/19/10 01/26/10 02/01/10 02/02/10