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MONTHYEARL-HU-08-005, Application for Order and Conforming License Amendments to Transfer Operating Authority Under Facility Operating Licenses2008-04-16016 April 2008 Application for Order and Conforming License Amendments to Transfer Operating Authority Under Facility Operating Licenses Project stage: Request L-HU-08-016, Corrected Operating License Pages Regarding Transfer of Operating Authority2008-08-0606 August 2008 Corrected Operating License Pages Regarding Transfer of Operating Authority Project stage: Request ML0822407612008-09-15015 September 2008 Order Approving Transfer of Licensed Operating Authority and Conforming Amendment Project stage: Other ML0825211822008-09-15015 September 2008 Order Approving Transfer of Operating Authority from NMC to NSPM Project stage: Other ML0822407502008-09-15015 September 2008 Safety Evaluation Associated with the Order and Conforming Amendments Authorizing Transfer of Operating Authority Project stage: Approval L-HU-08-021, ISFSI and Monticello, Confirmation of Transition Readiness as of September 22, 20082008-09-19019 September 2008 ISFSI and Monticello, Confirmation of Transition Readiness as of September 22, 2008 Project stage: Other ML0826815912008-09-22022 September 2008 (PINGP-1 and 2), Technical Specifications ISFSI, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245) Project stage: Approval ML0826812912008-09-22022 September 2008 Revised Operating Licenses & Technical Specifications, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245, MD9622 and MD9623) Project stage: Approval ML0826007722008-09-22022 September 2008 Operating Licenses Revised to Reflect Transfer of Operating Authority to NSPM Project stage: Other ML0825906762008-09-22022 September 2008 Letter to Transmit Conforming Amendments Number 188, 177, and 06 Re. License Transfer Project stage: Other ML0825906382008-09-22022 September 2008 Conforming Amendments to Facility Operating Licenses and Material License for the ISFSI to Reflect Transfer of Operating Authority to NSPM Project stage: Other ML0828105432008-10-17017 October 2008 Correction of Error in Amendment No. 6 of Material License SNM-2506 for the Independent Spent Fuel Storage Facility Regarding the Transfer of Operating Authority (Tac Nos. L24245, MD9622, and MD9623) Project stage: Other 2008-08-06
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Category:Letter
MONTHYEARML24298A0552024-10-30030 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 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 ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 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 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 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance 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 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 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) 2024-09-27
[Table view] Category:Technical Specification
MONTHYEARL-PI-24-010, Revisions 255 Through 264 for Technical Specification Bases2024-04-30030 April 2024 Revisions 255 Through 264 for Technical Specification Bases 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) ML22243A1822022-10-28028 October 2022 Correction Letter for Amendments 239 and 227 to Renewed Facility Operating Licenses - Enclosure - TS Page 5.5-5 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-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-21-007, 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 ML20118D3182020-04-27027 April 2020 Enclosure 4 - Technical Specifications (TS) Bases Control Program 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 ML18155A4312018-05-18018 May 2018 Changes to Technical Specification Bases ML18106A0412018-04-0505 April 2018 ISFSI - Technical Specifications Updating Instructions, Amendment 10 L-PI-16-045, Revisions to Technical Specifications Bases2016-05-20020 May 2016 Revisions to Technical Specifications Bases ML15327A2282015-11-17017 November 2015 License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes L-PI-15-087, Enclosures 7 & 8: Modeling of Fuel Assemblies Containing Both Ifba and Gadolinia Absorber Rods with Westinghouse Core Design Code Systems and Affidavit2015-10-31031 October 2015 Enclosures 7 & 8: Modeling of Fuel Assemblies Containing Both Ifba and Gadolinia Absorber Rods with Westinghouse Core Design Code Systems and Affidavit ML15209A5122015-07-17017 July 2015 Technical Specifications - Updating Instructions -Effective Date: 7/24/2015 ML14058A2512014-02-19019 February 2014 3801 Markup Bases L-PI-12-013, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology2012-02-24024 February 2012 Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology ML1021001982010-07-16016 July 2010 Licensing Bases for Turbine Building Internal Flooding L-PI-10-001, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.3, Diesel Fuel Oil, Storage Requirements2010-01-27027 January 2010 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.3, Diesel Fuel Oil, Storage Requirements L-PI-09-125, License Amendment Request and Exemption Request to Support the Use of Optimized Zirlotm Fuel Rod Cladding2009-11-24024 November 2009 License Amendment Request and Exemption Request to Support the Use of Optimized Zirlotm Fuel Rod Cladding L-PI-09-076, License Amendment Request (LAR) to Revise Technical Specifications in Accordance with TSTF-448, Revision 3 - Control Room Habitability2009-06-24024 June 2009 License Amendment Request (LAR) to Revise Technical Specifications in Accordance with TSTF-448, Revision 3 - Control Room Habitability ML0910506192009-04-15015 April 2009 License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0827402262008-11-0606 November 2008 License Amendment, Revise Containment Spray Nozzle Surveillance Requirements ML0828105432008-10-17017 October 2008 Correction of Error in Amendment No. 6 of Material License SNM-2506 for the Independent Spent Fuel Storage Facility Regarding the Transfer of Operating Authority (Tac Nos. L24245, MD9622, and MD9623) ML0823409202008-08-15015 August 2008 Tech Spec Page for Amendment 187 Emergency Diesel Generator Monthly Load Test Surveillance Requirement L-PI-08-047, License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+ Fuel2008-06-26026 June 2008 License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+ Fuel L-PI-07-060, Supplement to License Amendment Request (LAR) for Miscellaneous Technical Specification (TS) Improvements (TAC Nos. MD 2822 and MD 2823)2007-07-16016 July 2007 Supplement to License Amendment Request (LAR) for Miscellaneous Technical Specification (TS) Improvements (TAC Nos. MD 2822 and MD 2823) L-PI-07-048, License Amendment Request (LAR) Incorporating Technical Specification Task Force (TSTF) Industry Travelers TSTF-479, TSTF-485, and TSTF-4972007-07-0303 July 2007 License Amendment Request (LAR) Incorporating Technical Specification Task Force (TSTF) Industry Travelers TSTF-479, TSTF-485, and TSTF-497 L-PI-07-028, Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item Improvement..2007-05-10010 May 2007 Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item Improvement.. ML0708101312007-03-20020 March 2007 Technical Specification Pages Re Steam Generator Tube Integrity L-PI-06-058, License Amendment Request (LAR) to Revise Technical Specifications (TS) in Support of Containment Sump Resolution2006-12-14014 December 2006 License Amendment Request (LAR) to Revise Technical Specifications (TS) in Support of Containment Sump Resolution L-PI-04-112, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process2004-10-15015 October 2004 Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process ML0412102562004-04-28028 April 2004 Technical Specifications for Amd 162 and 153, Respectively ML0403707272004-02-0303 February 2004 Technical Specification for Amendment Nos. 161 and 152, Prairie Island Nuclear Generating Plant, Units 1 and 2 ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process L-PI-03-026, License Amendment Request (LAR) Dated March 19, 2003 Clarification of Licensed Operator Qualifications2003-03-19019 March 2003 License Amendment Request (LAR) Dated March 19, 2003 Clarification of Licensed Operator Qualifications 2024-04-30
[Table view] Category:Amendment
MONTHYEARL-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) ML22243A1822022-10-28028 October 2022 Correction Letter for Amendments 239 and 227 to Renewed Facility Operating Licenses - Enclosure - TS Page 5.5-5 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-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-21-007, 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 ML18106A0412018-04-0505 April 2018 ISFSI - Technical Specifications Updating Instructions, Amendment 10 L-PI-10-001, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.3, Diesel Fuel Oil, Storage Requirements2010-01-27027 January 2010 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.3, Diesel Fuel Oil, Storage Requirements L-PI-09-125, License Amendment Request and Exemption Request to Support the Use of Optimized Zirlotm Fuel Rod Cladding2009-11-24024 November 2009 License Amendment Request and Exemption Request to Support the Use of Optimized Zirlotm Fuel Rod Cladding L-PI-09-076, License Amendment Request (LAR) to Revise Technical Specifications in Accordance with TSTF-448, Revision 3 - Control Room Habitability2009-06-24024 June 2009 License Amendment Request (LAR) to Revise Technical Specifications in Accordance with TSTF-448, Revision 3 - Control Room Habitability ML0910506192009-04-15015 April 2009 License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0827402262008-11-0606 November 2008 License Amendment, Revise Containment Spray Nozzle Surveillance Requirements ML0828105432008-10-17017 October 2008 Correction of Error in Amendment No. 6 of Material License SNM-2506 for the Independent Spent Fuel Storage Facility Regarding the Transfer of Operating Authority (Tac Nos. L24245, MD9622, and MD9623) ML0823409202008-08-15015 August 2008 Tech Spec Page for Amendment 187 Emergency Diesel Generator Monthly Load Test Surveillance Requirement L-PI-07-060, Supplement to License Amendment Request (LAR) for Miscellaneous Technical Specification (TS) Improvements (TAC Nos. MD 2822 and MD 2823)2007-07-16016 July 2007 Supplement to License Amendment Request (LAR) for Miscellaneous Technical Specification (TS) Improvements (TAC Nos. MD 2822 and MD 2823) L-PI-07-028, Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item Improvement..2007-05-10010 May 2007 Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item Improvement.. ML0708101312007-03-20020 March 2007 Technical Specification Pages Re Steam Generator Tube Integrity L-PI-04-112, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process2004-10-15015 October 2004 Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process ML0412102562004-04-28028 April 2004 Technical Specifications for Amd 162 and 153, Respectively ML0403707272004-02-0303 February 2004 Technical Specification for Amendment Nos. 161 and 152, Prairie Island Nuclear Generating Plant, Units 1 and 2 ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process L-PI-03-026, License Amendment Request (LAR) Dated March 19, 2003 Clarification of Licensed Operator Qualifications2003-03-19019 March 2003 License Amendment Request (LAR) Dated March 19, 2003 Clarification of Licensed Operator Qualifications 2022-12-02
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 17, 2008 Mr. Michael D. Wadley Site Vice President Prairie Island Nuclear Generating Plant Northern States Power-Minnesota 1717 Wakonade Drive East Welch, MN 55089 SUB..IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 CORRECTION OF ERROR IN AMENDMENT NO.6 OF MATERIAL LICENSE SNM-2506 FOR THE INDEPENDENT SPENT FUEL STORAGE FACILITY REGARDING THE TRANSFER OF OPERATING AUTHORITY (TAC NOS.
L24245, MD9622, AND MD9623)
Dear Mr. Wadley:
By letter dated April 16, 2008, as supplemented by letter dated August 6, 2008, you applied for the subject amendment. On September 22,2008, the U. S. Nuclear Regulatory Commission staff issued amendment NO.6 to material license SNM-2506, for the independent spent fuel storage installation (ISFSI).
Subsequently, Mr. J. Arias of your staff identified an administrative error on page 6-1 of the technical specifications (TSs) for the Prairie Island Nuclear Generating Plant (PINGP) ISFSJ.
The amendment number in the page footer is incorrectly identified as "Amendment 4 dtd.
September 22,2008." The correct amendment number is "Amendment 6." Enclosed please find a corrected TS page 6-1 of the PINGP ISFSJ.
The correction does not change the approval conveyed by Amendment No.6, or the conclusion reached by the associated safety evaluation. We apologize for any inconvenience this error may have caused you.
Sincerely,
~:a~anager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282, 50-306, and 72-10
Enclosure:
As stated cc w/encls: Distribution via ListServ
ENCLOSURE CORRECTED TECHNICAL SPECIFICATION PAGE 6-1 FOR AMENDMENT NO.6 INDEPENDENT SPENT FUEL STORAGE INSTALLATION MATERIAL LICENSE NO. SNM-2506 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UI\JITS 1 AND 2
6.0 ADMINISTRATIVE CONTROLS 6.1 GENERAL The Prairie Island ISFSI is located on the Prairie Island Nuclear Generating Plant site and will be managed and operated by Northern States Power Company, a Minnesota corporation (NSPM) staff. The administrative controls shall be in accordance with the requirements of the Prairie Island Nuclear Generating Plant Facility Operating Licenses (DPR-42 and -60) and associated Technical Specifications, as appropriate.
6.2 ENVIRONMENTAL MONITORING PROGRAM The licensee shall include the Prairie Island ISFSI in the environmental monitoring program for the Prairie Island Nuclear Generating Plant. An environmental monitoring program is required pursuant to 10 CFR 72.44(d)(2). The licensee shall include the ISFSI in the environmental monitoring report for the Prairie Island Nuclear Generating Plant, and a copy shall be sent to the Director, Office of Nuclear Material Safety and Safeguards.
6.3 ANNUAL ENVIRONMENTAL REPORT An annual report, as reqUired by 10 CFR 72.44(d)(3), shall be submitted to the NRC Region III, Office, with a copy to the Director, Office of Nuclear Material Safety and Safeguards, within 60 days after January 1 of each year. This report should specify the quantity of each of the principal radionuclides released to the environment in liquid and in gaseous effluents during the previous year of operation and such other information as may be required by the Commission to estimate maximum potential radiation dose commitment to the public resulting from effluent release.
6-1 Amendment 6 dtd. September 22,2008
October 17, 2008 Mr. Michael D. Wadley Site Vice President Prairie Island Nuclear Generating Plant Northern States Power-Minnesota 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - CORRECTION OF ERROR IN AMENDMENT NO.6 OF MATERIAL LICENSE SNM-2506 FOR THE INDEPENDENT SPENT FUEL STORAGE FACILITY REGARDING THE TRANSFER OF OPERATING AUTHORITY (TAC NOS. L24245, MD9622, AND MD9623)
Dear Mr. Wadley:
By letter dated April 16, 2008, as supplemented by letter dated August 6, 2008 you applied for the subject amendment. On September 22,2008, the U. S. Nuclear Regulatory Commission staff issued amendment NO.6 to material license SNM-2506, for the independent spent fuel storage installation (ISFSI).
Subsequently, Mr. J. Arias of your staff identified an administrative error on page 6-1 of the technical specifications (TSs) for the Prairie Island Nuclear Generating Plant (PINGP) ISFSI. The amendment number in the page footer is incorrectly identified as "Amendment 4 dtd. September 22,2008." The correct amendment number is "Amendment 6." Enclosed please find a corrected TS page 6-1 of the PINGP ISFSI.
The correction does not change the approval conveyed by Amendment No.6, or the conclusion reached by the associated safety evaluation. We apologize for any inconvenience this error may have caused you.
Sincerely, lRAI 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, 50-306, and 72-10
Enclosure:
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