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Category:License-Not elsewhere specified
MONTHYEARML15209A5122015-07-17017 July 2015 Technical Specifications - Updating Instructions -Effective Date: 7/24/2015 ML15209A5092015-07-17017 July 2015 Technical Specifications - Updating Instructions 2015-07-17
[Table view] Category:Technical Specification
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 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 2022-12-02
[Table view] Category:Bases Change
MONTHYEARL-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 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 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-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-07-048, 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-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 2021-10-02
[Table view] Category:Technical Specifications
MONTHYEARML22357A1002023-03-31031 March 2023 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML22181A0002022-08-17017 August 2022 Issuance of Amendments Reactor Trip System Power Range Instrumentation Channels 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 ML22061A2062022-04-0101 April 2022 Issuance of Amendments TSTF-471, Rev. 1, TSTF-571-T, and Administrative Changes to Technical Specification Section 5.0 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 ML20346A0202021-03-15015 March 2021 Issuance of Amendment Nos. 235 and 223, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20356A0022021-02-0505 February 2021 Issuance of Amendment Nos. 234 and 222, Revise Technical Specifications 3.2.1 and 5.6.5 Identified in Westinghouse Nuclear Safety Advisory Letters NSAL-09-05, Revision 1, and NSAL-15-1 ML20210M0142020-09-0808 September 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules 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-19-040, 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 ML19045A4802019-04-16016 April 2019 Issuance of Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19029A0942019-01-29029 January 2019 Issuance of Amendment No. 213, One-Time Technical Specification Change to Extend Completion Time for EDGs D5 and D6 (Emergency Circumstances) ML17362A2022018-03-0505 March 2018 Issuance of Amendment Concerning Revision to the Prairie Island Nuclear Generating Plant, Units 1 and 2 Emergency Plan (CAC Nos. MF9345 and MF9346; EPID L-2017-LLA-0175) ML16133A4062016-06-16016 June 2016 Issuance of Amendment Nos. 217 and 205, Adoption of Technical Specifications Task Force TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation (CAC Nos. MF6449 and MF6450) ML15264A2092015-11-30030 November 2015 Issuance of Amendment Nos. 216 and 204 Regarding Revisions to Technical Specification 3.3.3 and Renewed Facility Operating License ML15229A1762015-08-26026 August 2015 Issuance of Amendment Nos. 215 and 203 Regarding Revision to Licensing Basis Analysis for a Waste Gas Decay Tank Rupture ML15209A5122015-07-17017 July 2015 Technical Specifications - Updating Instructions -Effective Date: 7/24/2015 ML15209A5092015-07-17017 July 2015 Technical Specifications - Updating Instructions L-PI-15-030, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-06-29029 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML15086A0462015-05-21021 May 2015 Issuance of Amendment Nos. 214 and 202 Regarding Revisions to Technical Specification 3.8.1, AC Sources - Operating ML15062A0132015-05-20020 May 2015 Issuance of Amendments 213 and 201 to Revise TS 3.5.3, ECCS - Shutdown L-PI-15-004, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown2015-02-26026 February 2015 Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown L-PI-14-034, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation2014-12-11011 December 2014 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation ML14058A2072014-02-19019 February 2014 Technical Specifications (3801 TS Markup) ML13214A0292013-08-0202 August 2013 Correction Letter for License Amendment Nos. 207 (Unit 1) and 194 (Unit 2) ML13113A4002013-07-0202 July 2013 License Amendments TSTF-510 L-PI-13-030, License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr).2013-05-23023 May 2013 License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr). ML13093A3442013-05-0909 May 2013 License Amendments for Fuel Oil System and TSTF-501 L-PI-12-028, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits2012-05-15015 May 2012 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits 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 ML1129011152011-12-0101 December 2011 Issuance of Amendments Revision of Technical Specifications 5.2.1, Onsite and Offsite Organizations and TS 5.3, Plant Staff Qualifications. L-PI-11-037, License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil2011-08-11011 August 2011 License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil ML11172A0222011-06-27027 June 2011 Technical Specifications, Unit 2, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant ML11172A0202011-06-27027 June 2011 Technical Specifications, Unit 1, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant L-PI-11-016, License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating.2011-02-0303 February 2011 License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating. L-PI-10-104, Supplement to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.102010-10-20020 October 2010 Supplement to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 ML1025715492010-09-16016 September 2010 Correction to Amendment Nos. 195 and 184 Regarding Technical Specification Changes to Control Room Habitability Requirements ML0925703672009-09-15015 September 2009 Correction to Technical Specifications (TAC Nos. MD9142 and MD9143) L-PI-08-080, License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.92008-11-0404 November 2008 License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.9 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) 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) ML0820504452008-07-18018 July 2008 Tech Spec Pages for Amendments 186 & 176 Adopting Provisions of Regulatory Guide (Rg) 1.52 Revision 3 ML0818402342008-06-27027 June 2008 Prairie, Units 1 and 2, Tech Spec Pages for Amendments 185 and 175 Regarding Incorporation of TS Task Force Travelers TSTF-479, TSTF-485 and TSTF-497 ML0812705062008-05-0101 May 2008 Submittal of Entire Re-Issue of ISFSI Technical Specifications ML0801404252008-01-28028 January 2008 Issuance of Amendments (TAC Nos. MD4209 & MD4210) - Tech Specs ML0735204002007-12-14014 December 2007 Technical Specifications in Support of Containment Sump Resolution L-PI-07-086, License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (SR)2007-11-19019 November 2007 License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (SR) ML0728403542007-10-31031 October 2007 Tech Spec Page for Amendments 181 and 171, Revise TS 3.7.2 Main Steam Valves Closure Times by Relocating the Isolation Valve Closure Times to a Licensee-Controlled Document Identified as a Bases Reference L-PI-07-061, License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load2007-08-16016 August 2007 License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load 2023-03-31
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TInK02 PASSPORT DOCUMENT To Facility Address From Address City Country Email Contact Date/Time Trans No.Total Items: NRC DOC CONTROL DESK COPY #383 PI Department ONE WHITE FLINT NORTH 11555 ROCKVILLE PIKE ROCKVILLE, MD 20852-2738 C-DOC CNTRL-PI Attention:
1717 WAKONADE DR EAST TRANSMITTAL Page: HllHlllll Ulllll I I tNllllllll WELCH UNITED STATES State: MN Postal Code: 55089 07/17/2015 10:16 Transmittal Group Id: 000283843 Title: 00002 0000031107 Item Facility Type Sub Document Number Sheet Doc Status Revision Doc Date Copy # Media Cpys 0001 PI LIC BASE ISFSI BASES ISSUED 010 383 HC 01 0002 PI LIC TECH ISFSI TECH SPECS ISSUED 009 383 HC 01 If a document was not received or is no longer required check the response below and return to sender.Documents noted above not received (identify those not received).
I no longer require distribution of these documents (identify those no longer required).
Date: Signature:
PRAIRIE ISLAND Technical Specifications UPDATING INSTRUCTIONS Effective Date: 7/24/2015 PINGP tj ISFSI REMOVE INSERT Page Revision Doc Type Page Revision Amendment/
All (6 pgs) 8 License All (6 pgs) 9 pages Record of RoR-1 5/14/14 Revisions RoR-1 7/24/2015 A, B 6/25/14 Current page list A, B 7/24/2015 Bases B RoR-l 8/27/13 Record of B RoR-I 7/24/2015 Revisions Bases A 8/27/13 Current A 7/24/2015 Pages REMOVE INSERT Page Revision Sect/Chap Page Revision 3.1.2-2 7 3.1.2 3.1.2-2 9 n/a 3.1.2-3 9 B 3.1.2-.4 8 3.1.2 3.1.2-4 10 B-3.1.2-5 7 3.1.2 3.1.2-5 10 NORTHERN STATES POWER COMPANY, A MINNESOTA CORPORATION (NSPM)DOCKET NO. 72-10 PRAIRIE ISLAND INDEPENDENT SPENT FUEL STORAGE INSTALLATION AMENDMENT TO MATERIALS LICENSE NO. SNM-2506 Amendment No. 9 License No. SNM-2506 The Nuclear Regulatory Commission (the Commission) has found that: A. The amendment application dated May 23, 2014, as supplemented by the letter on November 19, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;B. The Prairie Island Independent Spent Fuel Storage Installation will continue to operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance that (i) the activities authorized by this amendment can be conducted without endangering public health and safety, and (ii) such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to public health and safety; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by the enclosed changes to Materials License No.SNM-2506, indicated by margin notations.
- 3. This license amendment is effective as of the date of its issuance.FOR THE U.S. NUCLEAR REGULATORY COMMISSION
/RA/Michele Sampson, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards
Enclosure:
Amended License Date of Issuance:
April 10, 2015 NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION (10-2000)10 CFR 72 PAGE 1 OF 4 PAGES LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter 1, Part 72, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, and possess the power reactor spent fuel and other radioactive materials associated with spent fuel storage designated below; to use such material for the purpose(s) and at the place(s) designated below; and to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified herein.Licensee Northern States Power Company, a 3. License No. SNM-2506 Minnesota corporation (NSPM) 1jeiedment No 9 2. 414 Nicollet Mall .Minneapolis, Minnesota, 55401-1927
- 4. Expiration Date October 31, 2013 5. Docket or 72-10<'Reference No.6. Byproduct, Source, and/&,. .7. -Chemical or Physical Form .,8 Maximum Amount That Licensee Special Nuclear Material X May P6ssess at Any One Time-' Under.This License* Spent fuel assemblie's from Prairie Island Nuclear-Station Units I and 2 reactors, using natural water for cooling and enriched not greater than. 3.85 (TN-40) and not greater.4han 5.00 (TN-40HT) percent 9 U235, and associated radioactive<
materials related to receipt,.storage and transfer of the fuel.assemblies B. Irradiated fuel assembly inserts from the Prairie Island Nuclear Station Units 1 and 2 reactors.An insert may be a burnable poison rod assembly (BPRA) or a thimble plug device (TPD).A. As U 2 .cladwith zirconium.
or zirconiurn alloys~. ;4i B SS5 304 str.ucture, lnconel 718 spring, and .borated pyrex glass.A.715.29 TeU of spent fuel assermiblies B. One BPRA or TPD per spent fuel assembly.Northern States Power Company was incorporated in Minnesota as a wholly owned subsidiary of Xcel Energy Inc., effective August 18, 2000. This license, as amended, was amended to reflect the.Commission's consent per 10 CFR Part 72, Section 72.50, to the license transfer approved by order dated May 12, 2000.
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 4 PAGES (10.2000)2 License No. SNM-2506 Amendment No. 9 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10 SUPPLEMENTARY SHEET 9. Authorized Use: For use in accordance with the conditions in this license and the Technical Specifications contained in Appendix A. The basis for this license was submitted in the Safety Analysis dated August 31, 1990, and supplements dated October 29, 1990; April 2, June 5, October 9 and 31, November 15, December 11, 20, and 23, 1991; January 17, February 6, 10, and 12, March 2 and 5, April 3, 22, and 23, July 10, August 12, 13, and 14, 1992; October 2, 1995; August 31, October 29, and November 24, 1999; and February 2, March 14, October 16, 2000; and February 12, 2001; March 28, June 26, and August 29, 2008; June 26, and September 28, 2009; January 18, May 4, July 27, 2010;and July 17, December 5, 2013, and May 23, 2014 and as further supplemented and amended in accordance with 10 CFR 72.70 and 10 CFR 72.48.The material identified in 6 and 7 above is authorized for receipt, possession, storage, and transfer.10. Authorized Place of Use: The licensed material is to be received, possessed, transferred, and stored at the Prairie Island ISFSI located on the Prare Nuclear.Generatg Plant site in Goodhue County, Minnesota.
- 11. This site is described in Chabppter2 of the Technical Specifications anh&-Safety Analysis Report (TS/SAR)for the Prairie Island ISFSJ..12. The Technical Specjfications contained in Appendix A attached hereto are iicprporated into the license.NSPM shall operate the installation in accordance with the Technical Specifications in Appendix A.NSPM shall fullyimplement and maintain in effect all provisions, of the ISFSl-bphysical security, guard training and qualification, and safeguairds plans previously approved by the Commission and all amendments made authorityof 10,FR 72.56, 72.44(e), and 72.186. The plans, which contain saf~guards informatioi undei-0 73 .21, are entitild: "Prairie Island Nuclear Generating Plant Independent Spent Fue StorageInTstallation Security Plan," Revision 0, submitted by letter-datedMarc 10... , 1.992-;',ie Island Nuclearid-'nerating Plant Independent Spent Fuel Storage Installation Security Force Trainingiand Quaiifihcation Plan," Revision 0, submitted by letter dated Marchtjl0, 1992; and "Praiie Island Niclear Generating Plant Independent Spent Fuel Storage Installation.Safeguards ContirgecynyPlan,"Revision 0.,su'bmitted by letter dated March 10, 1992.14. The Technical Specificatioijs 1 for Environmental Protdction contained iinppendix A attached hereto are incorporated into the license')". .Specifications required pursuant to 10,CFR.72.44(d), limits on the release of radioactive materials for compliance with limits of 10 CFR Par20 and "as low as is reasonably achievable objective" for effluents are not applicable.
Spent fuel storage cask external surface contamination within the limits of Technical Specification 3.2.1 ensures that the offsite dose will be inconsequential.
In addition, there are no normal or off-normal releases or effluents expected from the double-sealed storage casks of the ISFSI.Specifications required pursuant to 10 CFR 72.44(d)(1), for operating procedures, for control of effluents, and for the maintenance and use of equipment in radioactive waste treatment systems, to meet the requirements of 10 CFR 72.104 are not applicable.
There are, by the design of the sealed storage casks at the ISFSI, no effluent releases.
Also, cask loading and unloading operations and Bwaste treatment will occur at the Prairie Island Nuclear Generating Plant, under the specifications of its operating licenses.
U i NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 3 OF 4 PAGES I (10-2000)
License No. SNM-2506 Amendment No. 9 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-10 SUPPLEMENTARY SHEET 15. No spent nuclear fuel shall be allowed to be loaded until such time as the following preoperational license conditions are satisfied:
A A training exercise (Dry Run) of all spent fuel storage cask loading and handling activities shall be held, which shall include, but not be limited to, those listed, and which need not be performed in the order listed: a. Moving cask in and out of spent fuel pool area b. Loading fuel assembly (using dummy assembly)c. Cask drying, sealing, and cover gas backfilling operations
- d. Moving cask to, and, on, the storage pad e. Returning the cask-io the auxiliary building f. Unloadingft4ii cask g. Decontarmiihating the cask h. All dry-run activities shall be done usihgwritten procedures
';i. The activities listed abov&~hall be' performed or modified and performed to show that each activitan be before acatual, fuel loading .: " B The Prairie Island NLuclear Generating Plant Emergency Plan shall be,.reviewed and modified, as required, tq.Jinclude theISFSI.C A training module shall be developed for the Prairie Island Nuclear 9enerating Plant Training Program, establishing an ISFSI Traihing cand 0ertification Program thalt will include the following:
- a. Cask Designi(overview)
- b. ISFSI Facility DesignrI(0verview)
- c. ISFSI Safety Analysis (overview)
- d. Fuel loading and cask handling procedures and off-normal procedures
- e. ISFSI License (overview).
D The Prairie Island Nuclear Generating Plant Radiation Protection Procedures shall be reviewed and modified, as required, to include the ISFSI.E The Prairie Island Nuclear Generating Plant Administrative Procedures shall be reviewed and modified, as required, to include the ISFSI.
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 4 OF 4 PAGES (10-2000)1:0 CFR 72 License No. SNM-2506 Amendment No. 9 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR DoktrRerncN.721 SUPPLEMENTARY SHEET F A procedure shall be developed and implemented for the documentation of the characterizations performed to select spent fuel to be stored in the casks. Such procedure shall include independent verification of fuel assembly selection by an individual other than the original individual making the selection.
G A procedure shall be developed and implemented for two independent determinations (two samples analyzed by different individuals) of the boron concentration in the water used to fill the cask cavity for fuel loading and unloading activities.
H Written procedures shall be implemented to describe actions to be taken during operation, off-normal, and emergency conditions.
- 16. The design, construction, and operation of the ISFSI shall be accomplished in accordance with the U.S.Nuclear Regulatory Commission Regulation's specifiedc inTitle. 10 of the U.S. Code of Federal Regulations.
All commitments to the applicable NRC regulator) guides and to engineering and construction codes shall be .carried out. 7 17. Fuel and cask movemeritand handling activities that are to be perform6e"'in the Prairie Island Nuclear Generating Plant Auxiiary Building will be governed by the requiremen ofthe Prairie Island Nuclear Generating Plant Facility Operating Licenses (DRP-42 and -60) and associated Technical Specifications.
- The TN-40HT confinement boundary baIse material:.and associp wsated welds shall be helium leak tested at the fabricator in acc6rdance with AN.N 14.5 to citeria. The TN-4O0bpnfinement boundary base material and,*ssociated welds shall be helium leak tested at the fabricator in accordance with ANSI N14.5 to "leaktight" criteria, if fabriatcatetdeafedateAte,.6 Amendment No: 7 approval.This license is effective as_.f the date of issuance shown below.19.2' 2.4.9, 9, 9, SFOR THE U.S. NUCLEAR REGULATORY COMMISSION.S i * 'IR-A!Michele Sampson, :ief Spent Fuel Licensing
'Branch Divis;ionE.bfSp0ent Fuel Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555 Date of Issuance:
October 19, 1993 As amended by Amendment No. 9 dated April 10, 2015 PRAIRIE ISLAND NUCLEAR GENERATING PLANT INDEPENDENT SPENT FUEL STORAGE INSTALLATION RECORD OF REVISIONS TECHNCIAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP Revision (REV) No.Date of Issue License Amendment No.Remarks ORIGINAL 1 2 3 4 5 5*10/19/93 3/17/94 2/1/96 8/7/00 8/18/00 2/12/01 5/1/08 9/22/08 8/20/10 3/10/14 License Issued 1 2 3 4 5 Correction to Amendment 5 Correction to Page 1 of License Change to p. 6-1 Change to p. 6-1 License reissue only Change to Sec. 3/4 Correction to page 1 of License, per NRC letter dated February 7, 2008 Transfer of operating authority Reformatted and Inclusion of TN-40HTdesign Revised absorber and aluminum plate minimum allowed thermal conductance Revise surveillance requirements in TS 3.1.2 6 7 8 6.7 8 9 7/24/2015 9 RoR-1 7/24/2015 PRAIRIE ISLAND NUCLEAR GENERATING PLANT INDEPENDENT SPENT FUEL STORAGE INSTALLATION TECHNCIAL SPECIFICATION CURRENT PAGE LIST LICENSE SNM-2506 PAGE AMENDMENT NRC Findings & 9 issuance (1 st page)NRC Findings &issuance (2n page)1 9 2 9 3 9 4 9 Appendix A -Record of Revision r PAGE Date RoR-1 7/24/2015 Page List PAGE Date A 7/24/2015 B 7/24/2015 Appendix A -Table of Contents[ i 8/20/10 Appendix A -Technical Specifications PAGE REVISION No.1.1-1 7 1.1-2 7 1.1-3 7 1.2-1 7 1.2-2 7 1.2-3 7 1.3-1 7.1.3-2 7 1.3-3 7 1.3-4 7 1.3-5 7 1.4-1 7 Appendix A -Technical Specifications PAGE REVISION No.1.4-2 7 1.4-3 7 1.4-4 7 1.4-5 7 1.4-6 7 2.0-1 7 2.0-2 7 2.0-3 7 3.0-1 7 3.0-2 7 3.0-3 7 3.0-4 7 3.0-5 7 3.1.1-1 7 3.1.1-2 7 3.1.2-1 7 3.1.2-2 9 3.1.2-3 9 3.1.3-1 7 3.1-3-2 7 3.1'4-1 7 3.1.4-2 7 3.1.5-1 7 3.1.5-2 7 3.1.6-1 7 3.1.6-2 7 3.2.1-1 7 3.2.1-2 7 3.2.2-1 7 3.2.2-2 7 3.3.1-1 7 3.3.1-2 7 3.4.1-1 7 3.4.1-2 7 4.0-1 7 A 7/24/2015 TECHNCLAL SPECIFICATION CURRENT PAGE LIST (CONTINUED)
PAGE REVISION No.4.0-2 7 4.0-3 7 4.0-4 7 4.0-5 8*4.0-6 7 4.0-7 7 4.0-8 7 4.0-9 7 4.0-10 7 4.0-11 7 4.0-12 7 4.0-13 8 4.0-14 7 4.0-15 7 4.0-16 7 4.0-17 7 5:0-1 7 5.0-2 7*Re-issued 6/3/14 to add sidebars B 7/24/2015 Cask Helium Backfill Pressure 3.1.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action A. 1 and B. 1 Return cask to pool and 7 days associated Completion reflood.Time not met.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 -----------------
NOTE ----------------
Not required to be met prior to the specified Frequency.
Verify that a helium environment has been Once within 34 established in the cask cavity, hours after commencing cask draining SR 3.1.2.2 -----------------
NOTE ----------------
Not required to be met prior to the specified Frequency.
Verify that the cask cavity pressure is < 14 mbar Once prior to absolute.
pressurization (SR 3.1.2.3)Prairie Island ISFSI Technical Specifications Amendment 9 3.1.2-2 Cask Helium Backfill Pressure 3.1.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.2.3 -----------------
NOTE ----------------
Not required to be met prior to the specified Frequency.
Verify that the cask cavity helium pressure is Once prior leak> 1345 mbar absolute and < 1445 mbar absolute, testing (SR 3.1.3.1)Prairie Island ISFSI Technical Specifications Amendment 9 1 3.1.2-3 PRAIRIE ISLAND NUCLEAR GENERATING PLANT INDEPENDENT SPENT FUEL STORAGE INSTALLATION RECORD OF REVISION BASES CHANGES AND LICENSE AMENDMENTS NSPM Date of License Revision Issue Amendment No. Remarks (REV) No.1 t"hrnrh" 1 iriainal Car iTnVn nRvt AqfTp('hn1(r t:, 7 8 8/20/2010 12/12/2012 7 Specifications Initial Issue of revised format and Inclusion of TN-40HT design.Clarify "helium environment" requirement in ISFSI SR 3.1.2.1.Revise B 3.1.5 paraphrase of regulatory requirements.
Revise SR for B 3.1.2.9 10 8/27/13 7/24/2015 9 Prairie Island ISFSI B RoR- I 7/24/2015
.BASES CURRENT PAGES PAGE DATE B RoR-1 7/24/2015 A 7/24/2015 i 8/20/10 PAGE REVISION No.B 2.0-1 7 B 2.0-2 7 B 3.0-1 7 B 3.0-2 7 B 3.0-3 7 B 3.0-4 7 B 3.0-5 7 B 3.0-6 7 B 3.0-7 7 B 3.0-8 7 B 3.0-9 7 B 3.0-10 7 B 3.0-11 7 B 3.1.1-1 7 B 3.1.1-2 7 B 3.1.1-3 7 B 3.1.2-1 7 B 3.1.2-2 7 B 3.1.2-3 7 B 3.1.2-4 10 B 3.1.2-5 10 PAGE REVISION No.B 3.1.3-1 7 B 3.1.3-2 7 B 3.1.3-3 7 B 3.1.3-4 7 B 3.1.4-1 7 B 3.1.4-2 7 B 3.1.4-3 7 B 3.1.5-1 9 B 3.1.5-2 7 B 3.1.5-3 7 B 3.1.5-4 7 B 3.1.5-5 7 B 3.1.6-1 7 B 3.1.6-2 7 B 3.1.6-3 7 B 3.2.1-1 7 B 3.2.1-2 7 B 3.2.1-3 7 B 3.2.2-1 7 B.3.2.2-2 7 B 3.2.2-3 7 B 3.3.1-1 7 B 3.3.1-2 7 B 3.3.1-3 7 B 3.3.1-4 7 B 3.4.1-1 7 B 3.4.1-2 7 B 3.4.1-3 7 Prairie Island ISFSI A 7/24/2015 Cask Helium Backfill Pressure B 3.1.2 BASES ACTIONS B.1 (continued)
If a helium cask environment cannot be achieved and maintained, fuel clad temperatures may increase beyond the analyzed condition.
Therefore, the cask will be required to be placed back into the spent fuel pool within 7 days and re-flooded.
This time is sufficient time to return the cask to the spent fuel pool and re-flood the cask cavity.Once placed in the spent fuel pool, the fuel is provided adequate decay heat removal to maintain the loaded fuel within limits.SURVEILLANCE SR 3.1.2.1 REQUIREMENTS This Surveillance is modified by a Note. The Note clarifies that meeting the Surveillance is not required, and thus there is not a failure to meet the LCO per SR 3.0.1 and SR 3.0.4 does not apply, prior to the specified Frequency.
While, the effective thermal conductivity of the cavity gas is not dependant upon pressure, it is dependant upon the make-up of the gases within the cask cavity. Thermal analyses have shown that maximum fuel cladding temperature limit of 752°F is not exceeded during LOADING OPERATIONS provided a 75% helium environment (based on partial pressure) is established within the cask. Thus, design basis heat removal requirements will be satisfied provided an environment of at least 75% helium has been established, and maintained in the cask cavity within the 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> vacuum drying time frame (Reference 3).SR 3.1.2.2 This Surveillance is modified by a Note. The Note clarifies that meeting the Surveillance is not required, and thus there is not a failure to meet the LCO per SR 3.0.1, and SR 3.0.4 does not apply prior to the specified Frequency.
Evacuating the cask cavity to the specified vacuum prior to pressurization (see SR 3.1.2.3) will ensure that the amount of oxidizing gases remaining in the cavity will be no greater than Prairie Island ISFSI B 3.1.2-4 Revision 10 I Cask Helium Backfill Pressure B 3.1.2 SURVEILLANCE REQUIREMENTM (continued) 0.25% (volume).
Below this concentration, degradation of stored cladding and fuel materials is not expected.SR 3.1.2.3 This Surveillance is modified by a Note. The Note clarifies that meeting the Surveillance is not required, and thus there is not a failure to meet the LCO per SR 3.0.1 and SR 3.0.4 does not apply, prior to the specified Frequency.
The long-term integrity of the stored fuel is dependent on storage in a dry, inert environment and maintenance of adequate heat transfer mechanisms.
Filling the cask cavity with helium at the initial pressure, following the evacuation in SR 3.1.2.2, will ensure that the amount of oxidizing gases remaining in the cavity will be no greater than 0.25% (volume).
At this concentration, degradation of stored cladding and fuel materials is not expected.
Also, maintaining pressure below the upper limiting value will ensure that cask cavity internal pressure will remain within limits for the life of the cask.Backfilling with helium at a specified pressure must be performed successfully on each cask prior to performance of leak testing activities and TRANSPORT and STORAGE OPERATIONS.
REFERENCES
- 1. SAR Section 8.2.2. SAR Section A8.2.3. SAR Section A3.3.Prairie Island ISFSI B 3.1.2-5 Revision 10