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MONTHYEAR2CAN030701, Arkansas One, Unit 2, License Amendment Request, Proposed Technical Change Regarding Containment Spray Nozzle Test Requirements2007-03-15015 March 2007 Arkansas One, Unit 2, License Amendment Request, Proposed Technical Change Regarding Containment Spray Nozzle Test Requirements Project stage: Request 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) Project stage: Request ML0810102312008-04-0909 April 2008 E-mail LAR to Revise Containment Spray Nozzle Srs. MD7362/63 Project stage: Other L-PI-08-038, Supplement to License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (R)2008-05-0707 May 2008 Supplement to License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (R) Project stage: Supplement ML0827402262008-11-0606 November 2008 License Amendment, Revise Containment Spray Nozzle Surveillance Requirements Project stage: Other 2008-11-06
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MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle ML21320A2262021-11-15015 November 2021 License Amendment Request: Standard Emergency Plan and Consolidated Emergency Operations Facility for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant 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-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 ML20058F9432020-02-27027 February 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - License Amendment Request: Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules Revision 4 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-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency L-PI-19-006, Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements2019-01-29029 January 2019 Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements L-PI-18-064, License Amendment Request (LAR) to Revise Current Licensing Basis, Supplement 12018-12-0404 December 2018 License Amendment Request (LAR) to Revise Current Licensing Basis, Supplement 1 L-PI-18-014, License Amendment Request (LAR) to Revise Current Licensing Basis2018-10-0202 October 2018 License Amendment Request (LAR) to Revise Current Licensing Basis L-PI-18-031, License Amendment Request to Adopt TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco.2018-06-26026 June 2018 License Amendment Request to Adopt TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco. L-PI-18-005, License Amendment Request to Revise License Condition Associated with Implementation of NFPA 8052018-05-18018 May 2018 License Amendment Request to Revise License Condition Associated with Implementation of NFPA 805 ML17090A2012017-03-31031 March 2017 License Amendment Request to Revise Technical Specification for Plant/Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML17094A5762017-03-29029 March 2017 License Amendment Request to Revise Emergency Action Level (EAL) Scheme ML17055C3592017-02-23023 February 2017 License Amendment Request: Revision to Emergency Plan Staff Augmentation Response Times L-PI-16-060, License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action2016-08-31031 August 2016 License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action L-PI-16-020, License Amendment Request Regarding One-Time Extension for Technical Specification Surveillance Requirement 3.8.4.3. DC Sources- Operating.2016-04-0707 April 2016 License Amendment Request Regarding One-Time Extension for Technical Specification Surveillance Requirement 3.8.4.3. DC Sources- Operating. L-PI-16-003, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2016-01-25025 January 2016 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process 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 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 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 L-PI-14-072, License Amendment Request (LAR) to Revise the Licensing Basis Analysis for a Waste Gas Decay Tank Rupture2014-08-21021 August 2014 License Amendment Request (LAR) to Revise the Licensing Basis Analysis for a Waste Gas Decay Tank Rupture L-PI-14-037, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources- Operating, Emergency Diesel Generator Voltage and Frequency Limits2014-06-0909 June 2014 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources- Operating, Emergency Diesel Generator Voltage and Frequency Limits ML14126A7272014-05-0505 May 2014 Supplement to License Amendment Request (LAR) for Cyber Security Plan Implementation Date Extension L-PI-13-102, License Amendment Request (LAR) to Revise Staff Augmentation Times in the Prairie Island Nuclear Generating Plant (PINGP) Emergency Plan2013-12-20020 December 2013 License Amendment Request (LAR) to Revise Staff Augmentation Times in the Prairie Island Nuclear Generating Plant (PINGP) Emergency Plan ML13333B6742013-11-27027 November 2013 License Amendment Request (LAR) for Northern States Power Company, Minnesota (NSPM) Cyber Security Plan Implementation Date Extension L-PI-13-076, Supplement to License Amendment Request for Exception to Technical Specification 5.5.14 Testing Requirements Associated with Steam Generator Replacement2013-07-25025 July 2013 Supplement to License Amendment Request for Exception to Technical Specification 5.5.14 Testing Requirements Associated with Steam Generator Replacement L-PI-13-071, Supplement to License Amendment Request (LAR) to Revise Emergency Plan (EP) Emergency Action Levels (Eals): RA 1.2 and Fuel Clad Barrier Loss Criteria2013-07-23023 July 2013 Supplement to License Amendment Request (LAR) to Revise Emergency Plan (EP) Emergency Action Levels (Eals): RA 1.2 and Fuel Clad Barrier Loss Criteria 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). L-PI-13-017, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System) - Shutdown2013-02-20020 February 2013 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System) - Shutdown L-PI-12-110, License Amendment Request (LAR) to Revise Emergency Plan (EP) Emergency Action Levels (Eals): RA1.2 and Fuel Clad Barrier Loss Criteria2012-12-13013 December 2012 License Amendment Request (LAR) to Revise Emergency Plan (EP) Emergency Action Levels (Eals): RA1.2 and Fuel Clad Barrier Loss Criteria ML12278A4052012-09-28028 September 2012 Prairie Island, Units 1 and 2, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors L-PI-12-054, Application to Revise Technical Specifications Associated with Steam Generator Replacement and Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection2012-07-25025 July 2012 Application to Revise Technical Specifications Associated with Steam Generator Replacement and Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection L-PI-12-055, License Amendment Request for Exception to Technical Specification 5.5.14 Testing Requirements Associated with Steam Generator Replacement2012-07-25025 July 2012 License Amendment Request for Exception to Technical Specification 5.5.14 Testing Requirements Associated with Steam Generator Replacement 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-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 L-PI-11-038, Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology2011-04-0606 April 2011 Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology L-PI-11-008, License Amendment Request (LAR) to Revise Technical Specification (TS) 5.2.1, Onsite and Offsite Organizations and TS 5.3, Plant Staff Qualifications.2011-02-0404 February 2011 License Amendment Request (LAR) to Revise Technical Specification (TS) 5.2.1, Onsite and Offsite Organizations and TS 5.3, Plant Staff Qualifications. 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. 2023-09-28
[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: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] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 6, 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 - ISSUANCE OF AIVIENDMENTS RE: LICENSE AMENDMENT TO REVISE CONTAINMENT SPRAY NOZZLE SURVEILLANCE REQUIREMENTS (TAC NOS. MD7362 AND MD7363)
Dear Mr. Wadley:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 190 to Facility Operating License No. DPR-42 and Amendment No. 179 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated November 19,2007, as supplemented by letter dated May 7,2008.
The amendments replace the current fixed Frequency for testing the containment spray nozzles in Surveillance Requirement 3.6.5.8 with a maintenance or event based Frequency.
A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
~"--'~1~
Thomas J\,)engert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosures:
- 1. Amendment No. 190 to DPR-42
- 2. Amendment No. 179 to DPR-60
- 3. Safety Evaluation cc w/encls: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NORTHERN STATES POWER COMPANY' DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 190 License No. DPR-42
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Nuclear Management Company, LLC'"
(the licensee), dated November 19, 2007, as supplemented by letter dated May 7, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that 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 the health and safety of the public; 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 changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:
- On September 22,2008, Nuclear Management Company, LLC (NMC), transferred its operating authority to Northern States Power Company, a Minnesota Corporation (NSPM). By letter dated September 3, 2008, NSPM stated that it would assume responsibility for actions and commitments submitted by NMC.
-2 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 190, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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,**.*~..i ,'\" -.1.....J Lois M. James, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: November 6, 2008
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NORTHERN STATES POWER COMPANY' DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 179 License No. DPR-60
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Nuclear Management Company, LLC*
(the licensee), dated November 19, 2007, as supplemented by letter dated May 7, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that 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 the health and safety of the public; 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 changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
- On September 22, 2008, Nuclear Management Company, LLC (NMC), transferred its operating authority to Northern States Power Company, a Minnesota Corporation (NSPM). By letter dated September 3, 2008, NSPM stated that it would assume responsibility for actions and commitments submitted by NMC.
-2 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 179 ,are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION cJc: ~ "?f'~"C Lois M. James, Chief d
Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: November 6, 2008
ATTACHMENT TO LICENSE AMENDMENT NOS. 190 AND 179 FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 DOCKET NOS. 50-282 AND 50-306 Replace the following pages of the Facility Operating License No. DPR-42 and DPR-60 with the attached revised pages. The changed areas are identified by a marginal line.
REMOVE INSERT DPR-42, License Page 3 DPR-42, License Page 3 DPR-60, License Page 3 DPR-60, License Page 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3.6.5-4 3.6.5-4
-3 (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NSPM to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purpose of volume reduction and decontamination.
C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 190 ,are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 1, submitted by letters dated October 18, 2006, and January 10, 2007.
Unit 1 Amendment No. 190
-3 (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purpose of volume reduction and decontamination.
C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.
(2) Technical Specifications The Technical Speci"fications contained in Appendix A, as revised through (
Amendment No. 179 , are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled:
"Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 1, submitted by letters dated October 18, 2006, and January 10, 2007.
Unit 2 Amendment No. 179
Containment Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.5.7 Verify each containment cooling train starts 24 months automatically on an actual or simulated actuation signal.
SR 3.6.5.8 Verify each spray nozzle is unobstructed. Following maintenance which could result in nozzle blockage Prairie Island Unit 1 - Amendment No. m 190 Units I and 2 3.6.5-4 Unit 2 - Amendment No. +49 179
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 190 TO FACILITY OPERATING LICENSE NO. DPR-42 AND AMENDMENT NO. 179 TO FACILITY OPERATION LICENSE NO. DPR-60 NORTHERN STATES POWER COMPANy1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306
1.0 INTRODUCTION
By application dated November 19, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML073240086), as supplemented by letter dated May 7,2008 (ADAMS Accession No. ML081290287), Nuclear Management Company, LLC 1 (the licensee),
requested changes to the Technical Specifications (TSs) for the Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP). The proposed changes would revise the testing frequency of the containment spray (CS) nozzles as specified in TS Surveillance Requirement (SR) 3.6.5.8. Specifically, the testing frequency for the CS nozzles is revised from 10 years to "following maintenance which could result in nozzle blockage."
The PINGP CS system consists of two trains each consisting of a CS pump, spray headers with associated power supplies, piping and valves. Attached to the spray headers are SPRACO Type 1713 nozzles. The nozzles are connected to four 360-degree ring headers with two ring headers per train and 84 nozzles per train (42 on each ring header). The nozzles have 3/8-inch diameter orifices. The licensee stated that these nozzles are not subject to clogging by particles less than 1/4-inch in maximum dimension. Either train provides adequate coverage of the containment volume. The PINGP Updated Safety Analysis Report, Section 6.4, provides additional information on the CS system.
Currently, PINGP TS SR 3.6.5.8 requires verification every 10 years that each CS nozzle is unobstructed. The licensee performs this verification by blowing smoke or air through the nozzles.
The proposed revision to SR 3.6.5.8 requires verification that each spray nozzle is unobstructed following maintenance that could result in nozzle blockage. Testing of the containment spray nozzles would not be required following CS system maintenance activities which successfully comply with the licensee's foreign material exclusion program.
I On September22, 2008, Nuclear Management Company, LLC (NMC), transferred its operating authority to Northern States Power Company, a Minnesota Corporation (NSPM). By letter dated September 3,2008, NSPM stated that it would assume responsibility for actions and commitments submitted by NMC.
-2
2.0 REGULATORY EVALUATION
The initial PINGP construction permit was issued by the U.S. Atomic Energy Commission (AEC) in June 1968. This is prior to the date specified in SECY 92-223 2 as the date for compliance with the General Design Criteria (GDC) of 10 CFR Part 50 Appendix A. The enclosure to the licensee's November 19, 2007, application states that PINGP was designed and constructed to comply with Northern States Power Company's understanding of the intent of the AEC GDC for Nuclear Power Plant Construction Permits, as proposed on July 10, 1967.
The applicable GDC for this change are Criterion 38, Reliability and Testability of Engineered Safety Features, and Criterion 60, Testing of Containment Spray Systems.
Criterion 38 states, in part, that all engineered safety features shall be designed to provide high functional reliability and ready testability. Revising the TSs so that flow testing of the CS nozzles is contingent on loss of foreign material controls does not reduce the reliability of the CS system since loss of foreign material control is the only identified mechanism by which blockage of spray nozzles could occur.
Criterion 60 states that a capability shall be provided to test periodically the delivery capability of the containment spray system at a position as close to the spray nozzles as is practical. This change does not affect the flow testing of pumps, only verification that the spray nozzles are not clogged. Although periodic nozzle flow testing will not be required when this change is implemented, reasonable assurance is still provided that the spray nozzles can perform their safety function.
3.0 TECHNICAL EVALUATION
The CS system piping that may be in contact with borated water is made of austenitic stainless steel, which is resistant to corrosion.
The licensee stated that the spray lines within the containment may be filled with borated water up to the 770-foot elevation, which is below the elevation at which water would enter the spray headers and nozzles (880-foot elevation). This assures that the spray nozzles remain dry during normal plant operation.
Due to their location at the top of the containment, introduction of foreign material exterior to the headers is unlikely. Because maintenance that could introduce foreign material is the most likely cause for obstruction, testing or inspection following such maintenance would suffice to verify the system's capability to perform its safety function. Therefore, the 1a-year test frequency is unnecessary. Verifying that the nozzles are not obstructed following maintenance that could introduce foreign materials internal to the spray ring headers (due, for example, to a loss of foreign material control) is more appropriate. The TS bases, provided for informational purposes by the licensee in its November 19, 2007 letter, discuss options includinq visual inspection of affected portions of the system, air or smoke tests, and draining and flushing of the system.
2 Memorandum for James M. Taylor. Executive Director for Operations. from Samuel J. Chilk, Secretary, Resolution of Deviations Identified During the Systematic Evaluation Program, SECY 92-223, September 18, 1992.
-3 Review of industry experience indicates that CS systems of similar design are highly reliable and are not subject to plugging after post-construction testing.
3.1 Prairie Island Experience PINGP Unit 1 CS nozzle air flow tests were conducted in 1978, 1982, 1988, 1992 and 2001, as required by the TSs. These tests confirmed that the nozzles were not plugged. The licensee did state that there were "anecdotal accounts" of an inadvertent CS pump actuation in 1974 during the Unit 1 startup activities. However, the licensee states that the pump was secured before the containment was sprayed down. Subsequently, the system was flushed, cleaned, and tested to verify that it was free of obstructions. Subsequent nozzle flow testing verified that the nozzles remained free of obstructions.
The licensee also reports that, since the last nozzle flow test on Unit 1, foreign material exclusion (FME) program controls were lost on Unit 1 during modifications on the system. The licensee describes this event and the corrective actions taken as a result of this event in a May 7,2008, letter to the Nuclear Regulatory Commission (NRC). During a 2004 refueling outage, foreign material was introduced into the system as a result of in-place machining of some of the system's valves. The foreign material was discovered when a check valve in the system failed a local leak rate test. The licensee subsequently strengthened the foreign material exclusion program. Among other changes, pipe dams and temporary covers are considered during operations such as grinding, valve lapping or filing. In 2005, the same valve machining did not cause an FME problem.
The licensee will designate the CS system as a system for which Very High foreign material control requirements will be applied. The licensee's May 7,2008, letter describes the requirements for Very High foreign material control.
3.2 Industry Experience and Failure Mechanisms An NRC staff review of industry experience using the NRC's Sequence Coding and Search System for Licensee Event Reports indicates that spray systems of similar design are highly reliable (i.e., not susceptible to plugging). The staff found that, with a few exceptions, once successfully tested after construction, CS nozzles have not been subject to blockage. There have been several exceptions.
In the case of one pressurized-water reactor (PWR) that is no longer operating, a chemical added to the inner surface of a spray system pipe to eliminate a corrosion problem detached and the loose material blocked some spray nozzles. Spray piping in currently operating PWRs, and in particular, that at PINGP is corrosion resistant; therefore, this failure mechanism is not applicable to PINGP.
The licensee for another PWR found debris, identified as construction debris, in the spray nozzle headers. The fraction of blockage was not significant and the sprays remained functional. The debris was found by visual observation, not by an air flow test.
Other problems have been identified in CS and fire protection systems in which water leakage resulted in corrosion and partial blockage. As discussed above, the PINGP design effectively
-4 precludes this condition since the piping, spray ring headers, and nozzles are of corrosion-resistant stainless steel, thereby precluding the formation of significant corrosion products.
3.3 Summary The NRC staff finds the licensee's proposed change to TS SR 3.6.5.8 to be acceptable based on industry experience, experience at PINGP, and the designation of the CS system as a system for which the foreign material controls are designated Very High.
4.0 STATE CONSULTATIOI\I In accordance with the Commission's regulations, the Minnesota State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (72 FR 71713). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: R. Lobel, NRR Date: November 6, 2008
November 6, 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 - ISSUANCE OF AMENDMENTS RE: LICENSE AMENDMENT TO REVISE CONTAINMENT SPRAY NOZZLE SURVEILLANCE REQUIREMENTS (TAC NOS. MD7362 AND MD7363)
Dear Mr. Wadley:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 190 to Facility Operating License No. DPR-42 and Amendment No. 179 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated November 19, 2007, as supplemented by letter dated May 7,2008.
The amendments replace the current fixed Frequency for testing the containment spray nozzles in Surveillance Requirement 3.6.5.8 with a maintenance or event based Frequency.
A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
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 and 50-306
Enclosures:
- 1. Amendment No. 190 to DPR-42
- 2. Amendment No. 179 to DPR-60
- 3. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION PUBLIC LPL3-1 r/f RidsNrrLATHarris Resource RidsOGCRpResource RidsAcrsAcnw_MailCTRResource RidsNrrDssScvb G. Hill, OIS RidsRgn3MailCenterResource R. Lobel, NRR RidsNrrDorlDpr Resource RidsNrrPMPrairielsandResource RidsNrrDorlLPL3-'1 Resource RidsNrrDirsltsbResource ADAMS ACCESSION' ML082740226 PKG' ML082740146 TS' ML082740280 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/DSS/SCVC (BC) NRR/DLR/RER1 (BC) OGC NRR/LPL3-1/BC NAME TWengert~ RDennig* JDozier BMizuno DATE to 1:3 1/08 \J 9/8/08 10109/08 10/17/08
- SE transmitted by memo of 918108 OFFICIAL RECORD COPY