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MONTHYEARML1002001312009-12-21021 December 2009 Report No. 0900634.401, Revision 2, Updated Leak-Before-Break Evaluation for Several RCS Piping at Prairie Island Nuclear Generating Plant, Units 1 & 2. Project stage: Request ML1005701342010-02-25025 February 2010 Acceptance Review of LAR to Apply Leak-Before-Break Methodology (TAC Nos. ME2976 and ME2977 Project stage: Acceptance Review ML1011802112010-05-0606 May 2010 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 Project stage: Withholding Request Acceptance ML1011708332010-05-0606 May 2010 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 Project stage: Withholding Request Acceptance ML1011708142010-05-0606 May 2010 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generation Plant, Units 1 and 2 Project stage: Withholding Request Acceptance ML1015506682010-06-10010 June 2010 Request for Additional Information Related 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 Project stage: RAI L-PI-10-077, 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 Additional ...2010-07-23023 July 2010 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 Additional ... Project stage: Supplement L-PI-10-085, Clarification of Responses to Requests for Additional Information Regarding a License Amendment Request for Certain Applications of Leak-Before-Break Methodology2010-08-20020 August 2010 Clarification of Responses to Requests for Additional Information Regarding a License Amendment Request for Certain Applications of Leak-Before-Break Methodology Project stage: Response to RAI L-PI-10-094, 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 - Response to RAI2010-10-0808 October 2010 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 - Response to RAI Project stage: Supplement ML1032803982010-12-14014 December 2010 RAI, Related to Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of LBB Methodology Project stage: RAI L-PI-11-006, 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 - Response to RAI2011-01-14014 January 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 - Response to RAI Project stage: Supplement L-PI-11-019, Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to Requests for Clarification2011-02-23023 February 2011 Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to Requests for Clarification Project stage: Supplement 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 Project stage: Supplement ML1120106962011-07-22022 July 2011 RAI, Related to Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology Project stage: RAI L-PI-11-070, Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI2011-08-0909 August 2011 Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI Project stage: Supplement ML1122008562011-10-27027 October 2011 Operating Plant, Units 1 and 2 - Issuance of Amendments Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology Project stage: Approval 2010-07-23
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Category:Letter type:L
MONTHYEARL-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 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 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-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy 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 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 L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring 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-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) 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-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles 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 L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request 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 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-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island 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-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report 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-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic 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-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI 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 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-19-031, 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-19-038, Submittal of Revised Pressure and Temperature Limits Report2019-09-19019 September 2019 Submittal of Revised Pressure and Temperature Limits Report L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)2019-08-27027 August 2019 Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019 Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For... L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2 L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-PI-19-003, Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)2019-02-0404 February 2019 Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP) 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-19-005, Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.692019-01-15015 January 2019 Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.69 L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018 Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805 2024-01-02
[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
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APR 0 6 2011 L-PI-I 1-038 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Supplement to License Amendment Request to Exclude the Dvnamic Effects Associated with Certain Postulated Pipe Ruptures From the Licensing Basis Based Upon Application of Leak-Before-Break Methodoloav - Support for Containment Particulate Monitor Response Calculation (TAC Nos. ME2976 and ME29771
References:
- 1. Letter from M. A. Schimmel, Northern States Power Company, a Minnesota corporation (NSPM), to Document Control Desk (Nuclear Regulatory Commission, NRC), "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-09-134, dated December 22, 2009, ADAMS Accession Number ML100200129.
- 2. Letter from M. A. Schimmel (NSPM) to Document Control Desk (NRC), "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 - Response to Request for Additional Information (TAC Nos. ME2976 and ME2977)," L-PI-11-006, dated January 14, 201 1, ADAMS Accession Number M L I 10140367.
- 3. Letter from M. A. Schimmel (NSPM) to Document Control Desk (NRC), "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 - Response to Requests for Clarification (TAC Nos. ME2976 and ME2977),11 L-PI-11-019, dated February 23, 201 1, ADAMS Accession Number ML110550582.
1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651,388.1121
Document Control Desk Page 2 8 In Reference 1, Northern States Power Company, a Minnesota corporation (NSPM),
doing business as Xcel Energy, submitted a License Amendment Request (MR)to 1
6 apply Leak-Before-Break (LBB) methodology to certain piping at the Prairie Island d
t Nuclear Generating Plant (PINGP), in References 2 and 3, NSPM submitted additional 9
information regarding calculated response times for the containment particulate I
4 radiation monitors to detect Reactor Coolant System (RCS) leaks.
b During informal telephone discussions held on March 7 and 14, 2011, the NRC staff requested historical information and other suppoFting documentation for the leakage detection response time calculation described in References 2 and 3. The enclosure to this letter provides the requested information, consistent with additional informal discussions held with the NRC staff on March 28, 2011. NSPM submits this supplement in accordance with 10 CFR 50.90.
The supplemental information provided in this letter does not impact the conclusions of
! the Determination of No Significant Hazards Consideration or Environmental a Assessment presented in the Reference Isubmittal.
I In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this LAR supplement by transmitting a copy of this letter to the designated State Official.
If there are any questions or if additional information is needed, please contact Sam Chesnutt at 651-267-7546.
Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on ##+a 0 6 2011 Kevin Davison Plant Manager, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota
ENCLOSURE This enclosure provides supplemental information from the Northern States Power Company, a Minnesota corporation (NSPM) doing business as Xcel Energy, associated with a License Amendment Request (WR) submitted December 22,2009 (Reference 1). This LAR requested approval to use Leak-Before-Break (LBB) methodology on certain piping at the Prairie Island Nuclear Generating Plant (PINCP).
The supplemental information in this enclosure provides support for the Reactor Coolant System (RCS) leakage detection response time calculation previously described in NSPM letters dated January 14 and February 23, 201 1 (References 2 and 3). The PINGP RCS leakage detection response time calculation was discussed during informal telephone discussions on March 7, 14, and 28, 201 1.
Referenced documents are identified at the end of this Enclosure.
Support for R - I I Response Calculation In References 2 and 3, NSPM described a calculation that demonstrates the response time capabilities for containment particulate radiation monitors 1R-I Iand 2R-11 for Units 1 and 2, respectively, to detect RCS leaks. In Reference 3, NSPM stated that the calculated response time of newly installed R - I Iinstrumentation has not been tested or benchmarked to actual plant leakage events because an active leak of sufficient magnitude and duration has not been experienced since installation of the monitors.
During informal telephone discussions on March 14 and 28, 201 1, data from historical RCS leakage events using the previous R - I Imonitors was discussed. In addition, information available in open literature which supports the leakage detection response time calculation was discussed. Particular considerations included the following:
The presence of particulate daughter products of noble gas decay, Rubidium-88 (Rb-88) and Cesium-138 (Cs-138) which are included in the source term for the R - I Iresponse time calculation, in sufficient quantities for detection on R - I I radiation monitors The behavior of particulate aerosols in containment and plateout in the sample tubing, and their effect on detection by the R-I Iradiation monitors Page 1 of 5
Enclosure NSPM RCS Leakage Detection Supplemental Information Prevalence of Daughter Products The use of daughter products of noble gas decay for evaluating the capabilities of radiation monitors to detect coolant leakage from the Reactor Coolant Pressure Boundary (RCPB) has been described in industry references, as discussed belaw ISA Standard, ISA-S67.03-I982 (Reference 4)) Section 7.2.1, "Air radioparticulate and radiogas activity monitors," includes the following:
"c) Assumptions for design computations These assumptions provide a uniform design basis and shall be used to estimate the capabilities of radiation monitors to detect coolant leakage from RCPB...
- 2) For particulate monitors, owing to differences in source terms in PWRs, only Rb-88 which is in secular equilibrium with its parent isotope Kr-88 need be considered. ..."
An IEEE paper titled "Enhancement of Reactor Coolant Leakage Measurement Using Radiation Instrumentation," also addresses the importance of daughter products of noble gas decay in detection of RCS leakage (Reference 5). Regarding daughter products, this paper states in Section I.B, "Particulate Monitor Model Considerations":
"a. 8 8 ~Source r of 8 8 ~ b The most important consideration for particulate monitoring of RCS leakage is the 8 8 ~daughter b generated by 8 8 ~ .r..I1 Regarding plateout, Section 1.B of this paper also states:
"c. Plateout Particulates are removed from the containment atmosphere by more mechanisms than those which remove gases. In addition to radioactive decay and purge, particulates are removed by plateout on internal containment surfaces and by operation of the recirculation cleanup system or the containment cooling units. Such factors are not readily quantifiable for a complex structure like the containment.
These plateout rates have little effect on the 8 8 ~concentration b because the plateout removal constants considered are much less than the 8 8 ~decay b constant. Plateout does have an effect on the build up of the other particulates because of their much longer half-lives. This limits the build up of the particulates over longer periods."
Page 2 of 5
Enclosure NSPM RCS Leakage Detection Supplemental Information These referenced documents confirm industry experience that Rb-88 will be present in sufficient concentrations for detection, and also that particulate transport to the R-I I detector will not be significantly affected by plateout. As described in Reference 3, the NSPM calculation conservatively accounts for aerosol removal mechanisms that could affect particulate transport.
Historical Examples of R-I IResponse to RCS Leakas Several RCS leakage events at PlNGP have been identified based, in part, on increased R-I Iindications. Two leakage events described bslow demonstrate the ability of the containment radiation monitoring sampling system to transport airborne particulates to the R-I Iradiation detector, despite the effects of plateout in containment or the sample line. In addition, containment grab sample analyses from one of these events demonstrate the presence of Rb-88 and Cs-138 in sufficient concentrations for detection.
I 1995 Unit 2 Reactor Coolant Pump Flancle Leak i
I In 1995, Unit 2 experienced a leak on the 22 Reactor Coolant Pump (RCP) main flange.
R-I Icount rate and containment grab sample analysis data include the following (note that radionuclide concentration data are only provided for particulates, to identify material that would contribute to the R-1Icount rate):
August 19, 1994:
R-I Iindication 3,202 counts per minute (cpm)
Bromine-82 (Br-82) 3.72 x 10-lomicrocuries per cubic centimeter (pCilcc)
Rb-88 3.28 x 10-' pCi/cc March 22, 1995:
R-I Iindication 1,829 cpm Count rate prior to increase April 5, 1995:
R-I Iindication 10,281 cpm Br-82 3.89 x 10-lopCi/cc Cs-I 37 3.43 x lo-" pCi/cc Cs-138 3.73 x lo- pCi/cc Na-24 9.14 x lo-" pCi/cc Rb-88 7.70 x 10-' pCi/cc Y-92 4.56 x lo- pCi/cc April 24, 1995:
R-I 1 indication 14,335 cpm Br-82 4.01 x lo-" pCi/cc Cs-I 38 6.76 x 10-lopCi/cc Rb-88 8.49 x lo-' pCi/cc Page 3 of 5
Enclosure NSPM RCS Leakage Detection Supplemental Information This Unit 2 RCP main flange leak demonstrated that the particulate daughter products of noble gas decay, Rb-88 and Cs-138, were present in sufficient quantities for detection. In addition, this event demonstrated particulate transport between the containment air and the detector despite the effects of plateout in containment or the sample line.
1994 Unit 1 CRDM Canopy Seal Leak In 1994 a leak in a control rod drive mechanism (CRDM) canopy seal weld in Unit 1 was detected by the R-I Imonitor. On July 13, 1994, the R - I 1 instrument was logged as indicating 2,000 cpm. A containment air grab sample conducted on the same day indicated 6.18 x 10-lopCi/cc of containment particulate activity. These values were recorded prior to the onset of the leak and represent baseline values.
A step change in the R-I Icount rate to 5,000 cpm was noted on July 19, 1994, By July 28, 1994, the R-11 count rate had reached 10,000 cpm. A containment air grab sample conducted on July 21, 1994 indicated 3.44 XIO-' pCi/cc of containment particulate activity.
In this instance, a very small leak resulted in an increase in the containment particulate activity of over five times the baseline and resulted in an increase in R - I 1 count rate of 8,000 cpm. It is also noted that RCS total radiogas and particulate source term for this event was low, less than 4 x 1om2pCi/cc gas and 7.5 x 10" pCi/cc particulates.
This Unit 1 CRDM canopy seal leak verifies that changes in the containment airborne particulate activity level resulting from a small leak were transported to the previous R-I I radiation detector despite the effects of any plateout in containment or the sample line.
For comparison between the new and previously installed R-I Iinstrument responses, the new R - I Isensitivity in terms of cpm per pCi/cc of source activity is at least double that of the previous R-I Iinstruments. In addition, the new R-I Iuses a much lower flow rate through the sample tubing than the previous R-I I , which will further minimize any losses due to deposition in the sample line. The previous R-I Isample flow rate was approximately 10 standard cubic feet per minute (scfm), whereas the current sample flow is conservatively limited to approximately 1.4 scfm to maintain laminar flow conditions. ANSI N13.1 (Reference 6) recommends laminar flow conditions in the sample tubing to minimize interactions between entrained particulates and tubing surfaces.
Conclusion A review of historical leakage events at PlNGP and open literature supports calculation assumptions regarding the prevalence of Rb-88 and Cs-138 as contributors to R-11 Page 4 of 5
Enclosure NSPM RCS Leakage Detection Supplemental Information count rate. This review also justifies that particulate transport behhreen the containment air and the detector is consistent with calculation assumptions, References
- 1. Letter from M. A. Schimmel (NSPM) to Document Control Desk (NRC), "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-09-134, dated December 22, 2009, ADAMS Accession Number ML100200129.
- 2. Letter from M. A, Schimmel (NSPM) to Document Control Desk (NRC),
"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 - Response to Request for Additional Information (TAC Nos. ME2976 and ME2977)," L-PI 006, dated January 14,201I, ADAMS Accession Number MLI 100140367.
- 3. Letter from M. A. Schimmel (NSPM) to Document Control Desk (NRC),
"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 - Response to Requests for Clarification (TAC Nos. ME2976 and ME2977)," L-PI-11-019, dated February 23,201 1, ADAMS Accession Number MLI 10550582,
- 4. Standard for Light Water Reactor Coolant Pressure Boundary Leak Detection, ISA-S67.03-1982, Instrument Society of America.
- 5. Enhancement of Reactor Coolant Leakage Measurement Using Radiation Instrumentation, Daniel G. Weis, PhD, PE, IEEE Transactions on Nuclear Science, Vol. 46, No. 3, June 1999, pp. 438-443.
- 6. Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities, ANSI N13.1, American National Standards Institute, February 19, 1969.
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