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MONTHYEARRS-12-073, Units 1 and 2 - License Amendment Request to Revise Technical Specifications Section 3.5.3, ECCS - Shutdown2012-07-23023 July 2012 Units 1 and 2 - License Amendment Request to Revise Technical Specifications Section 3.5.3, ECCS - Shutdown Project stage: Request 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 Project stage: Request L-PI-13-061, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System) - Shutdown.2013-06-25025 June 2013 Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System) - Shutdown. Project stage: Supplement ML14174B3942014-06-23023 June 2014 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Final Requests for Additional Information License Amendment to Revise Technical Specification Section 3.5.3, ECCS Shutdown Project stage: RAI L-PI-14-066, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System) - Shutdown2014-09-15015 September 2014 Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System) - Shutdown Project stage: Supplement L-PI-15-004, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown2015-02-26026 February 2015 Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown Project stage: Supplement ML15062A0132015-05-20020 May 2015 Issuance of Amendments 213 and 201 to Revise TS 3.5.3, ECCS - Shutdown Project stage: Approval 2014-06-23
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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:Technical Specifications
MONTHYEARML22357A1002023-03-31031 March 2023 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML22181A0002022-08-17017 August 2022 Issuance of Amendments Reactor Trip System Power Range Instrumentation Channels L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22061A2062022-04-0101 April 2022 Issuance of Amendments TSTF-471, Rev. 1, TSTF-571-T, and Administrative Changes to Technical Specification Section 5.0 L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 ML20346A0202021-03-15015 March 2021 Issuance of Amendment Nos. 235 and 223, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20356A0022021-02-0505 February 2021 Issuance of Amendment Nos. 234 and 222, Revise Technical Specifications 3.2.1 and 5.6.5 Identified in Westinghouse Nuclear Safety Advisory Letters NSAL-09-05, Revision 1, and NSAL-15-1 ML20210M0142020-09-0808 September 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency ML19045A4802019-04-16016 April 2019 Issuance of Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19029A0942019-01-29029 January 2019 Issuance of Amendment No. 213, One-Time Technical Specification Change to Extend Completion Time for EDGs D5 and D6 (Emergency Circumstances) ML17362A2022018-03-0505 March 2018 Issuance of Amendment Concerning Revision to the Prairie Island Nuclear Generating Plant, Units 1 and 2 Emergency Plan (CAC Nos. MF9345 and MF9346; EPID L-2017-LLA-0175) ML16133A4062016-06-16016 June 2016 Issuance of Amendment Nos. 217 and 205, Adoption of Technical Specifications Task Force TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation (CAC Nos. MF6449 and MF6450) ML15264A2092015-11-30030 November 2015 Issuance of Amendment Nos. 216 and 204 Regarding Revisions to Technical Specification 3.3.3 and Renewed Facility Operating License ML15229A1762015-08-26026 August 2015 Issuance of Amendment Nos. 215 and 203 Regarding Revision to Licensing Basis Analysis for a Waste Gas Decay Tank Rupture ML15209A5122015-07-17017 July 2015 Technical Specifications - Updating Instructions -Effective Date: 7/24/2015 ML15209A5092015-07-17017 July 2015 Technical Specifications - Updating Instructions L-PI-15-030, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-06-29029 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML15086A0462015-05-21021 May 2015 Issuance of Amendment Nos. 214 and 202 Regarding Revisions to Technical Specification 3.8.1, AC Sources - Operating ML15062A0132015-05-20020 May 2015 Issuance of Amendments 213 and 201 to Revise TS 3.5.3, ECCS - Shutdown L-PI-15-004, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown2015-02-26026 February 2015 Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown L-PI-14-034, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation2014-12-11011 December 2014 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation ML14058A2072014-02-19019 February 2014 Technical Specifications (3801 TS Markup) ML13214A0292013-08-0202 August 2013 Correction Letter for License Amendment Nos. 207 (Unit 1) and 194 (Unit 2) ML13113A4002013-07-0202 July 2013 License Amendments TSTF-510 L-PI-13-030, License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr).2013-05-23023 May 2013 License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr). ML13093A3442013-05-0909 May 2013 License Amendments for Fuel Oil System and TSTF-501 L-PI-12-028, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits2012-05-15015 May 2012 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits L-PI-12-013, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology2012-02-24024 February 2012 Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology ML1129011152011-12-0101 December 2011 Issuance of Amendments Revision of Technical Specifications 5.2.1, Onsite and Offsite Organizations and TS 5.3, Plant Staff Qualifications. L-PI-11-037, License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil2011-08-11011 August 2011 License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil ML11172A0222011-06-27027 June 2011 Technical Specifications, Unit 2, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant ML11172A0202011-06-27027 June 2011 Technical Specifications, Unit 1, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant L-PI-11-016, License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating.2011-02-0303 February 2011 License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating. L-PI-10-104, Supplement to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.102010-10-20020 October 2010 Supplement to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 ML1025715492010-09-16016 September 2010 Correction to Amendment Nos. 195 and 184 Regarding Technical Specification Changes to Control Room Habitability Requirements ML0925703672009-09-15015 September 2009 Correction to Technical Specifications (TAC Nos. MD9142 and MD9143) L-PI-08-080, License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.92008-11-0404 November 2008 License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.9 ML0826815912008-09-22022 September 2008 (PINGP-1 and 2), Technical Specifications ISFSI, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245) ML0826812912008-09-22022 September 2008 Revised Operating Licenses & Technical Specifications, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245, MD9622 and MD9623) ML0820504452008-07-18018 July 2008 Tech Spec Pages for Amendments 186 & 176 Adopting Provisions of Regulatory Guide (Rg) 1.52 Revision 3 ML0818402342008-06-27027 June 2008 Prairie, Units 1 and 2, Tech Spec Pages for Amendments 185 and 175 Regarding Incorporation of TS Task Force Travelers TSTF-479, TSTF-485 and TSTF-497 ML0812705062008-05-0101 May 2008 Submittal of Entire Re-Issue of ISFSI Technical Specifications ML0801404252008-01-28028 January 2008 Issuance of Amendments (TAC Nos. MD4209 & MD4210) - Tech Specs ML0735204002007-12-14014 December 2007 Technical Specifications in Support of Containment Sump Resolution L-PI-07-086, License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (SR)2007-11-19019 November 2007 License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (SR) ML0728403542007-10-31031 October 2007 Tech Spec Page for Amendments 181 and 171, Revise TS 3.7.2 Main Steam Valves Closure Times by Relocating the Isolation Valve Closure Times to a Licensee-Controlled Document Identified as a Bases Reference L-PI-07-061, License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load2007-08-16016 August 2007 License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load 2023-03-31
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Xcel Energy@
L-PI-15-004 FEB 2 6 2015 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, "ECCS [Emergency Core Cooling System]- Shutdown" (TAC Nos. MF0727 and MF0728)
By letter dated February 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13053A199), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submitted a license amendment request for Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, to remove Technical Specification (TS) 3.5.3 Limiting Condition for Operation (LCO) Note 1. By letters dated June 25,2013 (ML13178A024) and September 15, 2014 (ML14258A089), NSPM supplemented the February 20, 2013 LAR. By email dated November 24, 2014, NRC Staff requested additional information (RAI) on the February 20, 2013, LAR (ML13053A199). The enclosure to this letter provides the response to the NRC Staff RAI. NSPM submits this supplement in accordance with the provisions of 10 CFR 50.90.
The response to the RAI proposes additional TS changes which revise the scope of the requested license amendment. Accordingly, the enclosure to this letter revises the Determination of No Significant Hazards Consideration. However, the revised Determination of No Significant Hazards Consideration does not change the conclusions of the Determination of No Significant Hazards Consideration or Environmental Assessment presented in the February 20, 2013 (ML13053A199) submittal as supplemented June 25, 2013 (ML13178A024) and September 15, 2014 (ML14258A089).
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 and enclosure to the designated State Official.
1717 Wakonade Drive East
- Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-267-1736.
Summary 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 FEB 2 6 2015 1/M~ JJ~,~c ~
Kevin Davison Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, US NRC State of Minnesota
ENCLOSURE Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, "ECCS [Emergency Core Cooling System]- Shutdown" TAC Nos. MF0727 and MF0728 By letter dated February 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13053A199), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submitted a license amendment request for Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, to remove Technical Specification (TS) 3.5.3 Limiting Condition for Operation (LCO) Note 1. By letters dated June 25, 2013 (ML13178A024) and September 15, 2014 (ML14258A089), NSPM supplemented the February 20, 2013 LAR. By email dated November 24, 2014, NRC Staff requested additional information (RAI) on the February 20, 2013, LAR (ML13053A199).
NRC RAI:
The applicability of TS 3.5.3 is Mode 4 above 218 oF in the cold leg. As such, below 218 oF in the cold leg there is no requirement for ECCS [emergency core cooling system]. However, ECCS is necessary because RCS [reactor coolant system]
temperature is high enough to flash if there is a depressurization or loss of coolant (note: below 200 T ave ECCS is not necessary because RCS temperature is not high enough to flash if there is a depressurization or loss of coolant). Please explain why no ECCS is acceptable when the RCS temperature is high enough to flash if there is a depressurization or loss of coolant. How will the plant mitigate a depressurization event or loss of coolant below 218 oF in the cold leg.
NSPM Response:
Currently TS 3.5.3 is applicable in Mode 4 when both RCS cold legs are above the safety injection (SI) disable temperature specified in the Pressure and Temperature Limits Report (PTLR). The Limiting Condition for Operation (LCO) statement requires one train of the ECCS, which comprises an Sl pump and residual heat removal (RHR) pump, to be operable throughout the mode or other specified conditions of applicability.
Low temperature overpressurization evaluations for PINGP demonstrate that a single Sl pump injection below the temperature specified as the Sl disable temperature in the PTLR (currently specified as 218 oF) could overpressurize the RCS. With both Sl pumps incapable of injecting below the Sl disable temperature, the LCO requirement for ECCS would not be met. To remedy this situation, the PINGP TS 3.5.3 Applicability was revised to exclude the portion of Mode 4 when the temperature of at least one RCS cold leg is below the Sl disable temperature.
NSPM proposes in this LAR supplement to revise the TS 3.5.3 Applicability statement to apply to all of Mode 4. Attachment 1 to this Enclosure provides TS 3.5.3 marked up with the changes proposed by this license amendment supplement including removal of Page 1 of 4
RHR LCO Note RAI the Applicability clause, "when both RCS cold leg temperatures are > Sl pump disable temperature specified in PTLR." Attachment 2 to this Enclosure provides the TS 3.5.3 Bases marked up with the changes associated with the proposed TS 3.5.3 changes.
- to this Enclosure provides the retyped TS 3.5.3 page with all proposed changes incorporated. The TS and Bases changes proposed in Attachments 1, 2 and 3 to this Enclosure supersede in their entirety the TS and Bases changes previously provided in the attachments to the February 20, 2013 LAR (ML13053A199) enclosure.
To preclude inadvertent operation of the Sl pump required to be operable to meet TS 3.5.3 and further protect the RCS from overpressurization, PINGP license amendments 183 and 173 (ML080100186), for Units 1 and 2 respectively, added LCO Note 2 to PINGP TS 3.5.3 which states, "An Sl train may be considered OPERABLE when the pump is capable of being manually started from the control room." This note allows the LCO operability requirements to be met with the Sl pump disabled from automatic initiation for the current TS 3.5.3 Applicability. This same note will allow the LCO to be met with the proposed TS 3.5.3 Applicability to include the whole range of Mode 4.
The response to this RAI proposes significant TS changes in addition to those previously proposed in this license amendment request which are beyond the scope of the Significant Hazards Consideration previously provided. The following Significant Hazards Consideration supersedes the Section 4.3 "Significant Hazards Consideration",
previously provided in the Enclosure to the February 20, 2013 (ML13053A199) as modified by the supplement dated June 25, 2013 (ML13178A024):
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No This license amendment request proposes to revise the Technical Specification for ECCS operability requirements in Mode 4 by removing the LCO Note which allows the RHR subsystem to be considered operable for ECCS when aligned for shutdown cooling and revising the Applicability statement to include all of Mode 4. These changes will require one train of RHR to be aligned for ECCS operation throughout Mode 4.
The proposed changes do not affect the ECCS and RHR subsystem design, the interfaces between the RHR subsystem and other plant systems' operating functions, or the reliability of the RHR subsystem. The proposed changes do not change or impact the initiators and assumptions of the analyzed accidents.
Therefore, the ECCS and RHR subsystems will be capable of performing their accident mitigation functions, and the proposed TS changes do not involve an increase in the probability of an accident.
The proposed TS changes will require that one train of RHR is aligned for ECCS operation during Mode 4 which assures that one train of ECCS is operable to Page 2 of 4
RHR LCO Note RAI mitigate the consequences of a loss of coolant accident. Thus the proposed TS changes do not involve a significant increase in the consequences of an accident.
Therefore, the proposed Technical Specification changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No This license amendment request proposes to revise the Technical Specification for ECCS operability requirements in Mode 4 by removing the LCO Note which allows the RHR subsystem to be considered operable for ECCS when aligned for shutdown cooling and revising the Applicability statement to include all of Mode 4. These changes will require one train of RHR to be aligned for ECCS operation throughout Mode 4.
The proposed Technical Specification changes involve changes to when system trains are operated, but they do not change any system functions or maintenance activities. The changes do not involve physical alteration of the plant, that is, no new or different type of equipment will be installed. The changes do not alter assumptions made in the safety analyses but ensure that one train of ECCS is operable to mitigate the consequences of a loss of coolant accident. These changes do not create new failure modes or mechanisms which are not identifiable during testing and no new accident precursors are generated.
Therefore, the proposed Technical Specification changes do not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No This license amendment request proposes to revise the Technical Specification for ECCS operability requirements in Mode 4 by removing the LCO Note which allows the RHR subsystem to be considered operable for ECCS when aligned for shutdown cooling and revising the Applicability statement to include all of Mode 4. These changes will require one train of RHR to be aligned for ECCS operation throughout Mode 4.
This license amendment proposes Technical Specification changes which assure that the ECCS -Shutdown TS LCO requirements are met if a Mode 4 LOCA Page 3 of 4
RHR LCO Note RAI were to occur. With these changes, other TS requirements for shutdown cooling in Mode 4 will continue to be met. Based on review of plant operating experience, there is no discernable change in cooldown rates when utilizing a single train of RHR for shutdown cooling. Thus, no margin of safety is reduced as part of this change.
Therefore, the proposed Technical Specification changes do not involve a significant reduction in a margin of safety.
Although the response to the 10 CFR 50.92(c) questions have been is revised, the conclusion has not changed: Northern States Power Company, a Minnesota corporation (NSPM) concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and, accordingly, a finding of "no significant hazards consideration" is justified.
Page 4 of 4
ENCLOSURE,ATTACHMENT1 Technical Specification Pages (Markup) 3.5.3-1 1 page follows
ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS- Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.
NOTE~-----------------------------------------
- 1. An RHR train may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned to the EGGS mode of operation.
~ An SI train may be considered OPERABLE when the pump is capable of being manually started from the control room.
APPLICABILITY: MODE 4 'Nhen both RDS cold leg temperatures are > SI pump disable temperature specified in PTLR.
ACTIONS
NOTE------------------------------------------------------
LCO 3.0.4.b is not applicable to ECCS safety injection (SI) subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS residual A.l Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable. subsystem to OPERABLE status.
B. Required ECCS safety B.l Restore required ECCS SI 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> injection (SI) subsystem subsystem to OPERABLE inoperable. status.
Prairie Island Unit 1- Amendment No. 158 167 -+/--8J Units 1 and 2 3.5.3-1 Unit2-AmendmentNo. 149157-+/--7J-
ENCLOSURE,ATTACHMENT2 Bases Pages (Markup) 8 3.5.3-1 8 3.5.3-2 8 3.5.3-3 8 3.5.3-4 8 3.5.3-5 8 3.5.3-6 6 pages follow
ECCS - Shutdown B 3.5.3 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
B 3.5.3 ECCS- Shutdown BASES BACKGROUND The Background section for Bases 3.5.2, "ECCS-Operating," is applicable to these Bases, with the following modifications.
In MODE 4, the required ECCS train consists of two separate subsystems: safety injection (SI) and residual heat removal (RHR).
The ECCS flow paths consist of piping, valves, heat exchangers, and pumps such that water from the refueling water storage tank (RWST) or containment Sump B can be injected into the Reactor Coolant System (RCS) following the accidents described in Bases 3.5.2.
In the event of a loss of coolant accident (LOCA) while in the Applicability of Technical Specification (TS) 3.5.3. fluid in the RHR suction piping could flash to steam. resulting in the RHR system not remaining capable of responding to the LOCA. Also. if a LOCA occurs in MODE 4 that is of sufficient size to depressurize and drain the RCS. any operating RHR pump could lose its suction source at some point. As a result, any operating RHR pump is assumed to fail if it is not shut down prior to steam and/or air voiding. See References 1 and 2.
These issues are similar in that they both relate to the RHR system's ability to mitigate a LOCA while in MODE 4. and similar corrective actions are required to address both concerns. However, the immediate precursor of each failure is distinctly different. The first concern is a result of trapped fluid in the RHR system remaining at a temperature that is sufficiently high such that flashing will occur when the system is depressurized. The second concern is due to the fact that during a LOCA of sufficient size to depressurize and drain the RCS any operating RHR pump would lose its suction source.
Due to these issues, ohe RHR train must be aligned for ECCS Prairie. Island Unit 1- RevisionA..mendment No. 158 Units 1 and 2 B 3.5.3-1 Unit 2- RevisionAmendment No. 149
ECCS - Shutdown B 3.5.3 BASES BACKGROUND mode of operation to satisfy LCO 3.5.3 when in MODE 4.
(continued)
APPLICABLE Due to the lower heat generation rate associated with operation SAFETY in MODE 4 it has been judged that the full power licensing ANALYSES analyses described in the Applicable Safety Analyses section of Bases 3.5.2 would bound the consequences of a Design Basis Accident (DBA) in MODE 4. It is also recognized that due to the lower pressure and temperatures in the RCS, the probability of occurrence of a DBA is reduced. Therefore, the ECCS operational requirements are reduced. It is understood in these reductions that certain automatic SI actuations are not available. Since the RHR System may be aligned to provide normal shutdovm cooling, time may be required for manual alignment ofECC S equipment. In this MODE, the heat generation rate is lower and sufficient time exists for manual actuation of the required ECCS to mitigate the consequences of a DBA. Therefore, only one train ofECC S is required for MODE 4. This requirement dictates that single failures are not considered for this LCO due to the time available for operators to respond to an accident.
The ECCS trains satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).
Prairie Island Unit 1- RevisionAmendment No. 158 Units 1 and2 B 3. 5 .3-2 Unit 2 - Revisio nl..mendment No. 14 9
ECCS - Shutdown B 3.5.3 BASES (continued)
LCO In MODE 4, one of the two independent (and redundant) ECCS trains is required to be OPERABLE to ensure that sufficient ECCS flow is available to the core following a DBA.
- **In MODE 4, an ECCS train consists of an SI subsystem and an RHR subsystem. Each train includes the piping, instruments, and controls to ensure an OPERABLE flow path capable of taking suction from the RWST and transferring suction to the containment sump.
During an event requiring ECCS actuation, a flow path is required to provide an abundant supply of water from the RWST to the RCS via the SI subsystem capable (through manual actions) of injecting into each of the cold leg injection nozzles and reactor vessel upper plenum nozzles. In the long term, a flow path is required to provide recirculation flow via the RHR subsystem from the containment sump into each of the reactor vessel upper plenum nozzles.
This LCO is modified by onetwe Notes which. Note 1 allows an RHR train to be considered OPERABLE during alignment and operation fur decay heat removal, if capable of being manually realigned (remote or local) to the EGGS mode of operation and not othenvise inoperable. This allows operation in the RHR mode during l\10DE 4.
Note 2 allows an SI train to be considered OPERA BLE when the
- pump is capable of being manually started for ECCS injection from the control room.
APPLICABILITY In MODE S 1, 2, and 3, the OPERA BILITY requirements for ECCS are covered by LCO 3.5.2.
In MODE 4 with RCS temperature below 350°F and both RGS cold leg temperatures above the SI pump disable temperature specified in
. the PTLR, one OPERABLE ECCS train is acceptable without single failure consideration, on the basis of the stable reactivity of the reactor and the limited core cooling requirements.
Prairie Island Unit 1 -Revision~
Units 1 and 2 B 3.5.3-3 Unit 2 -Revision~
ECCS - Shutdown B 3.5.3 BASES APPLICABILITY In MODE 4*\vhen any RCS cold leg temperature is< the SI pump (continued) .*. disable temperature, and MODES 5 and 6, plant conditions are such that the probability of an event requiring ECCS injection is extremely low. Core cooling requirements in .MODE 4 vmen any RCS cold leg temperature is < the SI pump disable temperature are addressed by LCO 3.4.6, "RCS Loops MODE 4." Core cooling requirements in MODE 5 are addressed by LCO 3.4.7, "RCS Loops-MODE 5, Loops Filled," and LCO 3.4.8, "RCS Loops-MODE 5, Loops Not Filled." MODE 6 core cooling requirements are addressed by LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation-High Water Level, and LCO 3.9.6, "Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level."
ACTIONS A Note prohibits the application ofLCO 3.0.4.b to an inoperable
- ECCS safety injection (SI) subsystem when entering MODE 4-with both R{;S cold legs temperatures greater than the SI pamp disable temperature specified in the PTLR. There is an increased risk associated with entering MODE 4 'Nith both RCS cold legs temperat'..wes greater than the SI pump disable temperature specified in the PTLR from MODE 5 with an inoperable ECCS SI subsystem
- and the provisions ofLCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.
With no ECCS RHR subsystem OPERABLE, the plant is not prepared to respond to a loss of coolant accident or to continue a cooldown using the RHR pumps and heat exchangers. The Completion Time of immediately to initiate actions that would restore at least one ECCS RHR subsystem to OPERABLE status ensures that prompt action is taken to restore the required cooling capacity. Normally, in MODE 4, reactor decay heat is removed Prairie Island Unit 1 -Revision~
Units 1 and 2 B 3.5.3-4 Unit 2 -Revisi on ~
ECCS - Shutdown B 3.5.3 BASES ACTIONS A.1 (continued}
from the RCS by an RHR loop. If no RHR loop is OPERABLE for this function, reactor decay heat must be removed by some alternate method, such as use of the steam generators. The alternate means of heat removal must continue until the inoperable RHR loop
With both RHR pumps and heat exchangers inoperable, it would be unwise to require the plant to go to MODE 5, where the only available heat removal system is the RHR. Therefore, the
- appropriate action is to initiate measures to restore one ECCS RHR
. subsystem and to continue the actions until the subsystem is restored to OPERABLE status.
With no ECCS SI subsystem OPERABLE (neither train), due to the inoperability of the SI pump or flow path from the RWST, the plant is not prepared to provide high pressure response to Design Basis Events requiring SI. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time to restore at least one SI subsystem to OPERABLE status ensures that prompt action is taken to provide the required cooling capacity or to initiate actions
- to place the plant in MODE 5, where an ECCS train is not required.
When the Required Actions of Conditions B cannot be completed within the required Completion Time, a controlled shutdown should be initiated. Twenty- four hours is a reasonable time, based on operating experience, to reach MODE 5 in an orderly manner and without challenging plant systems or operators.
Prairie Island Unit 1 -Revisio n +9; Units 1 and 2 B 3.5.3-5 Unit 2 - Revision +9;
ECCS - Shutdo wn B 3.5.3 BASE S (continued)
SURVEILLANCE SR 3.5.3.1 REQUIREMENTS The applica ble Surveillance descriptions from Bases 3.5.2 apply.
REFER ENCE S The applica ble referen ces from Bases 3.5.2 apply.
- 1. NRC Inform ation Notice 2010-11.
- 2. Westin ghouse NSAL 8.
Prairie Island Unit 1 - Revisi on J.
Units 1 and 2 B 3.5.3-6 Unit 2 - Revisi on J.
ENCLOSURE,ATTACHMENT3 Technical Specification Pages (Retyped) 3.5.3-1 1 page follows
ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS- Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.
NOTE------------------------------------------
An SI train may be considered OPERABLE when the pump is capable of being manually started from the control room.
APPLICABILITY: MODE 4.
ACTIONS
NOTE------------------------------------------------------
LCO 3.0.4.b is not applicable to ECCS safety injection (SI) subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS residual A.l Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable. subsystem to OPERABLE status.
B. Required ECCS safety B.1 Restore required ECCS SI 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> injection (SI) subsystem subsystem to OPERABLE inoperable. status.
Prairie Island Unit 1- Amendment No. -l-6+ +8J.
Units 1 and 2 3.5.3-1 Unit 2- Amendment No.~ ill-