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MONTHYEARL-PI-10-098, Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.102010-10-14014 October 2010 Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 Project stage: Request 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. Project stage: Request ML1104702792011-02-16016 February 2011 Notice of Forthcoming Meeting with Licensee for Prairie Island Nuclear Generating Plant, Unit 1 to Discuss License Amendment Request to Revise Surveillance Requirement Footnote in Technical Specification 3.8.1, AC Sources - Operating. Project stage: Meeting ML1104904292011-02-16016 February 2011 Acceptance Review of LAR to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating Project stage: Acceptance Review ML1106600792011-03-0303 March 2011 March 3, 2011 Meeting Handouts - Revise Footnote in TS 3.8.1, Prairie Island Nuclear Generating Plant Project stage: Meeting ML1106104752011-03-0404 March 2011 Request for Additional Information Related to Request to Revise the Technical Specification 3.8.1, AC Sources - Operating, Footnote Requiring Battery Charger Modifications Project stage: RAI L-PI-11-024, Supplement to License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating.2011-03-15015 March 2011 Supplement to License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating. Project stage: Supplement ML1107401932011-03-22022 March 2011 Summary of March 3, 2011, Meeting to Discuss the Licensee'S February 3, 2011, License Amendment Request to Revise Surveillance Requirement Footnote in Technical Specification 3.8.1, AC Sources - Operating. Project stage: Meeting ML1110205512011-04-29029 April 2011 Issuance of Amendment Revision to Surveillance Requirements Footnote in Technical Specification 3.8.1, AC Sources - Operating Project stage: Approval 2011-03-15
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Category:Letter type:L
MONTHYEARL-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report 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) 2024-06-05
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption ML24155A2222024-05-28028 May 2024 Methodology Evaluation Report for Elimination of Response Time Testing Prairie Island Reactor Trip System Rev. 1 ML23215A1672023-12-15015 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 2024-06-03
[Table view] Category:Technical Specifications
MONTHYEARML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML22357A1002023-03-31031 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 2024-05-01
[Table view] |
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L-PI-11-016 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit I Docket 50-282 License No. DPR-42 License Amendment Request (LAR) to Revise Surveillance Reauirement (SR) Footnote in Technical Specification (TS) 3.8.1, "AC Sources - Qperatina" Pursuant to 10 CFR 50.90, the Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), hereby requests an amendment to the TS for the Prairie Island Nuclear Generating Plant (PINGP), Unit 1, to revise the TS 3.8.1, "AC Sources - Operating", SR 3.8.1 .I0 footnote requiring battery charger modifications. Although the purpose of this SR is to demonstrate emergency diesel generator (EDG) operation during a loss of offsite power, the footnote relates specifically to the Unit 1 12 Battery Charger. NSPM evaluated the proposed changes in accordance with 10 CFR 50.92 and concluded that they involve no significant hazards consideration. The enclosure to this letter, "Evaluation of the Proposed Changes" contains the licensee's evaluation of the proposed changes. NSPM requests expedited review of this LAR and approval by May 6, 201 1. The current SR 3.8.1 .I0 footnote requires testing of the Unit 1 02 EDG following implementation of 12 Battery Charger modifications during the Unit I Spring 201 1 refueling outage.
While performing the engineering associated with the modifications required by the footnote, NSPM identified different battery charger modifications that are technologically superior to those considered when the footnote was added to the TS. These different battery charger modifications meet the intent of the footnote, that is, they assure that D2 and its associated 12 Battery Charger will perform their required safety functions, however, the modifications do not meet the letter of the current footnote wording.
To meet TS requirements and allow D2 to be tested with the different battery charger modifications during the Spring 201 1 refueling outage, approval of this LAR is requested by May 6,201 1. Upon NRC approval, NSPM requests 15 days to implement the associated changes. In accordance with 10 CFR 50.91, NSPM is 171 7 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone:
651.388.1 121 Document Control Desk Page 2 notifying the State of Minnesota of this LAR by transmit.ting a copy of this letter and enclosure to the designated State Official.
If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1 121, 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 FE8 0 S 2011 Mark A. Schimmel 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, USNRC State of Minnesota ENCLOSURE Evaluation of the Proposed Changas License Amendment Requsst (LAR) to Revise Survsillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, "AC Sources -. Operating" 1.
SUMMARY
DESCRIPTION
- 2. DETAILED DESCRIPTION 2.1 Proposed Changes 2.2 Background
- 3. TECHNICAL EVALUATION
- 4. REGULATORY SAFETY ANALYSIS 4.1 Applicable Regulatary Requirementslcriteria 4.2 Precedent 4.3 Significant Hazards Consideration 4.4 Conclusions
- 5. ENVIRONMENTAL CONSIDERATION
- 6. REFERENCES ATTACHMENTS:
- 1. Technical Specification Pages (Markup)
- 2. Technical Specification Bases Pages (Markup)
- 3. Technical Specification Pages (Retyped)
Page 1 of 12 Enclosure TS 3.8.1 Footnote NSPM 1.
SUMMARY
DESCRIPTION This LAR is a request to amend Operating License OPR-42 for Prairie Island Nuclear Generating Plant (PINGP) Unit
- 1. Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), requests Nuclear Regulatory Commission (NRC) review and approval of proposed revisions to TS 3.8.1, "AC Sources - Operating", SR 3.8.1 .I0 footnote. Although the purpose of the SR is to demonstrate the emergency diesel generator (EDG) operation during a loss of offsite power with safety injection, the SR footnote relates specifically to the Unit 1 12 Battery Charger modifications.
The proposed changes will continue to assure that the 02 EDG and associated 12 Battery Charger perform their required safety functions, but allow use of different methods than required by the current footnote, NSPM requests review and approval of the revised SR footnote. 2. DETAILED DESCRIPTION 2.1 Proposed Chanqes Brief descriptions of the associated proposed TS changes are provided below along with discussion of the justification for the changes. The specific wording changes to the TS are provided in Attachments 1 and 3 to this enclosure.
TS 3.8.1, "AC Sources - Operating", SR 3.8.1.10 Footnote:
This LAR proposes to revise the SR 3.8.1.10 footnote by removing the requirement to automatically shed the 12 Battery Charger from its bus. This change is acceptable because NSPM proposes to install a modification which assures 12 Battery Charger will automatically perform its safety function without shedding from the bus. Although Bases changes are not a part of this LAR, Attachment 2 to this enclosure includes a marked up Bases page for information. The changes proposed in Attachment 2 are directly related to the changes proposed to TS 3.8.1. In summary these changes are acceptable because the revised SR will continue to demonstrate that the EDGs will perform their safety functions.
2.2 Backaround In October 201 0, NSPM determined that Unit 1 EDG D2 was inoperable due to incorrect alignment of the 12 Battery Charger during performance of the surveillance procedure (SP) which demonstrates the requirements of SR 3.8.1 .I0 are met. During Page 2 of 12 Enclosure TS 3.8.1 Footnote NSPM the course of NRC review and approval of an exigent L.AR which allowed 02 to be considered operable without 12 Battery Charger included in performance of the SP, a footnote was added to SR 3.8.1,10 which specified installation of 12 Battery Charger modifications to "automatically shed" the battery charger from its normal bus and "then automatically repower" the charger from its normal bus. NSPM requests review and approval of a revised SR 3.8,1 .I0 footnote which will allow installation of battery charger modifications that assure 12 Battery Charger performs its safety functions without automatically shedding the charger from its bus, NSPM requests expedited review of this LAR and approval by May 6, 201 1. The current SR 3.8.1 .I 0 footnote requires testing of the Unit 1 02 EDG following installation of 12 Battery Charger modifications during the Unit 1 Spring 201 1 refueling outage.
While performing the engineering associated with the modifications required by the current footnote, NSPM identified different battery charger modifications that are technologically superior to those considered when the footnote was added to the TS. These different battery charger modifications meet the intent of the footnote, that is, they assure that D2 and its associated 12 Battery Charger will perform their required safety functions. To allow D2 to be tested during the Spring 201 1 refueling outage with battery charger modifications that meet TS requirements, approval of this MR is requested by May 6,201 1. With the TS changes proposed in this LAR the plant will continue to operate safely and the health and welfare of the public is protected.
- 3. TECHNICAL EVALUATION PINGP is a two unit plant located on the right bank of the Mississippi River approximately 6 miles northwest of the city of Red Wing, Minnesota.
The facility is owned and operated by NSPM. Each unit at PINGP employs a two-loop pressurized water reactor designed and supplied by Westinghouse Electric Corporation. The initial PINGP application for a Construction Permit and Operating License was submitted to the Atomic Energy Commission (AEC) in April 1967. The Final Safety Analysis Report (FSAR) was submitted for application of an Operating License in January 1971. Unit 1 began commercial operation in December 1973 and Unit 2 began commercial operation in December 1974.
PINGP was designed and constructed to comply with NSPM's understanding of the intent of the Atomic Energy Commission (AEC) General Design Criteria (GDC) for Nuclear Power Plant Construction Permits, as proposed on July 10, 1967. PINGP was not licensed to NUREG-0800, "Standard Review Plan (SRP)" and was not part of the NRC Systematic Evaluation Program (SEP).
Enclosure TS 3.8.1 Footnote NSPM Current TS Requirements Basis and Limitations Xi B TS 3.8.1 SR 3.8.1.10 footnote currently states:
- A modification will be installed during or prior to the Unit 1 201 1 refueling outage to automatically shed the "1 Battery Charger from its normal bus and then automatically repower the charger from the bus within 60 seconds. Compliance with this SR will be demonstrated after implementation of the modification.
This footnote was incorporated into the TS by license amendment 198 (LA 198), ML102910206, for Unit 1, dated October 22, 2010. The purpose of this LA was to revise Technical Specification (TS) Surveillance Requirement (SR) 3.8.1.10(c) to allow 02 to be considered operable without the PlNGP Unit 1 12 Battery Charger energized during the Unit 1 integrated safety injection (SI) test, until completion of a battery charger modification during the Unit I 201 1 refueling outage.
This TS relief in LA 198 was required because NSPM determined that during the pre- initiation and restoration checks for the integrated SI test surveillance procedure, the 12 Battery Charger was manually turned off during pre-initiation and manually turned on during the equipment restoration section after completion of the test.
The 12 Battery Charger was designed to remain connected to the bus upon loss of offsite power (LOOP) and reenergize when the EDG repowers the bus during an SI and LOOP event. This condition brought into question the operability of 02 EDG, during an SI and LOOP event, and the adequacy of the surveillance procedure, as written, to meet SR 3.8.1 .I0 requirements for verification of load sequencing every 24 months.
This guidance to manually control the 12 Battery Charger during SP performance was incorporated into the procedures to address lockup of the 12 Battery Charger due to low input voltage during SP performance in the late 1990's. The intent of the SR footnote added by LA 198 was to assure that modifications are installed and tested prior to plant startup from the Unit 1 Spring 201 1 refueling outage to assure the 12 Battery Charger will perform its safety functions through automatic controls in accordance with the original battery charger design intent without manual actions. In the LAR dated October 14, 2010, ML102880105, which was the precursor to NRC issuance of LA 198, NSPM stated:
NSPM is planning a modification to the 12 Battery Charger that will automatically shed the battery charger during an undervoltage event (e.g. LOOP, Sl with LOOP or other undervoltage condition) and then repower the battery charger back on the bus within the 60 seconds required by the current TS. In the course of pursuing the modifications under consideration when the LAR dated October 14, 2010 was written, NSPM identified a different modification that assures the battery charger will perform its safety functions through automatic controls in accordance with the original design intent without manual actions and without shedding Page 4 of 12 Enclosure TS 3.8.1 Footnote NSPM from its bus. Since literal compliance with the wording of the current footnote would require shedding from the bus, NSPM requests the proposed revision to the SR 3.8.1 .I0 footnote to allow installation of the different modification, Proposed Changes This LAR proposes to replace the TS 3.8.1 SR 3.8.1 .I0 footnote with the following footnote:
- A modification will be installed during or prior to the Unit I 201 1 refueling outage to assure the 12 Battery Charger is automatically powered from its normal bus within 60 seconds. Compliance with this SR will be demonstrated after implementation of the modification. Technical Basis for Change 1 The purpose of the footnote to SR 3.8.1 .I0 is to require installation of battery charger modifications to assure the 12 Battery Charger performs its safety function. As discussed in the October 14,2010 LAR, ML102880105, the problem with the 12 Battery Charger is:
As the charger is starting up, the firing angle of the Silicon Controlled Rectifiers (SCRs) internal to the charger control circuitry advances to increase the charger output. The angle advances until the float voltage setpoint or current limit is reached. When the voltage drops on the incoming AC source, the firing angle of the SCRs advances further to compensate as it tries to maintain a constant DC output. When the AC input voltage drops low enough during sequence step 4, the firing angle actually advances further and up to the setpoint at which the SCRs become reverse biased. The SCRs need to be forward biased to be able to conduct and produce DC output. Therefore, when the SCRs become reverse biased, they no longer are able to conduct and produce any output. The condition essentially "locks up" the charger as the SCRs are stuck in a reverse biased condition and cannot return to a forward biased state without removing the AC input power from the charger to allow the control circuit capacitors to discharge. The charger can then be started up normally by returning AC power. Various options for resolution of the 12 Battery Charger lockup issue were considered. One of the options considered for correction of the issue was battery charger replacement. During initial investigations this was identified as a desirable option. However, preliminary discussions with vendors led to the conclusion that this could not be done in the time allowed due to expected durations for engineering development, qualification, manufacturing, and testing. The option described previously in the LAR dated October 14, 2010, ML102880105, which provided the basis for the SR 3.8.1 .I0 footnote, was to provide a new AC input power source and control the AC input power with a control circuit using an external Page 5 of 12 Enclosure TS 3.8.1 Footnote NSPM voltage sensing and load sequencing based control circuit. This control circuit would prevent the existing C&D Technologies, Inc. (C&D) battery chargers from being exposed to a low AC input voltage condition that could cause reverse biasing of the Silicone Controlled Rectifiers (SCRs) and result in lockup of the charger. This option was favored because it could be implemented with mostly standard catalog products and the work efforts were all within NSPM control, This option provided highest confidence in NSPM ability to meet the schedule to resolve the condition by the Unit 1 Spring refueling outage.
As the battery charger modification engineering efforts progressed, NSPM became aware of Ametek Solidstate Controls Incorporated (SCI) battery chargers installed at the Point Beach Nuclear Plant (PBNP) that could meet the PINGP detailed design requirements and would not be susceptible to the PINGP C&D charger lockup issue.
However, the PBNP chargers did not meet the seismic and physical dimension requirements for application at PINGP. Discussions with Ametek identified Ametek SCI battery chargers installed at the Vogtle Electric Generating Plant (VEGP) for which the charger ratings and qualifications enveloped the PINGP requirements and the physical dimensions were also compatible with PINGP requirements. Also, Ametek confirmed that the PINGP expedited schedule could be met if NSPM ordered chargers based on the mature VEGP design. Control features of the Ametek SCI chargers ensure that they are not susceptible to conditions which cause lockup of the C&D chargers at PINGP. The Ametek SCI chargers contain an internal control relay whose purpose is to prevent back feeding the control circuit board. The relay senses incoming AC line voltage and causes a shut off of the charger when the AC voltage drops below the relay dropout and restarts when the voltage returned to levels above the pickup.
The shutoff is instantaneous and the reset is controlled by the startup time delay of a few seconds. To provide assurance beyond engineering design review of the control circuit operation, the PBNP prototype charger was returned to Ametek for testing to demonstrate charger capabilities, operation, shutdown, and automatic restart during anticipated voltage transients outside the nameplate rating of the chargers. This information was used as a decision making aid for the final PINGP solution. Testing was performed above and below nameplate ratings to validate response because PINGP has known voltage excursions outside the nameplate range and automatic recovery of the charger following such transients is required for the battery charger to perform required safety functions.
The prototype charger was tested under varying load conditions, current limit set points, voltage fluctuations, and transient conditions. The data collected was informational in nature. Final documentation of charger capabilities, shut off and reset points, time delays, and other operating conditions will be documented in factory acceptance test procedures under the Ametek Quality Assurance program according to the NSPM purchase specification.
NSPM proposes to replace the 12 Battery Charger with a new safety-related battery charger manufactured by Ametek SCI. Replacement of 12 Battery Charger is Page 6 of 12 NSPM Enclosure TS 3.8.1 Footnote technologically superior and economicafly advantageous over the option on which the SR 3.8.1 .I0 footnote was based: repowering the existing chargers and creating an external voltage sensing and load sequencing based control circuit. Technical and economic advantages include the following: The design is simpler and all required logic is internal to charger. This is very advantageous since the substance of the modification is pecformed in the controlled environment of a fabrication shop.
Testing of the new battery charger will be performed in advance of installation. Engineering and procurement resources can be focused on the battery charger, its qualifications, performance and schedule as opposed to procurement of myriads of components and construction materials. This also reduces procurement risk since there are fewer components required to meet the schedule, Battery charger replacement is less intrusive on other plant systems. For example, the battery charger shedding modification would require use of the last spare breaker on Bus 16, new power cable installation, fire penetration work when routing new cables, and additions to the load sequencer cabinets. Simple component replacement does not require design coordination with existing bus voltage relay settings or logic, The current plant configuration includes maintenance sources at the 480V level which provide additional flexibility in outage electrical lineups. Simple replacement of the 12 Battery Charger preserves this plant feature. This proposed modification significantly reduces outage work time and outage testing time which frees management and engineering resources to focus on other safety significant activities.
Because the Ametek SCI battery charger is designed to cope with low input voltage, there is no need to pursue modifications which shed the battery charger from its bus. To allow installation of the Ametek SCI battery charger as the resolution of the 12 Battery Charger lockup issue, the SR 3.8.1.10 footnote requires revision since it specifically states that a modification will be installed that automatically sheds the 12 Battery Charger from its bus. Conclusions The 12 Battery Charger lockup has been experienced during voltage transients associated with loss of offsite power and emergency diesel generator load sequencing tests which prevented the battery charger from automatically performing its safety function.
In a previous LAR to allow D2 to be considered operable without including the 12 Battery Charger as a load during performance of SR 3.8.1 .lo, a footnote was added to this SR to require modifications to correct the 12 Battery Charger lockup issue. Based on engineering considerations at the time the previous LAR was submitted, the footnote includes specific requirements for the battery charger to be automatically shed from and repowered by its normal bus. Subsequently NSPM has identified a Enclosure TS 3.8.1 Footnote NSPM replacement battery charger that solves the lockup issue and determined that a battery charger replacement modification is technologically superior and economically advantageous to a modification which automatically sheds and repowers the battery charger. In this LAR NSPM requests NRC review and approval of a revised SR 3.8.1.10 footnote that will allow installation of a different modification, that is, 12 Battery Charger replacement.
The revised footnote assures that the D2 EDG and associated 12 Battery Charger perform their required safety functions without automatic shedding of the battery charger from its bus. Since the proposed modifications assure D2 and 12 Battery Charger perform their safety functions, operation, maintenance and testing of the Prairie Island Nuclear Generating Plant with the TS revisions proposed in this LAR will continue to protect the health and safety of the public, 4. REGULATORY SAFETY ANALYSIS 4.1 Applicable Regulatory Requirementslcriteria Title 10 Code of Federal Regulations 50.36, "Technical soecifications": (c) Technical specifications will include items in the following categories:
- 3) Sun/eillance requirements. Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. Technical Specification 3.8.1, "AC Sources - Operating", includes Surveillance Requirement (SR) 3.8.1.10, to demonstrate emergency diesel generator operation during a loss of offsite power in conjunction with a safety injection actuation. A footnote to SR 3.8.1. I0 requires battery charger modifications that automatically shed and repower the 12 Battery Charger. This license amendment request proposes to revise the SR 3.8.1 .I0 footnote to allow implementation of a battery charger modification that assures the 02 emergency diesel generator and its associated 12 Battery Charger perform their safety function without shedding the battery charger from its bus. With these proposed changes, the Technical Specifications will continue to assure that the necessary quality of the emergency diesel generators and their components is maintained and the limiting conditions for operation of these systems will continue to be met. Thus with the changes proposed in this license amendment request, the requirements of Title 10 CFR 50.36 continue to be met. Page 8 of 12 Enclosure TS 3.8.1 Footnote NSPM General Design Criteria The construction of the Prairie Island Nuclear Generating Plant was significantly completed prior to issuance of 10 CFR 50, Appendix A, General Design Criteria.
The Prairie lsland Nuclear Generating Plant was designed and constructed to comply with the Atomic Energy Commission General Design Criteria (AEC GDC) as proposed on July 10, 1967 as described in the plant Updated Safety Analysis Report.
AEC GDC proposed Criteria 24 and 39 provide design guidance for the operating capability of on- site emergency power systems.
Criterion 24 - Emeraencv Power For Protection Svstems In the event of loss of all offsite power, sufficient alternate sources of power shall be provided to permit the required functioning of the protection systems. During a loss of offsite power, AEC GDC Criterion 24 is met through the redundant source of emergency power from emergency diesel generators installed at the plant.
The instrumentation and controls portions of the protection systems are supplied from the 125 VDC station batteries during the diesel startup period. This license amendment request proposes to revise a footnote to the Technical Specification surveillance requirements to demonstrate emergency diesel generator operation during a loss of offsite power in conjunction with a safety injection actuation. The revised footnote will allow implementation of a battery charger modification which assures the 02 emergency diesel generator and its associated 12 Battery Charger perform their safety function without shedding the battery charger from its bus.
With these changes, the AEC GDC stated above will continue to be met when the plant is operated with the plant Technical Specifications revised as proposed.
Criterion 39 - Emersencv Power For Engineered Safetv Features Alternate power systems shall be provided and designed with adequate independency, redundancy, capacity, and testability to permit the functioning required of the engineered safety features.
As a minimum, the onsite power system and the offsite power system shall each, independently, provide this capacity assuming a failure of a single active component in each power system. AEC GDC Criterion 39 is partially met through the redundant source of emergency power from emergency diesel generators installed at the plant. This license amendment request proposes to revise a footnote to the Technical Specification surveillance requirements to demonstrate emergency diesel generator operation during a loss of offsite power in conjunction with a safety injection actuation. The revised footnote will allow implementation of a battery charger modification which assures the D2 emergency diesel generator and its associated 12 Battery Charger perform their safety function without shedding the battery charger from its bus. With these changes, the AEC GDC stated above will continue to be met when the plant is operated with the plant Technical Specifications revised as proposed. Page 9 of 12 Enclosure TS 3.8.1 Footnote NSPM Thus with the changes proposed in this license amendment request, the requirements of AEC GDC 24 and 39 continue to be met and the plant Technical Specifications will continue to provide the basis for safe plant operation.
4.2 Precedent The Surveillance Requirement 3.8.1 .I0 footnote is a one-time application Technical Specification requirement which is specific to Prairie island Nuclear Generating Plant Unit 1. There are many industry examples of one-time plant specific Technical Specification footnotes, however, Northern States Power Company, a Minnesota corporation (hereafter "NSPM"), is not aware of any that apply specifically to battery charger modification requirements.
Nor is NSPM aware of precedent for a license amendment request which modifies a one-time application Technical Specification footnote.
4.3 Sianificant Hazards Consideration Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below: 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 footnote to the emergency diesel generator Technical Specification surveillance requirement for loss of offsite power with safety injection actuation. The proposed footnote revision removes some specific requirements for battery charger modifications but will continue to assure that the applicable emergency diesel generator and its associated battery charger perform their required safety functions.
The emergency diesel generators and their associated battery chargers are not accident initiators and therefore, these changes do not involve a significant increase the probability of an accident. The proposed changes to the Technical Specification footnote will assure that the emergency diesel generator and the associated battery charger continue to perform their required safety function. Since the emergency diesel generator and the associated battery charger will provide required electrical power as assumed in the accident analyses, the results of the previous accident analyses are not changed and the changes proposed in this license amendment request do not involve a significant increase in the consequences of an accident. Page 10 of 12 Enclosure TS 3.8.1 Footnote NSPM Therefore, the proposed 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 footnote to the emergency diesel generator Technical Specification surveillance requirement for loss of offsite power with safety injection actuation, The proposed footnote revision removes some specific requirements for battery charger modifications but will continue to assure that the applicable emergency diesel generator and its associated battery charger perform their required safety functions. No new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of the proposed change. The proposed change does not challenge the performance or integrity of any safety-related system. The proposed change does involve modification of plant battery chargers, however, failures of battery chargers has been previously considered and bounded by assuming one safety related train of equipment fails. The modified battery chargers do not create new failure modes or mechanisms and no new accident precursors are generated. Surveillance testing requirements for the emergency diesel generator and battery charger will continue to demonstrate that the Limiting Conditions for Operation are met and the system components are functional. Therefore, the proposed 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 footnote to the emergency diesel generator Technical Specification surveillance requirement for loss of offsite power with safety injection actuation. The proposed footnote revision removes some specific requirements for battery charger modifications but will continue to assure that the applicable emergency diesel generator and its associated battery charger perform their required safety functions.
The proposed Technical Specification footnote change does not affect the availability, operability, or performance of safety-related systems and components: the affected emergency diesel generator and its associated battery will continue to perform their safety functions. The ability of operable structures, Page 11 of 12 Enclosure TS 3.8.1 Footnote NSPM systems, and components to pe~orm their designated safety function is unaffected by this proposed change.
The proposed change does not involve a significant reduction in a margin of safety because the proposed footnote changes do not reduce the margin of safety that exists in the present Technical Specifications or Updated Safety Analysis Report, The operability requirements of the Technical Specifications are consistent with the initial condition assumptions of the safety analyses and the surveillance testing requirements will continue to demonstrate the operability of the emergency diesel generator.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety. Based on the above, 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, 4.4 Conclusions In conclusion, based on the considerations discussed in above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. 5. ENVIRONMENTAL CONSIDERATION A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(~)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
- 6. REFERENCES None Page 12 of 12 ENCLOSURE, ATTACHMENT I Technical Specification Pages (Markup) 3.8.1-10 1 page follows SURVEILIANCI:
RI.:QI JIKIWNI:NrX'S (conti~rncd)
Sl JRV1311,I
'ANCT: -----. -"-&-- -"* -" . -- ------ - -- --, SR 3.8.1.10 ............................
NO']'f{S-----..-..-
------ ---- 1. All I9C; starts inuy be preceded by an engine prelubr: pcri~d. 2. 'l'his Surveillance shall not be perfbrmed in MODE 1, 2, 3, or 4, 3. 12 Battery Charger not required to be energized in SR 3 .8,1,10(c) until coinpietion of Unit I 20 1 1 refueling outage." a. De-energization of emergency buses; VerifL on an actual or simulated loss of ofLsite power signal in conjunction with an actual or simulated safety injection actuation signal:
- b. Load shedding from emergency buses; and 24 months
- c. DG auto-starts from standby condition and energizes emergency loads in 5 60 seconds.
SR 3.8.1.11 ............................
NOTE me------------------
All DG starts may be preceded by an engine prelube period. ................................................................
I *A modification will be installed during or prior to the Unit 1 201 1 refueling outage to- , ., , from its normal bus onds. Compliance with this SR will be demonstrated after implementation of the modification.
VerifL on an actual or simulated loss of offsite power signal that the DG auto-starts from standby condition.
Prairie Island Units 1 and 2 24 months Unit 1 - Amendment No. 44-8 4% 1 3.8.1-10 Unit 2 - Amendment No. 149 ENCLOSURE, ATTACHMENT 2 Technical Specification Basis (Markup) 13 3.8."122 1 page follows SU12.VElldI.,ANC~~~
Sj~--3-L~~Lj-L~l f-tE~QllllU IMEN'IS (continued) 111 thc c\*etlt ot'a IX3A coinciricr~t tvitli a loss c)f'oN'site po\\er, the 1)Cis arc rccl~~ircd to ~~ipply tlic necessary powct' to 11S1: systcius sr3 that the fi~el, IKS, and cotlt:iilitnc~~t dcsigx~ limits arc not cxcccded.
'I'his S~irvcillar~cc dctnoi~sirittcs tllc 1X; operatioll cturing a loss of' oSiBite popvcr actitatio~~ test signal in conjunction with an SX actuation signal. In lieu of actual dctnonstrc~tion ot'cut~ncction and loading oSel~~ergency loads, testing that adequately shows the capability of'the UCi system to pcrfbrtll these fiincticrns is acceptable.
'I'his testing may include any series of sequential, overlapping, or total steps so that the entire connection and loading sequence is verified.
'I'hc Frcq~iency of 24 months takes into consideration unit conditions required to pcrfbnl~ the Surveillance and is intended to be consistent with an expected fiiel cycle length 01'24 months, 'This SR is modified by t-wethree Notes. The reason for Note 1 is to minimize wear and tear on the DGs during testing. The reason fir Note 2 is that the performance of the Surveillance would remove a required offsite circuit from service, perturb the electrical distribution system, and challenge safety systems. Notc 3 is providcd to allow 132 I)(; to bc OPtlIZAf31,I':
without requiring the 12 13attc1-y Charger to be cnesgi;led until coniplction of'thc (!!lit 1 20U1 ~.cftte_lingoutag~:.
This Surveillance demonstrates the as designed operation of the standby power sources during loss of the offsite source. This test verifies DG starts on the loss of offsite power. Tests of other design features associated with loss of offsite power are satisfied by SR 3.8.1.10.
Prairie Island Units 1 and 2 Unit 1 - Revision 4-98 B 3.8.1-22 Unit 2 - Revision 4-98 ENCLOSURE, ATTACHMENT 3 Technical Spacification Pages (Retyped) 3.8.1-10 1 page follows AC Sources-Operat ing 3.8.1 2. 'T'his Surveillar~cc slrall not be perfc>rn~cd irz MOUE I, 2,3, or 4, SURVEILLANCI', RI3QllIR13Mt:N'l'S (contixluc - - SUIIV13IIdf,ANCE 1:JtIQt Ji34CY 3. 12 Battery Charger not requircd to be energized in SR 3.8.1 .lO(c) until completion of Unit 1 201 1 refueling outage,*
-------- -""-----""-------.."-"A
% ---+---- ---.--- SR 3,8.1,10 ------ ------- --------------..
N()'f'f:S
........................
I. All I>G starts nlay he prcccded by an enginc prclubc period. Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated safety injection actuation signal:
- a. De-energization of emergency buses;
- b. Load shedding from emergency buses; and
- c. DG auto-starts from standby condition and energizes emergency loads in 5 60 seconds. 24 months SR 3.8.1.11 ............................
NOTE ---------------
--- - - - ---- -- - All DG starts may be preceded by an engine prelube period. ................................................................
Verify on an actual or simulated loss of offsite power signal that the DG auto-starts from standby condition. 24 months I *A modification will be installed during or prior to the Unit 1 20 1 1 refueling outage to assure the 12 Battery Charger is automatically powered from its normal bus within 60 seconds. Compliance with this SR will be demonstrated after implementation of the modification.
Prairie Island Units 1 and 2 Unit 1 - Amendment No.
4-58 4-98 1 3.8.1-10 Unit 2 - Amendment No. 149