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Category:Letter type:L
MONTHYEARL-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report2019-09-19019 September 2019 Submittal of Revised Pressure and Temperature Limits Report L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)2019-08-27027 August 2019 Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019 Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For... L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2 L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-PI-19-003, Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)2019-02-0404 February 2019 Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-006, Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements2019-01-29029 January 2019 Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements L-PI-19-005, Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.692019-01-15015 January 2019 Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.69 L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018 Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805 2024-01-02
[Table view] Category:License-Operator
MONTHYEARML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML22270A2372022-09-26026 September 2022 Form 5.1-1 Post Exam Checklist IR 05000282/20223012022-08-31031 August 2022 NRC Initial License Examination Report 05000282/2022301; 05000306/2022301 ML22249A0062022-08-26026 August 2022 2.1-1 Examination Preparation Checklist for Prairie Island 08092022 ML22270A2252022-08-26026 August 2022 Ile Security Agreement - Final ML22249A0072022-08-19019 August 2022 Ile 2022 Post Exam Comments Letter ML22213A1852022-08-0808 August 2022 Plan, Operator Licensing Examination Approval ML22237A3022022-08-0808 August 2022 Ile 2.3-2 ML22237A3032022-08-0808 August 2022 Ile 2.3-4 ML22166A3892022-07-28028 July 2022 Issuance of Amendments 239 and 227 24-Month Operating Cycle ML22174A3902022-06-27027 June 2022 Licensed Operator Positive Fitness-For-Duty Test ML22237A3012022-05-27027 May 2022 Ile Licensee Letter Transmitting Proposed Exam and Test ML22242A3032022-03-24024 March 2022 2.3-1 Exam Outline Quality Checklist ML22242A3072022-03-24024 March 2022 3.4-1 Scenario Events & Evolutions Checklist RO & SRO ML22027A8012022-01-27027 January 2022 Confirmation of Initial License Examination ML21121A0002021-04-27027 April 2021 Preparation and Scheduling of Operator Licensing Examinations ML21110A5922021-04-19019 April 2021 GFE Results, March 2021 ML21082A4892021-03-23023 March 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information IR 05000282/20203012020-09-22022 September 2020 NRC Initial License Examination Report 05000282/2020301 and 05000306/2020301 ML20265A1722020-09-21021 September 2020 ES-201-1 L-PI-20-048, Post Exam Comments2020-09-21021 September 2020 Post Exam Comments ML20265A1802020-09-21021 September 2020 ES-403-1 L-PI-20-053, ES-201-32020-09-18018 September 2020 ES-201-3 ML20245E5482020-08-27027 August 2020 ES-D-1, Scenario Outline ML20252A2542020-08-27027 August 2020 Proposed facility-developed RO-SRO Written Examination ML20245E5792020-08-27027 August 2020 ES-301-6 ML20246G7462020-08-27027 August 2020 Ile As-Administered RO Admin JPMs ML20246G7432020-08-27027 August 2020 Ile As-Administered In-Plant JPMs ML20246G7322020-08-27027 August 2020 Ile As-Administered Simulator JPMs ML20245E5632020-08-27027 August 2020 ES-301-7 ML20245E5582020-08-27027 August 2020 ES-401-2, 3, 4, PWR Examination Outline ML20245E5822020-08-27027 August 2020 ES-201-2, Examination Outline Quality Checklist ML20245E5802020-08-27027 August 2020 75 Day Letter ML20245E5812020-08-27027 August 2020 ES-301-5, Transient and Event Checklist ML20252A2512020-08-27027 August 2020 Proposed Operating Test - Dynamic Simulator Scenarios ML20245E5692020-08-27027 August 2020 ES-401-9 ML20252A2482020-08-27027 August 2020 Proposed Operating Test - Walkthrough Portion JPMs ML20246G7542020-08-27027 August 2020 Ile As-Administered Scenarios ML20245E5702020-08-27027 August 2020 NRC Comments and Resolution on Licensee Outlines ML20245E5662020-08-27027 August 2020 ES-401-6 ML20245E5762020-08-27027 August 2020 ES-301-4 ML20246G7342020-08-27027 August 2020 Ile As-Administered SRO Admin JPMs ML20246G7402020-08-27027 August 2020 Ile As-Administered Written Exam ML20245E5742020-08-27027 August 2020 ES-301-3 ML20245E5642020-08-27027 August 2020 ES-401-4 ML20258A0162020-08-27027 August 2020 ES-401-6 ML20245E5452020-08-27027 August 2020 ES-301-1 and ES-301-2, Administrative Topics Outline ML20219A8402020-08-0707 August 2020 Operator Licensing Examination Approval ML20076F0592020-03-16016 March 2020 Preparation and Scheduling of Operator Licensing Examinations ML20023A2342020-01-23023 January 2020 Confirmation of Initial License Examination 2024-01-19
[Table view] Category:Other HQ and Regional Correspondence
[Table view] |
Text
_ Xcel EnergyJAN 2 6 2016 ,- ,L-PI-16-006
- ...... " " 'RIS 2015-05 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets Nos. 50-282 and 50-306 Renewed Facility Operating License Nos. DPR-42 and DPR-60 Operator Examination Updated Data for Prairie Island Nuclear Generating Plant
Reference:
- 1) NSPM to NRC, "Operator Examination Updated Data for Prairie Island Nuclear Generating Plant," (L-PI-15-067) dated August 4, 2015 Northern States Power Company, a Minnesota corporation (NSPM), dlbla Xcel Energy submitted on August 4, 2015 updated operator licensing examination data on NRC Form 536 for calendar years 2017 through 2020 for Prairie Island Nuclear Generating Plant (Reference 1).This was in response to the NRC Regulatory Issue Summary 2015-05, "Preparation and Scheduling of Operator Licensing Examinations", dated April 20, 2015. However, the class information that was submitted has been updated. A new NRC Form 536 for Prairie Island Nuclear Generating Plant operator licensing exam data is enclosed with this letter.If you have any questions regarding this request, please contact Chad Boegeman at (651) 267-7328.Regulatory Commitments This letter makes no new commitments or changes to any existing commitments.
Kevin Davison Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota Enclosure cc: Administrator, Region Ill, USNRC " Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR J1 {Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC -1717 Wakonade Drive East
651.388.1121 ENCLOSURE Operator Licensing Examination Data for Prairie Island Nuclear Generating Plant, Units I and 2 1 page follows NRC FORM 536 U. S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0131 EXPIRES: 10/31/2017
(,01-2015) fna Estimated burden per response to comply with this voluntary information collection request I
..,.>=hour.
This infonnation collection is used to plan budgets and resources for operator examinations.
Send comments regardting burden estimate to the FOIA, Privacy, and Information
= =, OPERALTOR LICENSING Collections Brenoh (f-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC% " EXAMVINATION DATA 20555-0001, or by internet e-mail to Infocollects.Resourcei~nrc.gov, and to the Desk Officer,"
of Information and Regulatory Affairs, NEOB-10202, (3150-0131), Office ot Management and Budget, Washington, DC 20503. Ifra means used to impose an information collection does not display a currently valid 0MB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
F~ACILUTY NRC REGION Prairie Island Nuclear Generating Plant III A. PROPOSED EXAMINATION PREPARATION SCHEDULE PROPOSED NUMBER CY2018 CY 2019 CY 2020 CY 2021 ESTIMATED NUMBER OF LICENSEE-PREPARED1010 EXAMINATIONS ESTIMATED NUMBER OF NRC-PREPARED0000 EXAMINATIONS B. INITIAL OPERATOR LICENSE EXAMINATIONS PROPOSED NUMBER CY 2018 CY 2019 CY 2020 CY 2021 NUMBER OF REACTOR6040 OPERATORS NUMBER OF SENIOR REACTOR OPERATORS -INSTANT 11 070 NUMBER OF SENIOR REACTOR1010 OPERATORS
-UPGRADE0 NUMBER OF SENIOR REACTOR0000 OPERATORS
-LIMITED0 PROPOSED DATES PRIMARY DATE 09/17/2018 06/08/2020 ALTERNATE DATE 09/24/2018 06/15/2020 C. PROPOSED GENERIC FUNDAMENTALS EXAMINATION (GFE) SCHEDULE CY 2016 cY 2018 PROPOSED _________
________NUBR MARCH JUNE SEPTEMBER DECEMBER MARCH JUNE SEPTEMBER DECEMBER ESTIMATED NUMBER OF 0 0 0 17 0 0 1 1 0 CANDIDATES NIRC FORM 536 (01-2015)
_ Xcel EnergyJAN 2 6 2016 ,- ,L-PI-16-006
- ...... " " 'RIS 2015-05 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets Nos. 50-282 and 50-306 Renewed Facility Operating License Nos. DPR-42 and DPR-60 Operator Examination Updated Data for Prairie Island Nuclear Generating Plant
Reference:
- 1) NSPM to NRC, "Operator Examination Updated Data for Prairie Island Nuclear Generating Plant," (L-PI-15-067) dated August 4, 2015 Northern States Power Company, a Minnesota corporation (NSPM), dlbla Xcel Energy submitted on August 4, 2015 updated operator licensing examination data on NRC Form 536 for calendar years 2017 through 2020 for Prairie Island Nuclear Generating Plant (Reference 1).This was in response to the NRC Regulatory Issue Summary 2015-05, "Preparation and Scheduling of Operator Licensing Examinations", dated April 20, 2015. However, the class information that was submitted has been updated. A new NRC Form 536 for Prairie Island Nuclear Generating Plant operator licensing exam data is enclosed with this letter.If you have any questions regarding this request, please contact Chad Boegeman at (651) 267-7328.Regulatory Commitments This letter makes no new commitments or changes to any existing commitments.
Kevin Davison Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota Enclosure cc: Administrator, Region Ill, USNRC " Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR J1 {Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC -1717 Wakonade Drive East
651.388.1121 ENCLOSURE Operator Licensing Examination Data for Prairie Island Nuclear Generating Plant, Units I and 2 1 page follows NRC FORM 536 U. S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0131 EXPIRES: 10/31/2017
(,01-2015) fna Estimated burden per response to comply with this voluntary information collection request I
..,.>=hour.
This infonnation collection is used to plan budgets and resources for operator examinations.
Send comments regardting burden estimate to the FOIA, Privacy, and Information
= =, OPERALTOR LICENSING Collections Brenoh (f-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC% " EXAMVINATION DATA 20555-0001, or by internet e-mail to Infocollects.Resourcei~nrc.gov, and to the Desk Officer,"
of Information and Regulatory Affairs, NEOB-10202, (3150-0131), Office ot Management and Budget, Washington, DC 20503. Ifra means used to impose an information collection does not display a currently valid 0MB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
F~ACILUTY NRC REGION Prairie Island Nuclear Generating Plant III A. PROPOSED EXAMINATION PREPARATION SCHEDULE PROPOSED NUMBER CY2018 CY 2019 CY 2020 CY 2021 ESTIMATED NUMBER OF LICENSEE-PREPARED1010 EXAMINATIONS ESTIMATED NUMBER OF NRC-PREPARED0000 EXAMINATIONS B. INITIAL OPERATOR LICENSE EXAMINATIONS PROPOSED NUMBER CY 2018 CY 2019 CY 2020 CY 2021 NUMBER OF REACTOR6040 OPERATORS NUMBER OF SENIOR REACTOR OPERATORS -INSTANT 11 070 NUMBER OF SENIOR REACTOR1010 OPERATORS
-UPGRADE0 NUMBER OF SENIOR REACTOR0000 OPERATORS
-LIMITED0 PROPOSED DATES PRIMARY DATE 09/17/2018 06/08/2020 ALTERNATE DATE 09/24/2018 06/15/2020 C. PROPOSED GENERIC FUNDAMENTALS EXAMINATION (GFE) SCHEDULE CY 2016 cY 2018 PROPOSED _________
________NUBR MARCH JUNE SEPTEMBER DECEMBER MARCH JUNE SEPTEMBER DECEMBER ESTIMATED NUMBER OF 0 0 0 17 0 0 1 1 0 CANDIDATES NIRC FORM 536 (01-2015)