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MONTHYEARML16007A4602016-01-0707 January 2016 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance Review for License Amendment Request Supporting Spent Fuel Pool Criticality TS Changes Project stage: Acceptance Review ML16144A8052016-05-23023 May 2016 Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Cover Letter Response to RAI Project stage: Response to RAI ML16160A0772016-06-24024 June 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance L-PI-16-100, Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes2017-02-16016 February 2017 Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes Project stage: Response to RAI ML17066A3732017-03-0909 March 2017 Spent Fuel Pool Criticality Technical Specification Changes Round 2 Request for Additional Information Public Meeting: March 9, 2017 Project stage: Meeting ML17093A6012017-04-0606 April 2017 March 9, 2017, Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Spent Fuel Pool Criticality License Amendment Request Project stage: Meeting L-PI-17-014, Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121...2017-04-19019 April 2017 Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121... Project stage: Meeting ML17279A1242017-09-30030 September 2017 Enclosure 5 to L-PI-17-041, Westinghouse WCAP-17400-NP, Supplemental 1, Revision 2, Spent Fuel Pool Criticality Safety Analysis Supplemental Analysis Including the Storage of Ifba Bearing Fuel Project stage: Supplement ML17279A1202017-10-0404 October 2017 Response to Request for Additional Information Re License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes Project stage: Response to RAI L-PI-17-041, Enclosure 6 to L-PI-17-041, Westinghouse Affidavits2017-10-0404 October 2017 Enclosure 6 to L-PI-17-041, Westinghouse Affidavits Project stage: Other ML17279A1212017-10-0404 October 2017 Enclosure 2 to L-PI-17-041, Westinghouse-Prepared RAI Responses CE-17-3, Rev. 1, Attachment 2 and Enclosure 3, Marked-Up Technical Specification Page 4.0-7 Project stage: Other ML17313B1902017-11-13013 November 2017 Request for Withholding Information from Public Disclosure (CAC Nos. MF7121 and MF7122; EPID L-2015-LLA-0002) Project stage: Withholding Request Acceptance ML17334A1782017-11-30030 November 2017 Issuance of Amendment Request Related to Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121 and MF7122, EPID L-2015-LLA-0002) Non-Proprietary Project stage: Approval 2017-11-30
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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:Meeting Summary
MONTHYEARML23184A0862023-07-11011 July 2023 6/23/2023 Summary of Pre Application Public Meeting with Xcel Energy on Prairie Island ISFSI Amendment Application ML23179A2102023-06-28028 June 2023 Summary of June 5, 2023, Public Meeting with Northern States Power Company Regarding Neutron Fluence Values for Reactor Pressure Vessel Welds ML23157A0232023-06-0606 June 2023 Summary of the May 24, 2023, Public Outreach to Discuss the NRC 2022 End-of-Cycle Plant Performance Assessment of Prairie Island Nuclear Generating Plant, Units 1 and 2 ML23123A3942023-05-15015 May 2023 Summary of Public Meeting with Northern States Power Company Regarding Planned License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water System ML22130A7172022-05-10010 May 2022 Summary of the May 3, 2022, Public Outreach to Discuss the NRC 2021 End-Of-Cycle Plant Performance Assessment of Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 ML21294A0442021-11-0808 November 2021 Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a License Amendment to Extended the Allowed Outage Time for the Vertical Motor Driven Cooling Water System Pump ML21229A1692021-08-23023 August 2021 Summary of August 11, 2021, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a Planned License Amendment Allow Bypass Testing of the Power Range Nuclear Instrumentation System Channels ML21167A1842021-06-16016 June 2021 Summary of the June 9, 2021, Public Outreach to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 ML21137A1042021-05-20020 May 2021 Summary of May 6, 2021, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a Planned License Amendment to Transition to a 24 Month Operating Cycle ML21040A4612021-02-11011 February 2021 Summary of February 3, 2021, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a Planned License Amendment to Combine the Emergency Plans and Create a Common Emergency Operations Facility ML20296A2382020-11-0303 November 2020 Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the License Amendment to Adopt TSTF-505 Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20274A2442020-10-16016 October 2020 Summary of 9/23/2020 Meeting with Northern States Power Co., Doing Business as Xcel Energy, on Potential License Exemption Request Related to Biennal Emergency Preparedness Exercise for Prairie Island Nuclear Generating Plant, Units 1 & 2 ML20216A6452020-08-0303 August 2020 Summary of the July 16, 2020, Public Webinar to Discuss the NRC 2019 End-of-Cycle Plant Performance Assessment of the Prairie Island Generating Plant ML20114E2302020-04-23023 April 2020 Meeting Summary from Call with S. Beimers Mnshpo and NRC January 2020 Prairie Island ISFSI EA ML20111A1322020-04-21021 April 2020 April 9, 2020, Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request Related to Adopt TSTF-569 at Prairie Island Nuclear Generating Plant, Unit 1 and 2 ML20057D3912020-03-0909 March 2020 Summary of February 18, 2020, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Ament Request Related to Low Temperature Overpressurization Protection ML19347D1592020-01-0707 January 2020 Summary of December 12, 2019, Meeting with Northern States Power Co., Doing Business as Xcel Energy, and Tennessee Valley Authority Planned License Amendment Requests for Prairie Island, Units 2 and 2, and Watts Bar, Units 1 and 2 ML19289A5322019-10-28028 October 2019 Summary of September 26, 2019, Teleconference with Northern States Power Company on Potential License Amendment Request to Adopt TSTF-505, Revision 2 ML19210D5432019-08-20020 August 2019 Summary of Teleconference with Northern States Power Company on Potential License Amendment Request to Adopt Probabilistic Risk Assessment Model ML19136A0272019-05-15015 May 2019 Memorandum to C. Regan Summary of March 28, 2019, Public Meeting with Xcel Energy to Discuss Seismic Consideration for a Proposed License Amendment Increasing the Amount of Special Nuclear Material Authorized for Storage at Prairie Island I ML19058A4672019-03-11011 March 2019 Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Amendment Request to Modify Renewed Facility Operating License Paragraph 2.C(4)(c) ML18065A5582018-03-12012 March 2018 Summary of February 20, 2018, Teleconference with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request to Adopt TSTF-425 ML17341A1292017-12-11011 December 2017 Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Changes to the Security Plans at the Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 ML17261B0362017-09-25025 September 2017 Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential Digital Feedwater Modifications at Prairie Island Nuclear Generating Plant, Units 1 and 2 ML17235B1802017-08-23023 August 2017 Summary of Open House to Discuss the 2016 End-Of-Cycle Plant Performance Assessment of Prairie Island ML17209A1192017-07-17017 July 2017 Summary of July 17, 2017, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request Related to Heavy Lifting Devices L-PI-17-014, Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121...2017-04-19019 April 2017 Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121... ML17093A6012017-04-0606 April 2017 March 9, 2017, Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Spent Fuel Pool Criticality License Amendment Request ML17034A1202017-02-0909 February 2017 Summary of January 24, 2017, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential Revision to the Emergency Action Level ML16111B1912016-04-28028 April 2016 Summary of Meeting with Northern States Power Company, a Minnesota Corporation, Doing Business as Xcel Energy, on National Fire Protection Association (NFPA) 805 License Amendment Request ML15271A2072015-10-0202 October 2015 July 9, 2015 Summary of Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, U.S, Nuclear Regulatory Commission and Northern States Power Company- Minnesota to Discuss Flood Analysis Associated with Monticello Nuclear ML15141A5092015-05-21021 May 2015 Meeting Summary with Public to Discuss the Results of the 2014 Problem Identification and Resolution Inspection for Prairie Island Nuclear Generating Plant ML15107A0592015-05-15015 May 2015 Summary of the April 14, 2015, Public Meeting with Xcel Energy and Westinghouse to Discuss a Future License Amendment Request Regarding the Use of Ifba Rods in Nuclear Fuel at the Prairie Island Nuclear Generating Plant ML15131A4482015-05-0707 May 2015 Reactor Oversight Process Task Force FAQ Log - April 16, 2015 ML14220A2832014-09-0808 September 2014 Summary of August 5, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, NRC, and Northern States Power Company - Minnesota to Discuss Flooding Analysis Associated with Monticello and Prairie Island Nuclear Gen ML14223A8012014-08-11011 August 2014 Public Meeting Summary to Discuss the 2013 Performance of Prairie Island Nuclear Generating Plant Units 1 and 2 ML14227A8852014-07-0202 July 2014 E-mail P Longmire, NRC, Re e-mail Fr Samuel Chesnutt, Xcel Energy, Re Meeting Summary for the June 16, 2014 Prairie Island ISFSI License Renewal Application RAI Discussion ML14153A0252014-06-20020 June 2014 Meeting Summary - Public Meeting on May 16, 2014, to Discuss Xcel Energy'S Flood Hazard Reevaluation Extension Request for the Monticello and Prairie Island Nuclear Generating Plants ML14168A0182014-05-16016 May 2014 Xcel Energy Responses to NRC Questions Regarding Flood Hazard Reevaluation Report Extension Requests ML14056A4942014-03-10010 March 2014 Summary of the February 19, 2014, Pre-Application Meeting to Discuss the Diesel Generator Voltage and Frequency Limits License Request ML13210A3022013-07-29029 July 2013 Summary of Public Meeting with Northern States Power Company to Discuss the 2012 Prairie Island Nuclear Generating Plant End-of-Cycle Performance Assessment ML13171A2472013-06-20020 June 2013 7/11/2013 - Notice of Public Meeting to Discuss 2012 End-Of-Cycle Performance Assessment for Prairie Island Nuclear Generating Plant, Units 1 and 2 ML13004A3722013-01-11011 January 2013 December 6, 2012, Summary of Meeting to Discuss the Licensee'S Proposed FLEX Strategy in Response to NRC Order EA-12-049 ML12326A9702012-11-21021 November 2012 Summary of October 24, 2012, Meeting with the Northern States Power Company, D/B/A Excel Energy Regarding Security Requirements and Changes Pertaining to Prairie Island TAC L24689 W/ Encl 1 (Attendees) and Encl 2 (Agenda) ML12292A4202012-11-0707 November 2012 September 27, 2012 - Summary of Pre-Application Meeting to Discuss the Diesel Generator Voltage and Frequency Limits License Amendment Request ML12214A2332012-07-31031 July 2012 July 17, 2012 Summary of Public Meeting to Discuss the Prairie Island Nuclear Generating Plant, Units 1 and 2, End-of-Cycle Plant Performance Assessment ML12121A5842012-05-17017 May 2012 Meeting Summary with Northern States Power Co, to Discuss the National Fire Protection Association Standard 805 (NFPA 805) License Amendment Request ML12128A4152012-05-14014 May 2012 Summary of Conference Telephone Call Regarding the 2012 Steam Generator Tube Inspections ML1124207612011-09-20020 September 2011 Summary of Pre-Application Meeting to Discuss the Future Extended Power Uprate License Amendment Request ML1122005212011-08-10010 August 2011 6/22/2011 Summary of Pre-Application Meeting Regarding the Diesel Fuel Oil System License Amendment Request 2023-07-11
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Prairie Island Nuclear Generating Plant Xcel Energy 1717 Wakonade Drive East Welch, MN 55089 L-PI-17-014 Apri119, 2017 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121 and MF7122)
References:
- 1) Letter from Kevin Davison (NSPM) to NRC (Document Control Desk),
"License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes," dated November 17, 2015 (ADAMS Accession No. ML15327A244)
- 2) Email from Robert Kuntz (NRC) to Glenn Adams (NSPM), "Official Use Only- Proprietary Information Enclosed- Request for Information Related to the Prairie Island SFP Criticality Analysis License Amendment Request (CAC Nos. MF7121 and MF7122)", dated October 31, 2016
- 3) Letter from Scott Northard (NSPM) to NRC (Document Control Desk),
"Response to NRC Request for Information- License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121 and MF7122," dated February 16, 2017 (ADAMS Accession No. ML17047A454)
- 4) Letter from Robert Kuntz (NRC) to NSPM, "Summary of March 9, 2017, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Spent Fuel Pool Criticality License Amendment Request (CAC Nos. MF7121 and MF7122)," dated April 6, 2017 (ADAMS Accession No. ML17093A601)
In a letter to the U.S. Nuclear Regulatory Commission (NRC) dated November 17, 2015 (Reference 1), the Northern States Power Company, a Minnesota corporation doing business as Xcel Energy (hereafter "NSPM"), requested an amendment to the Technical Specifications (TS) for Prairie Island Nuclear Generating Plant (PINGP).
Specifically, NSPM proposed to revise Technical Specification (TS) 3.7.16, "Spent Fuel Storage Pool Boron Concentration," and TS 4.3.1, "Fuel Storage Criticality," to allow spent fuel pool (SFP) storage of nuclear fuel containing a boron-based neutron
Document Control Desk Page 2 absorber in the form of zirconium diboride (ZrB 2 ) Integral Fuel Burnable Absorber (IFBA).
The IFBA-Gd spent fuel pool criticality analysis submitted by Reference 1 followed published NRC guidance (DSS-ISG-201 0-01 ), utilized NRC approved methods, and was consistent with the Prairie Island Licensing Basis. To complete their review, the NRC staff provided a second request for additional information (RAI)- Reference 2.
The NRC requested that the reactivity effect of fuel position eccentricity be treated differently than the method utilized in the approved 2013 criticality analysis and that a new reactivity effect of spacer grid growth be considered in the criticality analysis.
In Reference 3, NSPM deferred response to the Reference 2 RAis until the merits of those RAis could be discussed with NRC Staff.
At a public meeting held on March 9, 2017, NSPM sought to understand the basis for these RAis relative to the additional conservatisms that potentially result in unnecessary spent fuel movement and adverse safety impact. NSPM requested that NRC Staff reconsider the need for the RAis. To promote continued engagement to resolve the situation prior to the 2-year review metric, NSPM agreed to submit a summary of the public meeting and a proposed markup of the RAis based on its understanding from the discussions at the March 9, 2017 public meeting. To that end, NSPM provides a meeting summary (Enclosure 1) and a markup to the RAis (Enclosure 2).
In Reference 4, NRC provided its summary of the meeting.
NSPM will continue to work with the NRC's Licensing Project Manager to schedule further engagement with NRC Staff to resolve the scope of the RAis and separate engagement with technical staff to discuss any revised models and methods that the licensee may require to address the revised RAis.
If there are any questions or if additional information is needed, please contact Glenn Adams at 612-330-6777.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
Thomas Conboy Director Site Operations - Pra* re Island Nuclear Generating Plant Northern States Power Company - Minnesota
Enclosures:
- 1. Meeting Summary- Public Meeting 3/9/2017
- 2. Markup of RAis
Document Control Desk Page 3 cc: Regional Administrator, Region Ill, USNRC Project Manager, Prairie Island Nuclear Generating Plant, USNRC Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC State of Minnesota
L-PI-17-014 Enclosure 1, Meeting Summary- Public Meeting 3/9/2017 Page 1 of 4 Date: 3-9-2017 Time: 9:00am- 11:30 pm ET Location: One White Flint North, Rockville, MD (OWFN-12B4)
Participants:
NRC NSPM Rob Kuntz, Project Manager (DORL) Marty Murphy Katherine Brock, Deputy Division Director, DORL Tom Conboy Bob Lukes, Branch Chief (NRR/DSS/SNPB) Glenn Adams Amrit Patel (NRR/DSS/SNPB) Darius Ahrar Scott Krepel (NRR/DSS/SNPB) by phone Sean Martin Kent Wood (NRR/DSS/SNPB) Mark Brossart Hank Hoelscher (phone)
Gene Eckholt (phone)
Westinghouse Mike Wenner Doug Sipes Andrew Blanco NEI Kris Cummings No members of the public appeared in person or identified themselves by phone.
Topic
Introduction:
The purpose of this meeting is for the NRC staff and NSPM to discuss NRC staff's request for additional information as requested by NSPM letter dated February 16, 2017 (ADAMS Accession No. ML17047A454). The presentation slides were provided to NRC Staff two days prior to the meeting.
Main Points of Discussion:
Rob Kuntz provided preliminary administrative remarks about the meeting, and opening remarks including that no regulatory decisions would be made during the meeting.
NSPM presented slides to describe its project team, and the project principles and objectives. The project principles focused on maintaining adequate safety margins in analysis while also preserving nuclear safety by avoiding unnecessary fuel moves. The meeting objectives were outlined to explain the regulatory and technical basis for the Requests for Additional Information (RAis) and request their reconsideration. The second set of objectives was focused on the scope and schedule for an alternate approach to addressing the RAis (if still warranted after reconsideration of the RAis).
L-PI-17-014 Enclosure 1, Meeting Summary- Public Meeting 3/9/2017 Page 2 of 4 NSPM presented the plant's criticality analysis licensing history from 1997 to current time; a series of amendments that have progressively increased conservatism to align with the evolving regulatory guidance, from an approved Westinghouse topical methodology, through the Kopp Letter, to the Interim Staff Guidance (DSS-ISG-201 0-01 ). NSPM explained how the license amendment request under review was submitted with an analysis using the analysis methodology that NRC approved in 2013, and still aligned with the IS G. NRC Staff pointed out that one of the license amendment requests (approved in 1997) used a topical methodology that was later found to be non-conservative, so the increase in burn up requirements shown on the curve did not fully represent conservatism due to regulatory changes.
NSPM discussed its concerns with RAI-6, which relates to eccentric fuel positioning within a storage cell. The RAI requested that the analysis be corrected to treat the effect as a bias rather than an uncertainty. The stated justification for this RAI was: (1) an NEI agreement to support this treatment in draft NEI 12-16, and (2) the large reactivity impact on the Prairie Island spent fuel pool. The draft NEI12-16 document is not currently endorsed by the NRC.
NSPM stated their desire to understand how the RAis (RAI 6 and 7) were necessary to .
support the Staff's safety determination and were interested to understand why these RAis had not been identified during the pre-application meeting, acceptance review, or first round RAis. NSPM conveyed its concern of constantly changing and expanding criteria for an acceptable criticality analysis. NRC Staff conveyed that these RAis represented actual phenomena (eccentricity and grid growth) that have been known to have a potential reactivity effect and have been included in the draft NEI 12-16 guidance and previous RAis.
The NRC indicated that it was not its intent to specify that NSPM had to follow the NEI document and treatment as an uncertainty would be acceptable with adequate justification. NRC staff identified that precedent alone (i.e., historical treatment as an uncertainty) was not sufficient, yet did not provide insight regarding what would be considered adequate justification.
NEI was concerned that NRC Staff was referencing unapproved draft guidance in NEI 12-16 to justify an RAI. The draft guidance has not been endorsed by NRC, and the licensee has not committed to it. NEI clarified that the draft guidance only identifies that it is conservative to treat the effect as a bias, but does not limit approaches to treatment in this conservative manner.
NSPM discussed its concerns with RAI-7, which related to spacer grid growth due to irradiation. The stated justification for this RAI was: (1) a general concern for grid growth, (2) the identification of the issue in the draft NEI12-16 guidance, and (3) an internal NRC sensitivity study of uniform pin pitch changes that resulted in significant reactivity increase. NRC staff identified it had performed an internal study of the phenomena and had reviewed grid growth data, but it was highly varied and challenging to accurately estimate its reactivity effect. NSPM suggested that the data and
L-PI-17-014 Enclosure 1, Meeting Summary- Public Meeting 3/9/2017 Page 3 of 4 phenomena be better understood before used as an RAI basis. NSPM asked if the internal NRC study and supporting information had been made publicly available as the RAI basis and to support an understanding of the concern and associated analysis.
The NRC stated that it had not released the information.
NSPM did present information on the grid growth phenomenon for the Zirlo grids used at PINGP. However, the method of determining the grid growth and its statistical treatment is not established. Further, the NSPM preliminary analysis suggests that assuming uniform grid growth (axial and radial) would be overconservative.
NSPM then described the results of the "preliminary" analysis that was completed in January 2017 to address the RAis. In short, the increase in burnup requirements due to the RAis would result in a significant number of fuel moves in the spent fuel pool.
NSPM stressed its priority was ensuring nuclear safety and its concern that potentially unneeded fuel movement to address excessive conservatism added via the RAis (without clarity for the RAI safety basis and understanding of aggregate impact) was not aligned with that priority and was not in the best interest of safety. To support a continuation of the technical review in case that the RAis are ultimately determined to be valid, NSPM presented an alternate approach to address eccentricity and grid growth that would be less limiting than the "preliminary" approach, but still address the RAis.
For eccentricity, NSPM described the analog controls and indicators and the manual operations that provided them confidence that fuel placement was truly random and could be modeled as a 2x2 array surrounded by concentric fuel. NRC Staff raised concerns with proving randomness and offered some phenomena that should be addressed, including rack levelness and rack bottom plate sag. NRC Staff did not challenge the two statistical approaches offered by the licensee, but stated that modeling the location of a fuel assembly as concentric had to be "credible". However, the Staff provided no insights to quantify a level of credibility.
For grid growth, NSPM described using a median value of grid growth rather than a 95/95 maximum growth value. NRC Staff questioned whether treatment in this manner would also require additional consideration of an uncertainty for the deviation in growth.
NRC Staff thought it would be worthy of reviewing in a future meeting.
NSPM also suggested use of recent EPRI papers to reduce depletion uncertainty from five percent to three percent. This approach was offered as an alternative in the draft of NEI 12-16. NRC Staff stated concern with applying these papers because NEI 12-16.
was not approved guidance and these papers would have to be reviewed separately.
The NEI representative stated that these EPRI papers were getting their own separate reviews as stand-alone topical reports.
In summary, the safety basis and drivers for the RAis are not readily apparent relative to existing safety margins available in the regulation (1 0 CFR 50.68) and achieved through use of existing guidance and precedent for criticality analyses. NSPM believes that
L-PI-17-014 , Meeting Summary- Public Meeting 3/9/2017 Page 4 of 4 these RAis and associated phenomena should be assessed with an aggregate understanding of the available safety margin to preclude potential adverse safety impacts resulting from overconservative analysis causing unnecessary spent fuel movement. Lastly, NSPM finds it challenging as these RAis appear to be new concerns that the NRC staff is addressing solely through the RAI process and has not made the supporting information publicly available prior to issuance of the RAis.
NSPM requests the NRC staff reconsider and review the need for the RAis in light of the public meeting discussion. In the event the RAis are determined to be necessary, it was agreed that NSPM would summarize its understanding of the RAis and provide these to the NRC. (To that end, NSPM's revised understanding of the RAis is captured in Enclosure 2.)
L-PI-17-014 , Markup of RAis Page 1 of 2 RAI 6 - Proposed Markup Draft guidance document, NEI 12 16, "Guidance for Performing Criticality ,A,nalyses of Fuel Storage at Light VVater Reactor PO\ver Plants," is in the process of being finalized.
HovJever, the NRC technical staff has reached agreement vvith NEI on many aspects of the document without exception. One of these aspects is in regards to accounting for the reactivity effect of ((proprietary text)). The NRC staff did not identify that this accounting practice 'A'aS not implemented during its initial revie\3,f of vvc.a,p 17400 P, Supplement 1, Revision 1, "Prairie Island Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis: Supplemental Analysis for the Storage of IFBA Bearing Fuel," and consequently it vvas not identified in the corresponding requests for additional information issued on April 12, 2016.
In order for the NRC staff to complete its revie'N of \'VCAP 17400 P, Supplement 1, Revision 1, please correct the accounting of the ((proprietary text)) to align with the current NRC and industry understanding of this phenomena to ensure that the 10 CFR 50.68(b)(4) requirements are met. The NRC staff believes this correction is particularly necessary in this case because of the large reactivity effect specific to Prairie Island spent fuel pool storage conditions.
Please provide technical justification for treating the reactivity effect of eccentric fuel positioning as a bias or uncertainty.
RAI 6 Proposed Retyped Version Please provide technical justification for treating the reactivity effect of eccentric fuel positioning as a bias or uncertainty.
L-PI-17-014 , Markup of RAis Page 2 of 2 RAI 7 Proposed Markup A concern was recently brought to the attention of the NRC staff regarding the potential for fuel assembly spacer grid growth during irradiation and its impact on spent fuel pool criticality safety analyses. This concern has also been identified and is being addressed as part of NEI 12 16 guidance development. Please explain the extent of grid growth known to occur in the types of materials used in the Prairie Island nuclear fuel inventory.
The fuel assembly grids have been shown to expand over the course of their utilization in the reactor (see Figure 4 of Ref. 1). How does this affect the Prairie Island spent fuel pool criticality safety analysis in WCAP-17 400-P, Supplement 1, Revision 1 and the ability to meet 10 CFR 50.68(b)(4) requirements? The NRC staff has performed studies sho,Ning that the effect of uniform pitch changes of 0.5% and 1% under spent fuel pool storage conditions can result in reactivity effects of approximately 500 pcm and 1000 pcm, respectively. The NRC staff has performed studies showing that the effect of uniform pitch changes of 0.5% and 1% under spent fuel pool storage conditions can result in reactivity effects of approximately 500 pcm and 1000 pcm, respectively.
Reference
[1] Janga, Young Ki, et al. "/>,n Investigation on Irradiation induced Grid \Aiidth Gro*lJth in Advanced Fuels." (2011).
RAI 7 Proposed Retyped Version A concern was recently brought to the attention of the NRC staff regarding the potential for fuel assembly spacer grid growth during irradiation and its impact on spent fuel pool criticality safety analyses. Please explain the extent of grid growth known to occur in the types of materials used in the Prairie Island nuclear fuel inventory. How does this affect the Prairie Island spent fuel pool criticality safety analysis in WCAP-17400-P, Supplement 1, Revision 1 and the ability to meet 10 CFR 50.68(b)(4) requirements?