Letter Sequence Request |
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TAC:ME2609, Control Room Habitability, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) |
Results
Other: L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5, L-PI-11-060, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology, L-PI-11-079, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology, L-PI-13-111, Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement, ML102300296, ML102300297, ML102300298, ML111822669
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MONTHYEARL-PI-09-114, License Amendment Request to Adopt the Alternative Source Term Methodology2009-10-27027 October 2009 License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Request ML0935704512009-12-23023 December 2009 Acceptance Review of LAR to Adopt Alternative Source Term Methodology (TAC Nos. ME2609 & ME2610) Project stage: Acceptance Review L-PI-10-041, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology2010-04-29029 April 2010 Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Response to RAI L-PI-10-046, Response to Requests for Additional Lnformation License Amendment Request to Adopt the Alternative Source Term Methodology2010-05-25025 May 2010 Response to Requests for Additional Lnformation License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Request L-PI-10-054, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology2010-06-23023 June 2010 Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Response to RAI L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 52010-07-23023 July 2010 Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5 Project stage: Other ML1023002982010-07-23023 July 2010 Calculation No. GEN-PI-082, Revision 1, Control Rod Ejection Accident - AST, Attachment 4 Project stage: Other ML1023002972010-07-23023 July 2010 Calculation No. GEN-PI-081, Revision 1, Eab, LPZ, and CR Doses Due to Steam Generator Tube Rupture Accident - AST, Attachment 3 Project stage: Other ML1023002962010-07-23023 July 2010 Calculation No. GEN-PI-078, Revision 1, Main Steam Line Break (MSLB) Accident Analysis Using AST, Attachment 2 Project stage: Other ML1022200872010-08-10010 August 2010 Forthcoming Meeting with Northern States Power Company - Minnesota (Nspm), to Discuss the Prairie Island Nuclear Generating Plant Steam Generator Margin-to-Overfill Analysis as It Relates to Pingp'S License Amendment Request to Adopt... Project stage: Meeting ML1023002952010-08-12012 August 2010 Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Response to RAI ML1023805712010-08-25025 August 2010 Meeting Presentation Alternative Source Term Steam Generator Tube Rupture Margin to Overfill Evaluation - Prairie Island Nuclear Generating Plant Project stage: Request ML1025903972010-09-23023 September 2010 Prairie Island, Summary of Meeting with Northern States Power Company to Discuss the Alternative Source Term License Amendment Request Project stage: Meeting ML1032205572010-11-15015 November 2010 Draft RAI Concerning AST SGTR Mto Analysis Project stage: Draft RAI ML1032205552010-11-15015 November 2010 Draft RAI Concerning AST SGTR Mto Analysis Project stage: Draft RAI L-PI-10-112, Prairie Lsland Nuclear Generating Plant Units 1 and 2, Response to Request for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology (TAC Nos. ME2609 and ME26102)2010-12-17017 December 2010 Prairie Lsland Nuclear Generating Plant Units 1 and 2, Response to Request for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology (TAC Nos. ME2609 and ME26102) Project stage: Response to RAI ML1110400212011-04-0404 April 2011 NRR E-mail Capture - Prairie Island - Revised Alternative Source Term LAR Draft RAI 4-4-2011 Project stage: Draft RAI ML1035404332011-05-12012 May 2011 Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term Project stage: RAI L-PI-11-060, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-06-22022 June 2011 Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Other ML1118226692011-06-29029 June 2011 PINGP - AST Methodology - ME2609 and ME2610 Project stage: Other L-PI-11-068, Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-07-11011 July 2011 Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Response to RAI ML1120819672011-07-20020 July 2011 E-mail Prairie Island - Request for Clarification of June 22, 2011 Request for Additional Information (RAI) Response Project stage: RAI L-PI-11-079, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-08-0909 August 2011 Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Other ML1125503562011-09-0101 September 2011 Ngp - Draft RAI Concerning SGTR Instrumentation for Alternative Source Term LAR Project stage: Draft RAI ML1125503572011-09-0101 September 2011 PINGP Draft RAI - AST Instrumentation Project stage: Draft RAI ML1131100842011-11-0202 November 2011 Alternative Source Term Draft Request for Additional Information Project stage: Draft RAI ML1131100942011-11-0202 November 2011 RAI Prairie PINGP, Units 1 and 2 Project stage: RAI L-PI-11-099, Response to Requests for Additional Information Regarding Regulatory Guide 1.97 Instrumentation Associated with Adoption of the Alternative Source Term (AST) Methodology2011-12-0808 December 2011 Response to Requests for Additional Information Regarding Regulatory Guide 1.97 Instrumentation Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Response to RAI L-PI-12-010, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term Methodology2012-02-13013 February 2012 Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term Methodology Project stage: Response to RAI 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 Project stage: Response to RAI L-PI-12-082, Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2012-09-13013 September 2012 Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Response to RAI ML1125212892013-01-22022 January 2013 Issuance of Amendments Adoption of Alternative Source Term Methodology Project stage: Approval L-PI-13-111, Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement2014-01-13013 January 2014 Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement Project stage: Other 2011-12-08
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Category:Meeting Agenda
MONTHYEARPMNS20240269, Notice of Meeting with Northern States Power Company - Minnesota, Doing Business as Xcel Energy2024-02-26026 February 2024 Notice of Meeting with Northern States Power Company - Minnesota, Doing Business as Xcel Energy ML24029A0382024-01-31031 January 2024 January 31, 2024, Pre-application Meeting Presentation - Prairie Island ISFSI License Amendment Request to Add Grace to License Conditions ML24008A0132024-01-0808 January 2024 Notice of Public Meeting with Xcel Energy to Discuss the Prairie Island ISFSI Amendment ML23159A2542023-06-0808 June 2023 Pre-application Meeting with Xcel Energy to Discuss the Amendment Application for the Prairie Island ISFSI PMNS20230663, Notice of Meeting with Northern States Power Company, Doing Business as Xcel Energy2023-06-0202 June 2023 Notice of Meeting with Northern States Power Company, Doing Business as Xcel Energy ML23102A1752023-04-14014 April 2023 April 14, 2023 TS 3.7.8 LAR Pre-Submittal Meeting Slides PMNS20230262, Notice of Meeting with Northern States Power Company, Doing Business as Xcel Energy2023-04-12012 April 2023 Notice of Meeting with Northern States Power Company, Doing Business as Xcel Energy PMNS20220096, Pre-Application Meeting with Xcel Energy to Discuss Pressure-Temperature Limit Report Amendment for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Prairie Island)2022-02-0707 February 2022 Pre-Application Meeting with Xcel Energy to Discuss Pressure-Temperature Limit Report Amendment for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Prairie Island) PMNS20211339, Meeting with Northern States Power Company Regarding Prairie Island Nuclear Generating Plant, Units 1 and 2, License Amendment Request Related to the Cooling Water System2021-10-15015 October 2021 Meeting with Northern States Power Company Regarding Prairie Island Nuclear Generating Plant, Units 1 and 2, License Amendment Request Related to the Cooling Water System ML21221A0202021-08-11011 August 2021 Nis Pr Bypass Test Panel License Amendment Request PMNS20210949, Meeting with Northern States Power Company Regarding Prairie Island Nuclear Generating Plant, Units 1 and 2, Proposed License Amendment Request2021-07-21021 July 2021 Meeting with Northern States Power Company Regarding Prairie Island Nuclear Generating Plant, Units 1 and 2, Proposed License Amendment Request PMNS20210528, Meeting with Northern States Power Company Regarding Prairie Island Nuclear Generating Plant, Units 1 and 2, Proposed License Amendment Request2021-05-0505 May 2021 Meeting with Northern States Power Company Regarding Prairie Island Nuclear Generating Plant, Units 1 and 2, Proposed License Amendment Request ML21022A0082021-01-22022 January 2021 Teleconference with Xcel Energy to Discuss a Planned License Amendment Request for Monticello Nuclear Generating Plant (Monticello) and Prairie Island Nuclear Generating Plant, Units 1 and 2 (Prairie Island) ML20280A6092020-10-0606 October 2020 Teleconference to Discuss the Prairie Island Nuclear Generating Plant, Units 1 and 2, (Prairie Island) License Amendment Request to Adopt TSTF-505 Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML19347B0722019-12-12012 December 2019 TVA and Xcel Energy Slides for Joint Presubmittal Meeting to License Amendment Requests to Adopt WCAP-17661, Revision 1 ML19268A0422019-09-26026 September 2019 Pre-Application Meeting 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 ML19070A2412019-03-11011 March 2019 Notice of Meeting with Xcel Energy to Discuss a Seismic Considerations for a Proposed License Amendment Increasing the Amount of Special Nuclear Material Authorized for Storage at the Prairie Island ISFSI ML19074A1312019-03-11011 March 2019 Revised Notice of Meeting with Xcel Energy to Discuss a Seismic Considerations for a Proposed License Amendment Increasing the Amount of Special Nuclear Material Authorized for Storage at the Prairie Island ISFSI ML19045A6682019-02-14014 February 2019 Notice of Meeting with Xcel Energy to Discuss a Proposed License Amendment Increasing the Amount of Special Nuclear Material Authorized for Storage at the Prairie Island Independent Spent Fuel Storage Installation ML15183A3992015-07-0101 July 2015 Ltr. 07/01/15 Point Beach U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A3862015-07-0101 July 2015 Ltr. 07/01/15 Prairie Island U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4842015-07-0101 July 2015 Ltr. 07/01/15 Davis-Besse U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4792015-07-0101 July 2015 Ltr. 07/01/15 D.C. Cook U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting)(Drm) ML15183A4782015-07-0101 July 2015 Ltr. 07/01/15 Duane Arnold U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4722015-07-0101 July 2015 Ltr. 07/01/2015 Fermi U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4632015-07-0101 July 2015 Ltr. 07/01/15 Monticello U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4452015-07-0101 July 2015 Ltr. 07/01/15 Perry U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15182A4412015-07-0101 July 2015 Notice and Agenda - 2015 Operator Licensing Workshop ML15114A0432015-04-23023 April 2015 PI 2014 PIR and EOC Meeting Notice ML14169A5862014-06-13013 June 2014 Operator License Workshop Invitation ML13056A0262013-02-25025 February 2013 Regulatory Conference Slide Presentation 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) ML12318A0572012-11-13013 November 2012 12/6/2012 - Rescheduled Notice of Meeting with Xcel Energy Concerning Prairie Island Nuclear Generating Plant, Units 1 and 2 ML12306A3222012-11-0101 November 2012 Notice of Forthcoming Meeting with Xcel Energy Concerning Prairie Island Nuclear Generating Plant, Units 1 and 2 ML12249A2702012-09-11011 September 2012 Notice of Forthcoming Pre-Application Meeting with Xcel Energy, Inc. Concerning Prairie Island Nuclear Generating Plant ML12138A3312012-05-17017 May 2012 05/31/2012, Notice of Significant Licensee Meeting (non-public) Regarding Operator Licensing Workshop and Meeting ML1208703892012-03-30030 March 2012 Notice of Pre-Application Meeting with Xcel Energy Concerning Prairie Island Nuclear Generating Plant, Units 1 and 2, to Discuss Licensee'S Proposed NFPA 805, Performance Based Standard for Fire Protection for Light Weight Reactor ... ML1122803892011-08-18018 August 2011 Pre-Application Meeting for Prairie Island Nuclear Generating Plant (Ping) Extended Power Uprate (EPU) ML1121505252011-08-0404 August 2011 Notice of Forthcoming Pre-Application Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 to Discuss Extended Power Uprate License Amendment Request ML1119903462011-07-28028 July 2011 Meeting Presentation, Prairie Island Nuclear Generating Plant - Failure to Maintain the Train a and B Direct Current Electrical Power Subsystems Operable ML1113703982011-05-20020 May 2011 Notice of Forthcoming Pre-Application Meeting with Licensee for Prairie Island Nuclear Generation Plant, Units 1 and 2, to Discuss Proposed Technical Specification and Licensing Basis Changes to Diesel Fuel Oil System 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. ML1100502702011-01-0505 January 2011 Notice of Closed Pre-Application Meeting NSPM Staff to Discuss Proposed Physical Security Plan Changes That Will Be Submitted for NRC Review and Approval Via License Amendment Request ML1032603272010-11-24024 November 2010 Notice of Pre-Application Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 to Discuss Spent Fuel Pool Criticality and Extended Power Uprate ML1023805712010-08-25025 August 2010 Meeting Presentation Alternative Source Term Steam Generator Tube Rupture Margin to Overfill Evaluation - Prairie Island Nuclear Generating Plant ML1022200872010-08-10010 August 2010 Forthcoming Meeting with Northern States Power Company - Minnesota (Nspm), to Discuss the Prairie Island Nuclear Generating Plant Steam Generator Margin-to-Overfill Analysis as It Relates to Pingp'S License Amendment Request to Adopt... ML1009707112010-04-0808 April 2010 Revised Notice of Pre-Application Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 to Discuss Extended Power Uprate License Amendment Request ML1008205732010-03-26026 March 2010 Notice of Forthcoming Pre-Application Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 to Discuss Extended Power Uprate License Amendment Request ML0932901282009-12-0101 December 2009 Licensee Slides for Public Meeting ML0933102842009-12-0101 December 2009 Notice of Meeting with Prairie Island to Address Substantive Cross-Cutting Issues in the Area of Human Performance - Slides 2024-02-26
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24127A2402024-05-0707 May 2024 Presentation Slides for Prairie Island 2023 End-of-Cycle Meeting ML24029A0382024-01-31031 January 2024 January 31, 2024, Pre-application Meeting Presentation - Prairie Island ISFSI License Amendment Request to Add Grace to License Conditions ML23168A0032023-06-20020 June 2023 Handout for 6/23/2023 Pre-Application Public Meeting with Prairie Island Nuclear Generating Plant to Revise ISFSI TS 4.4 for TN-40HT Casks ML23156A2602023-06-0505 June 2023 2022 Prairie Island End-of-Cycle Meeting Presentation ML23102A1752023-04-14014 April 2023 April 14, 2023 TS 3.7.8 LAR Pre-Submittal Meeting Slides ML22130A5852022-05-10010 May 2022 2021 Monticello and Prairie Island Nuclear Generating Plant End-of-Cycle Meeting Presentation ML22048B1812022-02-18018 February 2022 Pre-Application Meeting for Prairie Island TS 5.6.6, PTLR, LAR ML21221A0202021-08-11011 August 2021 Nis Pr Bypass Test Panel License Amendment Request ML21166A3792021-06-15015 June 2021 Units 1 and 2 2020 End-of-Cycle Meeting Presentation ML21032A2632021-02-0303 February 2021 Slides for Public Meeting with Xcel Energy to Discuss a Planned Amendment to Combine the Emergency Plans and Create a Common Emergency Offsite Facility for Monticello and Prairie Island ML19347B0722019-12-12012 December 2019 TVA and Xcel Energy Slides for Joint Presubmittal Meeting to License Amendment Requests to Adopt WCAP-17661, Revision 1 ML19268A0422019-09-26026 September 2019 Pre-Application Meeting 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 ML19210D4512019-07-22022 July 2019 Abeyance Seal Preapplication Meeting Slides ML18051A1752018-02-20020 February 2018 Pre-Application Meeting License Amendment for TSTF-425 Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Xcel Energy 2/20/2018 ML17240A3382017-08-30030 August 2017 Non-Safety Related Digital Feedwater and Amsac/Dss Control Systems Replacement Project Presentation ML17198A2632017-07-17017 July 2017 Pre-Application Meeting ML17066A3732017-03-0909 March 2017 Spent Fuel Pool Criticality Technical Specification Changes Round 2 Request for Additional Information Public Meeting: March 9, 2017 ML17037D1172017-02-0707 February 2017 License Amendment Requests for Change in Emergency Plan Staff Augmentation Response Times Pre-Submittal Meeting for Prairie Island Nuclear Generating Plant Monticello Nuclear Generating Plant: February 7, 2017 ML17023A0652017-01-24024 January 2017 Pre-Submittal Call Regarding License Amendment Requests for Prairie Island Nuclear Generating Plant, Units 1 and 2 and Monticello Nuclear Generating Plant Emergency Action Level Scheme Changes ML15140A3342015-05-13013 May 2015 Public Meeting 05132015 Licensee Slides Only ML15105A0372015-04-14014 April 2015 Xcel Energy Slide Presentation to Support Pre-Application Meeting on April 14, 2015, to Discuss Nuclear Fuel Design Transition to Include Integral Fuel Burnable Absorber (Ifba) at the Prairie Island Nuclear Generating Plant ML14323B0222014-11-19019 November 2014 Regcon, November 19-20, 2014: 03-Info-Session-2 Ronald Johnson - Tribal Perspective on Continued Storage ML14153A0242014-05-16016 May 2014 Xcel Energy'S Presentation Slides Supporting a May 16, 2014, Public Meeting to Discuss the Flood Hazard Reevaluation Schedule for the Monticello and Prairie Island Nuclear Generating Plants ML14058A1732014-02-19019 February 2014 Diesel Generator Steady State Voltage and Frequency Limits - Prairie Island Nuclear Generating Plant Meeting February 19, 2014 ML13210A2012013-07-29029 July 2013 2012 End-of-Cycle Slides - Licensee ML13210A2002013-07-11011 July 2013 2012 End-of-Cycle Slides ML13056A0262013-02-25025 February 2013 Regulatory Conference Slide Presentation ML12340A5402012-12-0606 December 2012 Reactor Core Cooling & Heat Removal FLEX Strategy - Phase 1 ML12326A9712012-11-21021 November 2012 Encl 3 (Handouts - Public) to 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 ML12277A1762012-10-0404 October 2012 Steam Generator Replacement Presentation ML12275A4652012-09-27027 September 2012 Meeting September 27, 2012 - Handouts ML12275A3782012-09-27027 September 2012 Xcel Energy Prairie Island Nuclear Generating Plant Meeting Presentation, Diesel Generator Voltage and Frequency Limits. ML12205A2172012-07-23023 July 2012 NRC 2011 End-of-Cycle Slides ML12205A2202012-07-17017 July 2012 Licensee 2012 End-of-Cycle Slides ML12115A3112012-04-24024 April 2012 Meeting Slides: 04/24/2012 Meeting with Xcel Energy NFPA 805 Presubmittal - Prairie Island Nuclear Generating Plant ML1207904792012-03-14014 March 2012 March 14, 2012 Telecon Slides ML1122803892011-08-18018 August 2011 Pre-Application Meeting for Prairie Island Nuclear Generating Plant (Ping) Extended Power Uprate (EPU) ML1119903462011-07-28028 July 2011 Meeting Presentation, Prairie Island Nuclear Generating Plant - Failure to Maintain the Train a and B Direct Current Electrical Power Subsystems Operable ML1117804242011-06-22022 June 2011 June 22, 2011, Meeting Handout #1 - NRC Meeting Diesel Fuel Oil LAR for Prairie Island Ngp ML1120701572011-06-22022 June 2011 June 22, 2011, Meeting Handout #2 - Proposed Technical Specification Changes for Prairie Island Ngp Diesel Fuel Oil LAR ML1106600792011-03-0303 March 2011 March 3, 2011 Meeting Handouts - Revise Footnote in TS 3.8.1, Prairie Island Nuclear Generating Plant ML1034701142010-12-14014 December 2010 Excel Energy Slides for Public Meeting 12/14/2010 to Discuss Human Performance Issues ML1027802642010-10-0404 October 2010 Session 4 - Heather Westra Presentation at October 4, 2010, Public Meeting on Groundwater Protection ML1023805712010-08-25025 August 2010 Meeting Presentation Alternative Source Term Steam Generator Tube Rupture Margin to Overfill Evaluation - Prairie Island Nuclear Generating Plant ML1014502432010-05-26026 May 2010 Responses to Questions from the Prairie Island Indian Community Concerning Issues Related to Prairie Island Nuclear Generating Plant ML1012604192010-05-20020 May 2010 Meeting Presentation Prairie Island Annual Assessment Meeting - Reactor Oversight Program - 2009 ML1012503422010-05-0505 May 2010 Regulatory Conference Slides ML1015801072010-04-28028 April 2010 2R26 Outage, SG Tube Inspection Telecon Slides ML1010604782010-04-15015 April 2010 April 15, 2010, Meeting Slides - Pre-Application Meeting for Prairie Island Ngp Extended Power Uprate ML0932901282009-12-0101 December 2009 Licensee Slides for Public Meeting 2024-05-07
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24127A2402024-05-0707 May 2024 Presentation Slides for Prairie Island 2023 End-of-Cycle Meeting ML24059A4042024-03-0606 March 2024 March 6, 2023, Presubmittal Meeting for License Amendment Request to Modify Technical Specifications Definitions & Approve Plant-Specific Methods for Response Time Testing (EPID L-2024-LRM-0034) - Slides ML24029A0382024-01-31031 January 2024 January 31, 2024, Pre-application Meeting Presentation - Prairie Island ISFSI License Amendment Request to Add Grace to License Conditions ML23168A0032023-06-20020 June 2023 Handout for 6/23/2023 Pre-Application Public Meeting with Prairie Island Nuclear Generating Plant to Revise ISFSI TS 4.4 for TN-40HT Casks ML23156A2602023-06-0505 June 2023 2022 Prairie Island End-of-Cycle Meeting Presentation ML23102A1752023-04-14014 April 2023 April 14, 2023 TS 3.7.8 LAR Pre-Submittal Meeting Slides ML22130A5852022-05-10010 May 2022 2021 Monticello and Prairie Island Nuclear Generating Plant End-of-Cycle Meeting Presentation ML22048B1812022-02-18018 February 2022 Pre-Application Meeting for Prairie Island TS 5.6.6, PTLR, LAR ML21166A3792021-06-15015 June 2021 Units 1 and 2 2020 End-of-Cycle Meeting Presentation ML21124A0652021-05-0606 May 2021 Xcel Energy Presentation for May 6, 2021 Public Meeting to Discuss 24-Month Cycles at Prairie Island Nuclear Generating Plant, Units 1 and 2 ML21032A2632021-02-0303 February 2021 Slides for Public Meeting with Xcel Energy to Discuss a Planned Amendment to Combine the Emergency Plans and Create a Common Emergency Offsite Facility for Monticello and Prairie Island ML20266F1052020-09-23023 September 2020 (PINGP) COVID-19 Exemption Request for the 2020 Biennial Emergency Preparedness Exercise ML20212L8622020-07-29029 July 2020 2019 Monticello and Prairie Island EOC Presentation from Webinar ML20098F0682020-04-0909 April 2020 Preapplication Teleconference Presentation: License Amendment Request to Adopt TSTF-569 ML20057D3082020-02-18018 February 2020 Slides Potential License Amendment to Remove Note from LCO 3.4.12 and LCO 3.4.13 ML19268A0422019-09-26026 September 2019 Pre-Application Meeting 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 ML19210D4512019-07-22022 July 2019 Abeyance Seal Preapplication Meeting Slides ML19071A2782019-03-0707 March 2019 Enclosure 3: Meeting Slides (Summary of February 28, 2019, Public Meeting with Xcel Energy to Discuss Increasing the Amount of Special Nuclear Material Authorized for Storage at the Prairie Island ISFSI (W/Enclosures 1 and 2)) ML18162A0262018-06-12012 June 2018 License Amendment Request to Reclassify Certain Fuel Handling Equipment ML18051A1752018-02-20020 February 2018 Pre-Application Meeting License Amendment for TSTF-425 Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Xcel Energy 2/20/2018 ML17240A3382017-08-30030 August 2017 Non-Safety Related Digital Feedwater and Amsac/Dss Control Systems Replacement Project Presentation 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 ML17198A2632017-07-17017 July 2017 Pre-Application Meeting ML17066A3732017-03-0909 March 2017 Spent Fuel Pool Criticality Technical Specification Changes Round 2 Request for Additional Information Public Meeting: March 9, 2017 ML17037D1172017-02-0707 February 2017 License Amendment Requests for Change in Emergency Plan Staff Augmentation Response Times Pre-Submittal Meeting for Prairie Island Nuclear Generating Plant Monticello Nuclear Generating Plant: February 7, 2017 ML17023A0652017-01-24024 January 2017 Pre-Submittal Call Regarding License Amendment Requests for Prairie Island Nuclear Generating Plant, Units 1 and 2 and Monticello Nuclear Generating Plant Emergency Action Level Scheme Changes ML16280A0372016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 2 of 3 ML16280A0422016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 3 of 3 ML16280A0352016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 1 of 3 ML15140A3342015-05-13013 May 2015 Public Meeting 05132015 Licensee Slides Only ML15127A6562015-05-0707 May 2015 PI EOC Mtg NRC Slides ML15105A0372015-04-14014 April 2015 Xcel Energy Slide Presentation to Support Pre-Application Meeting on April 14, 2015, to Discuss Nuclear Fuel Design Transition to Include Integral Fuel Burnable Absorber (Ifba) at the Prairie Island Nuclear Generating Plant ML14323B0222014-11-19019 November 2014 Regcon, November 19-20, 2014: 03-Info-Session-2 Ronald Johnson - Tribal Perspective on Continued Storage ML14162A5202014-06-11011 June 2014 Slides: Prairie Island Independent Spent Fuel Storage Installation - License Renewal Application - Discussion of Requests for Additional Information, for June 16, 2014, Public Meeting ML14153A0242014-05-16016 May 2014 Xcel Energy'S Presentation Slides Supporting a May 16, 2014, Public Meeting to Discuss the Flood Hazard Reevaluation Schedule for the Monticello and Prairie Island Nuclear Generating Plants ML14084A3242014-03-21021 March 2014 M140321: Slides - Presented by Multiple Participants at Commission Briefing on Waste Confidence Rulemaking ML13210A2012013-07-29029 July 2013 2012 End-of-Cycle Slides - Licensee ML13210A2002013-07-11011 July 2013 2012 End-of-Cycle Slides ML13056A0262013-02-25025 February 2013 Regulatory Conference Slide Presentation ML12340A5402012-12-0606 December 2012 Reactor Core Cooling & Heat Removal FLEX Strategy - Phase 1 ML12326A9712012-11-21021 November 2012 Encl 3 (Handouts - Public) to 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 ML12277A1762012-10-0404 October 2012 Steam Generator Replacement Presentation ML12275A3782012-09-27027 September 2012 Xcel Energy Prairie Island Nuclear Generating Plant Meeting Presentation, Diesel Generator Voltage and Frequency Limits. ML12205A2172012-07-23023 July 2012 NRC 2011 End-of-Cycle Slides ML12205A2202012-07-17017 July 2012 Licensee 2012 End-of-Cycle Slides ML12115A3112012-04-24024 April 2012 Meeting Slides: 04/24/2012 Meeting with Xcel Energy NFPA 805 Presubmittal - Prairie Island Nuclear Generating Plant ML1207904792012-03-14014 March 2012 March 14, 2012 Telecon Slides ML1122803892011-08-18018 August 2011 Pre-Application Meeting for Prairie Island Nuclear Generating Plant (Ping) Extended Power Uprate (EPU) ML1119903462011-07-28028 July 2011 Meeting Presentation, Prairie Island Nuclear Generating Plant - Failure to Maintain the Train a and B Direct Current Electrical Power Subsystems Operable ML1117804242011-06-22022 June 2011 June 22, 2011, Meeting Handout #1 - NRC Meeting Diesel Fuel Oil LAR for Prairie Island Ngp 2024-05-07
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ALTERNATIVE SOURCE TERM Steam Generator Tube Rupture Margin to Overfill Evaluation Prairie Island Nuclear Generating g Plant August 25, 2010 1
Attendees Lynne Gunderson Projects Licensing Manager Tom Verbout AST Project Manager Steve Thomas AST Technical Lead Oley Nelson SGTR MTO Subject Matter Expert Amy Hazelhoff Senior Licensing Engineer 2
Meeting Purpose
- Gain mutual understanding g of p path forward 3
Agenda
- RG 1 1.183 183 Applicability
- NRC Concerns with 5/25/10 RAI Response
- Specific Aspects of SGTR MTO Evaluation
PINGP Major Projects Schedule 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 NRC Review License Renewal Hearings AST Key:
= Submittal MUR
= NRC Approval
= Implementation LBB EPU U1/U2 1R24 1R25 1R26 1R27 1R28 1R29 C24 C25 C26 C27 C28 C29 LEFM MUR U1 EPU Uprate 2R24 2R25 2R26 2R27 2R28 2R29 C24 C25 C26 C27 C28 LEFM MUR Uprate U2 RSG U2 EPU 5
PINGP Background
- Designed and constructed to the draft AEC GDC as proposed July 10, 1967
- Not licensed to NUREG-0800 or NUREG-75/087, Standard Review Plan
AST LAR and RAI Background
- Submitted October 2009 ((ADAMS #ML093160583))
- Six accident sequences analyzed for radiological consequences, including SGTR
- Radiological Consequence Analyses per RG 1.183
- SGTR radiological consequence analysis discussion in LAR included discussion of SGTR MTO evaluation
AST LAR and RAI Background
- Requested Details Regarding:
- Methods used in evaluation
- Input parameters and values p
- Operator action times credited
- Single failure considerations
- NSPM Responded R d d tto RAI ini May M 2010
- ADAMS Accession #ML101460064 8
Overview of PINGP SGTR MTO Licensing Basis USAR S USAR, Sectionti 14 14.5.4.1 5 4 1 states:
t t The recovery procedure can be carried out in a time scale which ensures that break flow to the secondary system is terminated before water level in the affected steam generator rises into the main steam pipe. Sufficient indications and controls are provided to enable the Operator to carry out these functions satisfactorily.
USAR Section 14 14.5.4.5 5 4 5 states:
There is ample time to carry out the above recovery procedure such that isolation of the ruptured steam generator is established before water level rises into the main steam pipes pipes. Normal operator vigilance assures that excessive water level will not be attained.
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Overview of PINGP SGTR MTO Licensing Basis
- USAR reliesli on recovery procedures d and d operator t
response to ensure ruptured steam generator is not overfilled
- SGTR MTO evaluation not considered a safety analysis within licensing basis
- Purpose of MTO evaluation is to demonstrate that operator response using recovery procedures with conservative ti inputs i t andd assumptions ti precludes l d overfilling ruptured steam generator 10
RG 1.183 Applicability RG 1.183 Section 5.1.4, Applicability of Prior Licensing Basis, states:
The NRC staff considers the implementation of an AST to be a significant change to the design basis of the facility that is voluntarily initiated by the licensee. In order to issue a license amendment authorizing the use of an AST and the TEDE dose criteria, the NRC staff must make a current finding of compliance with regulations applicable to the amendment. The characteristics of the ASTs and the revised dose calculational methodology may be incompatible with many of the analysis assumptions and methods currently reflected in the facilitys design basis analyses.
The NRC staff may find that new or un-reviewed issues are created by a particular site specific implementation of the AST site-specific AST, warranting review of staff positions approved subsequent to the initial issuance of the license. This is not considered a backfit as defined by 10 CFR 50.109,Backfitting. However, prior design bases that are unrelated to the use of the AST, or are unaffected by the AST, may continue as the facilitys facility s design basis basis. Licensees should ensure that analysis assumptions and methods are compatible with the ASTs and the TEDE criteria.
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RG 1.183 Applicability RG 1.183 Section 1.3.2, Re-Analysis Guidance, helps to determine if an analysis is affected by AST:
An An analysis is considered to be affected if the proposed modification changes one or more assumptions or inputs used in that analysis such that the results, or the conclusions drawn on those results, are no longer valid.
-Thus, an analysis is affected if the assumptions or inputs are changed h d which hi h requires i th the analysis l i tto b be revised i d 12
RG 1.183 Applicability Changes made to SGTR Radiological Consequence Analysis for AST:
- Break flow through ruptured SG tube
- Steam release from ruptured SG
- Steam S release ffrom intact SG
- Control Room Dose Considered 13
RG 1.183 Applicability MTO evaluation was not affected by the revised SGTR radiological consequence analysis:
-NNon-conservative ti tto use SGTR radiological di l i l consequence analysis transport calculation for the MTO evaluation
- No impact to RCS/SG differential pressures
- No impact to AFW and SI flow rates
- No impacts to system volumes
- No N changes h tto OOperator t Recovery R Procedures P d 14
RG 1.183 Applicability
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Conclusion:==
- No changes to inputs or assumptions in MTO evaluation l ti
- MTO evaluation was not affected by AST analyses
- Therefore, acceptable to retain the current design basis for the MTO evaluation for AST 15
RG 1.183 Applicability
Discussion of NRC Concerns on RAI Response
- Use of the simulator for the SGTR MTO analysis was not consistent with the guidance of SRP Section 15.0.I.6.C
- Data comparison showed that the calculated operator action times were significantly shorter than that calculated by using the NRC-approved methods for two similar Westinghouse 2-loop plants
- Use of the simulator for the MTO analysis was not consistent with the licensing basis as the current basis was changed by adopting d ti th the AST methodology th d l that th t reduced d d th the conservatisms in the current dose analysis 17
Discussion of NRC Concerns on RAI Response
- Use of the simulator for the SGTR MTO analysis was not consistent with the guidance of SRP Section 15.0.I.6.C
- SGTR MTO evaluation substantiates the licensing basis
- Simulator was only used to determine operator action times
- Operator action times were used as inputs to the evaluation method and were not part of the method
- Methods used provide conservative results 18
Discussion of NRC Concerns on RAI Response
- Data comparison showed that the calculated operator action times were significantly shorter than that calculated by using the NRC-approved methods for two similar Westinghouse 2-loop plants,
- Operator action times were recorded for each operating crew instead of being calculated
- Evaluation performed using each crews times to ensure that each crew could complete recovery procedures before the water could enter the main steam pipe
- PINGP has implemented procedural changes in recent years to p
enhance operator p performance
- Use of operator times based on the recovery procedures to conservatively demonstrate that the steam generator will not be overfilled is consistent with the licensing basis 19
Discussion of NRC Concerns on RAI Response
- Use of the simulator for the MTO analysis was not consistent with the licensing basis as the current basis was changed by adopting the AST methodology that reduced the conservatisms in the current dose analysis
- SGTR Radiological Consequence Analyses and SGTR MTO Evaluation are two separate evaluations
- SGTR MTO evaluation was not affected by analyses performed for the AST LAR
- Acceptable to retain current design and licensing basis for SGTR MTO evaluation 20
Conclusion
- SGTR MTO evaluation was not affected by AST analyses
- No changes to inputs or assumptions used in SGTR MTO evaluation as a result of the AST analyses
- Consistent with RG 1.183, it is considered acceptable to retain current licensing and design basis for SGTR MTO evaluation l ti 21
Technical Discussion Specific Aspects of the SGTR MTO Evaluation 22
Specific Aspects of the SGTR MTO Evaluation
- The SGTR MTO evaluation Th l ti iis performed f d tto substantiate the licensing basis
- SGTR MTO uses a conservative evaluation methodology coupled with conservative inputs and assumptions to provide conservative results
- SGTR MTO evaluation does not solely rely on the simulator
- Methods, assumptions, inputs and results are summarized on the following slides 23
Specific Aspects of the SGTR MTO Evaluation M th d Methods
- Evaluation is based on standard engineering principles:
- Determine available volume in ruptured SG
- Determine volume injected into ruptured steam generator
- Operator action times measured to reach specific steps (SI, I l t AFW Flow, Isolate Fl Break B k Flow Fl Terminated)
T i t d) in i the th recovery procedures for each crew
- Conservative design flow rates used
- MTO = Available Volume - Total volume Injected 24
Specific Aspects of the SGTR MTO Evaluation Key Assumptions and Inputs
- High Initial SG Level + Instrument Uncertainties
- Provides for maximum liquid volume; i.e., minimum available volume
- Conservative injection rate to ruptured SG
- Conservative injection rate to RCS 25
Specific Aspects of the SGTR MTO Evaluation Key Assumptions and Inputs (continued)
- Flow rate through ruptured SG tube determined based on static differential pressure
- Results R lt iin hi high h flflow rate t iinto t ruptured t d SG
- Two time periods considered
- No credit for steam release from ruptured SG
- Provides for minimum margin to overfill
- Timing for Operator Actions
- Times for each crew performing recovery procedures using plant simulator 26
Specific Aspects of the SGTR MTO Evaluation R
Results:
lt
- Demonstrate each crew can complete required actions in the recovery procedures prior to water level in affected steam generator reaching main steam pipe
- Available margin varies by crew
- Consistent with licensing basis as described in USAR
- Operators using recovery procedures preclude SG overfill 27
Path Forward
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