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MONTHYEARL-MT-13-038, Mngp'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2013-04-29029 April 2013 Mngp'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Response to RAI L-MT-13-088, Request Commitment Change for Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Nearterm Task Force Review of Insights from the Fukushima Dai-ichi Accident2013-09-12012 September 2013 Request Commitment Change for Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Nearterm Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Response to RAI L-MT-14-027, Request Commitment Change for Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(D Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights From2014-03-31031 March 2014 Request Commitment Change for Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(D Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights From. Project stage: Request ML14136A2892014-05-12012 May 2014 14C4229-RPT-001, Revision 3, Monticello Nuclear Generating Plant Seismic Hazard and Screening Report. Project stage: Request L-MT-14-093, Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.12014-12-23023 December 2014 Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 Project stage: Request L-MT-15-030, Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Response to Requests for Additional Information2015-05-22022 May 2015 Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Response to Requests for Additional Information Project stage: Response to RAI L-MT-15-060, Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Clarification of Response to Request for Additional Information2015-08-13013 August 2015 Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Clarification of Response to Request for Additional Information Project stage: Response to RAI ML15272A4212015-09-0404 September 2015 NRR E-mail Capture - Monticello Nuclear Station, Unit 1 - Technical Review Checklist Related to Interim ESEP Supporting Implementation of NTTF R2.1, Seismic Project stage: Other ML15281A0292015-10-14014 October 2015 Staff Review of Interim Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 Project stage: Approval 2014-05-12
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Category:Letter type:L
MONTHYEARL-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2 L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023 CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022 Industry Groundwater Protection Initiative Special Report L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022 L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022 Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022 Letter Submitting Post-Exam Package L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022 Sixth Interval Inservice Testing (1ST) Plan L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022 Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022 Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007) L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022 Changes to the Emergency Plan L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022 Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022 2021 Annual Radioactive Effluent Release Report L-MT-22-016, 2021 Annual Report of Individual Monitoring2022-04-28028 April 2022 2021 Annual Report of Individual Monitoring L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-04-18018 April 2022 Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022 License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System2022-03-15015 March 2022 Special Report for the Bypass of the Offgas Treatment Storage System L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)2022-03-0707 March 2022 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008) L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006) 2024-01-11
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) ML22220A2722022-08-0808 August 2022 Response to a Request for Additional Informational Regarding the Monticello Fuel Oil Storage Tank Inspection L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022 Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007) ML22161A9152022-06-10010 June 2022 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Response to a Request for Additional Information Xcel Energy Amendment Request to Create a Common Emergency Plan and Emergency Operations. L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022 Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-21-017, Response to Request for Additional Information (RAI) Related to License Amendment Request to Implement Technical Specifications Task Force Traveler TSTF-505, Revision 22021-04-20020 April 2021 Response to Request for Additional Information (RAI) Related to License Amendment Request to Implement Technical Specifications Task Force Traveler TSTF-505, Revision 2 L-MT-20-036, Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times2020-12-21021 December 2020 Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times L-MT-20-024, Response to Request for Additional Information (RAI) Monticello 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval2020-07-20020 July 2020 Response to Request for Additional Information (RAI) Monticello 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval L-MT-20-015, Response to Request for Additional Information (RAI) Long-Term Replacement Steam Dryer Inspection Plan2020-06-0808 June 2020 Response to Request for Additional Information (RAI) Long-Term Replacement Steam Dryer Inspection Plan ML20045E8942020-02-14014 February 2020 Response to a Request for Additional Information for Proposed 10 CFR 50.55a(z)(2) Alternatives to Utilize ASME Code Case N-786-3, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, and AS L-MT-19-030, Supplement to a Response for a 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.2019-05-15015 May 2019 Supplement to a Response for a 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-MT-19-024, Response to a Request for Additional Information for Removal of a Note Associated with Technical Specification 3.5.12019-04-18018 April 2019 Response to a Request for Additional Information for Removal of a Note Associated with Technical Specification 3.5.1 L-MT-19-018, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-03-13013 March 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power Reactors L-MT-18-058, Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ...2018-10-23023 October 2018 Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ... L-MT-18-041, Response to Request for Additional Information Re Request for Permanent Exemption from 10CFR50, App R, III.G.2.a Requirements for Exposed Structural Steel2018-07-20020 July 2018 Response to Request for Additional Information Re Request for Permanent Exemption from 10CFR50, App R, III.G.2.a Requirements for Exposed Structural Steel L-MT-18-032, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-03602018-06-0101 June 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-0360 ML18131A2232018-05-11011 May 2018 Prairie and Monticello - Response to Request for Additional Information Regarding Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Di L-MT-18-013, Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 152018-04-0505 April 2018 Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15 L-MT-17-071, Response to Request for Additional Information Regarding Risk-Informed Request for Exemption from 10CFR50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated Valves2017-11-20020 November 2017 Response to Request for Additional Information Regarding Risk-Informed Request for Exemption from 10CFR50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated Valves L-MT-17-066, Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events2017-09-28028 September 2017 Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events L-MT-17-065, License Amendment Request to Revise the Emergency Action Level Scheme - Supplement and Response to Requests for Additional Information2017-09-25025 September 2017 License Amendment Request to Revise the Emergency Action Level Scheme - Supplement and Response to Requests for Additional Information L-MT-17-063, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times2017-09-20020 September 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times L-MT-17-025, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accid2017-04-11011 April 2017 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident L-MT-17-022, Response to Second Round PRA Related RAIs for the License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2017-03-29029 March 2017 Response to Second Round PRA Related RAIs for the License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-17-007, Part 3 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2017-02-0707 February 2017 Part 3 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-17-002, Part 2 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50Appendix J Containment Type a Test Interval2017-01-31031 January 2017 Part 2 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50Appendix J Containment Type a Test Interval L-MT-16-062, Part 1 Response to Probabilistic Risk Assessment Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2016-12-16016 December 2016 Part 1 Response to Probabilistic Risk Assessment Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-16-058, Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.22016-11-22022 November 2016 Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 ML16288A0972016-10-14014 October 2016 and Monticello - Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools L-MT-16-044, Response to Request for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2016-10-10010 October 2016 Response to Request for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-16-045, Response to Request for Additional Information: License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.22016-10-0303 October 2016 Response to Request for Additional Information: License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 L-MT-16-041, License Amendment Request for Areva Extended Flow Window Supplement to Address Power Distribution Uncertainties2016-09-14014 September 2016 License Amendment Request for Areva Extended Flow Window Supplement to Address Power Distribution Uncertainties L-MT-16-038, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)2016-08-19019 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) L-MT-16-039, Response to Nuclear Security and Incident Response Requests for Additional Information Regarding Changes to the Monticello Nuclear Generation Plant Physical Security Plan (Revision 16) Pursuant to 10 CFR 50.54(p)(2)2016-08-15015 August 2016 Response to Nuclear Security and Incident Response Requests for Additional Information Regarding Changes to the Monticello Nuclear Generation Plant Physical Security Plan (Revision 16) Pursuant to 10 CFR 50.54(p)(2) ML16221A2742016-07-31031 July 2016 ANP-3435NP, Revision 2, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar. L-MT-16-026, Response to Request for Additional Information for Approval of Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection2016-06-0202 June 2016 Response to Request for Additional Information for Approval of Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection L-MT-16-028, Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information2016-05-18018 May 2016 Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information L-MT-16-024, Flood Hazard Reevaluation Report2016-04-21021 April 2016 Flood Hazard Reevaluation Report ML16091A2282016-03-29029 March 2016 Monticello Nuclear Generating Plant Exemption Request for Nonconforming Dry Shielded Canister Dye Penetrant Examinations, Supplemental Information to Respond to the Second Request for Additional Information (TAC No. L25058) L-MT-15-081, ANP-3435NP, Revision 1, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar.2015-12-0808 December 2015 ANP-3435NP, Revision 1, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar. ML15274A4732015-09-29029 September 2015 License Amendment Request for Areva Extended Flow Window Supplement to Respond to NRC Staff Questions ML15348A2172015-08-31031 August 2015 Enclosure 6, Areva Report ANP-3424NP, Non-Proprietary, Areva Responses to RAI from Scvb on MNGP EFW LAR, Revision 0, August 2015 2023-09-05
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Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 August 13, 2015 L-MT-15-060 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) -
Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 -
Clarification of Response to Request for Additional Information
References:
- 1) NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012. (ADAMS Accession No. ML12056A046)
- 2) Letter from K. Fili (NSPM) to Document Control Desk (NRC), Request Commitment Change for Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, L-MT-14-027, dated March 31, 2014. (ADAMS Accession No. ML14090A297)
- 3) Letter from K. Fili (NSPM) to Document Control Desk (NRC), Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1, L-MT-14-093, dated December 23, 2014. (ADAMS Accession No. ML14357A280)
- 4) Email from S. Wyman (NRC) to J. Fields (NSPM), Monticello ESEP Report Clarifications, dated April 8, 2015.
- 5) Letter from P. Gardner (NSPM) to Document Control Desk (NRC), Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) -
Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 -
Response to Requests for Additional Information, L-MT-15-030, dated May 22, 2015.
Document Control Desk Page 2 On March 12, 2012, the NRC issued Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, (information request) to all NRC power reactor licensees and holders of construction permits in active or deferred status (Reference 1).
On March 31, 2014, in accordance with this information request, Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, committed to provide an Expedited Seismic Evaluation Process (ESEP) report for the Monticello Nuclear Generating Plant (MNGP) to the NRC by December 31, 2014 (Reference 2).
On December 23, 2014, NSPM provided the MNGP ESEP Report to the NRC (Reference 3).
On April 8, 2015, the NRC sent an email (Reference 4) which contained requests for additional information (RAIs) related to the ESEP report provided in Reference 3. On May 22, 2015, NSPM provided responses to the RAIs (Reference 5).
On June 23, 2015, the NRC and NSPM held a conference call to discuss NSPMs response to RAI #6. In this conference call, NSPM provided further information related to validating the seismic adequacy of MNGP inaccessible components.
On August 6, 2015, the NRC and NSPM held a conference call to discuss NSPMs response to RAI #4. In this conference call the NRC requested that NSPM provide additional information relative to the High Confidence of a Low Probability of Failure (HCLPF) values for the specific set of relays discussed in RAI #4. to this letter documents the information provided in the June 23, 2015, conference call and provides additional clarifying information related to RAIs #6. to this letter provides the additional information the NRC requested relative to the HCLPF values for the specific set of relays discussed in RAI #4.
If there are any questions or if additional information is needed, please contact John Fields, Fukushima Response Licensing, at 763-271-6707.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Document Control Desk Page 3 I declare under penalty of perjury that the foregoing is true and correct.
Executed on A Peter A Site Vic re dent, Monticello Nuclear Generating Plant Northern S es Power Company - Minnesota Enclosures cc: Administrator, Region Ill, USNRC Director of Nuclear Reactor Regulation (NRR), USNRC NRR Project Manager, MNGP, USNRC Senior Resident Inspector, MNGP, USNRC
L-MT-15-060 ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION #6 CLARIFYING INFORMATION On April 8, 2015, the NRC sent Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, an email (Reference 1) which contained requests for additional information (RAIs) related to the Monticello Nuclear Generating Plant (MNGP) Expedited Seismic Evaluation Process (ESEP) report. On May 22, 2015, NSPM provided responses to the RAIs (Reference 2). On June 23, 2015, the NRC and NSPM held a conference call to discuss NSPMs response to RAI
- 6. In that conference call, NSPM provided further information related to validating the seismic adequacy of MNGP inaccessible components.
This enclosure documents the information provided in that conference call and provides additional clarifying information related to RAI #6.
The original NRC RAI #6 is provided below in italics font, followed by the original NSPM response (in normal font) (Reference 2), followed by the clarifying information request (in italics font) and finally, the clarification response is provided (in normal font) as discussed on the June 23, 2015 conference call with the NRC.
NRC Question 6 There are approximately 50 ESEL items identified as inaccessible because they are inside the drywell. The licensee does NOT intend to complete a walk-by or remote visual of the inaccessible ESEL items at a later date. It is relying on A-46 walkdown results, which are around 20 years old. This appears to be inconsistent with the augmented approach proposed by EPRI and accepted by NRC. Discuss the technical basis why these approximately 50 items do not need to be looked at, in order to verify condition and re-affirm the A-46 walkdown results.
Original NSPM Response For inaccessible components, NSPM relied on walk downs performed to meet the A-46 issue, the Recommendation 2.3 seismic walk downs performed in 2013 and in specific cases, other information as described below. The 2013 walkdowns Page 1 of 5
L-MT-15-060 observed the following components and areas in the drywell: (1) inboard Main Steam Isolation Valve (MSIV) - AO-2-80A, (2) SRV - RV-2-71A, (3) area walk-bys on the 933 and 951 elevations of the drywell. There was nothing noteworthy found during these walk downs.
The ESEL equipment that was determined to be inaccessible (due to location in the drywell) included valves, accumulators and temperature elements. Each component type was assessed as follows:
For valves, the Seismic Review Team (SRT) gathered valve drawings in addition to the A-46 Screening Evaluation Work Sheets (SEWS) and pictures, and performed the valve evaluation based on the methodology presented in EPRI NP 6041-SL (Reference 4).
Temperature elements were evaluated based on A-46 walk down notes and pictures. These components are directly attached/secured to structural components.
Therefore, the SRT determined that the information was adequate for the ESEP purpose.
Accumulators were evaluated based on the A-46 notes and pictures. Typically two large U bolt connections were utilized to secure the accumulator. With the large margin of these items, the SRT determined that the information was adequate for the ESEP purpose.
Clarifying Information Request From the June 23, 2015 conference call with the NRC regarding ESEP RAI #6, the NRC requested that NSPM provide further information related to validating the seismic adequacy of inaccessible components for MNGP. Specifically, the NRC requested that NSPM provide justification for each inaccessible item type stating why the current evaluation performed by NSPM (i.e., using the 20 year old walkdown data/photos) is acceptable.
NSPM Response The information below describes the approach NSPM used to evaluate the inaccessible items for seismic adequacy. In summary, as described in the initial response to RAI #6, NSPM relied on information performed to meet the A-46 requirements, the Near Term Task Force (NTTF) Recommendation 2.3 seismic walk-bys and walk-downs of the Drywell (DW), and other available information.
NSPM affirms that the inaccessible components seismic evaluation has been completed in accordance with EPRI NP 6041-SL and that no further evaluation is required.
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L-MT-15-060 Below is the specific list of MNGP inaccessible components with further justification for each components seismic adequacy evaluation.
Safety Relief Valves (SRVs) - RV-2-71A through RV-2-71H NSPM reviewed the SEWS evaluation from 1995 with photos.
A walk by was performed in 2013 (DW elevation 951).
The valves are located in an inert environment during plant operation.
RV-2-71A was specifically walked down in 2013 and documented on a Seismic Walkdown Checklist (SWC) with photos taken. The other seven valves are supported in a similar manner.
Valve drawings were reviewed.
The valves are rigidly mounted on seismic piping with supporting seismic analysis.
The NSPM design control program is applicable to these components and assesses any proposed changes to MNGP to ensure the seismic qualification continues to meet design and licensing requirements.
Discharge Vacuum Relief Valves (8 inch valves) - RV-3242A, RV-3243A, RV-3244A, RV-3245A, RV-7440A, RV-7441A, RV-7467A and RV-7468A NSPM reviewed the SEWS evaluation from 1995 with photos.
A walk by was performed in 2013 (DW elevation 951) and documented on an Area Walk-By Checklist (AWC).
The valves are located in an inert environment during plant operation.
These valves are supported in a similar manner as other seismic valves integral to piping systems.
The valves are rigidly mounted on seismic piping with supporting seismic analysis.
The NSPM design control program is applicable to these components and assesses any proposed changes to MNGP to ensure the seismic qualification continues to meet design and licensing requirements.
Drywell Purge/Vent Valves - AO-2386 and AO-2387 NSPM reviewed the SEWS evaluation performed in 2014.
The valves have a similar mounting as other seismically designed valves integral to piping systems.
NSPM did not walk by these valves due to their location in a locked high radiation area (located in Reactor Water Cleanup Pump Room).
The material condition of the valves was observed to be satisfactory during performance of a Local Leak Rate Test (LLRT) in 2015.
Valve drawings were reviewed.
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L-MT-15-060 The NSPM design control program is applicable to these components and assesses any proposed changes to MNGP to ensure the seismic qualification continues to meet design and licensing requirements.
High Pressure Coolant Injection/Reactor Core Isolation Cooling Steam Isolation Valves - MO-2035 and MO-2076 NSPM reviewed the SEWS evaluation from 1995 with photos.
Valve drawings were reviewed.
A walk by was performed in 2013 (Steam Chase) and documented on an AWC.
These valves are supported in a similar manner as other seismic valves integral to piping systems.
The NSPM design control program is applicable to these components and assesses any proposed changes to MNGP to ensure the seismic qualification continues to meet design and licensing requirements.
SRV Air System Solenoid Valves - SV-2-71A through SV-2-71M NSPM reviewed the SEWS evaluation from 1995 with photos.
An area walk by was performed in 2013 (DW elevation 951).
The valves are located in an inert environment during plant operation.
The valves are light weight and rigidly mounted to a steel frame.
All of these solenoid valves have a similar mounting.
The NSPM design control program is applicable to these components and assesses any proposed changes to MNGP to ensure the seismic qualification continues to meet design and licensing requirements.
DW Temperature Elements (TEs) - TE-4247A through TE-4247H NSPM reviewed four SEWS (TE-4247A, C, F, H) evaluations from 1995 with photos.
Photos show that these light weight TEs are rigidly mounted to DW structural steel.
An area walk by was performed in 2013 for TEs 4247A - D (TEs 4247E - H are located at higher elevations in the DW with similar mounting but are not as accessible).
Components are located in an inert environment during plant operation.
TEs are inherently rugged, and mounted to large I-beams.
The NSPM design control program is applicable to these components and assesses any proposed changes to MNGP to ensure the seismic qualification continues to meet design and licensing requirements.
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L-MT-15-060 SRV Accumulators - T-57A through T-57H NSPM reviewed SEWS evaluations from 1995 with photos.
Accumulator drawings were reviewed.
An area walk by was performed in 2013 (DW elevation 951).
Accumulators are fabricated from stainless steel, and are located in an inert environment during plant operation.
The accumulators are mounted to DW structural steel I-beams with stainless steel 3/4 U-bolts and nuts.
Mounting is similar for all these accumulators.
The NSPM design control program is applicable to these components and assesses any proposed changes to MNGP to ensure the seismic qualification continues to meet design and licensing requirements.
References
- 1) Email from S. Wyman (NRC) to J Fields (NSPM), Monticello ESEP Report Clarifications, dated April 8, 2015.
- 2) Letter from P. Gardner (NSPM) to Document Control Desk (NRC), Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) -
Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 -
Response to Requests for Additional Information, L-MT-15-030, dated May 22, 2015.
- 3) Not Used.
- 4) EPRI Report No.: NP-6041-SL, A Methodology for Assessment of Nuclear Power Plant Seismic Margin, Revision 1.
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L-MT-15-060 ENCLOSURE 2 MONTICELLO NUCLEAR GENERATING PLANT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION #4 CLARIFYING INFORMATION On August 6, 2015, the NRC and Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, held a conference call to discuss Request for Additional Information (RAI) #4 from Reference 1. In the conference call the NRC requested additional clarifying information regarding the High Confidence of a Low Probability of Failure (HCLPF) values presented in Table 4-1.
This enclosure provides the additional clarifying information related to RAI #4 that the NRC requested.
Clarifying Information Request From the August 6, 2015 conference call with the NRC regarding ESEP [Expedited Seismic Evaluation Process] RAI #4, the NRC requested that Table 4-1 from Reference 1 be augmented to also provide the HCLPF values that represent the ground level acceleration through to the anchorage or functional capacity of the installed component. This should include the peak acceleration when reporting the value.
NSPM Response In NSPM letter to NRC dated May 22, 2015 (Reference 1), NSPM provided Table 4-1 which included the functional capacities HCLPF values for 17 relays.
NSPM is providing Table 4 Revised, HCLPF for Relays, below. This revised table includes the same 17 relays provided in the original Table 4-1. The revised table provides the HCLPF values that represent the ground level acceleration through to the anchorage or functional capacity of the installed component. These values include peak acceleration.
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L-MT-15-060 Enclosure 2 Table 4 Revised - HCLPF for Relays GenRS Peak -
SFc2 min Relay Maximum Horizontal Host (clipped 4 - 16 Hz Functional Host Cabinet / Bldg /
Component (capacity/demand) HCLPF Floor Acceleration for Cabinet Demand (g)/Max Capacity Elevation ID of peak/ZPA (g) Host Cabinet (g) HCLPF (g)
ZPA1(g)) Peak/ZPA (g) 13A-K1 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K2 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K6 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K7 1.76/0.71 8.00/3.20 4.51 0.86 C-30/Admin/ 939 1.76 0.21 13A-K10 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K12 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K16 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K18 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K19 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K22 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K27 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K31 1.76/0.71 8.00/3.20 4.51 0.86 C-33/Admin/ 939 1.76 0.21 13A-K32 1.76/0.71 6.00/2.40 3.38 0.64 C-33/Admin/939 1.76 0.21 13A-K33 1.76/0.71 10.00/4.00 5.63 1.07 C-30/Admin/ 939 1.76 0.21 13A-K34 1.76/0.71 6.00/2.40 3.38 0.64 C-30/Admin/ 939 1.76 0.21 13A-K37 1.76/0.71 12.00/4.80 6.76 1.28 C-30/Admin/ 939 1.76 0.21 K102A 1.76/0.71 2.64/1.06 1.49 0.28 C-303A/Admin/939 1.76 0.21 1
ZPA = Zero Period Acceleration 2
SFC = ComponentSpecific Scale Factor Page 2 of 3
L-MT-15-060 The Review Level Ground Motion (RLGM) was determined by linearly scaling the MNGP Safe Shutdown Earthquake (SSE) for the structure by the maximum Safety Factor3 between the 1 and 10 Hz range.
The method used to derive the ESEP in-structure response spectra (ISRS) was to uniformly scale the existing SSE-based ISRS by the maximum SF between the SSE and the RLGM.
In order to eliminate conservatism for the components in Table 4 Revised, the In-Cabinet Response Spectra (ICRS) was generated through the application of the GenRS software. GenRS was used because the peak frequency of the input In-Structure Response Spectra (ISRS) was significantly different than the natural frequency of the subject cabinets.
The relays in Table 4 Revised used functional capacities drawn from EPRI NP-7147-SL (Reference 2), manufacturer test data, and Seismic Qualification Utility Reports and Testing Standardization (SQURTS) reports.
References
- 1) Letter from P. Gardner (NSPM) to Document Control Desk (NRC), Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) -
Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 -
Response to Requests for Additional Information, L-MT-15-030, dated May 22, 2015.
- 2) EPRI Report No.: NP-7147-SL, Seismic Ruggedness of Relays, August 1991.
3 Safety Factor = Ground Motion Response Spectra (GMRS)/SSE ratio Page 3 of 3