Letter Sequence Request |
---|
EPID:L-2022-LLR-0088, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative (Approved, Closed) |
|
MONTHYEARL-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 Project stage: Request ML23004A1982023-01-0404 January 2023 NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing Project stage: Draft RAI 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) Project stage: Request ML23017A2222023-01-13013 January 2023 Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email) Project stage: Other PMNS20230188, Notice of Meeting with Northern States Power Company, Doing Business as Xcel Energy2023-02-24024 February 2023 Notice of Meeting with Northern States Power Company, Doing Business as Xcel Energy Project stage: Request ML23074A1212023-04-0303 April 2023 March 8, 2023, Summary of Public Meeting with Northern States Power Company Regarding Monticello Nuclear Generating Plant Alternative Request PR-08 to Defer Quarterly Testing of Components of High Pressure Coolant Injection System Project stage: Meeting ML23107A2852023-04-25025 April 2023 Authorization and Safety Evaluation for Alternative Request PR-08 Project stage: Approval 2023-01-06
[Table View] |
|
---|
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
[Table view] |
Text
fl Xcel Energy 2807 West County Road 75 Monticello, MN 55362 January 6, 2023 L-MT-23-005 10 CFR 50.55a(z)(2)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 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)
References:
- 1) NSPM 50.55a Request to the NRC, " L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. PR 08, Request for HPCI Pump Quarterly Alternative", dated December 15, 2022 (ADAMS Accession No. ML22350A726)
- 2) Email from NRC to NSPM "Draft Request for Additional Information RE:
Monticello Nuclear Generating Plant Request PR 08, HPCI Pump Quarterly Testing", dated January 4, 2023 In Reference 1, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submitted a 50.55a request for the Monticello Nuclear Generating Plant (MNGP). The proposed request would defer the quarterly testing of components in the High Pressure Coolant Injection system until after the 2023 spring refueling outage when repairs to the 'G' SRV (Safety Relief Valve) will be completed. The NRC identified the need for additional information in Reference 2. The enclosure to this letter provides NSPM's response to Reference 2.
Please contact Mr. Ron Jacobson at 612-330-6542 or ronald.g.jacobson@xcelenergy.com if there are any questions or if additional information is needed.
Document Control Desk L-MT-23-005 Page2 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
~
~NH<,(I 6, :J"vi<-,;RrSo,J ~~
Shawn C. Hafen Plant Manager, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC
L-MT-23-005 NSPM ENCLOSURE RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING THE 50.55a REQUEST PR 08, HPCI PUMP QUARTERLY TESTING
1.0 BACKGROUND
In Reference 1, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submitted a 50.55a request for the Monticello Nuclear Generating Plant (MNGP). The proposed request would defer the quarterly testing of components in the High Pressure Coolant Injection system until after the 2023 spring refueling outage when repairs to the 'G' SRV (Safety Relief Valve) will be completed. The NRC identified the need for additional information in Reference 2. This enclosure provides NSPM's response to Reference 2.
2.0 RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION
RAI 1
The request includes a summary of the testing history for check valves HPCI-18, 20, 32, 9, and 10 for the last 10 years and indicates that the valves have no history of failures. The request also states that several of the valves have been disassembled and inspected in the last 10 years. Discuss the testing history (rather than only failures) and the reason for disassembly and inspection of these check valves.
RAI 1 RESPONSE The following table shows affected check valve testing; the biennial comprehensive test also satisfies the quarterly test. The check valve testing that will be deferred is only the open/close exercise testing that occurs when the HPCI pump runs. These check valves have no history of failure to open or close as required.
Check Test Frequency Recent Instances Results Valve of occurrence HPCI-9 Open Quarterly 9/18/2022 Satisfactory (CTO) 6/21/2022 3/22/2022 12/20/2021 Biennially 12/18/2020 Satisfactory HPCI-10 Open Quarterly 9/18/2022 Satisfactory (CTO) 6/21/2022 3/22/2022 12/20/2021 Biennially 12/18/2020 Satisfactory HPCI-18 Open Quarterly 9/18/2022 Satisfactory (CTO) 6/21/2022 3/22/2022 12/20/2021 Biennially 12/18/2020 Satisfactory Page 1 of 5
L-MT-23-005 NSPM ENCLOSURE Check Test Frequency Recent Instances Results Valve of occurrence HPCI-20 Open (BTO) Quarterly 9/18/2022 Satisfactory
& Close 6/21/2022 (CTC) 3/22/2022 12/20/2021 Biennially 12/18/2020 Satisfactory HPCI-32 Open Quarterly 9/18/2022 Satisfactory (CTO) 6/21/2022 3/22/2022 12/20/2021 Biennially 12/18/2020 Satisfactory CTO/CTC: Category C exercise test open/close BTO: Category C bi-directional exercise test open Leak tightness is managed through the corrective and preventive maintenance processes, which includes the disassembly and inspection discussed in the relief request. Leak tightness testing for the HPCI check valves occurs during refueling outages and will be performed per normal periodicity; leak tightness testing will not be deferred. The table below summarizes the preventive maintenance frequency, most recent test, and next occurrence.
Check Valve PM frequency Instances of Next Scheduled occurrence in last 10 years HPCI-9 10 years 2019 2029 HPCI-10 12 years None 2023 HPCI-18 14 years 2021* 2025 HPCI-20 12 years 2015 2027 HPCI-32 12 years 2013 2025
- HPCI-18 was disassembled due to it failing the leak tightness test in 2021. A chip found on the seat was removed, and the test was performed again with satisfactory results following the disassembly and inspection.
RAI 2
The request indicates that MOV MO-2036 has 21% open capability margin. Provide the type of valve and actuator for MO-2036 and the assumptions for calculating the open margin.
RAI 2 RESPONSE MO-2036 is a Flexible Wedge Anchor Darling 8 gate valve. The valve has a Limitorque SMB-01 actuator attached.
The 21% margin is the difference between the required thrust for opening with a maximum value at cracking load of 26,981 pounds versus the maximum seating force measured during the diagnostic test of 21,152 pounds. The 21% margin shows the difference in the actual closing thrust versus the potential maximum opening thrust required for the valve to operate.
Page 2 of 5
L-MT-23-005 NSPM ENCLOSURE
RAI 3
For HPCI pump P-209, the request states that the pump trending of flow/differential pressure, oil, and vibration are stable and within acceptable range. Provide the results of the last 3 tests to demonstrate the stable performance of the pump.
RAI 3 RESPONSE The results of the last three quarterly performances of the HPCI quarterly pump tests are provided in the following table.
Flow Flow DP acceptance Date (gpm) (psig) (gpm) DP acceptance (Psig) 3/22/2022 3150 1043 2900 to 3300 1136.1 to 929.7 7/8/2022 3150 1043 2900 to 3300 1136.1 to 929.7 9/22/2022 3000 1053 2900 to 3300 1157.0 to 946.8 Vibration data in the vertical and horizontal directions, and absolute value at the test locations, is required every two years but may be recorded more frequently. The results of the last three recorded vibration data sets are provided in the table below.
Date P3H P3V P4A P4H P4V P7H P7V P8A P8H P8V 12/18/2018 (displacement, mils) 0.638 0.146 0.325 0.602 0.162 0.480 0.315 0.261 0.369 0.259 12/22/2020 (displacement, mils) 0.5974 0.1969 .02807 0.5621 0.3457 0.2622 0.4637 0.3357 0.3816 0.2862 12/21/2021 (displacement, mils) 0.6324 0.1645 0.4785 0.6954 0.381 0.4315 0.2511 0.2388 0.3587 0.2037 Acceptable Range (mils) 1.520 0.437 0.717 1.420 0.520 1.022 0.647 0.590 0.792 0.512 Page 3 of 5
L-MT-23-005 NSPM ENCLOSURE The oil was last changed in June 2018. The last oil sample was taken on 9/22/2022. The sample results since that 2018 change have been satisfactory. The particle counts, viscosity, water content and other properties have all been at normal levels. The last three analyses are provided in the following table:
Water (%/Volume)
Total Acid Number Target: <0.0200%
(mg KOH/g Alert: 0.0200%
Date Viscosity Maximum) Alarm: 0.2000%
09/22/2022 31.61 0.14 0.0006 06/22/2021 31.70 <0.10 0.0018 09/21/2020 31.70 <0.10 0.0019 Acceptable Range 28.7 to 36.7 <0.45 Target <0.200%
RAI 4
Item 19 Full Description of Proposed Alternative, in the request states that the HPCI pump tests will be deferred in the fourth quarter of 2022 and first quarter of 2023. Explain the reference to the 2022 testing because a 10 CFR 50.55a(z) alternative to ASME OM Code test requirements cannot be implemented until authorized by the NRC.
RAI 4 RESPONSE The relief request was written to include a fourth quarter 2022 test that was originally scheduled for December 19, 2022. Applying the grace allowed by ISTA-3170, this test has a hard compliance date of January 15, 2023. The fourth quarter 2022 test remains yet to be performed and will be deferred pending approval of the relief request.
RAI 5
Item 14 Applicable ASME Code Requirements includes some strange symbols 'â in 2 places. Clarify the intention of these symbols.
RAI 5 RESPONSE The symbols of Item 14 were copied into the WRR portal as ellipses. The conversion of the ellipses to the strange symbols occurred following submission when the portal data was converted to a PDF. Item 14 should be replaced with the following:
ISTB-3400, Frequency of Inservice Tests. An inservice test shall be run on each pump as specified in Table ISTB-3400-1. That table specifies a Quarterly Group A Test for Pump Group A.
ISTA-3170, Inservice Examination and Test Frequency Grace. Components whose test frequencies are based on elapsed time per table ISTA-3170-1, which states quarterly (every 3 months) and specifies 92 days between tests.
Page 4 of 5
L-MT-23-005 NSPM ENCLOSURE ISTC-3510, Exercising Test Frequency. States in part: "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months..."
Mandatory Appendix III-3721, HSSC [High Safety Significance] MOVs [Motor Operated Valves]. States in part: "... HSSC MOVs that can be operated during plant operation shall be exercised quarterly ..."
3.0 REFERENCES
- 1. NSPM 50.55a Request to the NRC, " L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. PR 08, Request for HPCI Pump Quarterly Alternative", dated December 15, 2022 (ADAMS Accession No. ML22350A726)
- 2. Email from NRC to NSPM "Draft Request for Additional Information RE: Monticello Nuclear Generating Plant Request PR 08, HPCI Pump Quarterly Testing", dated January 4, 2023 Page 5 of 5