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 Issue dateTitleTopic
L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 218 December 2023Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2Offsite Dose Calculation Manual
L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 121 November 2023Subsequent 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 19 November 2023Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1Coatings
VT-2
Aging Management
Through Wall Leak
L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 322 September 2023Subsequent License Renewal Application Response to Request for Additional Information Set 3Coatings
Aging Management
License Renewal
Subsequent License Renewal
ML23262B03719 September 2023Response 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 65 September 2023Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6Fire Barrier
Coatings
Aging Management
License Renewal
Subsequent License Renewal
Fire Protection Program
L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 115 August 2023Subsequent License Renewal Application Response to Request for Additional Information Set 1Hydrostatic
Operating Basis Earthquake
Incorporated by reference
Aging Management
License Renewal
Dissimilar Metal Weld
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)6 January 2023Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)Anchor Darling
ML22220A2728 August 2022Response 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)22 July 2022Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)
ML22161A91510 June 2022and 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.Safe Shutdown
Health Physics Network
Offsite Dose Calculation Manual
Earthquake
Minimum staff
Fire Protection Program
Grace period
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 Methodologies6 June 2022Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome MethodologiesStroke time
Anticipated operational occurrence
Safe Shutdown Earthquake
Operating Basis Earthquake
MELLLA
L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency25 May 2022Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing FrequencySurveillance Frequency Control Program
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 220 April 2021Response to Request for Additional Information (RAI) Related to License Amendment Request to Implement Technical Specifications Task Force Traveler TSTF-505, Revision 2Mission time
Internal Flooding
Probabilistic Risk Assessment
Large early release frequency
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 Times21 December 2020Response 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 TimesSafe Shutdown
Reactor Vessel Water Level
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Multiple Spurious Operation
FLEX
Fukushima Dai-Ichi
Thermoset
Scram Discharge Volume
Large early release frequency
Earthquake
Fuel cladding
Offsite Circuit
Very Early Warning Fire Detection
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) Interval20 July 2020Response 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 Plan8 June 2020Response to Request for Additional Information (RAI) Long-Term Replacement Steam Dryer Inspection Plan
ML20045E89414 February 2020Response 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.15 May 2019Supplement 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.High winds
Internal Flooding
Probabilistic Risk Assessment
L-MT-19-024, Response to a Request for Additional Information for Removal of a Note Associated with Technical Specification 3.5.118 April 2019Response 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 Reactors13 March 2019Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power ReactorsHigh winds
Tornado Missile
Internal Flooding
Probabilistic Risk Assessment
FLEX
Large early release frequency
TORMIS
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 ...23 October 2018Response 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 Steel20 July 2018Response to Request for Additional Information Re Request for Permanent Exemption from 10CFR50, App R, III.G.2.a Requirements for Exposed Structural SteelFire Barrier
Fire Protection Program
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-03601 June 2018Response 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-0360Water Inventory Control
ML18131A22311 May 2018Prairie 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 155 April 2018Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15Probabilistic Risk Assessment
Exemption Request
Earthquake
Fuel cladding
Fatality
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 Valves20 November 2017Response 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 ValvesHot Short
Probabilistic Risk Assessment
Multiple Spurious Operation
Exemption Request
Fire Protection Program
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 Events28 September 2017Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External EventsHigh winds
Safe Shutdown Earthquake
Anchor Darling
FLEX
Tornado Generated Missile
Fukushima Dai-Ichi
Design basis earthquake
Spent Fuel Pool Instrumentation
Earthquake
L-MT-17-065, License Amendment Request to Revise the Emergency Action Level Scheme - Supplement and Response to Requests for Additional Information25 September 2017License Amendment Request to Revise the Emergency Action Level Scheme - Supplement and Response to Requests for Additional InformationSafe Shutdown
Time of Discovery
High winds
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Safe Shutdown Earthquake
Post Accident Monitoring
Hydrostatic
Probabilistic Risk Assessment
Operating Basis Earthquake
Operator Manual Action
Design basis earthquake
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Safeguards Contingency Plan
Battery sizing
Earthquake
Fuel cladding
Pressure Boundary Leakage
Fire Protection Program
Grace period
Backfit
Unidentified leakage
Failure to Scram
L-MT-17-063, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times20 September 2017Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response TimesHigh Radiation Area
Ultimate heat sink
Offsite Dose Calculation Manual
Probabilistic Risk Assessment
Locked High Radiation Area
Job Performance Measure
Minimum staff
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 Accid11 April 2017High 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 AccidentUltimate heat sink
Safe Shutdown Earthquake
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Seismically rugged
Earthquake
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 Interval29 March 2017Response 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 IntervalHigh winds
Ultimate heat sink
Probabilistic Risk Assessment
FLEX
Large early release frequency
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 Interval7 February 2017Part 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 IntervalHot Short
Mission time
Safe Shutdown Earthquake
Probabilistic Risk Assessment
FLEX
Large early release frequency
Earthquake
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 Interval31 January 2017Part 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 IntervalHigh winds
Ultimate heat sink
Mission time
Probabilistic Risk Assessment
FLEX
Tornado Generated Missile
Tornado Missile Protection
Severe Accident Management Guideline
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 Interval16 December 2016Part 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 IntervalProbabilistic Risk Assessment
L-MT-16-058, Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.222 November 2016Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2Safe Shutdown
ML16288A09714 October 2016and 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 Interval10 October 2016Response to Request for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test IntervalAging Management
Maintenance Rule Program
L-MT-16-045, Response to Request for Additional Information: License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.23 October 2016Response 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 Uncertainties14 September 2016License Amendment Request for Areva Extended Flow Window Supplement to Address Power Distribution UncertaintiesReactor Vessel Water Level
Anticipated operational occurrence
Minimum Critical Power Ratio
MELLLA
Fuel cladding
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)19 August 2016Seventh 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)FLEX
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)15 August 2016Response 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)
ML16221A27431 July 2016ANP-3435NP, Revision 2, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar.MELLLA
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 Inspection2 June 2016Response 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 InspectionEVT-1
L-MT-16-028, Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information18 May 2016Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information
L-MT-16-024, Flood Hazard Reevaluation Report21 April 2016Flood Hazard Reevaluation ReportSafe Shutdown
High winds
Internal Flooding
FLEX
Fukushima Dai-Ichi
Design basis earthquake
Earthquake
ML16091A22829 March 2016Monticello 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)Exemption Request
L-MT-15-081, ANP-3435NP, Revision 1, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar.8 December 2015ANP-3435NP, Revision 1, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar.MELLLA
ML15274A47329 September 2015License Amendment Request for Areva Extended Flow Window Supplement to Respond to NRC Staff QuestionsUnanalyzed Condition
Anticipated operational occurrence
MELLLA
Power change
ML15348A21731 August 2015Enclosure 6, Areva Report ANP-3424NP, Non-Proprietary, Areva Responses to RAI from Scvb on MNGP EFW LAR, Revision 0, August 2015