Letter Sequence Response to RAI |
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MONTHYEARL-MT-17-083, License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2017-12-19019 December 2017
License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
Project stage: Request
ML18022A1062018-01-22022 January 2018
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-425
Project stage: Acceptance Review
L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2018-03-28028 March 2018
Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
Project stage: Request
L-MT-18-020, Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Control2018-04-24024 April 2018
Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Control
Project stage: Supplement
L-MT-18-043, Online Reference Portal for NRC Review of License Amendment Requests to Adopt TSTF-425 and 10 CFR 50.692018-07-31031 July 2018
Online Reference Portal for NRC Review of License Amendment Requests to Adopt TSTF-425 and 10 CFR 50.69
Project stage: Request
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 ...
Project stage: Response to RAI
L-MT-18-073, Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee...2018-11-20020 November 2018
Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee...
Project stage: Supplement
ML19007A0902019-01-28028 January 2019
Issuance of Amendment Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B
Project stage: Approval
ML19065A2002019-03-11011 March 2019
Correction to License Amendment No. 200 Related to Adoption of TSTF-425, Relocated Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B
Project stage: Acceptance Review
2018-03-28
[Table View] |
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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
[Table view] |
Text
2807 West County Road 75 Monticello, MN 55362
(}, Xcel Energy*
RESPONSIBLE BY NATURE
- 800.895.4999 xcelenergy.com October 23, 2018 L-MT-18-058 10 CFR 50.90 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 Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (EPID L-2017-LLA-0434)
References:
- 1) NSPM Letter (L-MT-17-083) to NRC Document Control Desk, License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, dated December 19, 2017 (ADAMS Accession No. ML17353A189)
- 2) Nuclear Energy Institute (NEI) 04-10, Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies, Revision 1, dated April 2007 (ADAMS Accession No. ML071360456)
- 3) NSPM Letter (L-MT-18-020), Supplement to License Amendment Request:
Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (EPID L-2017-LLA-0434), dated April 24, 2018 (ADAMS Accession No. ML18114A401)
- 4) Email from NRC, Request for Additional Information RE: Monticello license amendment request to adopt TSTF425, dated September 26, 2018 (ADAMS Accession No. ML18269A357)
In Reference 1, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter NSPM), requested to amend Renewed Facility Operating License DPR-22 for the Monticello Nuclear Generating Plant (MNGP). The proposed amendment
Document Control Desk Page 2 would modify the MNGP Technical Specifications (TS) by relocating specific surveillance frequencies to a licensee-controlled program with implementation of NEI 04-10, "Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies", (Reference 2) . Reference 1 was supplemented to correct errors in two facts and observations (F&O) (Reference 3). On September 26, 2018, the NRG issued a request for additional information (RAI) (Reference 4). The response to the Reference 4 request is provided in the enclosure to this letter.
The information provided in this letter does not alter the evaluations performed in accordance with 10 CFR 50.92 .
Please contact Sara Scott, Licensing Manager, at 612-330-6698, if additional information or clarification is required.
Summary of Commitments This letter makes one new commitment and no revisions to existing commitments:
- The Fire PRA model update activities related to F&O 2-5 will be completed prior to implementation of TSTF-425.
I declare under penalty of perjury, that the foregoing is true and correct.
Executed on October l!J_, 2018.
Christopher R. Church Site Vice President, 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-18-058 NSPM Enclosure Response to Request for Additional Information:
Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program 1.0 Background In Reference 1, Northern States Power Company, a Minnesota corporation (hereafter NSPM),
doing business as Xcel Energy, requested to amend renewed Facility Operating License DPR-22 for the Monticello Nuclear Generating Plant (MNGP). The proposed amendment would modify the MNGP Technical Specifications (TS) by relocating specific surveillance frequencies to a licensee-controlled program with implementation of NEI 04-10, Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies, (Reference 2). Reference 1 was supplemented to correct errors in two Facts &
Observations (Reference 3). On September 26, 2018, the NRC issued a request for additional information (RAI) (Reference 4). The NSPM responses to the NRC RAIs are provided below.
2.0 Responses to Requests for Additional Information NRC RAI 01 - LAR Attachment 2, MNGP Open Fire PRA Peer Review Findings:
The LAR Attachment 2, Table 2-1, MNGP Open Fire PRA Peer Review Findings, provides resolutions for the open facts and observations (F&Os) from the full-scope 2015 and focused-scope 2017 Fire PRA (FPRA) peer reviews that were not closed by the October 2017 Finding Closure Review.
For F&O 2-5, the peer review team stated the influencing factors assigned in the FPRA model were based on engineering judgement and a set of rules documented in Section 5.6.2 of the Ignition Frequency Notebook. The peer review team further stated that the influencing factors assigned resulted in comparatively low values (i.e., averaging much less than 3). The resolution of this F&O indicates, in part, that a better justification of application of a very low factor in two compartments needs to be provided. As related to F&O 2-5, Attachment 3 of the MNGP submittal, dated March 28, 2018, (ADAMS Accession No. ML18087A323) for the implementation of a program related to 10 CFR 50.69 further indicates that the compartments 8 and 33 were assigned very low influencing factors.
The update for treatment of influence factors for the two fire compartment areas, compartments 8 and 33, which were assigned very low influencing factors, could have an impact on this risk-informed application. Additionally, Frequently Asked Question (FAQ) 12-0064, Close-Out of National Fire Protection Association 805 Frequently Asked Question 12-0064 on Hot Work/Transient Fire Frequency Influence Factors (ADAMS Accession No. ML12346A488), provides related guidance for consideration in the use of influencing factors in an FPRA.
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L-MT-18-058 NSPM Enclosure EITHER:
- a. Provide justification for why the treatment (use of the influencing factors) used in the MNGP FPRA for fire compartments 8 and 33 is appropriate for this application (e.g.,
explain how the influencing factors used for fire compartments 8 and 33 are consistent with or bound the guidance in FAQ 12-0064; discuss the results of a sensitivity analysis that confirms the F&O will have negligible impact on the surveillance test interval (STI) evaluations).
OR
- b. If justification to confirm the influencing factors used for fire compartments 8 and 33 cannot be provided, propose a mechanism that ensures F&O 2-5 will be resolved for supporting requirement IGN-A7 at Capability Category (CC) II, consistent with the NEI 04-10 guidance. The proposed mechanism should ensure the activities and changes associated with F&O 2-5 will be completed, appropriately reviewed, and any issues resolved prior to any future STI evaluations. Additionally, this mechanism should specify how F&O 2-5 will be resolved in the PRA (e.g., provide an explicit description or a reference to the appropriate section of the LAR). An example would be a table of listed implementation items referenced in a license condition.
NSPM Response to RAI 01(b):
In the November 2017 Fire PRA Peer Review Findings Closure Report, F&O 2-5 was characterized as a documentation issue noting that better justification of the application of the very low factor (0.3) needed to be made or potentially the use of the typical low factor (1.0) should be considered.
A detailed review performed in May 2018 recognized that the Transient Fire Frequency Influence Factors were not justifiable at the very low factor. The suggested guidance within FAQ 12-0064, Close-Out of National Fire Protection Association 805 Frequently Asked Question 12-0064 on Hot Work/Transient Fire Frequency Influence Factors, (Reference 5), was considered during this review. Based on this, the Transient Storage Factor for both Fire Zone 8 and 33 will be classified as low (1.0). Therefore, RAI 01 Option (b) is selected as the appropriate response approach.
The Fire PRA is currently undergoing an update in accordance with FP-PE-PRA-02, PRA Guideline for Model Maintenance and Update, and this change is being incorporated. The Fire PRA model update activities related to F&O 2-5 will be completed prior to implementation of TSTF-425. Once the Fire PRA model update is complete, this revised model will be used to address the surveillance test interval changes.
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L-MT-18-058 NSPM Enclosure 3.0 References
- 1. NSPM Letter (L-MT-17-083) to NRC Document Control Desk, License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, dated December 19, 2017 (ADAMS Accession No. ML17353A189)
- 2. Nuclear Energy Institute (NEI) 04-10, Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies, Revision 1, dated April 2007 (ADAMS Accession No. ML071360456)
- 3. NSPM Letter (L-MT-18-020), Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (EPID L-2017-LLA-0434), dated April 24, 2018 (ADAMS Accession No. ML18114A401)
- 4. Email from NRC, Request for Additional Information RE: Monticello license amendment request to adopt TSTF425, dated September 26, 2018 (ADAMS Accession No. ML18269A357)
- 5. Frequently Asked Question (FAQ) 12-0064, Close-Out of National Fire Protection Association 805 Frequently Asked Question 12-0064 on Hot Work/Transient Fire Frequency Influence Factors, dated January 17, 2013 (ADAMS Accession No. ML12346A488)
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