Letter Sequence Supplement |
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Results
Other: L-MT-12-088, Initial 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 Number EA-12-049), L-MT-13-017, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), L-MT-13-079, Monticello'S First 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 Number EA-12-049), L-MT-14-014, Plant'S Second 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-14-073, Plant'S Third 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 Number EA-12-049), L-MT-15-004, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049), L-MT-15-047, Update of Information Related to NRC Order Update of Information Related to NRC Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events, L-MT-15-059, Fifth 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 Number EA-12-049), L-MT-16-009, Sixth 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 Number EA-12-049), 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), ML13197A116, ML15072A098
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MONTHYEARL-MT-12-088, Initial 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 Number EA-12-049)2012-10-29029 October 2012
Initial 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 Number EA-12-049)
Project stage: Other
L-MT-13-017, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2013-02-28028 February 2013
Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
Project stage: Other
ML13182A0512013-07-0202 July 2013
Online Reference Portal for Review of Mitigation Strategies Submittal in Response to Order EA-12-049
Project stage: Approval
ML13197A1162013-07-15015 July 2013
Online Reference Portals for NRC Review of Mitigating Strategies Submittals (Order EA-12-049)
Project stage: Other
L-MT-13-079, Monticello'S First 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 Number EA-12-049)2013-08-28028 August 2013
Monticello'S First 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 Number EA-12-049)
Project stage: Other
ML13220A1392013-11-25025 November 2013
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies
Project stage: Acceptance Review
L-MT-14-014, Plant'S Second 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)2014-02-28028 February 2014
Plant'S Second 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)
Project stage: Other
L-MT-14-073, Plant'S Third 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 Number EA-12-049)2014-08-28028 August 2014
Plant'S Third 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 Number EA-12-049)
Project stage: Other
ML14290A3672014-10-22022 October 2014
Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Order EA-12-049 and EA-12-051
Project stage: Acceptance Review
ML14294A0612014-11-21021 November 2014
Relaxation of Certain Schedules Requirements for Order EA-12-049 Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events.
Project stage: Approval
L-MT-15-004, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049)2015-02-24024 February 2015
Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049)
Project stage: Other
ML15072A0982015-03-17017 March 2015
Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
Project stage: Other
L-MT-15-059, Fifth 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 Number EA-12-049)2015-08-20020 August 2015
Fifth 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 Number EA-12-049)
Project stage: Other
L-MT-15-047, Update of Information Related to NRC Order Update of Information Related to NRC Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events2015-10-12012 October 2015
Update of Information Related to NRC Order Update of Information Related to NRC Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events
Project stage: Other
L-MT-16-009, Sixth 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 Number EA-12-049)2016-02-22022 February 2016
Sixth 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 Number EA-12-049)
Project stage: Other
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)
Project stage: Other
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
Project stage: Supplement
2014-02-28
[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
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2807 West County Road 75 Monticello, MN 55362 800.895.4999 xcelenergy.com September 28, 2017 L-MT-17-066 10 CFR 2.202 10 CFR 50.4 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 Monticello Nuclear Generating Plant: 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 (TAC No. MF0923)
References:
- 1) NRC Order EA-12-049, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12, 2012. (ADAMS Accession No. ML12054A735)
- 2) NEI 12-06, Revision 2, Diverse and Flexible Coping Strategies (FLEX)
Implementation Guide, December 2015. (ADAMS Accession No. ML16005A625)
- 3) Letter from P. Gardner (NSPM) to Document Control Desk (NRC), Monticello Nuclear Generating Plant: Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events (TAC No. MF0923), L-MT-17-047, dated July 6, 2017. (ADAMS Accession No. ML17187A153)
On March 12, 2012, the Nuclear Regulatory Commission (NRC) staff issued Order EA-12-049, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," (Reference 1) to all NRC power reactor licensees and holders of construction permits in active or deferred status. Reference 1 was effective immediately and directed Northern States Power Company, a Minnesota corporation (NSPM),
doing business as Xcel Energy, to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event for the Monticello Nuclear Generating Plant (MNGP). Specific requirements were outlined in Attachment 2 of Reference 1. NSPM notified the Commission of full compliance with the Reference 1 Order in Reference 3.
Document Control Desk L-MT-17-066 Page 2 The purpose of this letter is to provide clarifications and supplemental information to support the Reference 3 compliance letter and Final Integrated Plan (FIP). NSPM is providing a clarification to the text and a figure regarding the Spent Fuel Pool (SFP) Cooling/Inventory strategy. Additionally, the NRC contacted NSPM by electronic mail requesting clarification of the FLEX strategy for reactor pressure vessel (RPV) makeup. The Enclosure of this letter provides clarification of both the SFP Cooling/Inventory strategy and the RPV makeup options.
For the RPV makeup options, the Enclosure includes justification supporting an alternative to the NEI 12-06, Revision 2 (Reference 2) guidance.
Please contact Lynne Gunderson at 651-267-7421, if additional information or clarification is required.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on September Zi, 2017.
Christoper R. Church Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC
L-MT-17-066 NSPM ENCLOSURE Monticello Nuclear Generating Plant 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 (TAC No. MF0923) 1.0 Background On March 12, 2012, the Nuclear Regulatory Commission (NRC) staff issued Order EA-12-049, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," (Reference 1) to all NRC power reactor licensees and holders of construction permits in active or deferred status. Reference 1 was effective immediately and directed Northern States Power Company, a Minnesota corporation (NSPM),
doing business as Xcel Energy, to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event (BDBEE) for the Monticello Nuclear Generating Plant (MNGP). Specific requirements were outlined in Attachment 2 of Reference 1. NSPM notified the Commission of full compliance with the Reference 1 Order in Reference 3.
Section 2.0 below provides clarification to the text and a figure in Reference 3, Enclosure 2, Final Integrated Plan. The clarification is specifically for Section 3.2.4, Structures, Systems and Components, Section 3.2.4.2, Alternate Connection, Figure 3.2.3-1, Monticello FLEX SFP Water Delivery Strategy, and Section 5.3.2, SFP Injection Makeup Strategy, all regarding the Spent Fuel Pool (SFP) Cooling/Inventory strategy.
Section 3.0 below provides supplemental information to support the Reference 3 compliance letter and Final Integrated Plan (FIP). The NRC requested clarification of the Diverse and Flexible Coping Strategies (FLEX) strategy for reactor pressure vessel (RPV) makeup, which uses a common section of piping for all RPV makeup options. NSPM has determined this is an alternative to the NEI 12-06, Revision 2 (Reference 2), guidance. The NRC requested clarification is provided in bold italics in Section 2.0 followed by the NSPM response and alternative justification.
2.0 Clarification of Final Integrated Plan - SFP Cooling/Inventory FIP Section 3.2.4 Clarification The introductory information in Section 3.2.4 discusses the three specific paths that have been assessed for providing makeup to the SFP. When developing the paths for procedures, NSPM wanted to provide as many options as possible for SFP inventory makeup. Although Path 1 is an option in response procedures for providing SFP for inventory makeup, Path 1 is not a credited option because it requires the fire system piping to be intact and uses local fire hose stations. The bases section of procedure C.5-4301, Spent Fuel Pool Makeup with FLEX Portable Diesel Pump, notes this is not a credited option. The Paths 2 and 3 are credited strategies for meeting the FLEX Order. NSPM revises the Section 3.2.4 bullets as follows to clarify the credited paths (changed text is italicized and underlined):
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L-MT-17-066 NSPM Enclosure
- Path 1 routes a fire hose from a FLEX portable diesel driven pump to the FLEX connection (see Figure 3.2.3-1) at RHRSW-68 to the refueling floor fire hose station located near the SFP. From the local fire hose stations, water can be supplied to the SFP. Path 1 route does not conform to NEI 12-06 and is not a credited path because it requires the fire system piping to be intact and uses local fire hose stations.
- Path 2 routes a fire hose directly from a FLEX portable diesel driven pump up the equipment hatch to the refueling floor. From there, the hose can be supplied to the SFP.
This path conforms to NEI 12-06, Table 3-2, by providing makeup via hoses directly to the SFP.
- Path 3 routes a fire hose directly from a FLEX portable diesel driven pump supplies water through RHRSW-68 to RHRSW-14 to fill the SFP directly using the RHR to SFP emergency return line. This path conforms to NEI 12-06, Table D-3, by providing SFP makeup without accessing the SFP area.
FIP Section 3.2.4.2, Figure 3.2.3-1 and Section 5.3.2 Clarifications:
Originally, MNGPs SFP Cooling/Inventory strategies included the use of spray capability through spray nozzles on the refueling floor using a portable FLEX pump. The MNGP Overall Integrated Plan (Reference 4) included SFP spray as a means of compliance with Order EA-12-049. This required the use of two 2 1/2 hoses for the strategies. However, as discussed in Reference 3, Enclosure 2, Section 3.2.4.4, Spray Option, the requirement for this capability was removed consistent with the endorsed guidance in NRC NEI guidance contained in NEI 12-06, Revision 2 (Reference 2). Based on the strategy change, only one 2 1/2 hose is required to implement the strategies.
Reference 3, Enclosure 2, currently makes the following references to two 2 1/2 hoses for the SFP Cooling/Inventory strategies:
- Section 3.2.4.2, Alternate Connection, refers to two, 2 1/2 hoses being routed
- Figure 3.2.3-1, Monticello FLEX SFP Water Delivery Strategy, depicts two 2 1/2 hoses from the Portable Diesel Driven Pump
- Section 5.3.2, SFP Injection Makeup Strategy, discusses the hose path that includes reference to two 2 1/2 outlets from flow splitters These above bullets are in conflict with the strategy change discussed above. Therefore, NSPM is correcting Section 3.2.4.2, Figure 3.2.3-1, and Section 5.3.2, as provided below.
These replace the referenced sections and the figure in Reference 3, Enclosure 2, in their entirety.
Section 3.2.4.2, Alternate Connection (changed text is italicized and underlined):
Path 2 - The alternate connection for SFP refilling is to route a hose from the FLEX pump into the reactor building railway and up the equipment hatch directly to the refuel floor. One, 2 1/2 hose is routed from the 5 hose manifold located outside the Reactor Building (RB). This path utilizes no permanently installed plant equipment. The FLEX SFP makeup connection is sufficiently sized to restore SFP level long-term after the loss of SFP cooling at a makeup rate of 200 gpm of makeup water for SFP boil off.
The revised Figure 3.2.3-1 is provided on the next page with only one 2-1/2 hose depicted for Path 2.
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L-MT-17-066 NSPM Enclosure Final Integrated Plan for Mitigating Strategies for Beyond-Design-Basis External Events and Reliable Spent Fuel Pool Instrumentation for Monticello Nuclear Generating Plant Figure 3.2.3-1 Page 3 of 6
L-MT-17-066 NSPM Enclosure Section 5.3.2, SFP Injection Makeup Strategy, second bullet (changed text is italicized and underlined):
o One of the two 21/2 outlets from the flow splitters described in Section 5.3.1 is used to route 21/2 fire hose through the reactor building railroad doors, up to 1027 elevation of the reactor building.
3.0 Supplemental Information NRC requested Clarification: The three RPV makeup options listed in FIP Section 3.1.5 appear to connect and flow through a single train (A train RHR/RHRSW). This conflicts with the provisions of NEI 12-06, Rev. 2, Table C-1 Performance Attribute bullet #1 for Depressurizing RPV for FLEX Injection (Page 80) (i.e. connections should not be in the same train/division). This results in a common section of piping for all portable FLEX pump RPV makeup options. The NRC staff views this as an alternative to NEI 12-06, Rev. 2. Please provide an alternative justification or show the ability to provide an additional flow path to the RPV that does not use this common piping NSPM Response:
As noted by the NRC in the above question, the three RPV makeup options listed in the MNGP FIP are routed to a single section of residual heat removal (RHR) piping (i.e., a single train).
Therefore, the single section of pipe is shared by the three FLEX injection flow paths and does not fully meet the intent of NEI 12-06, Revision 2 (Reference 2), regarding provisions for injection through separate trains. NEI 12-06, Revision 2, Table C-1, states in part Diverse injection points are required to establish capability to inject through separate divisions/trains, i.e., should not have both connections in one division/train. The MNGP configuration does not meet this provision in Reference 2. Therefore, NSPM proposes the following justification for the alternative to Reference 2.
The single piping section shared by the three FLEX injection flow paths is part of the RHR system, which is a Class I system per USAR Section 12.2.1.2. The RHR system is designed to withstand the design basis earthquake and is considered seismically robust. The common section of piping is welded steel piping designed to meet ASME Code requirements and withstand a design basis earthquake. The single section of piping is also protected from BDBEEs as it is installed within the Reactor Building. The Reactor Building is a Class I Structure, which is a seismically qualified and high winds and tornado missile-protected building as noted in USAR Section 12.2.1. The common piping begins in the train A RHR corner room (below ground level), transits the torus room (also below ground level), rises to approximately eight feet above ground level within a concrete block room on the ground floor of the reactor building, and enters the containment at that elevation. Two motor-operated valves are located within the concrete block room. This routing provides additional protection from tornado-generated missiles. Therefore, the single section of piping is reasonably protected from applicable external hazards.
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L-MT-17-066 NSPM Enclosure Seismic Category I piping systems have been confirmed to meet the licensing bases through several generic NRC programs, such as IE Bulletin 79-14. Periodic walkdowns by plant system engineers and ASME Section XI In-Service Inspections ensure that Seismic Category I piping systems are maintained in accordance with the licensing bases. Due to the inherent ruggedness Seismic Category I piping systems, the piping systems were not included on the equipment list for the Recommendation 2.3 seismic walkdowns. Additionally, examinations of power plant and industrial piping systems that have experienced strong motion earthquakes and shake-table tests well beyond the expected SSE acceleration have demonstrated inherent seismic ruggedness in piping systems.
There are two motor-operated control valves in the common piping shared by the three FLEX injection flow paths. Monticellos Flex Support Guidelines (FSGs) call for manual operation of one or both of these motor-operated valves to establish a flow path to the reactor. Since the valves are manually positioned in the FSGs, the valves were treated as inherently rugged in the Expedited Seismic Evaluation Process (ESEP). An earlier review under the Seismic Qualification Utility Group (SQUG) program covered both of these motor-operated valves and determined they have adequate seismic capacity. In addition, the valves are designed to Seismic Category I and are mounted close to ground level, which minimizes building amplification of seismic motion. If for some reason a valve cannot be opened, FSG C.5-3203 contains instructions to inject via a crosstie to the B loop of Low Pressure Coolant Injection (LPCI). None of the valves in either flow path is of the type covered by a 2013 10 CFR Part 21 notification of a defect or noncompliance for Anchor Darling Double Disk Gate Valves.
In the NRCs seismic prioritization letter (Reference 5), Monticello was classified as a low seismic hazard (Group 3) plant, meaning it has a reevaluated ground motion response spectrum greater than the design basis SSE. However, the exceedance in the 1-10 Hz range is relatively small and the maximum ground motion in the 1-10 Hz range is also not high. Given Monticellos low seismic hazard and the inherent ruggedness of nuclear Seismic Category 1 piping, it can be concluded that the actual seismic capacity of the common section of RHR piping substantially exceeds the seismic demand that would be placed on it by either a design basis safe shutdown earthquake or by the reevaluated ground motion response spectrum.
Other external hazards applicable to Monticello - snow, cold, ice, heat, and flooding - do not pose a material risk to piping systems or manually-operated valves. Based on the installation of the Class I piping in a seismically robust manner within a seismically qualified and missile-protected structure that reasonably protects the piping and connection points, NSPM concludes that the single RHR piping will be available to support the RPV makeup FLEX mitigation strategies for a BDBEE and that the proposed alternative to NEI 12-06 is acceptable for compliance with NRC Order EA-12-049.
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L-MT-17-066 NSPM Enclosure 4.0 References
- 1) NRC Order EA-12-049, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events,"
dated March 12, 2012. (ADAMS Accession No. ML12054A735)
- 2) NEI 12-06, Revision 2, Diverse and Flexible Coping Strategies (FLEX)
Implementation Guide, December 2015. (ADAMS Accession No. ML16005A625)
- 3) Letter from P. Gardner (NSPM) to Document Control Desk (NRC), Monticello Nuclear Generating Plant: Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events (TAC No. MF0923), L-MT-17-047, dated July 6, 2017. (ADAMS Accession No. ML17187A153)
- 4) NSPM Letter to NRC, Monticello Nuclear Generating Plants Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), L-MT-13-017, dated February 28, 2013 (ADAMS Accession No. ML13066A066)
- 5) NRC Letter to all Power Reactor Licensees, Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Re-Evaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident, dated May 9, 2014 (ADAMS Accession No. ML14111A147)
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