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Category:Letter type:L
MONTHYEARL-MT-24-038, Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI2024-10-15015 October 2024
Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI
L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2024-09-26026 September 2024
Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
L-MT-24-029, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI2024-09-13013 September 2024
Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI
L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024
Response to RCI for RR-017 ISI Impracticality
L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024
– Preparation and Scheduling of Operator Licensing Examinations
L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024
Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)
L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024
Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160
L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024
Response to Request for Additional Information - Alternative Request VR-09 for OMN-17
L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024
2023 Annual Radiological Environmental Operating Report
L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024
2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
L-MT-24-012, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component2024-04-25025 April 2024
Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component
L-MT-24-002, Submittal of Revision 41 to the Updated Safety Analysis Report2024-04-17017 April 2024
Submittal of Revision 41 to the Updated Safety Analysis Report
L-MT-24-004, Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)2024-04-17017 April 2024
Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)
L-MT-24-006, Subsequent License Renewal Application Annual Update 1 and Supplement 92024-02-29029 February 2024
Subsequent License Renewal Application Annual Update 1 and Supplement 9
L-MT-24-007, Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval2024-02-15015 February 2024
Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval
L-MT-24-001, 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval2024-01-30030 January 2024
10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval
L-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-23-053, Condition Prohibited by Technical Specifications Due to Inoperable Main Steam Line Low Pressure Isolation Switch2023-12-0404 December 2023
Condition Prohibited by Technical Specifications Due to Inoperable Main Steam Line Low Pressure Isolation Switch
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-23-032, 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-23-028, 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-23-031, 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
2024-09-26
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Text
2807 West County Road 75 Monticello, MN 55362 800.895.4999 xcelenergy.com June 14, 2017 L-MT-17-043 10 CFR 50.54(f)
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: Expedited Seismic Evaluation Process (ESEP) -
Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 -
Commitment Completion
References:
- 1) NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012. (ADAMS Accession No. ML12056A046)
- 2) Letter from K. Fili (NSPM) to Document Control Desk (NRC),
Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1, L-MT-14-093, dated December 23, 2014. (ADAMS Accession No. ML14357A280)
- 3) Email from S. Wyman (NRC) to J. Fields (NSPM), Monticello ESEP Report Clarifications, dated April 8, 2015. (ADAMS Accession No. ML16109A151)
- 4) Letter from P. Gardner (NSPM) to Document Control Desk (NRC),
Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Response to Requests for Additional Information, L-MT-15-030, dated May 22, 2015. (ADAMS Accession No. ML15142A862)
Document Control Desk Page 2
- 5) Letter from P. Gardner (NSPM) to Document Control Desk (NRC),
Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Proposed Resolution for Components Requiring Action, L-MT-16-025, dated July 22, 2016. (ADAMS Accession No. ML16204A159)
- 6) Letter from P. Gardner (NSPM) to Document Control Desk (NRC),
High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident, L-MT-17-025, dated April 11, 2017. (ADAMS Accession No. ML17101A598)
On March 12, 2012, the NRC issued Reference 1 to request seismic profile information associated with Near-Term Task Force (NTTF) Recommendation 2.1 from all NRC power reactor licensees.
In Reference 2, Northern States Power Company, a Minnesota corporation (NSPM),
d/b/a Xcel Energy, the licensee for Monticello Nuclear Generating Plant (MNGP),
responded to the NRC and provided an Expedited Seismic Evaluation Process (ESEP) report. The results indicated that additional action (e.g. evaluation, modification, or other action) was required to assure that sufficient seismic margin is available for a small set of plant equipment.
On April 8, 2015, the NRC sent an email (Reference 3) that contained requests for additional information (RAIs) related to the ESEP report provided in Reference 2. On May 22, 2015 (Reference 4), NSPM responded to the NRC requested information in Reference 3. As part of the response to the NRC, NSPM provided corrections to the ESEP report and provided two regulatory commitments; one commitment to identify the proposed resolution and the time frame for completion of the resolution and a second commitment to report to the NRC when the resolution was completed.
On July 22, 2016 (Reference 5), NSPM provided the response to fulfill the first commitment.
The purpose of this letter is to provide the response for the second commitment.
Specifically, NSPM committed to perform the following:
A letter will be provided to the NRC summarizing the HCLPF [High Confidence of a Low Probability of Failure] results of each component and confirming the resolution of each component.
Document Control Desk Page 3 Reference 5 identified that the following components would be replaced in the 2017 refueling outage (RFO) for MNGP. Each component would be replaced with a device that has a greater seismic capacity than the currently installed component. Each replaced component and its respective HCLPF value is listed below. In each case, the value exceeds the required HCLPF value of 0.19 g.
Component - HCLPF value Component - HCLPF value
- PS-13-87D - 1.19 g During the MNGP 2017 RFO, NSPM completed the replacement of the components identified in Reference 5. Based on completion of this scope of work, the commitment made in Reference 4 is complete and no further action remains.
In addition, the NRC contacted NSPM on April 24, 2017 and discussed the results of Reference 6. Based on this discussion, the NRC requested further justification for excluding relay 13A-K26 from consideration in Reference 6. Below is the requested additional justification:
Relay 13A-K26 is used by the Reactor Core Isolation Cooling (RCIC) system Auto-Isolation Signal as a permissive to open the steam line isolation valves to the RCIC turbine. This relay is normally in a deenergized state with normally closed contacts.
The RCIC steam line isolation valves are left in a normally open position. Since the steam line isolation valves are open, the Auto-Isolation Signal will be in a reset state.
Assuming contact chatter on relay 13A-K26 occurs coincident with a seismic event, the chatter will not affect the RCIC system performance as 13A-K26 is not energized and the RCIC steam isolation valves will already be open and thus able to perform their function.
Based on this information, contact chatter in relay 13A-K26 was determined to not negatively affect the stations response to a seismic event.
Please contact John Fields, Fukushima Response Licensing, at 763-271-6707, if additional information or clarification is required.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments. This letter closes a commitment made in Reference 4.
Document Control Desk Page4 I declare under penalty of perjury that the foregoing is true and correct.
Executed on June L_i, 2017.
cc: Administrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC
