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Category:Letter
MONTHYEARML24318C5002024-11-19019 November 2024 Letter to Robert Blanchard Tribal Chairman Bad River Band of Lake Superior Chippewa Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24312A3512024-11-18018 November 2024 Letter to Amy Spong, Deputy State Historic Preservation Officer, Re., NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5252024-11-18018 November 2024 Letter to J Garrett Renville Tribal Chairman Sisseton Wahpeton Oyate of the Lake Traversee Re NOA Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5272024-11-18018 November 2024 Letter to Thomas Fowler Chairman St. Croix Chippewa of Wisconsin Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5162024-11-18018 November 2024 Letter to James Williams Jr Chairman Lac Vieux Desert Band of Lake Superior Chippewa Indians Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5092024-11-18018 November 2024 Letter to Doreen Blaker President Keweenaw Bay Indian Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5072024-11-18018 November 2024 Letter Timothy Rhodd Chairman Iowa Tribe of Kansas and Nebraska Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5102024-11-18018 November 2024 Letter to Louis Taylor Chairman Lac Courte Oreilles Band of Lake Superior Chippewa Indians Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24312A1732024-11-18018 November 2024 Ltr. to Shawn Hafen, Site Vice President, Monticello Nuclear Generating Plant, Re., NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24312A3202024-11-18018 November 2024 Letter to Durell Cooper Tribal Chairman Apache Tribe of Oklahoma Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5062024-11-18018 November 2024 Letter to Robert Deschampe Tribal Chair Grand Portage Band of Lake Superior Chippewa Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24312A3462024-11-18018 November 2024 Letter to Jaime Loichinger Director Office of Federal Agency Programs, Achp NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5262024-11-18018 November 2024 Letter to Lonna Johnson Street Chairperson Spirit Lake Nation Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5112024-11-18018 November 2024 Letter to John Johnson President Lac Du Flambeau Band of Lake Superior Chippewa Indians Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5312024-11-18018 November 2024 Letter to Virgil Wind Chief Executive Mille Lacs Band of Ojibwe Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5222024-11-18018 November 2024 Letter to Darrell Seki Chairman Red Lake Nation Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5012024-11-18018 November 2024 Letter to Catherine Chavers Tribal Chairwoman Bois Forte Band Chippewa Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5202024-11-18018 November 2024 Letter to Grant Johnson President Prairie Island Indian Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5052024-11-18018 November 2024 Letter to Bruce Savage Tribal Chairperson Found Du Lac Band of Lake Superior Chippewa Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5292024-11-18018 November 2024 Letter to Kevin Jensvold Tribal Chairman Upper Sioux Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5242024-11-18018 November 2024 Letter to Cole Miller Chairman Shakopee Mdewakaton Sioux Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5032024-11-18018 November 2024 Letter to Anthony Reider President Flandreau Santee Sioux Tribe NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5172024-11-18018 November 2024 Letter to Robert Larsen President Lower Sioux Indian Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5152024-11-18018 November 2024 Letter to Faron Jackson Sr Chairman Leech Lake Band of Ojibwe Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5182024-11-18018 November 2024 Letter to Gena Kakkak Chairwoman Menominee Indian Tribe of Wisconsin Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5212024-11-18018 November 2024 Letter to Nicole Boyd Chairwoman Red Cliff Band of Lake Superior Chippewa Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5232024-11-18018 November 2024 Letter to Alonzo Denney Chairman Santee Sioux Nation Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5302024-11-18018 November 2024 Letter to Michael Fairbanks Chairman White Earth Nation Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5192024-11-18018 November 2024 Letter to Michael Laroque President Minnesota Chippewa Tribe Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5022024-11-18018 November 2024 Letter to Reggie Wassana Governor Cheyenne and Arapaho Tribes NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5282024-11-18018 November 2024 Letter to Jamie Azure Chairman Turtle Mountain Band of Chippewa Indians Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5322024-11-18018 November 2024 Letter to Robert Vanzile Jr Chairman Sokaogon Chippewa Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5042024-11-18018 November 2024 Letter to Jeffrey Stiffarm President Fort Belknap Indian Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR IR 05000263/20240032024-11-13013 November 2024 Integrated Inspection Report 05000263/2024003 ML24283A1192024-10-28028 October 2024 Letter to Shawn Hafen, Re Monticello Subsequent License Renewal Schedule Change L-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 ML24277A0202024-10-0303 October 2024 Operator Licensing Examination Approval Monticello Nuclear Generating Plant, October 2024 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 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 IR 05000263/20240052024-08-30030 August 2024 Updated Inspection Plan and Follow-Up Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2024005) L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure IR 05000263/20244202024-08-21021 August 2024 Security Baseline Inspection Report 05000263/2024420 - Cover Letter IR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS 2024-09-26
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure 05000263/LER-2024-001, 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 05000263/LER-2023-003, 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 05000263/LER-2023-002, Reactor Scram and Containment Isolation Due to Valve Responses During Main Turbine Control Valve Testing2023-11-13013 November 2023 Reactor Scram and Containment Isolation Due to Valve Responses During Main Turbine Control Valve Testing 05000263/LER-2023-001, Main Steam Isolation Valve Leakage Exceeds Technical Specification Requirements Due to Stem Scoring2023-05-17017 May 2023 Main Steam Isolation Valve Leakage Exceeds Technical Specification Requirements Due to Stem Scoring 05000263/LER-2022-001, Loss of Control Room Envelope Operability2022-07-0707 July 2022 Loss of Control Room Envelope Operability 05000263/LER-2017-0062018-01-12012 January 2018 Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests due to Use of a Test Fixture, LER 17-006-00 for Monticello Regarding Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Fixture 05000263/LER-2017-0052017-09-20020 September 2017 Diesel Generator Emergency Service Water System Automatic Transfer to Alternate Shutdown Panel, LER 17-005-00 for Monticello Nuclear Generating Plant Regarding Diesel Generator Emergency Service Water System Automatic Transfer to Alternate Shutdown Panel 05000263/LER-2015-0042017-08-22022 August 2017 Past Inoperability of Turbine Stop Valve Scram Function Exceeded Technical Specification Requirements, LER 15-004-01 for Monticello Regarding Past Inoperability of Turbine Stop Valve Scram Function Exceeded Technical Specification Requirements 05000263/LER-2017-0042017-08-16016 August 2017 High Pressure Coolant Injection Steam Stop Valve Failed to Open During Test, LER 17-004-00 for Monticello Regarding High Pressure Coolant Injection Steam Stop Valve Failed to Open During Test 05000263/LER-2017-0032017-06-14014 June 2017 Main Steam Isolation Valve Leakage Exceeds Technical Specification Limits, LER 17-003-00 for Monticello Regarding Main Steam Isolation Valve Leakage Exceeds Technical Specification Limits 05000263/LER-2017-0022017-06-13013 June 2017 Main Steam Isolation Valve Closure Time Outside of Technical Specification Requirements, LER 17-002-00 for Monticello Nuclear Generating Plant Regarding Main Steam Isolation Valve Closure Time Outside of Technical Specification Requirements 05000263/LER-2017-0012017-06-13013 June 2017 Reactor Scram and Group II Isolation Due to 11 Reactor Feed Pump (RFP) Removal from Service with 12 RFP Isolated, LER 17-001-00 for Monticello Regarding Reactor Scram and Group II Isolation Due to 11 Reactor Feed Pump (RFP) Removal from Service with 12 RFP Isolated 05000263/LER-2016-0012017-05-25025 May 2017 High Pressure Coolant Injection System Cracked Pipe Nipple Caused Oil Leak, LER 16-001-02 for Monticello Regarding High Pressure Coolant Injection System Cracked Pipe Nipple Caused Oil Leak 05000263/LER-2016-0032017-05-25025 May 2017 HPCI Declared Inoperable Due to Excessive Water Level in Turbine, LER 16-003-01 for Monticello Regarding HPCI Declared Inoperable Due to Excessive Water Level in Turbine 05000263/LER-2016-0022016-09-30030 September 2016 Inadequate Appendix R Fire Barrier Impacts Safe Shutdown Capability, LER 16-002-00 for Monticello Regarding Inadequate Appendix R Fire Barrier Impacts Safe Shutdown Capability 05000263/LER-2014-0022016-07-13013 July 2016 Torus to Drywell Vacuum Breaker Did Not Indicate Closed During Testing, LER 14-002-01 for Monticello Regarding Torus to Drywell Vacuum Breaker Did Not Indicate Closed During Testing 05000263/LER-2014-0032016-07-13013 July 2016 Torus to Drywell Vacuum Breaker Dual Indication During Testing, LER 14-003-01 for Monticello Nuclear Generating Plant RE: Torus to Drywell Vacuum Breaker Dual Indication During Testing 05000263/LER-2015-0072016-01-21021 January 2016 Loss of Residual Heat Removal Capability, LER 15-007-00 for Monticello Regarding Loss of Residual Heat Removal Capability 05000263/LER-2015-0062016-01-21021 January 2016 - Reactor Scram due to Group 1 Isolation from Foreign Material in the Main Steam Flow Instrument Line, LER 15-006-00 for Monticello Regarding Reactor Scram due to Group 1 Isolation from Foreign Material in the Main Steam Flow Instrument Line ML1015505712009-09-12012 September 2009 Event Notification for Monticello on State Offsite Notification Due to Not Meeting Permit Requirements L-MT-05-035, LER 50-004-00 for Monticello Nuclear Generating Plant Regarding Voluntary LER for Control Rod Drive Insert Line Leakage2005-05-12012 May 2005 LER 50-004-00 for Monticello Nuclear Generating Plant Regarding Voluntary LER for Control Rod Drive Insert Line Leakage ML0216100952002-05-15015 May 2002 LERs 02-001-01 & 02-002-01 for Monticello Nuclear Generating Plant Re Mechanical Pressure Regulator Failure Causes Reactor Scram & Application of Instrument Deviation Acceptance Criteria Allowed As-Found Settings to Be Outside Tech Spec Val 2024-08-27
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Xcel Energy August 27, 2024 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 Licensee Event Report 2024-002-00 2807 West County Road 75 Monticello, MN 55362 L-MT-24-024 10 CFR 50.73 Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), hereby submits Licensee Event Report (LER) 50-263/2024-002-00 per 10 CFR 50.73(a)(2)(v)(B) and 10 CFR 50.73(a)(2)(v)(D).
If you have any questions about this submittal, please contact Carrie Seipp, Senior Regulatory Engineer, at 612-330-5576.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
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Greg D Brown Plant Manager, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC State of Minnesota
ENCLOSURE MONTICELLO NUCLEAR GENERATING PLANT LICENSEE EVENT REPORT 50-263/2024-002-00 3 pages follow
Abstract
On June 28, 2024 at 0110 CDT Monticello Nuclear Generating Plant was in Mode 1 at 100 percent power and performing OSP-RHR-0556 Residual Heat Removal (RHR) Water Fill Verification Technical Specification Surveillance Procedure. When the RHR Low Pressure Coolant Injection (LPCI) Motor Valve MO-2012 "RHR Division 1 LPCI Injection Outboard Valve" was attempted to be cycled, the Motor Valve opened approximately one inch then stopped. With the Motor Valve incapable of opening, the A LPCI injection path was inoperable for injection as an Emergency Core Cooling system; and due to the plant design of the LPCI Loop Select Logic, this rendered both subsystems of LPCI inoperable.
The cause of the event was that the Motor Valve's motor pinion was not secured to the motor shaft because an incorrect-sized set screw was installed. The shorter motor pinion set screw relaxed, allowing the motor pinion to move axially along the motor shaft until it no longer engaged the worm shaft clutch gear.
On June 29, 2024, the motor pinion was adjusted back into position on the motor shaft. On August 7, 2024, the incorrect motor pinion set screw was replaced with the correct set screw.
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052 050 ASSESSMENT OF SAFETY CONSEQUENCES Actual safety consequences of the event were minimal for both normal operation and design basis event operation based on the operability during this time of all High Pressure Emergency Core Cooling System (ECCS), as well as both loops of the Low Pressure ECCS subsystem of Core Spray. The remaining functions of RHR including Drywell Spray and Suppression Pool Cooling remained operable despite the loss of the LPCI subsystem ability to inject into A LPCI Injection Path. Based on the operability of these additional sources of coolant to the core, the consequences of this event were minimal. There was no impact on the health and safety of the public or plant personal. There were no radiological or industrial impacts associated with this event. The health and safety of the public and site personnel were not impacted during this event.
CAUSE OF THE EVENT The Motor Valve failed to operate because the motor pinion was not secured to the motor shaft because an incorrect-sized set screw was installed. The shorter motor pinion set screw relaxed, allowing the motor pinion to move axially along the motor shaft until it no longer engaged the worm shaft clutch gear.
CORRECTIVE ACTIONS On June 29, 2024, the Motor Valves motor pinion was adjusted back into position on the motor shaft. On August 7, 2024, the incorrect motor pinion set screw on the Motor Valve was replaced with the correct set screw.
PREVIOUS SIMILAR EVENTS There were no previous similar events in the past three years.
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05000263/LER-2024-001, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component | Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure | Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
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