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Category:Letter
MONTHYEARML24283A1192024-10-28028 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 ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 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 ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS 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 ML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 ML24135A1902024-05-14014 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report IR 05000263/20240102024-05-13013 May 2024 Age-Related Degrading Inspection Report 05000263/2024010 ML24128A0042024-05-0909 May 2024 Letter to Minnesota State Historic Preservation Office- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renewal Application ML24127A1472024-05-0909 May 2024 Letter to Mille Lacs Band- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renew. Application 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) ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000263/20240012024-04-29029 April 2024 Plan - Integrated Inspection Report 05000263/2024001 ML24115A2902024-04-25025 April 2024 Sec106 Tribal, Jackson-Street, Lonna-Spirit Lake Nation ML24115A2872024-04-25025 April 2024 Sec106 Tribal, Dupuis, Kevin-Fond Du Lac Band of Lake Superior Chippewa ML24115A2932024-04-25025 April 2024 Sec106 Tribal, Johnson, Grant-Prairie Island Indian Community ML24115A3062024-04-25025 April 2024 Sec106 Tribal, Wassana, Reggie-Cheyenne and Arapaho Tribes 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 ML24115A3032024-04-25025 April 2024 Sec106 Tribal, Taylor, Louis-Lac Courte Oreilles Band of Lake Superior Chippewa Indians ML24115A3002024-04-25025 April 2024 Sec106 Tribal, Rhodd, Timothy-Iowa Tribe of Kansas and Nebraska ML24115A2972024-04-25025 April 2024 Sec106 Tribal, Miller, Cole-Shakopee Mdewakanton Sioux Community ML24115A2962024-04-25025 April 2024 Sec106 Tribal, Larsen, Robert-Lower Sioux Indian Community ML24115A2952024-04-25025 April 2024 Sec106 Tribal, Kakkak, Gena-Menominee Indian Tribe of Wisconsin ML24115A2982024-04-25025 April 2024 Sec106 Tribal, Reider, Anthony-Flandreau Santee Sioux Tribe ML24115A2912024-04-25025 April 2024 Sec106 Tribal, Jacskon, Sr., Faron-Leech Lake Band of Ojibwe ML24115A3052024-04-25025 April 2024 Sec106 Tribal, Vanzile, Jr., Robert-Sokaogon Chippewa Community ML24115A2992024-04-25025 April 2024 Sec106 Tribal, Renville, J. Garret-Sisseton Wahpeton Oyate of the Lake Travers Reservation ML24115A3022024-04-25025 April 2024 Sec106 Tribal, Stiffarm, Jeffrey-Fort Belknap Indian Community ML24115A3072024-04-25025 April 2024 Sec106 Tribal, Williams, Jr., James-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24115A2892024-04-25025 April 2024 Sec106 Tribal, Fowler, Thomas-St. Croix Chippewa of Wisconsin 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
[Table view] |
LER-2023-003, Condition Prohibited by Technical Specifications Due to Inoperable Main Steam Line Low Pressure Isolation Switch |
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text
fl Xcel Energy* 2807 West County Road 75 Monticello, MN 55362
December 4, 2023 L-MT-23-053 10 CFR 50.73
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 2023-003-00
Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), hereby submits Licensee Event Report (LER) 50-263/2023-003-00 per 10 CFR 50. 73(a)(2)(i)(B).
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.
Greg, D,efe'o,/~ -Bro.)H11 / ~-
Plant Manager, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota
Enclosure
cc: Administrator, Region 111, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC State of Minnesota ENCLOSURE
MONTICELLO NUCLEAR GENERATING PLANT LICENSEE EVENT REPORT 50-263/2023- 003- 00
3 pages follow
Abstract
On October 10, 2023 at 0826, with Monticello Nuclear Generating Plant in Mode 1 at 100 percent power, calibration commenced for PS-2-134B, the B1 Channel Main Steam Line Low Pr essure Isolation switch. The calibration is required for the Low Main Steam Line Pressure Isolation function for Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation. The B1 Channel switch was found out of tolerance low.
On October 7, 2023 at 0228, while at 10 percent power, the plant entered Mode 1, which is the Mode of Applicability for this Technical Specification 3.3.6.1 function. The condition of inoperability of the B1 Channel was not known upon entering Mode 1 and the required technical specification actions to place this Channel in trip were not taken. This event is reportable under 10CFR 50.73(a)(2)(i)(B) as an operation or condition prohibited by TS 3.3.6.1.
The cause of the inoperability was instrument drift. The B1 Channel switch was brought within tolerance prior to completion of the B1 channel calibration procedure on October 10, 2023 at 0901.
EVENT DESCRIPTION
On October 10, 2023 at 0826, with Monticello Nuclear Generating Plant in Mode 1 at 100 percent power, testing commenced for PS-2-134B [EIIS CODE: JM], the B1 Channel Main Steam Line Low Pressure Isolation switch, per the quarterly Technical Specification (TS) Surv eillance Requirem ent (SR) 3.3.6.1.4 channel calibration procedure for function 1.b. Function 1.b is the Low Main Steam Line (MSL) Pressure Isolation function for TS 3.3.6.1, Primary Containment Isolation Instrumentation. The B1 Channel switch was found out of tolerance at 641.6 psig compared to the TS allowable value of greater than or equal to 815 psig. The B1 Channel switch was brought into tolerance prior to completion of the B1 Channel switch SR 3.3.6.1.4 channel calibration procedure on October 10, 2023 at 0901.
On October 24, 2023, a review of past Operability was completed for the B1 Channel switch. The B1 Channel switch as-found and as-left values were acceptable during the previous SR 3.3.6.1.4 channel calibration procedure on July 3, 2023.
Based on review of the plant process computer MSL pressure data, the B1 Channel switch acceptably tripped at greater than the TS allowable value during the September 27, 2023 Scram. However, when the plant was starting up, in Mode 2, at 4 percent power on October 7, 2023 at 0047, the data showed the B1 Channel switch reset prior to 686.7 psig. Since this switch is designed to reset at a higher pressure than the trip pressure, this was the first indication that the B1 Channel switch was below the allowable value. Since the plant mode switch was in Startup, the MSL low pressure Containment Isolation signal was bypassed.
On October 7, 2023 at 0228 while at 10 percent power, the plant entered Mode 1, which is the Mode of Applicability for Technical Specification 3.3.6.1 function 1.b. The condition of inoperability of the B1 Channel was not known upon entering Mode 1 and the required technical specification actions to place this Channel in trip were not taken.
The Primary Containment Isolation system receives inputs from four channels for the MSL Low Pressure trip function. The trip function, active only during Mode 1, uses a one-out-of-two taken twice logic to initiate isolation of all Main Steam Isolation valves (MSIVs), MSL drain valves, and recirculation sample isolation valves. One of the two A channels and one of the two B channels must trip to initiate the Primary Containment Isolation. In Mode 1, with one channel inoperable, TS 3.3.6.1 Condition A requires placing that channel in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. When Condition A is not met, Condition E, as directed by Condition C and Table 3.3.6.1-1 requires entry to Mode 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
This event is reportable under 10 CFR 50.73(a)(2)(i)(B) as an operation or condition prohibited by TS 3.3.6.1.
DATES AND APPROXIMATE TIMES OF MAJOR OCCURANCES
- July 3, 2023 at 0850: The B1 Channel switch as-found and as-left values were acceptable per the SR 3.3.6.1.4 channel calibration procedure.
- September 27, 2023 at 1041: During Reactor Scram and Group 1 isolation on C channel MSL high flow, the B1 Channel switch tripped at 925.5 psig, which is acceptably greater than the TS minimum allowable value.
- October 7, 2023 at 0047: During plant startup, the B1 Channel switch reset prior to 686.7 psig, which is less than the TS minimum allowable value.
- October 7, 2023 at 0228: Event Date. Plant mode switch was placed in r un and the plant entered Mode 1.
- October 8, 2023 at 0228: The required completion time to place the B1 Channel in trip based on TS 3.3.6.1 Condition A for One or more required channels inoperable.
- October 8, 2023 at 0828: The required completion time to be in Mode 2 due to TS 3.3.6.1 Condition E, as directed by Condition C and Table 3.3.6.1-1.
- October 10, 2023 at 0801: PS-2-134A, the A1 Channel MSL Low Pressure Isolation switch, SR 3.3.6.1.4 channel calibration procedure commenced and identified an acceptable as-found value.
- October 10, 2023 at 0825: The A1 Channel switch SR 3.3.6.1.4 channel calibration procedure concluded with an acceptable as-left value.
- October 10, 2023 at 0826: Discovery Date. The B1 Channel switch SR 3.3.6.1.4 channel calibration procedure commenced and identifie d an unacceptable as-found value of 641.6 psig.
- October 10, 2023 at 0901: The B1 Channel switch SR 3.3.6.1.4 channel calibration procedure concluded with an acceptable as-left value of 842.1 psig.
- October 24, 2023: Past Operability review concluded the B1 Channel switch was inoperable since entering Mode 1 on October 7, 2023 at 0228 until the condition was identified and corrected on October 10, 2023.
- November 20, 2023 at 0825 CST: The B1 Channel switch SR 3.3.6.1.4 procedure commence d at half of the required Surveillance Frequency and identified an acceptable as found value.
- November 20, 2023 at 0915 CST: The B1 Channel switch SR 3.3.6.1.4 procedure concluded at half of the required Surveillance Frequency with an acceptable as left value.
ASSESSMENT OF SAFETY CONSEQUENCES
There were no radiological, environmental, or industrial impacts associated with this event. The health and safety of the public and site personnel were not impacted during this event.
The Primary Containment Isolation function was maintained during the period of inoperability of the B1 Channel since at least one A Channel and one B Channel would have initiated a Primary Containment Isolation if low MSL pressure was present. The three other MSL Low Pressure Isolation Channels were operable in the condition of inoperability of the B1 Channel prior to performance of the SR 3.3.6.1.4 channel calibration procedure. When PS-2-134A, the A1 Channel MSL Low Pressure Isolation switch, was removed from service for calibration per the SR 3.3.6.1.4 channel calibration procedure prior to the testing of the B1 Channel switch, both the A2 Channel and B2 Channel were Operable.
There were no structures, systems, or components (SSCs) whose inoperability contributed to this event.
CAUSE OF THE EVENT
The cause of the failure of the B1 Channel switch was instrument drift. Since no specific failure mechanism was identified, a performance at half of the required SR 3.3.6.1.4 channel calibration procedure period was performed on November 20, 2023. The as-found and as-left values were acceptable.
CORRECTIVE ACTIONS
The B1 Channel switch was brought within tolerance prior to completion of the SR 3.3.6.1.4 channel calibration procedure on October 10, 2023.
PREVIOUS SIMILAR EVENTS
No previous similar events have occurred at MNGP in the prior 3 years.
NOTES All times are in Central Daylight Time (CDT) unless otherwise noted.