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Category:Letter
MONTHYEARIR 05000282/20240032024-11-13013 November 2024 Integrated Inspection Report 05000282/2024003, 05000306/2024003 & 07200010/2024001 ML24310A1682024-11-0505 November 2024 Core Operating Limits Report (COLR) for Cycle 34, Revision 0 ML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 April 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 To Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables ML24262A1512024-03-15015 March 2024 L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam ML24010A0582024-03-0505 March 2024 Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 2024-09-27
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 April 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables 05000282/LER-2023-001, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2023-12-0404 December 2023 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables 05000306/LER-2023-001, Gt/Xfmr Lockout Due to Failure of Lightning Arrester Caused Unit 2 Reactor Trip2023-07-18018 July 2023 Gt/Xfmr Lockout Due to Failure of Lightning Arrester Caused Unit 2 Reactor Trip 05000282/LER-2022-001, Fuel Assemblies Incorrectly Placed in Spent Fuel Pool2022-10-17017 October 2022 Fuel Assemblies Incorrectly Placed in Spent Fuel Pool 05000282/LER-2021-002, Loss of Electrical Bus Results in 121 Motor Driven Cooling Water Pump Auto Start2021-12-13013 December 2021 Loss of Electrical Bus Results in 121 Motor Driven Cooling Water Pump Auto Start 05000306/LER-2021-001, Turbine Driven Auxiliary Feedwater Pump Actuation Signal Due to Procedure Error2021-11-18018 November 2021 Turbine Driven Auxiliary Feedwater Pump Actuation Signal Due to Procedure Error 05000282/LER-2021-001, (Pingp), Unit 1, 12 Diesel Driven Cooling Water Pump Auto Start Due to Low System Pressure2021-03-22022 March 2021 (Pingp), Unit 1, 12 Diesel Driven Cooling Water Pump Auto Start Due to Low System Pressure 05000282/LER-2020-001, (PINGP) Unit 1, Reactor Trip Caused by Spurious Neutron Flux Signal During Reactor Protection System Testing2020-10-19019 October 2020 (PINGP) Unit 1, Reactor Trip Caused by Spurious Neutron Flux Signal During Reactor Protection System Testing ML19353A4092019-12-19019 December 2019 Technical Specification 5.6.8 Special Report: Inoperable Containment Isolation Valve Indication Supplemental Report 05000306/LER-2017-0032018-01-11011 January 2018 Both Containment SEa) Pump Control Switches in Pull-out in Mode 4, LER 17-003-00 for Prairie Island Nuclear Generating Plant, Unit 2 Regarding Both Containment Spray Pump Control Switches in Pull-Out in Mode 4 05000306/LER-2017-0022017-12-11011 December 2017 Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect, LER 17-002-00 for Prairie Island, Unit 2, Regarding Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect 05000306/LER-2017-0012017-11-29029 November 2017 23 Containment Fan Coil Unit Operability, LER 17-001-00 for Prairie Island, Unit 2, Regarding 23 Containment Fan Coil Unit Operability 05000282/LER-2016-0062017-02-15015 February 2017 121 Motor Driven Cooling Water Pump Auto Start, LER 16-006-00 for Prairie Island Nuclear Generating Plant, Units 1 and 2 Regarding 121 Motor Driven Cooling Water Pump Auto Start 05000306/LER-2015-0022016-06-22022 June 2016 21 Feedwater Pump Lockout, Unit 2 Reactor Trip Due to Pressure Switch Failure, LER 15-002-01 for Prairie Island, Unit, Regarding 21 Feedwater Pump Lockout, Reactor Trip Due to Pressure Switch Failure 05000282/LER-2016-0042016-06-21021 June 2016 1 OF 4, LER 16-004-00 for Prairie Island, Unit 1, Regarding Missing Fire Barrier Between Fire Area (FA) 59 and 85 / Fire Hazard Analysis Drawings Do Not Match Boundary Description 05000282/LER-2016-0022016-03-25025 March 2016 Listed System Actuation - Motor-Driven Cooling Water Pump Auto-Start, LER 16-002-00 for Prairie Island, Unit 1, Regarding Listed System Actuation - Motor-Driven Cooling Water Pump Auto-Start 05000306/LER-2016-0012016-02-12012 February 2016 Unit 2 Reactor Trip due to a Ground Fault resulting in a Generator Trip, LER 16-001-00 for Prairie Island, Unit 2, Regarding Reactor Trip Due to a Ground Fault Resulting in a Generator Trip L-PI-15-071, Cancellation of License Event Report (LER)50-282/2015-001-00, 14 Fan Coil Unit Leak2015-09-0303 September 2015 Cancellation of License Event Report (LER)50-282/2015-001-00, 14 Fan Coil Unit Leak L-PI-11-023, Reinstatement of Licensee Event Reports Associated with Flooding Scenarios2011-03-31031 March 2011 Reinstatement of Licensee Event Reports Associated with Flooding Scenarios L-PI-07-101, LER 07-03-001 for Prairie Island, Unit 1 Regarding Unanalyzed Condition Due to Breached Fire Barrier2008-01-25025 January 2008 LER 07-03-001 for Prairie Island, Unit 1 Regarding Unanalyzed Condition Due to Breached Fire Barrier L-PI-06-046, Cancellation of Licensee Event Report (LER) 1-05-01, Discovery of Single Failure Vulnerability of Unit 1 Safeguards Buses2006-06-0909 June 2006 Cancellation of Licensee Event Report (LER) 1-05-01, Discovery of Single Failure Vulnerability of Unit 1 Safeguards Buses 2024-09-16
[Table view] |
LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies |
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text
(l Xcel Energy*
September 16, 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Units 1 and 2 Docket Nos. 50-282 and 50-306 Renewed Facility Operating License Nos. DPR-42 and DPR-60 1717 Wakonade Drive Welch, MN 55089 L-Pl-24-041 10 CFR 50.73 Prairie Island Nuclear Generating Plant Licensee Event Report 2024-001-00 Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), hereby submits Licensee Event Report (LER) 50-282/2024-001-00 per 10 CFR 50.73(a)(2)(i)(B).
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
L BryanV urrier Plant Manager, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC State of Minnesota
ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT LICENSEE EVENT REPORT 50-282/2024-001-00 4 pages follow
Abstract
Prairie Island Nuclear Generating Plant, Unit 1
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Auxiliary Building Special Ventilation System Inoperable during movement of irradiated fuel assemblies.
05 02 2024 2024 001 00 09 16 2024 Prairie Island Unit 2
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100
Nathan Fedora 612-342-8971
10 31 2024 On May 02, 2024, the Prairie Island Nuclear Generating Plant (PINGP) Units 1 and 2 were operating at 100 percent power while performing fuel handling operations. For a 33-minute period between 12:52 and 13:25, radiation monitors 1R-37 and 2R-30 were both out of service while movement of irradiated fuel assemblies was occurring. On July 11, 2024, while completing a review of the design and licensing basis of radiation monitors 1[2]R-37, 1[2]R-30, it was determined that these monitors are required for Auxiliary Building Special Ventilation System operability during movement of irradiated fuel assemblies per Technical Specification (TS) 3.7.12. Changes to Procedures have been implemented. This will ensure compliance with TS going forward when irradiated fuel is being moved. Additional causes and corrective actions will be provided as a supplement to this LER.
This event is reportable under 10 CFR 50.73(a)(2)(i)(B) for an Operation or Condition Prohibited by Technical Specifications.Page of
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
052 050 CAUSE OF THE EVENT The cause of this event is being investigated and will be provided in a supplement to this LER.
Initial review has determined that a lack of procedural guidance related to the function of the radiation monitors contributed to the event.
CORRECTIVE ACTIONS Changes to Procedures have been implemented. This will ensure compliance with TS going forward when irradiated fuel is being moved.
Additional corrective actions will be provided in the supplement to this LER.
PREVIOUS SIMILAR EVENTS There were no previous similar events in the past three years.
ADDITIONAL INFORMATION All times are in Central Daylight Time.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
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Prairie Island Nuclear Generating Plant, Unit 1
- - 282 2024 001 00