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Category:Letter
MONTHYEARML25071A3562025-03-13013 March 2025 And Prairie Island Nuclear Generating Plant Site Specific Emergency Action Level Technical Basis Documents Change ML25073A0452025-03-13013 March 2025 Ametek Sci - Notification of Potential Defect - 10CFR Part 21 L-PI-25-006, Units, 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in Actuated Positions2025-03-12012 March 2025 Units, 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in Actuated Positions ML25071A0332025-03-12012 March 2025 Confirmation of Initial License Examination IR 05000282/20240062025-03-11011 March 2025 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024006 and 05000306/2024006) L-PI-25-013, (PINGP) Unit 2 Inservice Testing (IST) 5th Interval Proposed Alternative RR-11 in Accordance with Crf 50.55a(z)(2)2025-03-11011 March 2025 (PINGP) Unit 2 Inservice Testing (IST) 5th Interval Proposed Alternative RR-11 in Accordance with Crf 50.55a(z)(2) ML25069A3222025-03-10010 March 2025 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generatig Plant ML25059A2822025-03-0303 March 2025 Project Manager Assignment ML25059A3112025-02-28028 February 2025 Submittal of Fitness for Duty Performance Data for 2024 ML25055A1032025-02-24024 February 2025 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML25043A1252025-02-12012 February 2025 Independent Spent Fuel Storage Installation (ISFSI) Annual Effluent Report, January Through December 2024 IR 05000282/20240042025-02-11011 February 2025 Integrated Inspection Report 05000282/2024004 and 05000306/2024004 ML25027A0992025-01-24024 January 2025 Interim Report of a Potential Deviation of 2 Inch Globe Valve ML25021A2802025-01-23023 January 2025 – Proposed Alternative RR-10 Regarding Letdown Line Isolation Train B Control Valve CV-31279 IR 05000282/20250122025-01-22022 January 2025 Notification of 10 CFR 50.69 Risk Informed Categorization and Treatment of Sscs for Nuclear Power Reactors Inspection 05000282/2025012 05000306/2025012 05000306/LER-2024-002, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to High Negative Neutron Flux Rate Trip2024-12-19019 December 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to High Negative Neutron Flux Rate Trip L-PI-24-051, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification (TS) Definitions and Adopt Plant Specific Methods for Response Time Testing (Rtt)2024-12-18018 December 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification (TS) Definitions and Adopt Plant Specific Methods for Response Time Testing (Rtt) ML24354A2952024-12-18018 December 2024 ISFSI and Monticello Nuclear Generating Plant - Independent Spent Fuel Storage Installation Decommissioning Funding Plans IR 05000282/20244022024-12-17017 December 2024 Cyber Security Inspection Report 05000282/2024402 and 05000306/2024402 (Public) ML24271A2922024-11-20020 November 2024 – Correction of License Amendment Nos. 243 and 231 Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (EPID-L-2022-LLA-0184) ML24324A1722024-11-20020 November 2024 Request for Information for the NRC Age Related Degradation - Inspection Report 05000282/2025011 & 05000306/2025011 IR 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 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 ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information 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 2025-03-03
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000306/LER-2024-002, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to High Negative Neutron Flux Rate Trip2024-12-19019 December 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to High Negative Neutron Flux Rate Trip 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 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-2019-001, For Prairie Island Nuclear Generating Plant, Unit 2, Reactor Coolant Isolation Valve Leakage Results in Condition Prohibited by Technical Specifications2019-09-27027 September 2019 For Prairie Island Nuclear Generating Plant, Unit 2, Reactor Coolant Isolation Valve Leakage Results in Condition Prohibited by Technical Specifications 05000306/LER-2018-001-01, Automatic Actuation of Emergency Diesel Generator D52018-09-17017 September 2018 Automatic Actuation of Emergency Diesel Generator D5 05000306/LER-2018-002, RHR Flood Barriers Compensatory Measures2018-07-18018 July 2018 RHR Flood Barriers Compensatory Measures 05000306/LER-2018-001, For Prairie Island Nuclear Generating Plant, Unit 2, Automatic Actuation of Emergency Diesel Generator D52018-07-16016 July 2018 For Prairie Island Nuclear Generating Plant, Unit 2, Automatic Actuation of Emergency Diesel Generator D5 05000282/LER-2018-001, Motor Driven Cooling Water Pump Auto Start Due to Smoking Packing on 11 Cooling Water Pump2018-03-0707 March 2018 Motor Driven Cooling Water Pump Auto Start Due to Smoking Packing on 11 Cooling Water Pump 05000306/LER-1917-003, Regarding Both Containment Spray Pump Control Switches in Pull-Out in Mode 42018-01-11011 January 2018 Regarding Both Containment Spray Pump Control Switches in Pull-Out in Mode 4 05000306/LER-1917-002, Regarding Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect2017-12-11011 December 2017 Regarding Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect 05000306/LER-1917-001, Regarding 23 Containment Fan Coil Unit Operability2017-11-29029 November 2017 Regarding 23 Containment Fan Coil Unit Operability 05000282/LER-2016-006, Regarding 121 Motor Driven Cooling Water Pump Auto Start2017-02-15015 February 2017 Regarding 121 Motor Driven Cooling Water Pump Auto Start 05000282/LER-2015-005-01, Regarding Condition Prohibited by Technical Specifications2016-10-10010 October 2016 Regarding Condition Prohibited by Technical Specifications 05000282/LER-2016-005, Regarding 121 Motor Driven Cooling Water Pump Auto Start2016-10-0707 October 2016 Regarding 121 Motor Driven Cooling Water Pump Auto Start 05000282/LER-2016-004, Regarding Missing Fire Barrier Between Fire Area (FA) 59 and 85 / Fire Hazard Analysis Drawings Do Not Match Boundary Description2016-06-21021 June 2016 Regarding Missing Fire Barrier Between Fire Area (FA) 59 and 85 / Fire Hazard Analysis Drawings Do Not Match Boundary Description 05000282/LER-2016-002, Regarding Listed System Actuation - Motor-Driven Cooling Water Pump Auto-Start2016-03-25025 March 2016 Regarding Listed System Actuation - Motor-Driven Cooling Water Pump Auto-Start 05000282/LER-2016-001, Regarding Unanalyzed Condition Due to Non-Compliant Fire Protection Manual Operator Actions2016-02-18018 February 2016 Regarding Unanalyzed Condition Due to Non-Compliant Fire Protection Manual Operator Actions 05000306/LER-2016-001, Regarding Reactor Trip Due to a Ground Fault Resulting in a Generator Trip2016-02-12012 February 2016 Regarding Reactor Trip Due to a Ground Fault Resulting in a Generator Trip 05000282/LER-2015-005, Regarding Possible Misapplication of C18.1, Engineered Safeguards Equipment Support Systems2015-11-0909 November 2015 Regarding Possible Misapplication of C18.1, Engineered Safeguards Equipment Support Systems 05000282/LER-2015-006, Regarding Quarterly Containment Spray Pump Surveillance Test Method2015-10-0505 October 2015 Regarding Quarterly Containment Spray Pump Surveillance Test Method 05000282/LER-2015-002, Cancellation of Licensee Event Report (LER) 50-282/2015-002-00, 14 Fan Coil Unit Leak (Lower Head)2015-09-0303 September 2015 Cancellation of Licensee Event Report (LER) 50-282/2015-002-00, 14 Fan Coil Unit Leak (Lower Head) 05000282/LER-2015-001, 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 05000306/LER-2015-003, Regarding Turbine/Reactor Trip - Low Bearing Oil Pressure2015-08-0505 August 2015 Regarding Turbine/Reactor Trip - Low Bearing Oil Pressure 05000282/LER-2015-004, Regarding Manual Reactor Trip Due to Trip of Condensate and Main Feedwater Pump2015-07-23023 July 2015 Regarding Manual Reactor Trip Due to Trip of Condensate and Main Feedwater Pump 05000306/LER-2015-002, Regarding 21 Feedwater Pump Lockout, Unit 2 Reactor Trip Due to Pressure Switch Failure2015-06-0101 June 2015 Regarding 21 Feedwater Pump Lockout, Unit 2 Reactor Trip Due to Pressure Switch Failure 05000282/LER-2014-004-01, (Pingp), Unit 1, Regarding Regarding Unanalyzed Condition Due to Lack of Appropriate Fuse Protection - Supplement2015-03-31031 March 2015 (Pingp), Unit 1, Regarding Regarding Unanalyzed Condition Due to Lack of Appropriate Fuse Protection - Supplement 05000282/LER-2014-002-01, Regarding Emergency Diesel Generators Declared Inoperable Due to Not Meeting High Energy Line Break Requirements2015-01-30030 January 2015 Regarding Emergency Diesel Generators Declared Inoperable Due to Not Meeting High Energy Line Break Requirements 05000282/LER-2014-005, Transmittal of LER 14-005-00, for Prairie Island, Units 1 & 2 Regarding Vital Equipment Not Identified Safeguards Information2014-10-27027 October 2014 Transmittal of LER 14-005-00, for Prairie Island, Units 1 & 2 Regarding Vital Equipment Not Identified Safeguards Information 05000282/LER-2014-003, Regarding Emergency Diesel Generator Auto Start Due to Degraded Bus Voltage Signal2014-08-20020 August 2014 Regarding Emergency Diesel Generator Auto Start Due to Degraded Bus Voltage Signal 05000282/LER-2014-002, Regarding Emergency Diesel Generators Declared Inoperable Due to Not Meeting High Energy Line Break Requirements2014-08-0404 August 2014 Regarding Emergency Diesel Generators Declared Inoperable Due to Not Meeting High Energy Line Break Requirements 05000306/LER-2014-002, Regarding 23 Fan Coil Unit Lower Northeast Face Corner Gasket Leaking2014-07-15015 July 2014 Regarding 23 Fan Coil Unit Lower Northeast Face Corner Gasket Leaking 05000306/LER-2014-001, Re Unanalyzed Condition Due to Removal of Multiple Steam Generator Lateral Support Shims and Bumpers2014-03-0303 March 2014 Re Unanalyzed Condition Due to Removal of Multiple Steam Generator Lateral Support Shims and Bumpers 05000282/LER-2013-002, Regarding Unanalyzed Condition - Fuel Oil Inadequate Replenishment2013-11-18018 November 2013 Regarding Unanalyzed Condition - Fuel Oil Inadequate Replenishment 05000282/LER-2013-001, Regarding Control Room Envelope Inoperable2013-10-0808 October 2013 Regarding Control Room Envelope Inoperable 05000282/LER-2012-005-01, Regarding Diesel Generators Inoperable Due to Exhaust Fire2013-07-25025 July 2013 Regarding Diesel Generators Inoperable Due to Exhaust Fire 05000282/LER-2012-004, Cancellation of LER 12-004-00 for Prairie Island Nuclear Generating Plant, Unit 1, Emergency Diesel Generators Declared Inoperable Due to High Ambient Temperatures2012-12-13013 December 2012 Cancellation of LER 12-004-00 for Prairie Island Nuclear Generating Plant, Unit 1, Emergency Diesel Generators Declared Inoperable Due to High Ambient Temperatures 05000282/LER-2012-005, Regarding Diesel Generators Inoperable Due to Exhaust Fire2012-10-12012 October 2012 Regarding Diesel Generators Inoperable Due to Exhaust Fire 05000306/LER-2012-002, Diesel Generators Inoperable Due to Missing Flood Control Barrier Seal2012-09-14014 September 2012 Diesel Generators Inoperable Due to Missing Flood Control Barrier Seal 05000282/LER-2012-002, For Prairie Island, Unit 1, Regarding Unplanned Actuation of 121 Motor Driven Cooling Water Pump2012-05-30030 May 2012 For Prairie Island, Unit 1, Regarding Unplanned Actuation of 121 Motor Driven Cooling Water Pump 2024-09-16
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Xcel Energye January 28,201 1 L-PI-1 1 -003 10 CFR 50.73 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Conditions Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, herewith encloses Licensee Event Report (LER) 50-2821201 0-004-00.
Summary of Commitments This letter contains no new commitments and no changes to existing commitments.
Kevin Davison Plant Manager, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Prairie Island Nuclear Generating Plant (PINGP), USNRC Resident Inspector, PINGP, USNRC Department of Commerce, State of Minnesota f
I1 j
P 171 7 Wakonade Drive East Welch, Minnesota 55089-9642 ii Telephone: 651.388.1 121 E
ENCLOSURE LICENSEE EVENIT REPORT 60-28212010-004-08 4 Pages Follow
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[7 50.73(a)(2)(il)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(4) a 50.73(a)(2)(ii)(B) 50.73(a)(2)(v[ii)(B) 20.2203(a)(2)(i)
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50.36(c)(l)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(~)(2) 5OS73(a)(2)(v)(A) 73.71 (a)(4)
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE).
O NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
Safety related battery chargers have the potential to stop providing an output, or "lock up", if their AC input voltage drops below their nameplate minimum voltage of 90% of 480V at the battery charger Motor Control Center. Exact voltage, duration of voltage dip, and charger loading conditions which cause lock up of chargers are unknown. If a reduction in input voltage results in a battery charger locking up, the battery charger will not be able to recharge the battery from a partially discharged state unless operator actions are taken to restore the battery charger.
On October, 22, 201 0, an operability determination concluded that specific Design Basis Accident scenarios may include this undervoltage condition which could cause the battery chargers to lock up. The design basis requirements of the safeguards battery are such that it can carry expected shutdown loads for the DC system for one hour. Compensatory measures in the form of new operator actions have been put in place to support restoration of the battery chargers within this timeframe.
i NRC FORM 366 (10-2010)
EVENT DESCRIPTION
At the Prairie Island Nuclear Generating Plant (PINEP), the safeguards 125 VDC Electrical Power system1 for each unit consists of two independent and redundant safety related DC electrical power subsystems (Train A and Train B). 125 VDC Subsystems 11 and 12 serve Unit 1 and 125 VDC Subsystems 21 and 22 serve Unit 2. Each subsystem consists of one 125 VDC battery, battery charger, and associated distribution equipment.
The 125 VDC Systems supply instrumentation, control, and motive power to safety related equipment. Redundant safety related equipment is divided between the two DC subsystems associated with each unit such that the loss of one DC subsystem does not affect redundant circuits.
There are five safeguards battery chargers, one per 125 VDC Subsystem plus one portable battery charger. The installed battery chargers are supplied from the associated safeguards 480 VAC System Motor Control Center (MCC)*. The battery chargers supply DC electrical power to the connected loads while maintaining the safeguards batteries in a fully charged condition during normal operation.
Safety related battery chargers have the potential to stop providing an output, or "lock up", if their AC input voltage drops below their nameplate minimum voltage of 90% of 480V at the battery charger MCC. Exact voltage, duration of voltage dip, and charger loading conditions which cause lock up of chargers are unknown. On October 22, 2010, an operability determination concluded that specific Design Basis Accident (DBA) scenarios may include this undervoltage condition which could cause the battery chargers to lock up. Compensatory measures were put in place to restore the battery chargers in the event of battery charger lock up.
The past operability review performed in December of 201 0 concluded that there is reasonable doubt that the battery chargers would have performed their safety functions if called upon during the scenarios discussed in the October 22, 201 0 operability determination. On December 23, 201 0, with PlNGP Units 1 and 2 operating in MODE 1 at 100% power, this condition was reported via ENS Notification#46508.
The reported condition represents inoperability of the battery charger in both trains of the 125 VDC Electrical Power System. This is reportable as common-cause inoperability of independent trains or channels under 10 CFR 5OW73(a)(2)(vii),
a condition that could have prevented fulfillment of a safety function under 10 CFR 50.73(a)(2)(v)(D), and an unanalyzed condition under 10 CFR 50.73 (a) (2) (i i) (B).
' Ells System Code: EJ Ells System Code: ED
Review of analytical documentation identified two DBA scenarios in which the baMery charger" AAC input voltage could reach values low enough to cause the chargers to lock up. The DBA scenarios are 1) Safety Injection (SI) with Loss of Bffiste Power (LOOP) and 2) SI without LOOP. A condition evaluation found that voltages calculated during the DBA for a dual unit trip with one unit in Safety Injection (SI) and the other unit in Mot Shutdown may result in a voltage dip of 8O0/0 or below at one or more battery charger MCC" depending on the plant distribution system configuration and grid system conditions. 80% was used in the evaluation based on past integrated St test SP1083 test data and conditions in which the 12 Battery Charger experienced lock up. The evaluation also concluded that during an SI, when powered by any of the emergency diesel generators3, the potential exists for the battery chargers to experience inadequate input voltage that could cause them to lock up due to out of sequence loading occurring. The evaluation concluded that this would only affect the battery chargers that are on an SI unit during a LOOP and would not affect the battery chargers on the non-SI unit.
If a reduction in input voltage results in battery charger lock up, the battery charger will not be able to recharge the battery from a partially discharged state without manual action. The design basis requirements of the safeguards battery is such that it can carry expected shutdown loads for the DC system for one hour. However, a specific battery charger would not be able to recharge the battery or supply its emergency loads if it locks up and is not restarted before minimum battery terminal voltage is reached. Operator actions would need to be taken to restore the battery charger.
Procedure changes have been made to support restoration of the battery charger. Emergency procedures were revised to verify that battery charger operation is normal. Abnormal operating procedures were revised to add specific guidance to restore the battery chargers. Staffing concerns have been addressed by designating a Battery Charger Watch.
The condition described in this LER represents a Safety System Functional Failure reportable under i
k 10 CFR 50.73(a)(2)(v)(D).
I I
SAFETY SIGNIFICANCE
Under certain undervoltage conditions, the battery chargers may lock up. As discussed above, the safety related batteries have design basis requirements to carry expected shutdown loads for the DC system for one hour. Operating procedures were in place to give guidance to restart the battery chargers if a voltage transient had occurred.
Ells System Code: EK
CAUSE
A 1994 design change replaced the battery chargers. The new chargers were susceptible to the lock up condition as described above. The potential for the baltery chargers to lock up was not detected by post-modification testing,
CORRECTIVE ACTION
To address staffing concerns, the responsibilities of a designated Battery Charger Watch were outlined in an operating procedure. Procedure changes have been mads to support restoration of the battery chargers.
A modification will be installed during or prior to the Unit 1 201 1 refueling outage to ensure that 12 Battery Charger will perform its design function. Additional steps to resolve the existing non-conforming condition on the remaining battery chargers are being driven by the corrective action program.
PREVIOUS SIMILAR EVENTS
LER 50-2821201 0-005-00 was submitted on November 8, 201 0. This LER reported the failure to complete Surveillance Requirements (SR) as required by TS.
SR 3.8.1.1 0(c) is partially fulfilled by the performance of SP 1083. In 1997, during performance of the Integrated SI test for Unit I, the 12 Battery Charger stopped running (due to undervoltage conditions) after bus restorations. In 1999, SP1083 was changed to turn off the 12 Battery Charger during the performance of the SP. In September of 2010, site personnel determined that the SP 1083 testing configuration did not fulfill the TS requirements.
In October of 201 0, additional evaluations were completed to review the extent of the condition experienced by 12 Battery Charger for other voltage support considerations for all four station Battery Chargers. These evaluations identified the condition reported in this LER.
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05000282/LER-2010-001, For Prairie Island, Unit 1, Regarding Unanalyzed Condition Due to Postulated High Energy Line Break on Cooling Water System | For Prairie Island, Unit 1, Regarding Unanalyzed Condition Due to Postulated High Energy Line Break on Cooling Water System | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000306/LER-2010-001, Regarding Unit 2 Turbine Trip During Reactor Shutdown Resulting in a Reactor Scram | Regarding Unit 2 Turbine Trip During Reactor Shutdown Resulting in a Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2) | 05000306/LER-2010-002, For Prairie Island, Unit 2, Regarding Turbine Shutdown Due to Loss of a Main Feed Water Pump That Resulted in a Reactor Scram | For Prairie Island, Unit 2, Regarding Turbine Shutdown Due to Loss of a Main Feed Water Pump That Resulted in a Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000282/LER-2010-002, Regarding Postulated Flooding of Unit 1 Fuel Oil Transfer Pump Motor Starters Could Have Resulted in Reduced Fuel Oil Inventory | Regarding Postulated Flooding of Unit 1 Fuel Oil Transfer Pump Motor Starters Could Have Resulted in Reduced Fuel Oil Inventory | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000282/LER-2010-003, Regarding Postulated Flooding of Battery Rooms Due to Lnadequate Battery Room Door Threshold Seals | Regarding Postulated Flooding of Battery Rooms Due to Lnadequate Battery Room Door Threshold Seals | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000306/LER-2010-003, Regarding Unit 2 Fuel Oil Transfer Pumps Are Vulnerable to a Potential Common Mode Failure | Regarding Unit 2 Fuel Oil Transfer Pumps Are Vulnerable to a Potential Common Mode Failure | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(viii)(A) | 05000282/LER-2010-004, For Prairie Island, Unit 1, Regarding Battery Charger Inoperability Due to Potential Undervoltage Conditions | For Prairie Island, Unit 1, Regarding Battery Charger Inoperability Due to Potential Undervoltage Conditions | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | 05000282/LER-2010-005, Regarding Surveillance Required by Technical Specifications for the Emergency Diesel Generator Not Completed | Regarding Surveillance Required by Technical Specifications for the Emergency Diesel Generator Not Completed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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