3-25-2016 | At 1110 Central Standard Time ( CST) on 1/29/2016, the Prairie Island Nuclear Generating Plant ( PINGP) performed a planned overspeed post-maintenance test ( PMT) of 22 Diesel-Driven Cooling Water Pump ( DDCLP) in accordance with plant maintenance procedure. During the overspeed trip test PMT, 22 DDCLP tripped as expected, and 121 Motor-Driven Cooling Water Pump (MDCLP) unexpectedly started automatically ("auto-started") on low pressure in the cooling water pump discharge header. This event is reportable under 10 CFR 50.73(a)(2)(iv)(A) as an event that resulted in automatic actuation of an emergency service water system that does not normally run and that serves as ultimate heat sink.
The cause of the 121 MDCLP auto-start was a low-pressure transient in the cooling water pump discharge when 121 MDCLP started. The health and safety of the public was not at risk.
Corrective actions to be taken for this event include revising plant procedures to ensure 121 MDCLP is running prior to performing the overspeed trip test PMT and to ensure the pump is running or in pullout position to prevent auto-start of 121 MDCLP when stopping a DDCLP. |
---|
|
---|
Category:Letter
MONTHYEARML24298A0552024-10-30030 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 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 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 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance 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 L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) 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 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] |
comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
Event Description
At 1110 CST on 1/29/2016, PINGP performed a planned overspeed trip test PMT of 22 DDCLP (EIIS Component Identifier P) in accordance with preventive maintenance procedure PM 3002-2-22, 22 DDCLP Diesel Minor Periodic Maintenance. During the overspeed trip test, 22 DDCLP tripped, and 121 MDCLP (EIIS Component Identifier P) auto-started on low pressure in the cooling water pump discharge header. This event is reportable under 10 CFR 50.73(a)(2)(iv)(A) as an event that resulted in automatic actuation of an emergency service water system that does not normally run and that serves as ultimate heat sink.
Event Analysis
The PINGP Cooling Water (CL) System (EIIS System Identifier BI) is a shared system for Units 1 and 2 and provides a heat sink for the removal of process and operational heat from safety-related components during a Design Basis Accident or transient. During normal operation and shutdown, the CL System also provides this function for various safety-related and nonsafety-related components.
Five CL pumps are connected to a common pump discharge header that directs CL flow into two separate headers: three motor-driven pumps and two diesel-driven pumps. 121 MDCLP can function as a safeguards replacement when a diesel driven pump is taken out of service. In this configuration, the pump is aligned manually to the appropriate train of safeguards power and motor-operated valves are administratively disabled in accordance with technical specifications.
11 and 21 MDCLPs were running, and 121 MDCLP was not aligned as safeguards. Data from the Emergency Response Computer System (ERCS) showed that tripping 22 DDCLP resulted in a reduction of 8 psig in Loop A CL header pressure, 10 psig in Loop B CL header pressure, and over 1000 gpm in Loop B CL flow. 22 DDCLP developed a greater than normal discharge pressure while running at higher than normal speed during the overspeed PMT, and tripping the pump the higher speed caused a higher than expected change in pressure compared to stopping the pump from normal speed.
Operators correctly performed steps from plant operating and maintenance procedures intended to prevent an automatic start of 121 MDCLP. No inappropriate action was identified related to human performance. 121 MDCLP has auto-started on low pressure on previous occasions.
Pressure transients in the discharge header occur when stopping a DDCLP. Corrective actions taken since the last auto-start in April 2012 were effective in preventing auto-starts during monthly surveillance testing according to SP 1106A and SP 1106B, but they were not effective in this instance. Those corrective actions focused on running two MDCLPs and ensuring the pump discharge header was cross-connected to minimize the discharge header pressure transient when stopping a DDCLP. During this event, 22 DDCLP was running at an elevated speed, resulting in a larger transient when 22 DDCLP was stopped.
Safety Significance
121 MDCLP and other equipment operated as intended during the event. The low pressure transient was confined to the pump discharge header and did not result in below normal pressure in either cooling water Prairie Island, Unit 1 05000-282 comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
system header. Therefore, this event was of low safety significance since there was no loss of cooling water supply to safety-related or nonsafety-related system loads.
There was no radiological, environmental, nor industrial impact associated with this event, and the health and safety of the public were not affected. This event did not challenge nuclear safety as all plant systems nor Unit 2.
The likelihood of an automatic pump start during monthly surveillance tests (surveillance procedures SP 1106A, 12 Diesel Cooling Water Pump Monthly Test, and SP 1106B, 22 Diesel Cooling Water Pump Monthly Test) is low since no unexpected start has occurred on low pressure since April 2012 by requiring two MDCLPs are operating prior to stopping a DDCLP.
Cause
The cause of the 121 MDCLP auto-start was a low-pressure transient in the cooling water pump discharge header resulting from the trip of 22 DDCLP during planned overspeed PMT.
Corrective Action To eliminate a 121 MDCLP auto-start during the overspeed trip test PMT, PM 3002-2-22 and PM 3002-2-12, 12 DDCLP Diesel Minor Periodic Maintenance, were revised to ensure 121 MDCLP is running prior to performing PMT.
To eliminate a 121 MDCLP auto-start during SP 1106A, SP 1106B, and C35, these procedures will be revised to ensure 121 MDCLP is running or in pullout position when stopping a DDCLP.
Previous Similar Events
Previous instances of 121 MDCLP auto-start have occurred and determined to be caused by having only one MDCLP running prior to shutting down the DDCLP.
Access and Management System (ADAMS) Accession Number ML091390396). On 3/19/2009, 121 MDCLP auto-started when 12 DDCLP was tripped in accordance with procedure resulting in a transient of the cooling water system pressure. The momentary drop in pressure was large enough to auto-start the 121 MDCLP while it was aligned for safeguards service.
(ADAMS Access Number ML112840145). On 12/23/2010, 121 MDCLP was not aligned as a safeguards replacement pump and auto-started. The actuation of the 121 MDCLP was determined to be reportable under 10 CFR 50.73(a)(2)(iv)(A). Corrective actions to resolve the issue included performing a Cooling Water System review to determine methods and any single point vulnerabilities that can be performed to minimize the potential for auto-starts of a cooling water pump. Operating procedures were evaluated to determine if procedural or operation period changes can be made to reduce the likelihood of auto-starting a Cooling Water Pump.
Prairie Island, Unit 1 05000-282 comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to Infocollects.Resource@nrc,gov, and to the Desk Officer, Office of Information and Regulatory Affairs, used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
121 MDCLP auto-started while shutting down 22 DDCLP. The corrective action was to revise operating procedure C35 to ensure two MDCLPs are running prior to stopping the DDCLP.
|
---|
|
|
| | Reporting criterion |
---|
05000306/LER-2016-001 | 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 | | 05000282/LER-2016-001 | Unanalyzed Condition Due to Non-Compliant Fire Protection Manual Operator Actions | | 05000282/LER-2016-002 | 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000282/LER-2016-003 | Unanalyzed Condition - Procedures Credited by Appendix R Calculations not in Place | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000282/LER-2016-004 | 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 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000282/LER-2016-005 | 121 Motor Driven Cooling Water Pump Auto Start | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000282/LER-2016-006 | 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
|