01-05-2018 | During performance of the High Pressure Coolant Injection ( HPCI) Pump Operability Test, the Unit 1 HPCI turbine did not trip when the Remote HPCI Turbine Trip pushbutton was depressed. Operations shut down HPCI by isolating the steam supply valves to trip the HPCI turbine. The Unit 1 HPCI system was declared inoperable, but remained available. The cause was determined to be accumulation of wear debris within the HPCI turbine stop valve oil resetting solenoid valve causing the valve to stick in the energized position. This wear debris was a result of a manufacturing deficiency.
The immediate corrective action was to replace the turbine stop valve oil resetting solenoid valve. Follow-up corrective action is to evaluate the preventative maintenance frequency for the HPCI turbine stop valve oil resetting solenoid valve.
The safety impact of this condition was minimal. The HPCI system was still available to function, despite the issue with the HPCI Turbine Stop Valve oil resetting solenoid. The event is being reported because HPCI is a single train system and the loss of HPCI could potentially impact the plant's ability to mitigate the consequences of an accident. |
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Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 ML24004A0052024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0042 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 ML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) ML23319A3342023-11-20020 November 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2 and 10 CFR 50.69 RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000254/20230032023-11-0909 November 2023 Integrated Inspection Report 05000254/2023003 and 05000265/2023003 RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23206A0382023-09-21021 September 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230112023-09-20020 September 2023 Safety-Conscious Work Environment Issue of Concern Team Inspection Report 05000254/2023011 and 05000265/2023011 RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval SVP-23-038, Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities2023-08-14014 August 2023 Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities IR 05000254/20230022023-08-0808 August 2023 Integrated Inspection Report 05000254/2023002 and 05000265/2023002 ML23178A0742023-08-0707 August 2023 Issuance of Amendment Nos. 296 and 292 Adoption of TSTF-416 Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location ML23216A0362023-08-0707 August 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI ML23216A0562023-08-0404 August 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 SVP-23-031, Regulatory Commitment Change Summary Report2023-07-14014 July 2023 Regulatory Commitment Change Summary Report ML23181A1062023-06-30030 June 2023 Postponement- Information Meeting (Open House) with a Question-And-Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML23179A1932023-06-28028 June 2023 07122023 Letter-Significant Public Meeting to Discuss NRC End-of-Cycle Performance Assessment of Quad Cities Nuclear Plant for Performance for 2022 Calendar Year IR 05000254/20234012023-06-26026 June 2023 Cyber Security Inspection Report 05000254/2023401 and 05000265/2023401 IR 05000265/20230402023-06-22022 June 2023 Reissue Quad Cities Nuclear Power Station 95001 Supplemental Inspection Supplemental Report 05000265/2023040 and Follow Up Assessment Letter RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167B1722023-06-16016 June 2023 95001 Supplemental Inspection Report 05000265/2023040 and Follow-Up Assessment Letter RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23144A3632023-05-26026 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23033A4042023-05-15015 May 2023 Exemption from the Requirements of 10 CFR Part 2, Section 2.109(B) Related to Submission of Subsequent License Renewal Application Letter IR 05000254/20234022023-05-15015 May 2023 Security Baseline and ISFSI Inspection Reports 05000254/2023402, 05000265/2023402, 07200053/2023401 ML23132A2022023-05-12012 May 2023 Annual Radiological Environmental Operating Report ML23125A0612023-05-0808 May 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230012023-05-0808 May 2023 Integrated Report 05000254/2023001 and 05000265/2023001 RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell SVP-23-018, Radioactive Effluent Release Report for 20222023-04-28028 April 2023 Radioactive Effluent Release Report for 2022 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23110A0622023-04-25025 April 2023 Transmittal of Final Quad Cities Nuclear Power Plant, Unit 1 Accident Sequence Precursor Report (Licensee Event Report 254-2022-001) ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration 2024-02-05
[Table view] Category:Licensee Event Report (LER)
MONTHYEARSVP-22-072, Manual Scram Due to Feedwater Regulator Valve Failure Increasing Reactor Water Level2022-12-30030 December 2022 Manual Scram Due to Feedwater Regulator Valve Failure Increasing Reactor Water Level 05000254/LER-2017-0042018-01-0505 January 2018 Unit 1 HPCI Did Not Trip Due to Wear Debris in the Turbine Stop Valve Oil Resetting Solenoid, LER 17-004-00 For Quad Cities Nuclear Power Station, Unit 1 re: Unit 1 HPCI Did Not Trip Due to Wear Debris in the Turbine Stop Valve Oil Resetting Solenoid 05000254/LER-2017-0032017-11-17017 November 2017 Control Room Emergency Ventilation Air Conditioning Piping Refrigerant Leak Due to High Cycle Fatigue, LER 17-003-00 for Quad Cities, Unit 1, Regarding Control Room Emergency Ventilation Air Conditioning Piping Refrigerant Leak Due to High Cycle Fatigue 05000265/LER-2017-0012017-07-13013 July 2017 High Pressure Coolant Injection Minimum Flow Valve Failed to Open, LER 17-001-00 for Quad Cities, Unit 2, Regarding High Pressure Coolant Injection Minimum Flow Valve Failed to Open 05000254/LER-2017-0022017-05-26026 May 2017 Four Main Steam Isolation Valves (MSIVs) Closure Times Exceeded, LER 17-002-00 for Quad Cities, Unit 1, Regarding Four Main Steam Isolation Valves (MSIVs) Closure Times Exceeded 05000254/LER-2017-0012017-03-22022 March 2017 Secondary Containment Interlock Doors Opened Simultaneously, LER 17-001-00 for Quad Cities, Unit 1, Regarding Secondary Containment Interlock Doors Opened Simultaneously 05000265/LER-2016-0022016-06-24024 June 2016 High Pressure Coolant Injection System Declared Inoperable Due to Valve Packing Leak, LER 16-002-00 for Quad Cities Nuclear Power Station Unit 2 - RE: High Pressure Coolant Injection System Declared Inoperable Due to Valve Packing Leak 05000265/LER-2016-0012016-05-19019 May 2016 Main Steam Isolation Valve Local Leak Rate Tests Exceed Technical Specification Limits, LER 2016-001-00 for Quad Cities Nuclear Power Station, Unit 2 Regarding Main Steam Isolation Valve Local Leak Rate Tests Exceed Technical Specification Limits 05000254/LER-2016-0022016-03-14014 March 2016 Secondary Containment Differential Pressure Momentarily Lost Due to Air Line Failure (RWCU Pump Rm), LER 16-002-00 for Quad Cities Units 1 and 2, Regarding Secondary Containment Different Pressure Momentarily Lost due to Air Failure (RWCU pump Rm) 05000254/LER-2016-0012016-03-10010 March 2016 Secondary Containment Differential Pressure Momentarily Lost Due to Air Line Failure (RWCU Hx Rm), LER 16-001-00 for Quad Cities, Unit 1, Regarding Secondary Containment Differential Pressure Momentarily Lost Due to Air Line Failure (RWCU Hx Rm) 05000254/LER-2015-0102016-02-0505 February 2016 Loss of Control Room Emergency Ventilation System Due to Differential Pressure Switch Failure, LER 15-010-00 for Quad Cities, Unit 1, Regarding Loss of Control Room Emergency Ventilation System Due to Differential Pressure Switch Failure SVP-03-036, LER 03-S01-00, Security Event Report for Quad Cities, Unescorted Protected Area Access Granted Based on Falsified Information and Inadequate Screening Caused by a Failure of Administrative Controls.2003-03-0303 March 2003 LER 03-S01-00, Security Event Report for Quad Cities, Unescorted Protected Area Access Granted Based on Falsified Information and Inadequate Screening Caused by a Failure of Administrative Controls. ML17252B4771976-09-15015 September 1976 LER 76-059-00 for Dresden, Units 2 and 3 Re Review of Quad-Cities Unusual Event Letter Led to Discovery That Dresden'S Standby Gas Treatment System Deviated from Single Failure Criteria That Disabled the SBGT System ML18348A2401976-08-0606 August 1976 LER 1976-027-00, Reportable Occurrence of Control Rods for Quad-Cities, Unit 1 ML18348A2391976-08-0404 August 1976 LER 1976-026-00, Reportable Occurrence of Control Rods for Quad-Cities, Unit 1 2022-12-30
[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 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.
3. LER NUMBER
004 2017 00
PLANT AND SYSTEM IDENTIFICATION
General Electric - Boiling Water Reactor, 2957 Megawatts Thermal Rated Core Power Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
EVENT IDENTIFICATION
Unit 1 HPCI Did Not Trip Due to Wear Debris in the Turbine Stop Valve Oil Resetting Solenoid
A. CONDITION PRIOR TO EVENT
Unit: 1 Reactor Mode: 1 Event Date: November 7, 2017 Event Time: 18:10 hours Mode Name: Power Operation Power Level: 100%
B. DESCRIPTION OF EVENT
On November 7, 2017 at 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br />, during performance of the quarterly High Pressure Coolant Injection (HPCI) [BJ] Pump Operability test, the Unit 1 HPCI turbine [TRB] failed to trip when the remote HPCI Turbine Trip pushbutton [HS] was depressed. Operations directed the shutdown of the Unit 1 HPCI system by isolating the HPCI steam supply valves [ISV], causing HPCI flow to reduce to 0 GPM. After the isolation was completed, Unit 1 HPCI was declared inoperable but available. There were no other structures, systems or components (SSC) inoperable during this event time period that could have contributed to this event.
After troubleshooting, the internal HPCI stop valve oil resetting solenoid [PSV] was replaced. Following the replacement of the solenoid valve, the HPCI system was declared operable on November 8, 2017 at 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br />.
C. CAUSE OF EVENT
The cause of the HPCI turbine failure to trip was determined to be accumulation of wear debris within the HPCI stop valve oil resetting solenoid valve causing the solenoid valve to stick in the energized position. The wear debris was caused by a manufacturing deficiency.
D. SAFETY ANALYSIS
System Design According to the Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2 Updated Final Safety Analysis Report (UFSAR) Section 6.3.2.3, the HPCI subsystem is designed to pump water into the reactor vessel under Loss of Coolant Accident (LOCA) conditions which do not result in rapid depressurization of the pressure vessel. The loss of coolant might be due to a loss of reactor feedwater or to a small line break which does not cause immediate depressurization of the reactor vessel. The sizing of the HPCI subsystem is based upon providing adequate core cooling during the time that the pressure in the reactor vessel decreases to a value that the Core Spray [BM] subsystem and/or the Low Pressure Coolant Injection (LPCI) [BO] subsystem become effective. The HPCI subsystem is designed to pump 5600 gallons per minute into the reactor vessel within a reactor pressure range of 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 e-mail to Infocollects.Resourcenrc.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 rot conduct or sponsor, and a person is not required to respond to, the information collection.
3. LER NUMBER
004 2017 00 about 1120 pounds per square inch gage (psig) to 150 psig. Initiation of the HPCI subsystem occurs automatically on signals indicating reactor low-low water level or high drywell pressure. HPCI injection into the reactor vessel may be accomplished manually by the operator or without operator action by the HPCI automatic initiation circuitry. HPCI can also operate in a pressure control mode of consuming steam from the reactor vessel without providing full injection into the vessel (down to and including zero injection).
Safety Impact The safety significance of this event is minimal. The HPCI Turbine Stop Valve would not trip, however this did not impact the injection function of HPCI, until the system was isolated via the steam supply valves. The HPCI steam supply valves would have to be manually opened to allow HPCI to function as an injection system. The HPCI system was declared inoperable but available once the steam supply valves were closed.
Since HPCI is a single train safety system, this notification is being made in accordance with 10 CFR 50.73 (a)(2)(v)(D), Event or Condition that Could Have Prevented Fulfillment of a Safety Function.
Risk Insights Automatic HPCI trip failure is represented in the Quad Cities Full Power Internal Events (FPIE) PRA model, which includes the HPCI turbine steam stop valve and others to manually control HPCI and prevent level overfill. The accident sequences involved are Automatic Transit without a Scram (ATWS) sequences, for which a HPCI trip failure leads to Boron dilution. ATWS sequences contribute about 3.7% to Core Damage Frequency (CDF). This assessment looks at the oil resetting solenoid valve trip failure. The PRA assessment found that there is minimal risk impact since the changes in CDF and LERF due to the HPCI (mechanical) trip failure are very small.
E. CORRECTIVE ACTIONS
Immediate:
1. Replaced solenoid valve internal to HPCI Turbine Stop Valve and verified proper operation.
Follow-up:
1. Evaluate PM frequency change for Turbine Stop Valve internal solenoid valve replacements. Also evaluate current design for improvement by changing solenoid valve model or manufacturer.
F. PREVIOUS OCCURRENCES
The Station events database, LERs, and INPO Consolidated Event System (ICES) were reviewed for similar events at Quad Cities Nuclear Power Station. This event was attributed to wear debris in the HPCI Turbine Stop Valve oil resetting solenoid valve.
No previous occurrences applicable to the circumstances of this event were identified in this search.
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 e-mail to infocollects.Resource:'y nrc.gov. and to the Desk Officer, Office cf Information and Regulatory Affairs, used to impose an information collection does not display a currently valid OMB control number, the NRC may riot conduct or sponsor, and a person is not required to respond to, the information collection.
3. LER NUMBER
004 2017 00
G. COMPONENT FAILURE DATA
Failed Equipment: Solenoid Valve Component Manufacturer: Barksdale Component Model Number: Q165A322BBG-1 Component Part Number: N/A This event has been reported to ICES as Report No. 426159
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05000265/LER-2017-001 | High Pressure Coolant Injection Minimum Flow Valve Failed to Open LER 17-001-00 for Quad Cities, Unit 2, Regarding High Pressure Coolant Injection Minimum Flow Valve Failed to Open | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000254/LER-2017-001 | Secondary Containment Interlock Doors Opened Simultaneously LER 17-001-00 for Quad Cities, Unit 1, Regarding Secondary Containment Interlock Doors Opened Simultaneously | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000254/LER-2017-002 | Four Main Steam Isolation Valves (MSIVs) Closure Times Exceeded LER 17-002-00 for Quad Cities, Unit 1, Regarding Four Main Steam Isolation Valves (MSIVs) Closure Times Exceeded | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000254/LER-2017-003 | Control Room Emergency Ventilation Air Conditioning Piping Refrigerant Leak Due to High Cycle Fatigue LER 17-003-00 for Quad Cities, Unit 1, Regarding Control Room Emergency Ventilation Air Conditioning Piping Refrigerant Leak Due to High Cycle Fatigue | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000254/LER-2017-004 | Unit 1 HPCI Did Not Trip Due to Wear Debris in the Turbine Stop Valve Oil Resetting Solenoid LER 17-004-00 For Quad Cities Nuclear Power Station, Unit 1 re: Unit 1 HPCI Did Not Trip Due to Wear Debris in the Turbine Stop Valve Oil Resetting Solenoid | |
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