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Category:Letter
MONTHYEAR05000265/LER-2024-002-01, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-10-30030 October 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure SVP-24-065, Offsite Dose Calculation Manual (ODCM) Section 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Report Main Chimney High Range Noble Gas Monitor2024-10-29029 October 2024 Offsite Dose Calculation Manual (ODCM) Section 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Report Main Chimney High Range Noble Gas Monitor IR 05000254/20240102024-10-28028 October 2024 Age Related Degradation Inspection Report 05000254/2024010 and 05000265/2024010 and Notice of Violation RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests SVP-24-059, Correction to Registration of Use of Casks to Store Spent Fuel2024-10-0404 October 2024 Correction to Registration of Use of Casks to Store Spent Fuel ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24247A1642024-09-30030 September 2024 Alternative Request RP-01 IR 05000254/20244022024-09-12012 September 2024 Material Control and Accounting Program Inspection Report 05000254/2024402 and 05000265/2024402 (Public) SVP-24-054, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds2024-09-11011 September 2024 Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000254/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2024005; 05000265/2024005) RS-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval ML24183A1082024-08-0808 August 2024 – Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b SVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024 Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities IR 05000254/20243012024-08-0101 August 2024 NRC Initial License Examination Report 05000254/2024301; 05000265/2024301 SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024 Registration of Use of Casks to Store Spent Fuel 05000265/LER-2024-002, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-07-22022 July 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions SVP-24-041, Regulatory Commitment Change Summary Report2024-07-0505 July 2024 Regulatory Commitment Change Summary Report SVP-24-043, Registration of Use of Casks to Store Spent Fuel2024-07-0505 July 2024 Registration of Use of Casks to Store Spent Fuel ML24162A0982024-07-0303 July 2024 – Issuance of Amendment Nos. 301 and 297 Adoption of 10 CFR 50.69 Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024 Registration of Use of Casks to Store Spent Fuel RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations SVP-24-039, Ile Post Exam Package Letter2024-06-12012 June 2024 Ile Post Exam Package Letter RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed ML24110A0492024-05-28028 May 2024 Audit Report Related to the TSTF-505 and 10 CFR 50.59 Amendments ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24141A2102024-05-20020 May 2024 Operator Licensing Examination Approval - Quad Cities Nuclear Power Station, May 2024 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000254/20240012024-05-14014 May 2024 Integrated Inspection Report Nos. 05000254/2024001 and 05000265/2024001 SVP-24-034, Annual Radiological Environmental Operating Report2024-05-10010 May 2024 Annual Radiological Environmental Operating Report 05000265/LER-2024-001, Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing2024-05-10010 May 2024 Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing RS-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report ML24109A0662024-05-0202 May 2024 – Relief Request I5R-26, Revision 0 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests SVP-24-028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2024-04-26026 April 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVP-24-029, Radioactive Effluent Release Report for 20232024-04-26026 April 2024 Radioactive Effluent Release Report for 2023 ML24114A1712024-04-23023 April 2024 State of Illinois (IEMA-OHS) Comment Quad Cities HI-STORM Exemption Environmental Assessment IR 05000254/20245012024-04-0505 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000254/2024501 and 05000265/2024501 RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-04-0505 April 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion SVP-24-024, Corrected Radioactive Effluent Release Report for 20222024-04-0505 April 2024 Corrected Radioactive Effluent Release Report for 2022 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report SVP-24-023, Ile Outline Submittal Letter2024-03-29029 March 2024 Ile Outline Submittal Letter RS-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF2024-03-19019 March 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF ML23340A1552024-03-15015 March 2024 – Issuance of Amendment Nos. 299 and 295 Adoption of TSTF-564, Safety Limit MCPR RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS2024-03-15015 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS SVP-24-018, Ile Proposed Exam Submittal Letter2024-03-13013 March 2024 Ile Proposed Exam Submittal Letter 2024-09-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000265/LER-2024-002-01, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-10-30030 October 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure 05000265/LER-2024-002, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-07-22022 July 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure 05000265/LER-2024-001, Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing2024-05-10010 May 2024 Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing 05000265/LER-2023-001-01, Turbine Trip and Automatic Reactor Scram Due to High Moisture Separator Level2023-11-30030 November 2023 Turbine Trip and Automatic Reactor Scram Due to High Moisture Separator Level 05000265/LER-2023-001, Turbine Trip and Automatic Reactor Scram Due to High Moisture Separator Level2023-10-10010 October 2023 Turbine Trip and Automatic Reactor Scram Due to High Moisture Separator Level SVP-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 05000265/LER-2022-002, Manual Scram Due to Feedwater Regulator Valve Failure Decreasing Reactor Water Level2022-09-0101 September 2022 Manual Scram Due to Feedwater Regulator Valve Failure Decreasing Reactor Water Level 05000254/LER-2022-003, Both Trains of Standby Gas Treatment Inoperable Due to Blockage in the Common Discharge Line2022-09-0101 September 2022 Both Trains of Standby Gas Treatment Inoperable Due to Blockage in the Common Discharge Line 05000254/LER-2022-002, Low Pressure Coolant Injection Manually Isolated Due to Valve Test Equipment Issue2022-07-0808 July 2022 Low Pressure Coolant Injection Manually Isolated Due to Valve Test Equipment Issue 05000265/LER-2022-001, Electromatic Relief Valve 3B Did Not Actuate Due to Incorrectly Oriented Plunger Well Plastic Guides2022-05-20020 May 2022 Electromatic Relief Valve 3B Did Not Actuate Due to Incorrectly Oriented Plunger Well Plastic Guides 05000254/LER-2022-001, Regarding High Pressure Coolant Injection System Inoperable Due to Gland Seal System Malfunction2022-01-26026 January 2022 Regarding High Pressure Coolant Injection System Inoperable Due to Gland Seal System Malfunction 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 2024-07-22
[Table view] |
LER-2022-001, Electromatic Relief Valve 3B Did Not Actuate Due to Incorrectly Oriented Plunger Well Plastic Guides |
Event date: |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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2652022001R00 - NRC Website |
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text
Constellation,.,
SVP-22-030 10 CFR 50.73
May 20, 2022
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Quad Cities Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DPR-30 NRC Docket No. 50-265
Subject: Licensee Event Report 265/2022-001-00 "Electromatic Relief Valve 3B Did Not Actuate Due to Incorrectly Oriented Plunger Well Plastic Guides"
Enclosed is Licensee Event Report 265/2022-001-00 "Electromatic Relief Valve 3B Did Not Actuate Due to Incorrectly Oriented Plunger Well Plastic Guides," for Quad Cities Nuclear Power Station, Unit 2.
This report is submitted in accordance with 10 CFR 50. 73(a)(2)(i)(B) for an operation or condition which was prohibited by the plant's Technical Specification.
There are no regulatory commitments contained in this letter.
Should you have any questions concerning this report, please contact Sherrie Grant at (309) 227-2800.
Brian Wake Site Vice President Quad Cities Nuclear Power Station
cc: Regional Administrator-NRC Region Ill NRC Senior Resident Inspector - Quad Cities Nuclear Power Station
Abstract
On March 21, 2022, with Unit 2 in shutdown, Electromatic Relief Valve (ERV) 2-O2O3-3B, 2B Main Steam Line Relief Valve, did not stroke in accordance with work package instructions. The valve was being tested to satisfy Technical Specification Surveillance Requirement (TS SR) 3.5.1.10, verify each Automatic Depressurizing System (ADS) valve actuator strokes when manually actuated. All other Unit 2 ADS valves were found to stroke satisfactorily.
The cause of the failure was unclear vendor guidance and insufficient procedural guidance regarding the orientation for the installation of the internal plunger well plastic guides. The guides were incorrectly installed during rebuild which caused actuator binding. The failure will be prevented by revising the site maintenance rebuild procedure with input from the manufacturer.
This event is being reported in accordance with 10 CFR 50. 73(a)(2)(i)(B), an operation or condition which was prohibited by the plant's Technical Specification. TS 3.5.1 Condition Hallows one ADS valve to be inoperable for a period of 14 days. This ADS valve was found to be inoperable for the entire cycle.
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
Electromatic Relief Valve 38 Did Not Actuate Due to Incorrectly Orientated Plunger Well Plastic Guides
CONDITION PRIOR TO EVENT
Unit: 2 Event Date: March 21, 2022 Event Time: 1030 CDT
Reactor Mode: 4 Mode Name: Cold Shutdown Power Level: 0%
No structures, systems or components were inoperable at the start of this event that contributed to the event.
A. DESCRIPTION OF EVENT
On March 21, 2022, with Unit 2 in shutdown for refueling outage Q2R26, and during performance of the Technical Specification (TS) Surveillance Requirement (SR) 3.5.1.10, the 2-0203-38 Electromatic Relief Valve (ERV)[SB] failed to actuate. TS SR 3.5.1.1 O requires each Automatic Depressurizing System (ADS)[SB] valve actuator stroke when manually actuated. All other Unit 2 ADS valves were found to stroke successfully. The 2-0203-38 actuator was replaced and stroked successfully prior to completion of refueling outage Q2R26, restoring the system to operable.
The 2-0203-38 ERV failed actuator was originally installed in March 2020 after having been rebuilt earlier in the month in preparation for refue.ling outage Q2R25. The actuator had been rebuilt in accordance with revision 10 of site maintenance rebuild procedure. In the April 2020, all the Unit 2 ADS ERVs were successfully stroked multiple times prior to unit startup from Q2R25, confirming no actuator binding was observed on any of the Unit 2 ERVs. Revision 11 of the site maintenance rebuild procedure, which included corrective actions from the 2-0203-3D ERV failure, was implemented in August 2020 after startup from the Q2R25 refuel outage.
Initial assessment of the removed 2-0203-38 ERV was that solenoid actuator was burnt out and there was significant binding of the actuator. The actuator was sent to Constellation Powerlabs for further evaluation and cause determination, which was completed prior to startup from the Q2R26 refueling outage. An extent of condition review, including inspection of the other Unit 2 ERVs was performed as well as a review of the rebuild work instructions for the Unit 1 ERVs. No significant or similar issues with either unit's ERVs were found during the extent of condition review.
This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), an operation or condition which was prohibited by the plant's Technical Specification. TS 3.5.1 Condition H allows one ADS valve to be inoperable for a period of 14 days. The 2-0203-38 ERV was found to be inoperable for the entire cycle.
B. CAUSE OF EVENT
The cause of the failure was unclear vendor guidance and insufficient procedural guidance regarding orientation for the installation of the internal plunger well plastic guides. The internal plunger well plastic guides were found to be incorrectly installed in the 2-0203-38 ERV actuator, which caused actuator binding. Contributing to the failure was that the upper guide bracket did not have proper straightness and was found warped. This resulted in the plunger legs being out-of-squareness and increased friction with the plunger well.
C. SAFETY ANALYSIS
System Design
The 2-0203-38 ERV is part of the ADS. The ADS consist of five valves (4 relief valves (ERVs) and one safety/relief valve (Target Rock valve)).
Per the Updated Final Safety Analysis Report (UFSAR) 6.3.3.1.4, "The ADS is designed to depressurize the reactor to permit either the Low Pressure Coolant Injection (LPCI) or Core Spray subsystem to cool the reactor core during a small break Loss of Coolant Accident (LOCA)." Pressure relief of the reactor vessel may be accomplished manually by the operator or without operator action by the automatic depressurization circuitry.
Safety Impact Per TS Bases 3.5.1 Condition H.1, with one ADS valve out of service, the overall reliability of the ADS is reduced, because a single failure in the OPERABLE ADS valves could result in a reduction in depressurization capability. In addition, TS Bases for SR 3.5.1.10 states the actuator of each of the ADS ERVs and the dual function safety/relief valves (S/RVs) is stroked to verify that the pilot valve strokes when manually actuated. The SR, together with the valve testing performed as required by American Society of Mechanical Engineers (ASME) code for pressure relieving devices, verify the capability of each relief valve to perform its function.
Per UFSAR 6.3.3.1.4, Automatic Depressurization Subsystem, "All five available ADS valves were assumed operable in the LOCA analysis. One ADS valve from the five valves modeled in the LOCA analysis was assumed to fail for the single failure evaluation resulting in the operation of four valves being credited." Based on the ADS system design and accident/transient analysis, four of the five ADS valves are needed to perform the required safety function.
An engineering evaluation concluded that the plant design/licensing bases are met with one failed ERV.
Therefore, this is not a Safety System Functional Failure (SSFF). The extent of condition inspection on the other Unit 2 ERVs showed no actuator binding and the review performed on the Unit 1 ERVs found
no reason for potential actuator binding. The Target Rock valve design is significantly different from the ERVs. As a result, the rebuild procedure is different and the plastic guide orientation issue does not apply to the Target Rock valve. -
This event is a Maintenance Rule Functional Failure (MRFF).
D. CORRECTIVE ACTIONS
Immediate:
- 1. The site maintenance rebuild procedure was revised to address straightness of the upper guide bracket, using plunger and upper guide bracket as a single matched assembly, and information regarding the orientation of the plastic guides in August 2020.
- 2. The 38 ERV and actuator were replaced and successfully tested during Q2R26.
- 3. All other Unit 2 ERVs were inspected for a similar condition and successfully tested during Q2R26.
Follow up:
- 1. Review and enhance the site maintenance ERV rebuild procedure to ensure clear guidance on the installation of the plunger well plastic guides along with other procedure enhancements identified during the investigation. This procedure revision will be reviewed by the manufacturer to ensure correct positioning of various sub-components within the actuator.
E. PREVIOUS OCCURENCES
A review of previous QCNPS events revealed a similar event in 2020 in which the 3D ERV actuator was found to not actuate due to an out of specification plunger received from the vendor. The cause was different between the 3D ERV in 2020 and the 38 ERV in 2022.
LER (265/2020-002-00) Electromatic Relief Valve 3D Did Not Actuate Due to Out of Specification Plunger
- - The cause of this 3D ERV failure was determined to be an out of specification plunger provided by the manufacturer. The contributing cause was a bent upper guide bracket. The out of specification plunger combined with the bent upper guide bracket caused excessive binding in the actuator. In the current 38 ERV failure event, the actuator binding was caused by the internal plunger well plastic guides being incorrectly installed due to unclear vendor guidance regarding the orientation of the guides.
F. COMPONENT FAILURE DATA
Failed Equipment: Relief Valve Actuator Component Manufacturer: General Electric Component Model Number: 36282632G001 Component Part Number: N/A
This event will be reported to IRIS.
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05000265/LER-2022-001, Electromatic Relief Valve 3B Did Not Actuate Due to Incorrectly Oriented Plunger Well Plastic Guides | Electromatic Relief Valve 3B Did Not Actuate Due to Incorrectly Oriented Plunger Well Plastic Guides | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000254/LER-2022-001, Regarding High Pressure Coolant Injection System Inoperable Due to Gland Seal System Malfunction | Regarding High Pressure Coolant Injection System Inoperable Due to Gland Seal System Malfunction | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000265/LER-2022-002, Manual Scram Due to Feedwater Regulator Valve Failure Decreasing Reactor Water Level | Manual Scram Due to Feedwater Regulator Valve Failure Decreasing Reactor Water Level | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000254/LER-2022-002, Low Pressure Coolant Injection Manually Isolated Due to Valve Test Equipment Issue | Low Pressure Coolant Injection Manually Isolated Due to Valve Test Equipment Issue | 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 | 05000254/LER-2022-003, Both Trains of Standby Gas Treatment Inoperable Due to Blockage in the Common Discharge Line | Both Trains of Standby Gas Treatment Inoperable Due to Blockage in the Common Discharge Line | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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