05-26-2017 | On March 27, 2017, during refueling outage Q1R24 at 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br />, the Unit 1 Main Steam Isolation Valve ( MSIV) as-found closure time test results indicated that four MSIVs failed to close within the required Technical Specification (TS) time of less than or equal to five seconds. The safety significance of this event was minimal.
The cause of three of the slow closure timing events was due to a less than optimal replacement frequency for the MSIV actuators, and the cause of the fourth slow closure timing event was due to a less than optimal replacement frequency for the MSIV springs.
Corrective actions included replacing the 1-0203-1B and 1-0203-1D MSIV actuators, replacing the springs on the 1-0203-2C MSIV, readjusting the as-left closure times on all four MSIVs and satisfactory retesting prior to startup. Follow-up corrective actions include replacing the 1-0203-2D MSIV actuator and changing the preventive maintenance frequency and description.
Since the MSIV slow closure times were due to degradation from less than optimal replacement frequencies, it is likely the degradation occurred over time since the last successful refueling outage testing and during power operations when the required TS 3.6.1.3, Primary Containment Isolation Valves was applicable. Therefore, this condition is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), which requires reporting of any operation or condition that was prohibited by the plant's TS. |
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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] |
comments regarding burden estimate to the Information Services Branch (T-2 F43), 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
2017 - 00 002
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
Four Main Steam Isolation Valves (MSIVs) Closure Times Exceed Technical Specifications Limit
A. CONDITION PRIOR TO EVENT
Unit: 1 Reactor Mode: 4 Event Date: March 27, 2017 Event Time: 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br /> Mode Name: Cold Shutdown Power Level: 0%
B. DESCRIPTION OF EVENT
On March 27, 2017, while Unit 1 was in Mode 4 for refueling outage Q1R24, Operations was performing surveillance, "MSIV Closure Timing," when four of the eight Unit 1 Main Steam [SB] Isolation Valves [ISV] (MSIVs), 1-0203-1B, 1- 0203-1D, 1-0203-2C, and 1-0203-2D failed to close within the required cold shutdown Technical Specification (TS) limit of greater than or equal to three seconds and less than or equal to five seconds. The closure times for those four MSIVs were 5.7, 5.2, 5.1, and 5.6 seconds, respectively. The other four MSIVs all closed within the required TS time.
As part of the event investigation, the actuator vendor provided that an increase in closure timing of the valves is linked to degradation of the actuator [HCU] because it has surpassed its recommended eight year lifespan. The current preventive maintenance (PM) frequency for valve actuator replacement was established based off of the theoretical lifespan of the elastomers. The PM frequencies are currently at 12 years (six refueling outages) for MSIVs 1-0203-1B and 1-0203-1D and 14 years (seven refueling outages) for MSIVs 1-0203-2C and 1-0203-2D. The actuators for MSIVs 1-0203-1B, 1-0203-1D and 1-0203-2D were last replaced in November 2002, while the 1-0203- 2C MSIV actuator was last replaced in March 2015. However, when the 1-0203-2C MSIV actuator was replaced in March 2015, the springs were not replaced. The springs had been in-service for nearly 15 years.
Since the MSIV slow closure times were due to age related degradation from less than optimal PM frequencies, it is likely the degradation occurred over time since the last successful refueling outage testing and during power operations when the required TS 3.6.1.3, Primary Containment Isolation Valves, was applicable. Therefore, this condition is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), which requires reporting of any operation or condition that was prohibited by the plant's Technical Specifications.
comments regarding burden estimate to the Information Services Branch (T-2 F43), 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
2017 00 002
C. CAUSE OF EVENT
The cause of the slow closure timing for MSIVs 1-0203-1B, 1-0203-1D and 1-0203-2D is due to a less than optimal replacement frequency of the MSIV actuator. The basis of this decision was because ten Unit 1 MSIVs have had slow closure times since the valve actuator replacement PM frequency was extended in 2002. The vendor recommended replacement frequency is eight years (every fourth outage) and the Exelon PM Template replacement frequency is eight years as well. The current PM frequency is either every sixth (twelve years) or every seventh (fourteen years) refueling outage.
The cause of the slow closure for the 1-0203-2C MSIV was due to a less than optimal replacement frequency of the MSIV springs. The springs were replaced for the 1-0203-2C MSIV after being in-service for nearly 15 years. The MSIVs are normally open valves, which have their springs in compression for the entire cycle. If a spring is in compression for nearly 15 years continuously, the overall free length and spring rate decrease with age.
D. SAFETY ANALYSIS
System Design The design of the MSIVs is to prevent reactor coolant [AD] inventory loss and protect plant personnel in the event of steam line breakage outside the isolation valves, and to complete the primary containment [NH] boundary after a Loss of Coolant Accident (LOCA). The MSIVs are 20-inch air/spring operated, balanced "Y"-type globe valves. There are four main steam lines and each steam line has two isolation valves, one inside (inboard MSIV) and one outside (outboard MSIV) of primary containment.
Updated Final Safety Analysis Report (UFSAR) Section 6.2.4.1 provides the valve closure time for the main steam line is based on the main steam line break accident discussed in Section 15.6. Ensuring the MSIV closure time less than or equal to five seconds, sufficient coolant will remain in the reactor vessel to provide adequate core cooling. The valves are designed to close and to be leak-tight during the worst conditions of pressure, temperature, and steam flow following a break in the main steam line outside the containment. The MSIVs are leak tested in accordance with the 10 CFR 50 Appendix J program. UFSAR Section 15.6 provides that a maximum MSIV closure time of 10.5 seconds would limit the total amount of liquid and steam lost from the primary system to prevent the core from being uncovered, and this closure time will ensure the radiological doses are well below the guidelines set forth in 10 CFR 100.
Proper adjustment of the MSIV closure times prevents operation outside of the operational and design limits.
Safety Impact Technical Specifications and the In-Service Testing program require the MSIVs to close in a three to five second time range. Five seconds is fast enough to prevent a gross release of fission products, and three seconds is slow enough to minimize the severity of the pressure transient resulting from isolating the main steam lines during full power operation. Slow MSIV stroke times would challenge the steam release limits of a steam line break outside of containment should the corresponding inboard valve simultaneously fail to close.
The Unit 1 MSIVs 1-0203-1B, 1-0203-1D, 1-0203-2C, and 1-0203-2D failed to close within the required Technical Specification limit of less than or equal to five seconds. The closure times for those four MSIVs were 5.7, 5.2, 5.1, and 5.6 seconds, respectively, however, the four MSIVs all closed inside the UFSAR limit of less than or equal to 10.5 seconds. Although the required five second Technical Specification limit was not met for these four MSIVs, the MSIVs were capable of performing the required UFSAR safety function during the operating cycle prior to Q1 R24.
comments regarding burden estimate to the Information Services Branch (T-2 F43), 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
2017 - 00 002 Furthermore, since the MSIVs were not required to be operable or available at the time of discovery, this condition did not create any actual plant or safety consequences since the unit was not in an accident or transient condition requiring the use of main steam line isolation valves during this period of time.
Risk Insights The closure times for the four MSIVs were 5.7, 5.2, 5.1, and 5.6 seconds and recorded as slow, but the MSIVs did fully close. The MSIV success criterion in the Plant Probabilistic Risk Assessment (PRA) model, however, does not depend on closure time. Therefore, a difference of a fraction of a second between actual MSIV closure time and the acceptance criterion for the Technical Specification closure time has no effect on the PRA model. As a result, there is no effect on Core Damage Frequency (CDF) or Large Early Release Frequency (LERF).
In conclusion, the failure of the four MSIVs to close within the required time would not have caused the station to exceed the inventory and dose release limits. Furthermore, the impact on risk of this event is negligible. Therefore, the overall safety significance of this event was minimal.
E. CORRECTIVE ACTIONS
Immediate:
1. The 1-0203-1B and 1-0203-1D MSIV actuators were replaced during the outage, Q1R24 in 2017.
2. The 1-0203-2C MSIV springs were replaced during the outage, Q1R24 in 2017.
3. All four MSIVs were adjusted for proper as-left closure times, and retested satisfactorily.
Follow-up:
1. The 1-0203-2D MSIV actuator will be replaced during the next refuel outage, Q1R25, in 2019.
2. The PM frequency will be changed to eight years for replacing the Unit 1 and Unit 2 MSIV actuators with additional instructions to replace the MSIV springs during the actuator replacement.
F. PREVIOUS OCCURRENCES
The station events database, LERs, and INPO ICES were reviewed for similar events at Quad Cities. Specifically, this event was primarily attributed to a less than optimal replacement frequency of the MSIV actuators and springs. Based on the causes of this event and associated corrective actions, the events listed below, assisted with the resolution of this event.
- Station Issue Report (IR) 1213432, Unit 1 Outboard MSIV 1-0203-2C Failed QCOS 0250-04 (05/09/2011) - The 1-0203-2C outboard MSIV closure time exceeded the acceptance criteria for cold timing, which is less than or equal to five seconds. The stroke time recorded was 5.2 seconds. The cause was dirty contacts within the control circuitry creating an electrical time delay. This is one of the ten slow closure time events on Unit 1 since 2002, which led to the current action to reduce the valve actuator PM frequency. Therefore, IR 1213432 provided useful insights associated with this event.
- Station Issue Report (IR) 333083, Unit 2 Inboard MSIV 2-0203-1C Slow Closure (05/09/2005) - While performing QCOS 0250-04, "MSIV Closure Timing," the 2-0203-1C MSIV closure time was 5.05 seconds, which is outside of the surveillance acceptance criteria of 3-5 seconds. The cause of the slow valve stroke time was determined to be within the human response time for actuating the stopwatch. This previous event is similar in that stopwatches continue to be used to perform the closure time surveillance. However, this past event is not directly applicable comments regarding burden estimate to the Information Services Branch (T-2 F43), 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
2017 - 00 002 and is not considered a significant station experience that would have directly contributed to preventing the event of this current LER.
- LER 2013-002-00 Outboard Main Steam Isolation Valves (MSIVs) Stroke Times Exceeded (03/11/2013) — All four Unit 1 outboard MSIVs closed slowly due to actuator seals had degraded due to age and wear. The vendor recommended a replacement frequency of eight years for the actuators. This event was four of the ten slow closure events on Unit 1 since 2002, which led to the current action to reduce the valve actuator PM frequency.
Therefore, LER 2013-002-00 provided useful insights associated with this event.
G. COMPONENT FAILURE DATA
The failed component was the air/hydraulic actuator on three of the four MSIVs and springs on the fourth MSIV.
These actuators are Model Numbers SA-A104 and SA-A119 manufactured by Rotork Hiller. The MSIVs are manufactured by Crane.
This event has been reported to ICES under record #407880.
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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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