4-25-2016 | On January 23, 2016, James A. FitzPatrick Nuclear Power Plant (JAF) initiated a manual Scram in response to lowering screenwell water level due to frazil ice blockage, and subsequently closed the Main Steam Isolation Valves ( MSIV). A post Scram review identified that MSIV 29A0V-8613 closed slowly. On January 26, 2016, testing per ST-1B identified that MSIV 29A0V-86C closed slowly. In both cases, the inboard MSIVs performed satisfactorily.
Troubleshooting identified that the problem originated in the solenoid valve cluster assemblies (SVCA) and they were replaced and tested successfully. A failure analysis was performed by Exelon PowerLabs on the SVCAs. On February 25, 2016, the Exelon PowerLabs analysis concluded that the DC pilot valves, 2950V-86B3 and 2950V-86C3, exhibited slow vent times. Additional corrective actions include changing the preventative maintenance frequency from 8 years to 6 years and initiating further investigation through the component's vendor.
Two MSIVs exceeded the closing time of Technical Specification Surveillance Requirement (SR) 3.6.1.3.6. This condition caused two independent channels of a system used to control the release of radioactive material to become inoperable; reportable per 10 CFR 50.73(a)(2)(vii). |
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Category:Letter
MONTHYEARIR 05000333/20240902024-10-29029 October 2024 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000333/2024090 JAFP-24-0055, Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation2024-10-29029 October 2024 Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation IR 05000333/20244022024-10-28028 October 2024 Material Control and Accounting Program Inspection Report 05000333/2024402 (Cover Letter Only) ML24276A1332024-10-17017 October 2024 Issuance of Amendment No. 357 Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision-4, and Administrative Changes ML24282B0302024-10-11011 October 2024 Project Manager Assignment 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 ML24207A0192024-10-0909 October 2024 SE Addendum Related to the License Amendment No. 338 for Implementation of the Alternative Source Term (DPO-2021-001) JAFP-24-0051, Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-0882024-10-0303 October 2024 Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-088 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24270A0742024-09-30030 September 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0134) - LTR ML24270A1452024-09-26026 September 2024 Notice of Enforcement Discretion for James A. Fitzpatrick Nuclear Power Plant JAFP-24-0046, Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation2024-09-25025 September 2024 Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 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 ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket 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 JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 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 JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 ML24106A0152024-04-15015 April 2024 Request for Withholding Information from Public Disclosure Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24107A6972024-04-12012 April 2024 Engine Systems, Inc Part 21 Report Re EMD Cylinder Liner Water Leak 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 ML24068A0532024-03-28028 March 2024 Issuance of Amendment No. 354 Revise Technical Specifications Section 3.3.1.2, Source Range Monitors Instrumentation 2024-09-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket 05000333/LER-2023-004, For James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem2023-12-0101 December 2023 For James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem 05000333/LER-2022-003-02, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low2023-09-0808 September 2023 Safety Relief Valves Lift Setpoint Found Out of Tolerance Low 05000333/LER-2023-002-01, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2023-08-14014 August 2023 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 05000333/LER-2023-003, Emergency Diesel Generator Fuel Oil Supply Procedure Error B Subsystem2023-06-23023 June 2023 Emergency Diesel Generator Fuel Oil Supply Procedure Error B Subsystem 05000333/LER-2023-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2023-06-13013 June 2023 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 05000333/LER-1922-003-01, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low2023-04-28028 April 2023 Safety Relief Valves Lift Setpoint Found Out of Tolerance Low 05000333/LER-2023-001, Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System2023-04-19019 April 2023 Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System 05000333/LER-2022-002-01, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation2023-01-31031 January 2023 Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation 05000333/LER-2021-001-01, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas2023-01-10010 January 2023 Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas 05000333/LER-2022-003, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low2022-11-30030 November 2022 Safety Relief Valves Lift Setpoint Found Out of Tolerance Low 05000333/LER-2022-002, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation2022-11-22022 November 2022 Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation 05000333/LER-2022-001, Exhaust Drain Pot Line Filled with Water Up to HPCI Turbine Due to Relay Failure2022-06-28028 June 2022 Exhaust Drain Pot Line Filled with Water Up to HPCI Turbine Due to Relay Failure 05000333/LER-2021-003, Air Solenoid Valve Condition Results in Main Steam Isolation Valve (MSIV) Fast Closure Test Failure2022-01-14014 January 2022 Air Solenoid Valve Condition Results in Main Steam Isolation Valve (MSIV) Fast Closure Test Failure 05000333/LER-2021-002, Automatic High Pressure Coolant Injection (HPCI) System Function Prevented by Control Circuit Relay Failure2022-01-14014 January 2022 Automatic High Pressure Coolant Injection (HPCI) System Function Prevented by Control Circuit Relay Failure 05000333/LER-2021-001, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas2021-10-22022 October 2021 Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas 05000333/LER-2020-003-01, High Pressure Coolant Injection Inoperable Due to Oil Leak2021-09-0808 September 2021 High Pressure Coolant Injection Inoperable Due to Oil Leak JAFP-17-0051, LER 17-03-00 for FitzPatrick Regarding Inadvertent Isolation of the High Pressure Coolant Injection System2017-06-0505 June 2017 LER 17-03-00 for FitzPatrick Regarding Inadvertent Isolation of the High Pressure Coolant Injection System 05000333/LER-2017-0012017-03-13013 March 2017 Vent Line Socket Weld Failure, LER 17-001-00 for James A. Fitzpatrick Nuclear Power Plant RE: Vent Line Socket Weld Failure 05000333/LER-2016-0042016-08-23023 August 2016 Transformer Fault Results in Manual Scram and Secondary Containment Vacuum Below Technical Specification Limit, LER 16-004-00 for James A. Fitzpatrick Regarding Transformer Fault Results in Manual Scram and Secondary Containment Vacuum Below Technical Specification Limit 05000333/LER-2016-0032016-08-0303 August 2016 Concurrent Opening of Reactor Building Airlock Doors, LER 16-003-00 for James A. FitzPatrick Regarding Concurrent Opening of Reactor Building Airlock Doors 05000333/LER-2016-0022016-04-25025 April 2016 Sticking DC Pilot in Solenoid Valve Cluster Assembly Results in Slow MSIV Closures, LER 16-002-00 for James A. Fitzpatrick Nuclear Power Plant, Regarding Sticking DC Pilot in Solenoid Valve Cluster Assembly Results in Slowly MSIV Closure 05000333/LER-2016-0012016-03-23023 March 2016 System Actuations during Manual Scram in Response to Frazil Ice Blockage and Residual Transfer, LER 16-001-00 for James A. FitzPatrick Regarding System Actuations during Manual Scram in Response to Frazil Ice Blockage and Residual Transfer 05000333/LER-2015-0082016-02-16016 February 2016 Containment Atmosphere Dilution System Reliability Degraded due to Manufacturer Defect in Temperature Transmitters, LER 15-008-00 for James A. Fitzpatrick Regarding Containment Atmosphere Dilution System Reliability Degraded Due to Manufacturer Defect in Temperature Transmitters 05000333/LER-2015-0062016-02-0404 February 2016 Transitory Secondary Containment Differential Pressure Excursions, LER 15-006-01 for James A. FizPatrick Regarding Transitory Secondary Containment Differential Pressure Excursions 05000333/LER-2015-0072016-02-0101 February 2016 Slow Exhaust Fan Start Leads to Secondary Containment Vacuum Below Technical Specification Limit, LER 15-007-00 for James A. Fitzpatrick Regarding Slow Exhaust Fan Start Leads to Secondary Containment Vacuum Below Technical Specification Limit ML1015505722009-12-28028 December 2009 Event Notification for Fitzpatrick on Offsite Notification for Elevated Tritium Levels ML0509505652004-12-17017 December 2004 Final Precursor Analysis - Fitzpatrick Grip Loop 2024-09-04
[Table view] |
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James A. FitzPatrick Nuclear Power Plant 05000 — 333
3. LER NUMBER
— 002 — 00 2016
Background
James A. FitzPatrick Nuclear Power Plant (JAF) has four main steam lines [El IS identifier: SB] between the reactor and the main turbine [TA]. These lines are designed to isolate in the event of design basis accidents. In the event of a main steam line break, the isolation prevents further radiological release. In the event of a loss of coolant (LOCA) accident, they isolate to maintain coolant inside of containment.
Two isolation valves are provided in series in a horizontal run of each main steam line, as close as practical to the primary containment. One inside (inboard) and the other outside (outboard) together form part of the primary containment barrier for Reactor Coolant System breaks inside the containment and part of the Reactor Coolant Pressure Boundary for main steam line breaks outside the primary containment.
The closure time of the main steam isolation valves (MSIVs) is a significant variable from a radiological standpoint. The MSIVs are required to close within 3 to 5 seconds after signal generation. The closure speed is designed to be slower than 3 seconds in order to lessen the pressure transient caused by an inadvertent simultaneous closure of all steam lines. The closure speed is designed to be faster than 5 second to minimize the release of fission products to the environment and retain reactor coolant.
Each MSIV is controlled by a solenoid I SUPPLY I valve cluster assembly (SVCA). There are three solenoid valves within the AC PILOT 2 WAY SVCA; AC Pilot solenoid valve, AC Test solenoid valve and a DC pilot solenoid valve. These three solenoids port air to and from other control TEST 3 WAY valves. The normally energized AC pilot valve and DC pilot valve must move to the de-energized position to change the DC PILOT 4 WAY position of the 2 and 4 way valves MSIV ACTUATOR which closes the MSIV. When both solenoids are de-energized, the below ♦ NORMAL CLOSED piston operator space is vented.
Simultaneously, the above piston operator space is pressurized, thus assisting the spring in closing the MSIV.
This licensee event report (LER) addresses a slow closure response for outboard MSIV 29A0V-86B and 29A0V-86C due to their DC pilot solenoid valves 2950V-86B3 and 2950V-86C3.
Event Description
On January 23, 2016, control room Operators inserted a manual Scram due to lowering intake levels resulting from frazil ice conditions in Lake Ontario. As part of the plant shutdown the MSIVs were closed. The closing time for the "B" outboard MSIV 29A0V-86B, was slow by as much as 9 seconds after the other valves indicated closed. The SVCA and 4-way valve were replaced and 29A0V-86B then stroked satisfactorily.
On January 27, 2016, the MSIV fast closure test ST-1B was performed on all MSIVs. MSIV 29A0V-86C closed in 6.9 seconds and all other MSIVs tested satisfactorily. The SVCA and 4-way valve were replaced and 29A0V-86C then stroked satisfactorily.
CLOSED
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James A. FitzPatrick Nuclear Power Plant 05000 — 333
3. LER NUMBER
— 002 — 00 2016
Event Analysis
On January 27, 2016, 29A0V-86C was taken closed using the slow close push button; the manual control switch was then taken from "Auto-open" to "closed". At this point, Operators released the slow close push button and the expected response was that the valve would remain closed. It temporarily drifted open and then reclosed. This can occur because both the AC and DC solenoids need to deenergize in order to close the MSIVs. If either the AC or DC solenoids stick in their seats the 2-way and 4-way valves would be positioned to port instrument air to the underside of the MSIV actuator piston causing the valve to open.
A failure analysis on the SVCA for MSIVs 29A0V-86B and 29A0V-86C was conducted by Exelon PowerLabs and the results were delivered to JAF on February 25, 2016, in report ENT-40072. The only anomaly discovered was that both DC pilots in the SVCAs exhibited slow average vent times of 4.94-seconds for 29S0V-86B3 and 1.95-seconds for 29S0V-86C3 instead of an instantaneous actuation. A momentarily 'stuck' AC or DC solenoid could explain an increase in MSIV stroke time. However, the Exelon PowerLabs tests confirm that the AC solenoid consistently stroked to relieve air pressure instantaneously while the DC solenoid exhibited a delay.
The slow DC pilot valve responses affected the required closing time in two MSIVs. This condition caused two independent channels of a system used to control the release of radioactive material to become inoperable; reportable per 10 CFR 50.73(a)(2)(vii).
Cause
The common cause of the delayed closure of MSIVs 29A0V-86B and 29A0V-86C was "sticking" of DC solenoid valves 29S0V-86B3 and 29S0V-86C3.
Similar Events Internal The ST-1B MSIV fast closure testing and results are trended by the 1ST Program. Prior to this event there were two recent instances where MSIV closing time was greater than 5 seconds at JAF.
CR-JAF-2014-04335 - Close time on 29A0V-86B was 5.5 seconds during ST-1B testing. The apparent cause was high resistance in an electrical contact for the MSIV pilot closure logic.
CR-JAF-2008-01147 - Close time on 29A0V-86C was 43.12 seconds during ST-1B testing. The apparent cause was attributed to contamination introduced through the instrument air system into the 4-way valve.
External Limerick Generating Station, Unit 1, LER-2012-001 — Three MSIVs failed hot closing stroke time due to issues with testing accuracy.
Quad Cities Nuclear Power Station, Unit 1, LER-2013-002 — Four outboard MSIVs failed to close within 5 seconds because the actuator seals had degraded due to age and wear.
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.
James A. FitzPatrick Nuclear Power Plant 05000 — 333
3. LER NUMBER
— 002 — 00 2016 Manufacturer:
Manufacturer Model Number:
NPRDS Manufacturer Code:
NPRDS Component Code:
FitzPatrick Component ID:
Automatic Valve Corp AV 6910-075 A613
FSV
29S0V-86B3 and 29S0V-86C3
FAILED COMPONENT IDENTIFICATION:
Corrective Actions
Completed Actions
- SVCAs were replaced and both MSIVs were tested successfully.
Future Actions
- MSIV SVCA Preventative Maintenance (PM) frequency change from 8 years to 6 years
- Vendor is investigating the DC pilot solenoid failures and additional corrective actions will be based on the results.
Safety Significance
There was no actual radiological or nuclear safety consequence during this event.
Two isolation valves in each main steam line close automatically to prevent fuel damage by limiting the loss of reactor coolant in the case of a major steam system leak, and to limit the release of radioactive materials by isolating the primary containment. Valve stroke time is required to be short enough to limit the release of radioactive material in accordance with accident analyses. 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 core damage, and this closure time will ensure that any radiological doses are well below the guidelines set forth in 10 CFR 100.
This deficiency only affected two outboard MSIVs. In both cases, the inboard MSIVs performed satisfactorily.
Therefore, all main steam lines were able to perform their intended safety function to isolate.
References
- Exelon PowerLabs Report: ENT-40072, Failure Analysis on MSIV Solenoid Valve Cluster Assemblies 29A0V-86B and 29A0V-86C