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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
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James A. FitzPatrick NPP P.O. Box 110 Constellation. Lycoming, NY 13093
Alexander Sterio Site V ice President-JAF
JAFP-24-0027 June 24, 2024
United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-059 NRC Docket No. 50-333
Subject: LER: 2024-001-00, EDG Lube Oil Check Valve Bonnet Cap Leak due to Failed Gasket
Dear Sir or Madam:
This report is being submitted pursuant to 10 CFR 50. 73(a)(2)(i)(B) and 10 CFR
- 50. 73(a)(2)(v)(A).
There are no new regulatory commitments contained in this report.
Questions concerning this report may be addressed to Mr. Mark Hawes, Regulatory Assurance, at (315) 349-6659.
Sincerely,
Alexander Sterio Site Vice President
ADS/MH
Enclosure: LER: 2024-001-00, EDG Lube Oil Check Valve Bonnet Cap Leak due to Failed Gasket
cc: USNRC, Region I Administrator USNRC, Project Manager USNRC, Resident Inspector INPO Records Center (IRIS)
Abstract
On April 24, 2024, at 1948, with James FitzPatrick Nuclear Power Plant (JAF) at 100% power, the B Emergency Diesel Generator (EDG) was being operated for surveillance testing when lube oil leaked from the bonnet cap of check valve 93EDG-57B. The leak originated when a gasket between the body-to-bonnet connection failed. The gasket was installed on October 11, 2023. Investigation into the cause of the failed gasket is ongoing and a supplement will be provided.
This deficiency would have prevented the fulfillment of the B EDG subsystem safety function due to not meeting the lube oil inventory requirement. The other 3 EDG units were not affected by this deficiency.
This condition was prohibited by Technical Specifications (TS), which is reportable per 10 CFR 50.73(a)(2)(i)(B). In addition, during this period, when A EDG subsystem was inoperable for planned maintenance, both subsystems were inoperable, a condition reportable per 10 CFR 50.73(a)(2)(v)(A). The condition was corrected by replacing the check valve on April 25, 2024.
NRC FORM 366 (04-02-2024)
Background
The Emergency Onsite Power Supply System [EIIS identifier: EK] consists of two redundant Emergency Diesel Generator (EDG) subsystems. Each EDG subsystem consists of two EDG units. The capability of the two units in the subsystem to start, force parallel, and attain rated voltage and frequency together within 10 seconds, and run the necessary engineered safeguard loads, meet s the requirements for the Emergency AC Power System.
The EDG lubrication system [LA] is designed to provide sufficie nt lubrication (lube oil) to permit proper operation by circulating the lube oil to the diesel engine work ing surfaces and to remove excess heat generated by friction during operation. The lube oil inventory volume required to ensure 7 days continuous operation is 168 gallons based on the manufacturer's consumptio n values and without reaching the recommended minimum level.
In standby, the system circulates warmed oil through the EDG en gines to promote successful quick starts.
This is accomplished by a 5/8-inch line with a swing check valv e (93EDG-57B for B EDG unit), which closes during EDG operation to prevent bypassing flow. The check valve has a bonnet cap to access internals for preventive maintenance.
Event Description
On April 24, 2024, with James A. FitzPatrick Nuclear Power Plan t (JAF) at 100% power, a surveillance test was started at 19:12, involving an operational test of the B EDG subsystem. Operators were monitoring the performance when they discovered lube oil spraying from the top of check valve 93EDG-57B. At 19:48, the B EDG unit was declared inoperable. Operators secured the EDG as well as the circulating and turbocharger lube oil pumps. The leak originated from the bonnet cap.
With the engine in standby, the leak rate was approximately 60 drops per minute (dpm). A leak rate could not be observed with the system pressurized during the event; howev er, it was estimated that 11.5 gallons of lube oil was lost due to the leak. The operations staff estimated th at the engine was running for approximately 5 minutes with the leak before the engine was secured. Therefore, the leak rate was approximately 2.3 gallons per minute (gpm), or 138 gallons per hour (gph). The magnitude of the lube oil leak would have exhausted the lube oil supply and this deficiency would have prevented the fu nction of B EDG unit to fulfill its mission time.
The A, C, and D check valves did not have any similar leaking c ondition. The A EDG subsystem remained Operable and the D EDG unit remained available during this ev ent.
The check valve 93EDG-57B was replaced on April 25 by 13:00. Th ere was no leakage following the repair.
The Post Maintenance Testing was completed satisfactory restori ng the B EDG subsystem to Operable. NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 04/30/2027 (04-02-2024)
- 1. FACILITY NAME 050 2. DOCKET NUMBER 3. LER NUMBER NUMBER NO.
James A. FitzPatrick Nuclear Power Plant 05000333 052 2024 - 001 - 00
Event Analysis
On October 11, 2023, a planned preventive maintenance task was performed to open the bonnet cap and inspect the check valve internals, per industry Operating Exper ience. During post maintenance testing, with B EDG operating, an oil leak was identified. A temporary repa ir to install a gasket and use thread sealant was evaluated and installed to prevent oil leakage.
The failed check valve 93EDG-57B was sent to a laboratory for i nvestigation. Examination revealed uneven compression of the gasket and a crack in the thread root. A gas ket installed in the bonnet cap showed damage and delamination. The investigation into the causes of uneven c ompression is ongoing and a supplement to this report will be submitted by August 21, 2024.
This deficiency existed between when the repair was performed o n October 11, 2023, and when the check valve was restored to operable on April 25, 2024. During this p eriod, the gasket repair maintained operating lube oil system pressure temporarily, but it would not be expec ted to perform its function through the EDG mission time. The required lube oil inventory of 7 days require d per Technical Specification (TS) surveillance requirement (SR) 3.8.3.2 would not be met based on the increase d rate of consumption cause by this oil leak.
This deficiency renders the B EDG subsystem inoperable. The a llowed restoration time required by TS 3.8.1 for one inoperable EDG subsystem would be exceeded. This event is being reported as a condition prohibited by TS in accordance with 10 CFR 50.73(a)(2)(i)(B). During this period, when A EDG subsystem was inoperable due to testing, both subsystems were inoperable, and these events are reportable per 10 CFR 50.73(a)(2)(v)(A).
Cause
The mechanistic cause of the lube oil leak from check valve 93E DG-57B was from a failed gasket installed on the bonnet connection due to uneven compression of the gasket. The investigation into the causes of uneven compression is ongoing and a supplement to this report will be submitted by August 21, 2024.
Similar Events
No previous similar events.
FAILED COMPONENT IDENTIFICATION:
Manufacturer: Jenkins Brothers Manufacturer Model Number: 92-A Manufacturer Code: J036 Component Code: V FitzPatrick Component ID: 93EDG-57B NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 04/30/2027 (04-02-2024)
- 1. FACILITY NAME 050 2. DOCKET NUMBER 3. LER NUMBER NUMBER NO.
James A. FitzPatrick Nuclear Power Plant 05000333 052 2024 - 001 - 00
Corrective Actions
Completed Actions On April 25, 2024, check valve 93EDG-57B replaced and the B E DG subsystem was restored to Operable.
Planned Actions This information will be included with the supplement to this r eport.
Safety Significance
Nuclear safety - There were no actual nuclear consequences.
From October 11, 2023, until the failure of the gasket on April 24, 2024, there were 9 successful surveillance tests performed (approximately 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> total loaded on the ele ctrical bus). The gasket repair would have held pressure and EDG would operate until the gasket failure; theref ore, both EDGs units in the B EDG subsystem would have started and automatically powered the emer gency bus. Operators could have responded to a B EDG unit lube oil leak by securing it, but d uring a Loss of Coolant Accident (LOCA) event the low lube oil pressure trip signal is bypassed so B EDG un it would not automatically trip until it failed.
The D EDG unit, in the B EDG subsystem, remained available to supply power to the emergency bus.
References Issue Report - IR 04708722, Oil Leak Identified at 93EDG-57B, d ated October 11, 2023 Issue Report - IR 04769343, 93EDG-57B (lube oil gallery check v alve) Failure, dated April 25, 2024 Engineering Change - EC 639982, Install Gasket to Seal Bonnet C ap Leak on 93EDG-57B Check Valve, dated October 13, 2024