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Category:Letter
MONTHYEARRS-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 05000373/LER-2023-001-01, Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate2024-10-0909 October 2024 Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000373/20244012024-09-27027 September 2024 County Station – Security Baseline Inspection Report 05000373/2024401 and 05000374/2024401 ML24263A2062024-09-19019 September 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS ML24260A0492024-09-16016 September 2024 Operator Licensing Examination Approval - Lasalle County Station, Unit 1 and 2, September 2024 RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification 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 05000373/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Lasalle County Station (Report 05000373/2024005; 05000374/2024005) IR 05000373/20244022024-08-28028 August 2024 County Station - Cyber Security Inspection Report 05000373/2024402 and 05000374/2024402 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 05000373/LER-2024-004-01, Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer2024-08-22022 August 2024 Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer IR 05000373/20240022024-08-13013 August 2024 County Station - Integrated Inspection Report 05000373/2024002 and 05000374/2024002 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 05000373/20244202024-08-0505 August 2024 County Station - Security Baseline Inspection Report 05000373 2024420 and 05000374 2024420 05000373/LER-2024-003-01, Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-07-31031 July 2024 Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions ML24178A2522024-06-27027 June 2024 County Station – Acknowledgement of Response to NRC Inspection Report 05000373/2024001 and 05000374/2024001 and Disputed Non-Cited Violation 05000373/LER-2024-004, Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer2024-06-19019 June 2024 Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer 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 05000373/LER-2024-003, Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-06-0606 June 2024 Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded IR 05000373/20240102024-05-29029 May 2024 County Station - Commercial Grade Dedication Inspection Report 05000373/2024010 and 05000374/2024010 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 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report 05000373/LER-2024-002, Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip2024-05-17017 May 2024 Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip ML24131A1512024-05-13013 May 2024 County Station - Integrated Report 05000373/2024001 and 05000374/2024001 IR 05000373/20240012024-05-13013 May 2024 County Station - Integrated Report 05000373/2024001 and 05000374/2024001 RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 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 05000373/LER-2024-001, Core Operating Limits Report Thermal Limits Exceeded2024-04-26026 April 2024 Core Operating Limits Report Thermal Limits Exceeded ML24108A1562024-04-15015 April 2024 Updated Final Safety Analysis Report (Ufsar), Revision 26 and Fire Protection Report (Fpr), Revision 11 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 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 ML24071A2122024-03-12012 March 2024 County Station - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection IR 05000373/20230062024-02-28028 February 2024 Annual Assessment Letter for Lasalle County Station, Units 1 and 2 (Report 05000373/2023006; 05000374/2023006) RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24018A0682024-02-0909 February 2024 Issuance of Amendment Nos. 262 and 247 Revised Design Bases of Lower Downcomer Braces ML24024A1332024-01-24024 January 2024 Confirmation of Initial License Examination IR 05000373/20230042024-01-24024 January 2024 County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004 IR 05000373/20230122024-01-18018 January 2024 County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012 ML23354A2902024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information IR 05000373/20230032023-11-0909 November 2023 County Station Integrated Inspection Report 05000373/2023003, 05000374/2023003, and 07200070/2023001 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000373/LER-2023-001-01, Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate2024-10-0909 October 2024 Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate 05000373/LER-2024-004-01, Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer2024-08-22022 August 2024 Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer 05000373/LER-2024-003-01, Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-07-31031 July 2024 Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded 05000373/LER-2024-004, Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer2024-06-19019 June 2024 Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer 05000373/LER-2024-003, Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-06-0606 June 2024 Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded 05000373/LER-2024-002, Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip2024-05-17017 May 2024 Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip 05000373/LER-2024-001, Core Operating Limits Report Thermal Limits Exceeded2024-04-26026 April 2024 Core Operating Limits Report Thermal Limits Exceeded RA23-067, Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation2023-12-0404 December 2023 Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation 05000373/LER-2017-0072017-08-18018 August 2017 Low Pressure Core Spray System Inoperable due to Loss of Cooling, LER 17-007-00 for LaSalle County Station, Unit 1, Regarding Low Pressure Core Spray System Inoperable due to Loss of Cooling 05000374/LER-2017-0032017-08-0909 August 2017 High Pressure Core Spray System Inoperable due to Injection Valve Stem-Disc Separation, LER 17-003-01 for LaSalle County Station, Unit 2 Regarding High Pressure Core Spray System Inoperable due to Injection Valve Stem-Disc Separation 05000373/LER-2017-0062017-07-14014 July 2017 Low Pressure Core Spray Inoperable due to Minimum Flow Valve Failure in Closed Position, LER 17-006-00 for LaSalle, Unit 1, Regarding Low Pressure Core Spray Inoperable due to Minimum Flow Valve Failure in Closed Position 05000374/LER-2017-0042017-07-14014 July 2017 Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test, LER 17-004-01 for LaSalle, Unit 2, Regarding Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test 05000373/LER-2017-0052017-04-18018 April 2017 Manual Reactor Scram Resulting From Feedwater Regulating Valve Failure Causing High Reactor Water Level, LER 17-005-00 for LaSalle County, Unit 1, Regarding Manual Reactor Scram Resulting From Feedwater Regulating Valve Failure Causing High Reactor Water Level 05000373/LER-2017-0042017-04-17017 April 2017 Secondary Containment Inoperable Due to Interlock Doors Open, LER 17-004-00 for LaSalle County, Unit 1, Regarding Secondary Containment Inoperable Due to Interlock Doors Open 05000373/LER-2017-0032017-04-14014 April 2017 Automatic Reactor Scram due to Main Generator Trip on Differential Current During Back-Feed Operations, LER 17-003-00 for LaSalle County Station, Unit 1, Regarding Automatic Reactor Scram due to Main Generator Trip on Differential Current During Back-Feed Operations 05000374/LER-2017-0022017-03-30030 March 2017 High Pressure Core Spray System Declared Inoperable due to Cooling Water Strainer Backwash Valve Stem-Disc Separation, LER 17-002-00 for LaSalle, Unit 2, Regarding High Pressure Core Spray System Declared Inoperable due to Cooling Water Strainer Backwash Valve Stem-Disc Separation 05000374/LER-2017-0012017-03-24024 March 2017 Manual Reactor Scram due to Turbine-Generator Run-Back Caused by Stem-Disc Separation in Stator Water Cooling Heat Exchanger Inlet Valve, LER 17-001-00 for LaSalle County, Unit 2 Regarding Manual Reactor Scram due to Turbine-Generator Run-Back Caused by Stem-Disc Separation in Stator Water Cooling Heat Exchanger Inlet Valve 05000373/LER-2017-0012017-02-0808 February 2017 Reactor Core Isolation Cooling System Inoperable Longer than Allowed by the Technical Specifications due to Low Suction Pressure Trips, LER 17-001-00 for LaSalle County, Unit 1, Regarding Reactor Core Isolation Cooling System Inoperable Longer than Allowed by the Technical Specifications due to Low Suction Pressure Trips 05000374/LER-2016-0012016-04-18018 April 2016 Secondary Containment Inoperable Due to Interlock Doors Open, LER 16-001-00 for LaSalle County, Unit 2, Regarding Secondary Containment Inoperable Due to Door Interlock Doors Open 05000373/LER-2016-0012016-04-11011 April 2016 Secondary Containment Inoperable due to Reactor Building Ventilation Damper Failure, LER 16-001-00 for LaSalle County, Unit 1 & 2, Regarding Secondary Containment Inoperable Due to Reactor Building Ventilation Damper Failure 2024-08-22
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LER-2024-004, Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer |
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LaSalle County Station 2601 North 21 " Road Constellation Marseilles. IL 61341 815-415-2000 Telephone
RA24-021 10 CFR 50.73
June 19, 2024
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
LaSalle County Station, Unit 1 Renewed Facility Operating License No. NPF-11 NRC Docket No. 50-373
Subject: Licensee Event Report 2024-004-00, Emergency Diesel Generator Auto-Start and Load due to Loss of Station Auxiliary Transformer
In accordance with 10 CFR 50.73(a)(2)(iv)(A), Constellation Energy Generation, LLC (CEG) is submitting Licensee Event Report (LER) Number 2024-004-00 for LaSalle County Station, Unit 1.
There are no regulatory commitments contained in this letter.
Should you have any questions concerning this report, please contact Ms. Laura Ekern, Regulatory Assurance Manager, at (815) 415-2800.
Christopher J. Smith Plant Manager LaSalle County Station
Enclosure : Licensee Event Report 2024-004-00
cc : Regional Administrator-NRC Region Ill NRC Senior Resident Inspector - LaSalle County Station NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB : NO. 3150-0104 EXPIRES : 04/30/2027 (04-02-2024)
- 1. Facility Name ~ 050 2. Docket Number 3.Page LaSalle County Station, Unit 1 052 00373 1 OF 5
- 4. Title Emergency Diesel Generator Auto-Start and Load due to Loss of Station Auxiliary Transformer
- 5. Event Date 6. LER Number 7. Report Date 8. Other Facilities Involved
Month Day Year Year Number No. Month Day Year NA 050 NA Sequential Revision Facility Name Docket Number
04 20 2024 2024 004 00 06 19 2024 Facility - - NA 052 NA Name Docket Number
- 9. Operating Mode 1 110. Power Level 100 percent
11. This Report is Submitted Pursuant to the Requirements of 10 CFR § : (Check all that apply)
'1f0 QFR Part 20 D 20.2203(a)(2)(vi) 1 O CFR Part 50 50.73(a)(2)(ii)(A) 0 50. 73(a)(2)(viii)(A) D 73.1200(a) 20.2201(b) D 20.2203(a)(3)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(ii)(B) D 50.73(a)(2)(viii)(B) 73.1200(b) 20.2201(d) D 20.2203(a)(3)(ii) 50.36(c)(1)(ii)(A) D 50.73(a)(2)(iii) D 50.73(a)(2)(ix)(A) D 73.1200(c)
D 20.2203(a)(1) D 20.2203(a)(4) D 50.36(c)(2) ~ 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x) 73.1200(d)
D 20.2203(a)(2)(i) 10 CFR Part 21 D 50.46(a)(3)(1i) D 50.73(a)(2)(v)(A) 10 CFR Part 73 D 73.1200(e)
D 20.2203(a)(2)(11) D 21.2(c) 50.69(g) D 50. 73(a)(2)(v)(B) D 73.77(a)(1) 73.1200(f)
D 20.2203(a)(2)(iii) 50.73(a)(2)(I)(A) 0 50.73(a)(2)(v)(C) 0 73. 77(a)(2)(i) 73.1200(g)
D 20.2203(a)(2)(Iv) 50. 73(a)(2)(I)(B) D 50.73(a)(2)(v)(D) D 73.77(a)(2)(ii) 73.1200(h) 20.2203(a)(2)(V) 50.73(a)(2)(i)(C) D 50. 73(a)(2)(vii)
D OTHER (Specify here, in abstract, or NRC 366A).
- 12. Licensee Contact for this LER Licensee Contact Phone Number (Include area code)
Joseph Reda, Operations Director (815) 415-2200
- 13. Complete One Line for each Component Failure Described in this Report
Cause System Component Manufacturer Reportable to IRIS Cause System Component Manufacturer Reportable to IRIS
X FK BKR W120 y X EB BKR 1005 y
- 14. Supplemental Report Expected Month Day Year
- 15. Expected Submission Date No ~ Yes (If yes, complete 15. Expected Submission Date) 07 31 2024
16. Abstract (Limit to 1326 spaces, i.e., approx imately 13 single-spaced typewritten lines)
On April 20, 2024, with LaSalle Unit 1 operating at 100 percent power and gas circuit breaker (GCB) 11-13 open to support transmission system operator testing of power line L0104 relays, oil circuit breaker (OCB) 1-13 tripped open on differential current resulting in the loss of the Unit 1 station auxiliary transformer (SAT). Bus 141 Y (Division 1 ), normally supplied by the Unit 1 SAT, failed to fast transfer to the Unit 1 unit auxiliary transformer (UAT), resulting in the Division 1 emergency diesel generator (EOG) to automatically start and load onto the 141Y bus, causing a load shed of the 141Y bus and momentary loss of power to the 141 Y bus. The loss of the Unit 1 SAT also caused the Division 3 EDG to automatically start and load, as designed, onto bus 143 (Division 3).
The load shed on bus 141Y caused power to be lost to the Unit 1 "A" (1A) reactor protection system (RPS) bus, resulting in a "A" RPS half-scram condition and closure of isolation valves in multiple systems. All actuations and isolations performed as designed. During the fast transfer of Division 2 from the Unit 1 SAT to UAT, the Unit 1 reactor building ventilation system (VR)
'B' supply isolation damper and "A' exhaust isolation damper went shut unexpectedly causing a loss of Unit 1 VR.
These events are reportable in accordance with 10 CFR 50. 73(a)(2)(iv)(A).
Plant and System Identification
LaSalle Country Station Unit 1 is a General Electric Boiling Water Reactor with 3546 Megawatts Thermal Rated Core Power. The affected system was the alternating current (AC) power system. The affected component is 345 kV oil circuit breaker (OCB) 1-13, the mechanism operated contacts (MOC) 15 and 16 of air circuit breaker (ACB) 1412, and the TSC switch contacts on ACS 1415.
Condition Prior to Event
Unit(s): 1 Date: April 20, 2024 Time : 07:04 CDT Reactor Mode(s): 1 Mode(s) Name : Power Operation Power Level: 100 percent
Description
Emergency Diesel Generator (EOG) Actuation and Load
On April 20, 2024, with gas service breaker (GCB) 11-13 open to support transmission system operator (TSO) testing of power line L0104 relays, OCB 1-13 tripped open on differential current resulting in the loss of the Unit 1 station auxiliary transformer (SAT). Bus 141Y (engineered safety feature (ESF) Division 1), which is normally supplied by the Unit 1 SAT, failed to fast transfer to the Unit 1 unit auxiliary transformer (UAT), resulting in the Division 1 EOG to automatically start and load onto the 141 Y bus, causing a load shed of the 141 Y bus and a momentary loss of power to the 141 Y bus. The loss of the Unit 1 SAT also caused the Division 3 EOG to automatically start and load, as designed, onto bus 143 (ESF Division 3), which is normally supplied by the Unit 1 SAT. Bus 142Y (ESF Division 2) fast transferred to the Unit 1 UAT,
as expected, resulting in no requirement for the Division 2 EOG to automatically start. The automatic starting of the Division 1 and Division 3 EDGs is considered a valid actuation due to the loss of power to ESF buses.
During the fast transfer of ESF Division 2 from the Unit 1 SAT to UAT, the Unit 1 reactor building ventilation system (VR)
'B ' supply isolation damper and "A' exhaust isolation damper went shut unexpectedly causing a loss of Unit 1 VR. This resulted in a main steam tunnel high temperature condition which was bypassed per station procedure. The dampers were reopened, and Unit 1 VR was restored.
Reactor Protection System (RPS) Unit 1 "A" Half-Scram
As a result of the load shed on bus 141Y, power was lost to the Unit 1 "A" (1A) RPS bus, resulting in a "A" RPS half-scram condition and closure of isolation valves in multiple systems. The condition was considered an invalid actuation because it was the result of losing power to the bus and not the result of a valid input signal to the RPS or intentional manual action. All actuations and isolations performed as designed.
The loss of the 1A RPS bus resulted in isolations of the reactor water cleanup system, main steam line drains, reactor coolant system sampling, instrument nitrogen system, reactor recirculation hydraulic power units, and containment monitoring system. The loss of the 1A RPS bus also resulted in the loss of power to portions of the average power range monitor, local power range monitor, oscillation power range monitor, and control rod block systems; as well as portions of the radiation monitoring for the main steam lines, reactor building vent, and fuel pool vent. Appropriate actuations and primary containment isolations occurred as designed.
After the loss of power to the 1A RPS bus, the applicable Technical Specification (TS) timeclocks and actions were entered. Power was restored to the 1A bus by transferring the bus to the alternate power supply in accordance with plant
procedures. The half-scram and isolations were reset, and the equipment was returned to operable status. All applicable TS timeclocks and actions were exited.
Cause
EDG Actuation and Load
The cause of OCB 1-13 tripping open is under investigation through the corrective action program. A supplemental LER will be submitted once the cause has been finalized.
Troubleshooting determined the cause of the fast transfer failure of bus 141 Y from the Unit 1 SAT to the Unit 1 UAT was increased resistance across MOC 15 and 16 of ACS 1412, and the TSC switch contacts were open on ACB 1415, Unit 1 UA T feed breaker to bus 141 Y.
RPS Unit 1A Half-Scram
The cause of the RPS Unit 1 A loss of power and half scram was the momentary loss of power from the 141Y bus due to the load shed caused by the fast transfer failure. The loss of power from the 141Y bus resulted in a loss of power to the 1A RPS motor-generator set that normally powers the 1A RPS.
Reportability and Safety Analysis
EOG Actuation and Load
The loss of the Unit 1 SAT and actuation of the Division 1 and Division 3 emergency diesel generators was initially reported as an 8-hour notification (ENS 57083) in accordance with 10 CFR 50. 72(b)(3)(iv)(A) for a valid actuation of the emergency AC electrical power systems. This event is also required to reported in accordance with 10 CFR 50.73(a)(2)(iv)(A) as an event that results in the valid actuation of the emergency AC electrical power systems.
RPS Unit 1 A Half-Scram
The loss of the Unit 1A RPS bus and associated RPS actuation is considered an invalid actuation because it was not the result of a valid signal and not an intentional manual action. The loss of the RPS bus resulted in general containment isolation signals that actuated containment isolation valves in more than one system or multiple main steam isolation valves while the unit was critical. Therefore, the loss of the RPS bus is reportable in accordance with 10 CFR 50. 73(a)(2)(iv)(A).
Safety System Functional Failure Review
The system equipment responses do not result in a safety system functional failure (SSFF) as defined in accordance with NEI 99-02, "Regulatory Assessment Performance Indicator Guideline." The EOG and RPS safety systems performed their as-designed safety functions.
NRC FORM 366 A (04-02-202 4 ) Page_3_ of _ 5 _
Corrective Actions
Corrective actions taken in response to the conditions were :
- Entered the required TS timeclocks and actions and notified the TSO to secure all testing.
- Transferred the 1 A RPS bus to the alternate power supply, reset the half-scram, and exited applicable TS timeclocks and actions.
- Closed OCB 1-13 and reenergized the Unit 1 SAT
- Transferred buses 141Y, 142Y, and 143 to the Unit 1 SAT; shutdown the Division 1 and Division 3 EDGs; and exited applicable TS timeclocks and actions.
- Transferred the 1A RPS bus back to the normal power supply.
- Racked out and then racked in ACB 1415 to close the TSC switch contacts.
- Cleaned MOC 15 and 16 on ACB 1412 to decrease the resistance back to acceptable levels.
- Develop electrical maintenance procedure to check all 4 kV and 6 kV switchgear breaker contacts to confirm alignment for fast transfer logic.
- Update the normal startup procedure to incorporate new electrical maintenance procedure during bus alignment.
The investigation for this event is still ongoing. A supplemental LER will be submitted once the investigation is complete, and the corrective actions will be updated as needed.
Previous Occurrences
There have been no previous occurrences of an EOG actuation in the past 3 years.
There have been two occurrences of RPS half-scrams in the past 3 years that were attributed to a loss of power.
Unit 1 LER 373-2024-002-00
On March 25, 2024, LaSalle Unit 1 was operating at 100 percent power, when the 18 RPS MG set electric power monitoring assembly (EPMA) output breaker tripped due to an underfrequency condition, which resulted in the loss of the 1 B RPS bus. The loss of power to this bus created a half-scram condition and initiated closure of isolation valves in multiple systems. The condition was an invalid actuation because it was not the result of actual plant conditions and not an intentional manual action. The cause of the MG set EPMA output breaker trip was the EPMA trip card for the output breaker being out of range high for the underfrequency setpoint which caused the trip on underfrequency. As a result, the EPMA trip card was replaced, and the system was restored back to its original configuration.
Unit 2 LER 374-2021-002-00
On May 31, 2021, LaSalle Unit 2 was operating at 100 percent power, when the 2A RPS motor generator (MG) set output breaker tripped due to an overload condition, which resulted in a loss of 2A RPS bus. Loss of power to this bus created a half-scram and initiated closure of outboard isolation valves in multiple systems. The condition was an invalid actuation because it was not the result of actual plant conditions and not an intentional manual action. The cause of the issue was a degraded voltage adjustment potentiometer (device 1 P) on the 2A RPS MG set, which was causing intermittent resistance readings. The intermittent resistance caused the output voltage of the RPS MG set to fluctuate. As a result, the degraded potentiometer and the voltage regulator were replaced as part of the trouble-shooting efforts, and the system was restored back to its original configuration.
Component Failure Data
Manufacturer : Westinghouse Electric Company Device: Oil Circuit Breaker, 345 kV Component ID : 0SYOCB1-13, 345 kV Oil Circuit Breaker 1-13
Manufacturer : ITE Circuit Breaker Limited Device: Air Circuit Breaker, 4160 V Component ID : ACB 1412 Bus Feed from SAT 1AP91 E (TR 142)
Manufacturer: ITE Circuit Breaker Limited Device: Air Circuit Breaker, 4160 V Component ID : ACB 1415 1AP04E / 1AP03E (141Y / 141X) Bus Tie