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Category:Licensee Event Report (LER)
MONTHYEAR05000318/LER-2024-002, Automatic Reactor Trip Due to Main Turbine Loss of Load2024-09-16016 September 2024 Automatic Reactor Trip Due to Main Turbine Loss of Load 05000317/LER-2024-003, A Diesel Generator Inoperable Due to Potential Transformer Failure2024-09-0606 September 2024 A Diesel Generator Inoperable Due to Potential Transformer Failure 05000318/LER-2024-001-01, Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip2024-08-20020 August 2024 Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip 05000317/LER-2024-001-01, Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed2024-07-0202 July 2024 Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed 05000317/LER-2024-002, Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus2024-04-29029 April 2024 Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus 05000318/LER-2024-001, Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip2024-04-24024 April 2024 Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip 05000318/LER-2023-004-01, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-04-12012 April 2024 Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000317/LER-2024-001, Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed2024-03-13013 March 2024 Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed 05000318/LER-2023-004, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-002, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank 05000317/LER-2023-001, Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank2023-11-27027 November 2023 Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank 05000318/LER-2023-001-01, Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power2023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power 05000318/LER-1923-001, Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power2023-05-11011 May 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power 05000318/LER-2022-003, Pressurizer Safety Valve As-Found Settings (Low) Outside Technical Specification Limits Due to Setpoint Drift2022-11-21021 November 2022 Pressurizer Safety Valve As-Found Settings (Low) Outside Technical Specification Limits Due to Setpoint Drift 05000318/LER-2022-002, Unplanned Safety Injection Actuation Signal Due to Human Error2022-11-11011 November 2022 Unplanned Safety Injection Actuation Signal Due to Human Error ML22063A7032022-03-0303 March 2022 Automatic Reactor Trip Due to High Reactor Coolant System 05000318/LER-2022-001, Forwards LER 2022-001-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip Due to High Reactor Coolant System Pressure2022-03-0303 March 2022 Forwards LER 2022-001-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip Due to High Reactor Coolant System Pressure 05000318/LER-2021-004, Manual Reactor Trip Due to Lowering Steam Generator Levels2022-01-18018 January 2022 Manual Reactor Trip Due to Lowering Steam Generator Levels 05000318/LER-2021-003, Auxiliary Feedwater Pump Inoperable Due to Improper Reset of Trip Throttle Valve2021-09-23023 September 2021 Auxiliary Feedwater Pump Inoperable Due to Improper Reset of Trip Throttle Valve 05000318/LER-2002-002, Manual Reactor Trip Due to Lowering Steam Generator Level Following Main Feedwater Regulating Valve Going Shut2021-05-19019 May 2021 Manual Reactor Trip Due to Lowering Steam Generator Level Following Main Feedwater Regulating Valve Going Shut 05000318/LER-2021-001, Calvert Cliff Nuclear Power Plant Unit No. 2, Pressure Heater Sleeve Weld Pressure Boundary Leakage Caused by Primary Water Stress Corrosion Cracking2021-04-21021 April 2021 Calvert Cliff Nuclear Power Plant Unit No. 2, Pressure Heater Sleeve Weld Pressure Boundary Leakage Caused by Primary Water Stress Corrosion Cracking 05000317/LER-2020-001, Regarding Undervoltage Condition on 4.16kV Electrical Bus 11 Resulted in Actuation of Emergency Diesel Generator 1 a2021-01-27027 January 2021 Regarding Undervoltage Condition on 4.16kV Electrical Bus 11 Resulted in Actuation of Emergency Diesel Generator 1 a ML19169A0592019-06-13013 June 2019 Reactor Vessel Level Monitoring System Special Report, Rev. 1 05000318/LER-2017-0012017-04-19019 April 2017 Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due To Setpoint Drift, LER 17-001-00 For Calvert Cliffs, Unit 2 re: Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due to Setpoint Drift 05000318/LER-2016-0012017-01-24024 January 2017 Automatic Reactor Trip Due to Main Turbine Electro-Hydraulic Control Fluid Leak, LER 16-001-00 for Calvert Cliffs Nuclear Power Plant, Unit No. 2 Regarding Automatic Reactor Trip Due to Main Turbine Electro-Hydraulic Control Fluid Leak 05000317/LER-2016-0032016-07-29029 July 2016 Unit 1 Automatic Trip on Loss of Load due to Spurious Steam Generator High Level Turbine Trip, LER 16-003-00 for Calvert Cliffs Nuclear Power Plant, Unit No. 1 Regarding Automatic Trip on Loss of Load due to Spurious Steam Generator High Level Turbine Trip 05000317/LER-2016-0042016-07-20020 July 2016 High Energy Line Break Barrier Breeched Due to Human Performance Error Causing Both Service Water Trains to be Inoperable, LER 16-004-00 for Calvert Cliffs, Unit 1 Regarding High Energy Line Break Barrier Breeched Due to Human Performance Error Causing Both Service Water Trains to be Inoperable 05000317/LER-2016-0022016-04-14014 April 2016 Pressurizer Safety Relief Nozzle Dissimilar Metal Weld Flaw Exceeded American Society of Mechanical Engineers Code Allowable Limit, LER 16-002-00 for Calvert Cliffs, Unit 1, Regarding Pressurizer Safety Relief Nozzle Dissimilar Metal Weld Flaw Exceeded American Society of Mechanical Engineers Code Allowable Limit 05000317/LER-2016-0012016-03-21021 March 2016 Manual Reactor Trip Due to High Secondary Side Sodium Levels Due to a Condenser Tube Leak, LER 16-001-00 for Calvert Cliffs Nuclear Power Plant Unit 1, Regarding Manual Reactor Trip Due to High Secondary Side Sodium Levels Due to a Condenser Tube Leak 05000318/LER-2015-0012016-01-27027 January 2016 Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip, LER 15-001-00 for Calvert Cliffs, Unit 2, Regarding Manual Reactor Trip Due to Steam Generator Feed Pump 22 Trip ML0319504602003-07-0303 July 2003 Special Report: National Pollution Discharge Elimination System Permit # MD0002399 Violation 2024-09-06
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Abstract
On July 18, 2024 at 1524, Calvert Cliffs Nuclear Power Plant Unit 2 incurred an uncomplicated automatic reactor trip from 100 percent power due to a Main Turbine Loss of Load trip initiated by the Reactor Protection System (RPS). The Loss of Load trip was the result of an internal Main Generator Exciter failure that led to a loss of field on the Main Generator that in turn led to a load reject trip from the Main Turbine. The direct cause of the Exciter failure was a failed stationary field pole electrical connection. An engineering analysis performed to determine the failure mechanism for the stationary failed field pole electrical connection identified cyclic fatigue as the cause for the failure. Impacted Exciter components were replaced and an extent of condition inspection on the other field pole electrical connections was performed prior to returning the Exciter to service. The root cause evaluation for this event is still in progress at this time.
PLANT AND SYSTEM IDENTIFICATION YEAR 2024 -
SEQUENTIAL NUMBER 002 REV NO.
00 Calvert Cliffs Nuclear Power Plant, Unit 2, is a Combustion Engineering Pressurized Water Reactor with a licensed maximum power level of 2737 megawatts thermal. The Energy Industry Identification System code used in the text is identified as [TL].
A. CONDITION PRIOR TO EVENT Unit: 2 Date: July 18, 2024 Power level: 100 Mode: Unit 2 was in Mode 1 when the event occurred.
B. DESCRIPTION OF EVENT At 1524 on 07/18/2024, the Control Room received an alarm on Unit 2 for Main Generator Loss of Field / Out of Step. In response to receipt of this unexpected alarm, the Unit 2 Control Room Operators identified erratic reactive load swings on both Unit 1 and Unit 2 as indicated on Control Room panel indications. As the Operators were retrieving the associated alarm manual response manual and commencing detailed monitoring activities, the Unit 2 reactor was automatically tripped (scrammed) by RPS due to a Loss of Load actuation.
The Unit 2 Control Room staff implemented immediate post trip actions and successfully responded to an uncomplicated reactor trip.
During troubleshooting activities to determine the cause of the Unit 2 Loss of Load trip, a local inspection of the Unit 2 Exciter identified a failed stationary field pole connection. The failed stationary field pole connection was identified at this time as being the direct cause for a loss of field / loss of excitation on the Main Generator which led to a Main Generator lockout that resulted in a load reject trip of the Main Turbine and the subsequent RPS Loss of Load automatic trip.
C. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES July 18, 2024 15:23:34: Unit 1 and Unit 2 begin to experience reactive load swings as identified on the site's three 500KV high line reactive load trends (identified during post-trip data review).
15:24:43: Generator lockout/ loss of field indication was received on the Unit 2 Plant Computer.
15:24:43: Turbine load reject indication was received on the Unit 2 Plant Computer.
15:24:44: RPS initiates an automatic trip for Unit 2.
18:33: The Shift Manager completes Event Notification#57233 to satisfy the requirements of 1 0CFR50. 72(b)(2)(iv)(B).
D. CAUSE OF EVENT
- 2. DOCKET NUMBER YEAR 05000318 2024 -
- 3. LER NUMBER SEQUENTIAL NUMBER 002 REV NO.
00 The method of discovery for this event was self-revealing and is documented in the site's Corrective Action Program (CAP) under IR 04788102. The direct cause cited for the Unit 2 automatic trip is the loss of an Exciter stationary field pole electrical connection resulting in a complete loss of excitation on the Main Generator. The current root cause is identified as cyclic fatigue to the point of failure on the Exciter stationary field pole electrical connection. The cyclic fatigue is attributed to a combination of long-term vibration of the Exciter and long-term out of specification Exciter air temperature.
The root cause evaluation for the Unit 2 main turbine loss of load trip due to the failure of the exciter electrical connection is still in progress at the time of this Licensee Event Report (LER) submittal; therefore, a supplement to the LER will be submitted following completion of the associated CAP product.
E. SAFETY ANALYSIS The subject event satisfies the criteria in NUREG-1022, Revision 3, for any event or condition that resulted in manual or automatic actuation of any of the systems listed in 1 0CFR50. 73, paragraph (a)(2)(iv)(B).
Specifically, for this event, the Reactor Protection System actuated. Therefore, this event is reportable pursuant to 10CFR50.73(a)(2)(iv)(A). The resultant automatic trip was uncomplicated and there were no safety consequences as a result of the event. All safety systems functioned and operated as designed.
F. CORRECTIVE ACTIONS During the forced outage following the July 18, 2024 Unit 2 automatic trip, the following immediate actions were taken prior to restarting the unit:
Two Exciter stationary field poles were replaced - the stationary field pole that experienced the failed connection and the adjacent stationary field pole that had indications of a partial failure at the corresponding connection location. The two connection locations for the replaced stationary field poles are connected to one another by a jumper (metal bar). The jumper was determined to not be impacted by the failure and was reused.
An extent of condition inspection of the remaining Exciter stationary field poles was performed and no other issues or concerns were identified.
Following completion of the forced outage to effect repairs to the Exciter, Unit 2 was paralleled to the grid on 7/23/24.
As part of the continuing root cause evaluation, corrective actions will be developed as appropriate to address the identified root and contributing causes of the event.
G. PREVIOUS OCCURRENCES
- 2. DOCKET NUMBER YEAR 05000318 2024 -
- 3. LER NUMBER SEQUENTIAL NUMBER 002 REV NO.
00 A review of Calvert Cliffs' events was performed. No events were identified from this review that involved a reactor trip due to a failure of a Main Generator Exciter.
H. COMPONENT FAILURE DATA Component Exciter IEEE 803 FUNCTION ID EXC IEEE805 SYSTEM ID TL Page_4_ of _4_
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05000318/LER-2024-001-01, Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip | Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip | | 05000318/LER-2024-001, Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip | Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip | | 05000317/LER-2024-001-01, Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed | Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed | | 05000317/LER-2024-001, Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed | Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000318/LER-2024-002, Automatic Reactor Trip Due to Main Turbine Loss of Load | Automatic Reactor Trip Due to Main Turbine Loss of Load | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000317/LER-2024-002, Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus | Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000317/LER-2024-003, A Diesel Generator Inoperable Due to Potential Transformer Failure | A Diesel Generator Inoperable Due to Potential Transformer Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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