|
---|
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
[Table view] |
LER-2024-003, A Diesel Generator Inoperable Due to Potential Transformer Failure |
Event date: |
|
---|
Report date: |
|
---|
Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
---|
3172024003R00 - NRC Website |
|
text
Abstract
On July 2, 2024, the Main Control Room received alarm 4KV BUS U/V, 480V BUS U/V, 125V DC, Window AA06. Initial investigation using the Alarm Response Manual (ARM) did not identify any abnormal degraded conditions and the 1A Emergency Diesel Generator (EDG) was immediately determined to be operable. Follow-up investigation and troubleshooting identified a failed potential transformer associated with the 17 4KV bus protective relays, which would result in the 1A EDG output breaker tripping open on overcurrent during load sequencing in an emergency scenario. The 1A EDG was promptly declared inoperable on July 8, 2024, and the station entered Technical Specification Condition 3.8.1.B for Unit 1 and 3.8.1.E for Unit 2. After entering the Technical Specification Conditions the site took all requisite Required Actions. The potential transformer was replaced on July 10, 2024, and following a successful surveillance run, the 1A EDG was declared operable on July 11, 2024.
Prior to entering the Technical Specification Conditions and taking the associated requisite Required Actions, in the period between July 2, 2024, and July 8, 2024, the station exceeded the completion time for Technical Specification LCO 3.8.1 for Unit 1 and 3.8.1 for Unit 2; therefore, this event is reportable under 10CFR50.73(a)(2)(i)(B) as an operation or condition which was prohibited by the plant's Technical Specifications.
(See Page 2 for required number of digits/characters for each block)
(See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/) Page 4 of 4 E. SAFETY ANALYSIS The subject event satisfies the criteria in NUREG-1022, Revision 3, for any operation or condition that was prohibited by the plants technical specifications. The 4kV Bus U/V, 480 V Bus U/V, 125 VDC received in the Main Control Room on 7/2/2024 at 2 am. The 1A EDG was declared inoperable on 7/8/2024, and the station entered TS Condition 3.8.1.B for Unit 1 and 3.8.1.E for Unit 2. After entering the TS Conditions the site took all requisite Required Actions. The 1A EDG was declared operable on July 11, 2024. However, prior to entering the TS Conditions and taking the associated requisite Required Actions on 7/8/2024, Unit 1 exceeded the completion time for TS Condition 3.8.1.B and the completion time for the subsequently Required Actions.
Additionally, Unit 2 exceeded the completion time for TS Condition 3.8.1.E and the completion time for the subsequently Required Actions. Therefore, this event is reportable pursuant to 10CFR 50.73(a)(2)(i)(B). This event did not result in any actual nuclear safety consequences.
F. CORRECTIVE ACTIONS The potential transformer was replaced on 7/10/2024, and following a successful surveillance run the 1A EDG was declared Operable on 7/11/2024. Training, observations, and procedure change actions have been taken to address the human performance factors that contributed to the event.
G. PREVIOUS OCCURRENCES A review of previous Calvert Cliffs events was performed for the last three years. The review did not identify any events stemming from the failure of a potential transformer which resulted in a condition prohibited by the plants Technical Specifications.
H. COMPONENT FAILURE DATA Component IEEE 803 IEEE 805 FUNCTION ID SYSTEM ID Transformer, Potential.
XPT EK
|
---|
|
|
| | Reporting criterion |
---|
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 |
|