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Category:Licensee Event Report (LER)
MONTHYEAR05000318/LER-2024-002-01, Automatic Reactor Trip Due to Main Turbine Loss of Load2025-01-24024 January 2025 Automatic Reactor Trip Due to Main Turbine Loss of Load 05000318/LER-2024-003, Automatic Reactor Trip Due to Main Turbine Loss of Load2024-12-0909 December 2024 Automatic Reactor Trip Due to Main Turbine Loss of Load 05000318/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 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 ML23331A2992023-11-27027 November 2023 Submittal of 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-2023-001, 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 05000318/LER-2019-001, Misapplication of Technical Specification Following Failed Surveillance Resulted in Operation Prohibited by Technical Specifications2019-06-28028 June 2019 Misapplication of Technical Specification Following Failed Surveillance Resulted in Operation Prohibited by Technical Specifications ML19169A0592019-06-13013 June 2019 Reactor Vessel Level Monitoring System Special Report, Rev. 1 05000317/LER-2018-001-01, Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due to Damaged Internals2019-02-0707 February 2019 Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due to Damaged Internals 05000317/LER-2018-001, For Calvert Cliffs Nuclear Power Plant, Units No. 1 and 2, Both Unit 2 Emergency Diesel Generators Inoperable Due to Depressurization in Common Air Start Headers2018-12-0707 December 2018 For Calvert Cliffs Nuclear Power Plant, Units No. 1 and 2, Both Unit 2 Emergency Diesel Generators Inoperable Due to Depressurization in Common Air Start Headers 05000317/LER-2018-003-01, Control Room Loss of Ventilation Due to Smoke Detector Failure Causing Common Supply Damper to Shut2018-10-0808 October 2018 Control Room Loss of Ventilation Due to Smoke Detector Failure Causing Common Supply Damper to Shut 05000317/LER-2018-003, Control Room Loss of Ventilation Due to Smoke Detector Failure Causing Common Supply Damper to Shut2018-08-27027 August 2018 Control Room Loss of Ventilation Due to Smoke Detector Failure Causing Common Supply Damper to Shut 05000317/LER-2018-002, Items Non-Conforming to Design for Tornado Missile Protection2018-06-0707 June 2018 Items Non-Conforming to Design for Tornado Missile Protection 05000318/LER-2017-001, For Calvert Cliffs, Unit 2 Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due to Setpoint Drift2017-04-19019 April 2017 For Calvert Cliffs, Unit 2 Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due to Setpoint Drift 05000318/LER-2016-001, Regarding Automatic Reactor Trip Due to Main Turbine Electro-Hydraulic Control Fluid Leak2017-01-24024 January 2017 Regarding Automatic Reactor Trip Due to Main Turbine Electro-Hydraulic Control Fluid Leak 05000317/LER-2016-003, Regarding Automatic Trip on Loss of Load Due to Spurious Steam Generator High Level Turbine Trip2016-07-29029 July 2016 Regarding Automatic Trip on Loss of Load Due to Spurious Steam Generator High Level Turbine Trip 05000317/LER-2016-004, Regarding High Energy Line Break Barrier Breeched Due to Human Performance Error Causing Both Service Water Trains to Be Inoperable2016-07-20020 July 2016 Regarding High Energy Line Break Barrier Breeched Due to Human Performance Error Causing Both Service Water Trains to Be Inoperable 05000317/LER-2016-002, Regarding Pressurizer Safety Relief Nozzle Dissimilar Metal Weld Flaw Exceeded American Society of Mechanical Engineers Code Allowable Limit2016-04-14014 April 2016 Regarding Pressurizer Safety Relief Nozzle Dissimilar Metal Weld Flaw Exceeded American Society of Mechanical Engineers Code Allowable Limit 05000317/LER-2016-001, Regarding Manual Reactor Trip Due to High Secondary Side Sodium Levels Due to a Condenser Tube Leak2016-03-21021 March 2016 Regarding Manual Reactor Trip Due to High Secondary Side Sodium Levels Due to a Condenser Tube Leak 05000318/LER-2015-001, Regarding Manual Reactor Trip Due to Steam Generator Feed Pump 22 Trip2016-01-27027 January 2016 Regarding Manual Reactor Trip Due to Steam Generator Feed Pump 22 Trip 05000317/LER-2015-003, Regarding Diesel Generator Inoperable Due to Lube Oil Filter Fouling Due to Coolant Leakby on a Cylinder Liner2015-11-0909 November 2015 Regarding Diesel Generator Inoperable Due to Lube Oil Filter Fouling Due to Coolant Leakby on a Cylinder Liner 05000317/LER-2015-002, Regarding Automatic Reactor Trips Due to Transmission System Disturbance2015-06-0505 June 2015 Regarding Automatic Reactor Trips Due to Transmission System Disturbance 05000317/LER-2015-001, Regarding Component Cooling and Shutdown Heat Exchanger Lineup Potential to Exceed Design Basis Temperatures2015-03-20020 March 2015 Regarding Component Cooling and Shutdown Heat Exchanger Lineup Potential to Exceed Design Basis Temperatures 05000317/LER-2014-007, Regarding Reactor Coolant System Pressure Boundary Leakage in Reactor Coolant Pump Differential Pressure Transmitter Tubing2014-09-19019 September 2014 Regarding Reactor Coolant System Pressure Boundary Leakage in Reactor Coolant Pump Differential Pressure Transmitter Tubing 05000318/LER-2014-002, Diesel Generator Technical Specification Surveillance Requirement Missed Due to Human Performance Error2014-08-0707 August 2014 Diesel Generator Technical Specification Surveillance Requirement Missed Due to Human Performance Error 05000317/LER-2014-006, Regarding Reactor Trip Due to Reactor Protective System Matrix Relay Testing Pushbutton Failure2014-06-26026 June 2014 Regarding Reactor Trip Due to Reactor Protective System Matrix Relay Testing Pushbutton Failure 05000317/LER-2014-005, Regarding Condition Prohibited by Technical Specifications Due to Human Performance Error2014-05-12012 May 2014 Regarding Condition Prohibited by Technical Specifications Due to Human Performance Error 05000317/LER-2014-004, Regarding Unfused 250 Vdc Circuits Result in 10 CFR Part 50 Appendix R Unanalyzed Condition Due to Original Design Did Not Adequately Address Fire Protection Requirements2014-05-0101 May 2014 Regarding Unfused 250 Vdc Circuits Result in 10 CFR Part 50 Appendix R Unanalyzed Condition Due to Original Design Did Not Adequately Address Fire Protection Requirements 05000317/LER-2014-003, Regarding Pressurizer Safety Valves As-Found Settings (Low) Outside Technical Specification Limits Due to Inadequate Lift Spring Performance2014-04-24024 April 2014 Regarding Pressurizer Safety Valves As-Found Settings (Low) Outside Technical Specification Limits Due to Inadequate Lift Spring Performance 05000317/LER-2014-002, Regarding Condition Prohibited by Technical Specifications Due to Auxiliary Feedwater Train Inoperable Due to Human Performance Error2014-04-0303 April 2014 Regarding Condition Prohibited by Technical Specifications Due to Auxiliary Feedwater Train Inoperable Due to Human Performance Error 05000317/LER-2014-001, Regarding Reactor Trip Due to Turbine Control System Reboot2014-03-20020 March 2014 Regarding Reactor Trip Due to Turbine Control System Reboot 2025-01-24
[Table view] |
LER-2002-002, Re Potential High Pressure Safety Injection Pump Run-Out Failure |
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3172002002R00 - NRC Website |
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Peter E. Katz Plant General Manager 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410 495-4101 Constellation Nuclear Calvert Cliffs Nuclear Power Plant A Member of the Constellation Energy Group April 18, 2002 U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318; License Nos. DPR 53 & DPR 69 Licensee Event Report 2002-02 Potential High Pressure Safety Injection Pump Run-out Failure The attached report is being sent to you as required under 10 CFR 50.73 guidelines. Should you have questions regarding this report, we will be pleased to discuss them with you.
Very truly yours, "I---I I
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PEK/TER/bjd Attachment cc:
R. S. Fleishman, Esquire J. E. Silberg, Esquire Director, Project Directorate I-1, NRC D. M. Skay, NRC H. J. Miller, NRC Resident Inspector, NRC R. I. McLean, DNR
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Abstract
On February 21, 2002, a potential high pressure safety injection (HPSI) pump run-out failure mode was determined to exist if a large break loss-of-coolant-accident (LOCA) occurred during reverse flow testing of HPSI pump discharge check valves. The test resulted in a plant configuration where the non-tested HPSI pump was aligned to both HPSI headers. If a large break LOCA had occurred during the test, the remaining operable HPSI pump would have supplied coolant to both headers. High pressure safety injection pump flow-rate would have increased and probably caused the pump to fail due to run-out.
High pressure safety injection pumps have been verified to operate satisfactorily at flow-rates up to 771 gpm. However, the increased flow-rate when injecting into two headers pushes the predicted flow above this value. It is not known at what flow-rate run-out failure of a HPSI pump would occur. This potential HPSI failure is caused by a procedural deficiency that has been present since startup.
The test procedure has been changed to ensure that the operable HPSI pump is only aligned to it's own header during this test.
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IV.
CORRECTIVE ACTIONS
Both STP's 0-65-1 and 2 have been revised to include a step to shut the HPSI header isolation valve, for the HPSI pump being tested, while a HPSI pump discharge check valve is being reverse flow tested. (1 -SI-654 for testing 13 HPSI pump; 1-SI-656 for testing 11 HPSI pump; 2-SI-654 for testing 23 HPSI pump; 2-SI-656 for testing 21 HPSI pump.) These procedural changes will prevent a HPSI pump from being aligned to two HPSI headers during future performance of STP 0-65-1 and 2.
V.
ADDITIONAL INFORMATION
A.
Affected Component Identification:
IEEE 803 IEEE 805 Component or System EIIS Funct System ID Reactor RCT Reactor Core System AC HPSI Pump AC HPSI Discharge Check Valve AC HPSI Cross-Connect Valve AC B.
Previous similar events
A review of Calvert Cliffs' Licensee Event Reports over the past several years has been performed. The review did not identify any similar reportable events.
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