07-29-2016 | On May 31, 2016 at 1626, Calvert Cliffs Unit 1 experienced an automatic reactor trip. The cause of the trip was a spurious high level steam generator signal due to a failed Steam Generator 11 Channel B High Level Turbine Trip Under Voltage Logic Module, 12/4BL-XA27.
The spurious high level trip signal resulted in a turbine trip followed by an automatic reactor protection system trip on loss of load. The failed under voltage logic module was sent off-site to the vendor to conduct a failure analysis. The analysis identified two most probable causes for the failure. The first most probable cause was due to an intermittent failure of an integrated circuit of the under voltage logic module. The second most probable cause was due to an inadvertent solder bridge between a pin on the integrated circuit chip and the board. A refurbished logic module was installed and subsequently tested prior to the unit returning to power. The corrective action planned to prevent recurrence is to replace the current Engineered Safety Features Actuation System (which includes the non-safety high level turbine trip) with a system that will eliminate single point vulnerabilities within this system.
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Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 IR 05000318/20240072024-11-0606 November 2024 Assessment Follow-Up Letter for Calvert Cliffs Nuclear Power Plant, Unit 2 (Report 05000318/2024007) IR 05000317/20240032024-10-22022 October 2024 Integrated Inspection Report 05000317/2024003, 05000318/2024003, and Independent Spent Fuel Storage Installation Report 07200008/2024001 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 ML24283A0012024-10-0909 October 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000317/20245012024-10-0707 October 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000317/2024501 and 05000318/2024501 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000317/20240052024-08-29029 August 2024 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2024005 and 05000318/2024005) ML24240A2462024-08-27027 August 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report ML24240A1112024-08-27027 August 2024 Registration of Use of Casks to Store Spent Fuel 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 05000317/20240022024-08-0606 August 2024 Integrated Inspection Report 05000317/2024002 and 05000318/2024002 IR 05000317/20240102024-07-31031 July 2024 Age-Related Degradation Inspection Report 05000317/2024010 and 05000318/2024010 ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24198A0442024-07-16016 July 2024 Inservice Inspection Report IR 05000317/20244012024-07-0909 July 2024 Security Baseline Inspection Report 05000317/2024401 and 05000318/2024401 ML24177A1832024-06-25025 June 2024 Inservice Inspection Report 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 ML24161A0012024-06-0909 June 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML24150A0522024-05-29029 May 2024 Operator Licensing Examination Approval ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24136A1962024-05-15015 May 2024 Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report IR 05000317/20240012024-05-0707 May 2024 Integrated Inspection Report 05000317/2024001 and 05000318/2024001 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 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 ML24101A1942024-04-22022 April 2024 Closeout Letter for GL 2004-02 ML24114A0182024-04-18018 April 2024 Electronic Reporting of Occupational Exposure Reporting 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 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 IR 05000317/20240402024-04-11011 April 2024 95001 Supplemental Inspection Report 05000317/2024040 and Follow-Up Assessment Letter 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 ML24082A0082024-03-22022 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24078A1152024-03-18018 March 2024 10 CFR 50.46 Annual Report ML24059A0632024-03-15015 March 2024 Authorization and Safety Evaluation for Alternative Request ISI-05-021 (EPID L-2023-LLR-0006) - Non-Proprietary IR 05000317/20230062024-02-28028 February 2024 Annual Assessment Letter for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, (Reports 05000317/2023006 and 05000318/2023006 ML24052A0072024-02-14014 February 2024 Core Operating Limits Report for Unit 1, Cycle 27, Revision 0 ML24040A0962024-02-0909 February 2024 Notification of Readiness for NRC 95001 Inspection ML24040A1492024-02-0909 February 2024 Response to NRC Request for Additional Information Regarding Final Response to Generic Letter 2004-02 IR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 2024-09-06
[Table view] 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-2024-002, 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 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 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 ML22063A7032022-03-0303 March 2022 Automatic Reactor Trip Due to High Reactor Coolant System 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 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] |
I. DESCRIPTION OF EVENT:
Energy Industry Identification System (EIIS) codes are identified in the text as [XX]
A. INITIAL CONDITIONS:
Unit 1 was operating in Mode 1 at 100 percent power on May 31, 2016 prior to the event.
B. EVENT:
On May 31, 2016 at 1626, Calvert Cliffs Unit 1 reactor [RCT] tripped. The cause of the trip was a spurious high level steam generator [SG] signal due to a failed Steam Generator 11 Channel B High Level Turbine Trip Under Voltage Logic Module [IMOD], 12/4BL-XA27. The spurious high level trip signal resulted in a main turbine [TRB] trip followed by an automatic reactor protection system [JD] (RPS) trip on loss of load. Following the reactor trip, all safety systems performed as designed to safely shutdown the unit in an uncomplicated trip. The unit remained in Mode 3 while troubleshooting was conducted.
The failed under voltage logic module was sent off-site to the vendor to conduct a failure analysis. The analysis identified two most probable causes for the failure. The first most probable cause was an intermittent failure of an integrated circuit of the under voltage logic module. The second most probable cause was an inadvertent solder bridge between pin 6 on the U5 chip and board.
Following installation of a refurbished under voltage logic module and subsequent testing of the module, the unit commenced startup activities. Unit 1 was returned to Mode 1 at 2040 on June 1, 2016. The unit returned to full power on June 2, 2016 at 1040.
C. INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED
TO THE EVENT:
There were no structures, systems or components inoperable at the start of the event that contributed to the event.
D. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES:
May 31, 2016 — 1626: Spurious hi level trip signal from 12/4BL-XA27 resulting in a main turbine trip. The main turbine trip resulted in an automatic reactor trip due to loss of load.
entered Mode 2.
June 1, 2016 — 2040: Unit 1 entered Mode 1.
June 1, 2016 — 2355: Paralleled Unit 1 Main Generator to the grid.
June 2, 2016 — 1040: Unit 1 returned to 100% power.
E. FAILURE MODES:
refueling outage. Following the Unit 1 trip, 12/4BL-XA27 reset shortly after the trip without any external input. The under voltage logic module subsequently tripped and reset several more times during the hours following the reactor trip. After initial on-site troubleshooting, the under voltage logic module was sent off-site to the vender. The vendor's evaluation determined two most probable causes for the failure of the under voltage logic module. The first most probable cause was an intermittent failure of an integrated circuit of the under voltage logic module. The second most probable cause was due to an inadvertent solder bridge between pin 6 on the U5 chip and the board. A refurbished logic module was installed and subsequently tested satisfactorily prior to the unit returning to power.
F. METHOD OF DISCOVERY:
The method of discovery was self-revealing upon the failure of 12/4BL-XA27 while in operation.
This event is documented in the site's Corrective Action Program under IR 02676088.
II. CAUSE OF EVENT
A. SAFETY CONSEQUENCES:
There were no human performance issues related to the reactor trip or the following recovery and the unit shutdown.
The spurious high level trip signal of 12/4BL-XA27 resulted in an automatic RPS actuation due to loss of load following the main turbine trip. The loss of load trip from 100 percent power is an analyzed anticipated operational occurrence event and the plant responded according to the analysis, with no complications.
The steam generator high level trip function is a non-Engineered Safety Features Actuation System [JE] (ESFAS) function. The purpose of this trip is to protect the main turbine against damage from water carryover.
This event satisfies the criteria in NUREG-1022, Revision 3, for RPS actuation. Therefore, this event is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A). An immediate event notification report (51967) was also made pursuant to 10 CFR 50.72(b)(2)(iv)(B).
B. CORRECTIVE ACTIONS:
The faulty under voltage logic module was replaced with a refurbished under voltage logic module.
The corrective action planned to prevent recurrence is to replace the current ESFAS (which includes the non-safety high level turbine trip) with a system that will eliminate single point vulnerabilities within ESFAS.
A supplemental licensee event report will be submitted if additional information is subsequently developed that would significantly change the corrective actions for this event.
III. PREVIOUS SIMILAR EVENTS:
A review of Calvert Cliffs' licensee event reports in the last four years was performed. This review did not identify an event that involved the same underlying concern or reason for this event.
A. COMPONENT INFORMATION:
COMPONENT IEEE 803 IEEE 805
FUNCTION ID SYSTEM ID
Logic Module, 12/4BL-XA27 IMOD JC 12/4BL-XA27, 11 SG high level turbine trip under voltage logic module was manufactured by Vitro Labs and was recently refurbished by FTI, Inc.
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05000318/LER-2016-001 | 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000317/LER-2016-001 | 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000317/LER-2016-002 | 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 | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000317/LER-2016-003 | 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000317/LER-2016-004 | 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 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
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