On April 1, 2016 at 20:24, Unit 2 entered Technical Specification 3.8.1 due to the A Diesel Generator ( DG) being inoperable due to misaligned contacts on a Mechanism-Operated Cell ( MOC) switch resulting in Fan 1V222A starting without a time delay. Based upon review of the history and cause, the condition likely existed since the supply breaker was replaced on July 19, 2010. The A DG was still able to perform its intended safety function; however, since the condition results in inability to meet Surveillance Requirement 3.8.1.18, the A DG must be considered inoperable during periods when 1V222A would have been available to start (without a time delay). As a result, this event is reportable as a condition prohibited by Technical Specifications, in accordance with 10CFR50.73(a)(2)(i)(B), since the inoperability is assumed to have existed for a period of time greater than allowed by the Technical Specifications. A review of historical information for the last three years identified instances in which one of the other DGs (B, C, or D) was inoperable.
Based on this information, this condition is also reportable as a condition that could have prevented fulfillment of a safety function in accordance with 10CFR50.73(a)(2)(v)(D).
The direct cause of the MOC switch contacts not aligning properly was mis-adjustment of the MOC switch linkage. The apparent cause of the MOC switch contacts not aligning properly is inadequate post maintenance testing (PMT) for the breaker swap because PMT did not check MOC switch contact alignment.
Procedures will be revised to include visual inspection to ensure the MOC switch contacts are properly aligned during post maintenance testing.
There were no actual consequences to the health and safety of the public as a result of this event. |
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Category:Letter
MONTHYEARML24289A1252024-10-22022 October 2024 – Authorized Alternative to Requirements of the ASME OM Code PLA-8145, Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-81452024-10-21021 October 2024 Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-8145 ML24291A1562024-10-16016 October 2024 Missed Annual Inventory Required by 40 CFR 266, Subpart in PLE 0026645 PLA-8148, Registration for the Use of Spent Fuel Storage Casks 311, 308, and 3102024-10-15015 October 2024 Registration for the Use of Spent Fuel Storage Casks 311, 308, and 310 PLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024 Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141 PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 ML24260A2312024-09-17017 September 2024 Senior Reactor and Reactor Operator Initial License Examinations 05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor 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 ML24233A2192024-09-0303 September 2024 – Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR 05000387/20240052024-08-29029 August 2024 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005) 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear IR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML24197A0982024-07-15015 July 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010 PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) 05000387/LER-2024-001, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) ML24092A4022024-04-0101 April 2024 Annual Financial Report (PLA-8098) PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024 Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109) PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance ML24067A2512024-03-19019 March 2024 Authorized Alternative to Requirements of the ASME Code ML24044A2532024-03-14014 March 2024 Associated Independent Spent Fuel Storage Installation – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0077 (Security Notifications, Reports, and Recordkeeping & Suspicious Activity Reporting)) IR 05000387/20240112024-02-29029 February 2024 Commercial Grade Dedication Inspection Report 05000387/2024011 and 05000388/2024011 IR 05000387/20230062024-02-28028 February 2024 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2023006 and 05000388/2023006) ML24039A1882024-02-27027 February 2024 Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods ML24037A3072024-02-22022 February 2024 Summary of Regulatory Audit in Support of Relief Request 5RR-02 PLA-8099, Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099)2024-02-13013 February 2024 Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099) IR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 05000387/LER-2023-004, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-01-0909 January 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8088, Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088)2023-12-0505 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088) 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear 05000387/LER-2024-001, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage 05000387/LER-2023-004, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-01-0909 January 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2023-003, D Diesel Generator Inoperable Due to Clogged Fuel Injectors2023-11-0909 November 2023 D Diesel Generator Inoperable Due to Clogged Fuel Injectors 05000387/LER-2023-002, Unplanned Lnoperability of the High Pressure Coolant Injection (HPCI) System Due Failure of the HPCI Turbine Stop Valve to Fully Close, Most Likely Due to Internal Corrosion and2023-06-0606 June 2023 Unplanned Lnoperability of the High Pressure Coolant Injection (HPCI) System Due Failure of the HPCI Turbine Stop Valve to Fully Close, Most Likely Due to Internal Corrosion And. 05000388/LER-2023-001, Secondary Containment Bypass Leakage Limit Exceeded Due Inadequate Procedure Guidance Resulting in Failure of the Inboard Containment Isolation Valve to Close and Pressurize2023-05-25025 May 2023 Secondary Containment Bypass Leakage Limit Exceeded Due Inadequate Procedure Guidance Resulting in Failure of the Inboard Containment Isolation Valve to Close and Pressurize 05000387/LER-2023-001, Inadvertent Contact Between Relay Cover and Relay Trip Contacts Resulted in Automatic Actuation of the ‘B’ Emergency Diesel Generator2023-05-22022 May 2023 Inadvertent Contact Between Relay Cover and Relay Trip Contacts Resulted in Automatic Actuation of the ‘B’ Emergency Diesel Generator 05000387/LER-2022-003, Inoperable 13.8kV Startup Transformer Due to Misaligned Load Tap Charger Local/Remote Control Switch2022-12-19019 December 2022 Inoperable 13.8kV Startup Transformer Due to Misaligned Load Tap Charger Local/Remote Control Switch 05000387/LER-2022-002-01, Automatic Reactor Scram Due to Reactor Protection System Actuation on High Reactor Vessel Pressure Signal Following Inadvertent Closure of Inboard Main Steam Isolation Valve2022-12-0505 December 2022 Automatic Reactor Scram Due to Reactor Protection System Actuation on High Reactor Vessel Pressure Signal Following Inadvertent Closure of Inboard Main Steam Isolation Valve 05000388/LER-2022-001, Re Inadequate Performance of Loss of Safety Determination Resulting in Both Divisions of Core Spray Being Inoperable2022-11-23023 November 2022 Re Inadequate Performance of Loss of Safety Determination Resulting in Both Divisions of Core Spray Being Inoperable 05000388/LER-2021-004-01, From Susquehanna Steam Electric Station, Unit 2 Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications Due to Inadequate Valve Modification2022-11-0303 November 2022 From Susquehanna Steam Electric Station, Unit 2 Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications Due to Inadequate Valve Modification 05000387/LER-2022-001-01, From Susquehanna Steam Electric Station Unit 1 - Main Steam Line Isolation Valve Leakage Due to Seating Surfaces Wear and Material Deposits2022-08-10010 August 2022 From Susquehanna Steam Electric Station Unit 1 - Main Steam Line Isolation Valve Leakage Due to Seating Surfaces Wear and Material Deposits 05000387/LER-2022-002, Automatic Reactor Scram Due to High Reactor Vessel Pressure Following Inadvertent Closure of Inboard Main Steam Isolation Valve2022-07-21021 July 2022 Automatic Reactor Scram Due to High Reactor Vessel Pressure Following Inadvertent Closure of Inboard Main Steam Isolation Valve 05000387/LER-2022-001, Main Steam Isolation Valve Leakage2022-06-0101 June 2022 Main Steam Isolation Valve Leakage 05000388/LER-2021-005-01, Condition Prohibited by Technical Specification Due to Setpoint Drift Attributed to Age Related Degradation2022-04-11011 April 2022 Condition Prohibited by Technical Specification Due to Setpoint Drift Attributed to Age Related Degradation 05000387/LER-2021-005-01, Automatic Reactor Scram Due to Turbine Control Valve Fast Closure2022-03-30030 March 2022 Automatic Reactor Scram Due to Turbine Control Valve Fast Closure 05000388/LER-2021-003-01, Automatic Reactor Scram Due to Main Turbine Trip Caused by Inadvertent Trip of the Main Generator Output Breakers2022-03-24024 March 2022 Automatic Reactor Scram Due to Main Turbine Trip Caused by Inadvertent Trip of the Main Generator Output Breakers 05000387/LER-2021-004-01, Loss of 1B RHRSW Pump Due to Cable Damage During Excavation Activities2022-03-21021 March 2022 Loss of 1B RHRSW Pump Due to Cable Damage During Excavation Activities 05000388/LER-2021-001-01, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch2022-03-21021 March 2022 Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch 05000388/LER-2021-005, Condition Prohibited by Technical Specification Due to Setpoint Drift2022-02-11011 February 2022 Condition Prohibited by Technical Specification Due to Setpoint Drift 05000388/LER-2021-002-01, Loss of Secondary Containment Due to Failed Differential Pressure Transmitter2022-02-0808 February 2022 Loss of Secondary Containment Due to Failed Differential Pressure Transmitter 05000387/LER-2021-005, Automatic Reactor Scram Due to Turbine Control Valve Fast Closure2022-01-26026 January 2022 Automatic Reactor Scram Due to Turbine Control Valve Fast Closure PLA-7977, Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications2021-12-0909 December 2021 Main Turbine Pressure Regulator Inoperable for Longer than Allowed by Technical Specifications PLA-7976, Automatic Reactor Scram Due to Main Turbine Trip2021-12-0909 December 2021 Automatic Reactor Scram Due to Main Turbine Trip 05000387/LER-2021-004, Loss of 1B RHRSW Pump Due to Cable Damage During Excavation Activities2021-12-0101 December 2021 Loss of 1B RHRSW Pump Due to Cable Damage During Excavation Activities 05000387/LER-2021-003-01, Automatic Reactor Scram Due to Main Turbine Trip Caused by a C Isophase Bus Ground Fault2021-11-11011 November 2021 Automatic Reactor Scram Due to Main Turbine Trip Caused by a C Isophase Bus Ground Fault 05000388/LER-2021-002, Re Loss of Secondary Containment2021-10-28028 October 2021 Re Loss of Secondary Containment 05000387/LER-2021-003, Automatic Reactor Scram Due to Main Turbine Trip2021-09-16016 September 2021 Automatic Reactor Scram Due to Main Turbine Trip 05000388/LER-2021-001, Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch2021-09-0101 September 2021 Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switch 05000388/LER-2017-0102018-02-0202 February 2018 Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches, LER 17-010-00 for Susquehanna, Unit 2 Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches 05000387/LER-2017-0072017-10-0909 October 2017 Secondary Containment Declared Inoperable Due to the opening of a plenum., LER 17-007-00 for Susquehanna Steam Electric Station Regarding Secondary Containment Declared Inoperable Due to Supply Air Flow 05000387/LER-2017-0052017-10-0404 October 2017 Automatic Reactor Protection System Trip on High Neutron Flux, LER 17-005-01 for Susquehanna, Unit 1 Regarding Automatic Reactor Protection System Trip on High Neutron Flux 05000388/LER-2017-0082017-09-18018 September 2017 1 OF 3, LER 17-008-00 for Susquehanna, Unit 2, Regarding Condition Prohibited by Technical Specifications Due to a Loose Terminal Block Associated with a Primary Containment Isolation Valve 05000387/LER-2017-0062017-09-0606 September 2017 Control Room Envelope In-leakage Exceeded the Technical Specification Limit, LER 17-006-00 for Susquehanna, Unit 2, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Exhaust Fan 05000387/LER-2017-0042017-08-0404 August 2017 Secondary Containment Declared Inoperable Due to Failure of an Exhaust Fan Breaker., LER 17-004-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Failure of an Exhaust Fan Breaker 05000387/LER-2017-0012017-05-0505 May 2017 Secondary Containment Breach Due to Simultaneous Opening of Airlock Doors, LER 17-001-00 for Susquehanna, Unit 2, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Sticking Door Latch 05000388/LER-2017-0022017-05-0505 May 2017 Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 during Unit 2 Refueling, LER 17-002-00 for Susquehanna, Unit 2, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 During Unit 2 Refueling 05000387/LER-2017-0032017-05-0505 May 2017 Susquehanna Steam Electric Station Unit 1 05000387, LER 17-003-00 for Susquehanna, Units 1 and 2, Regarding Loss of Secondary Containment Zone 3 Due to Fan Trip 05000387/LER-2017-0022017-04-12012 April 2017 Secondary Containment Breach due to Simultaneous Opening of Airlock Doors, LER 17-002-00 for Susquehanna, Unit 1, Regarding Secondary Containment Breach due to Simultaneous Opening of Airlock Doors 05000388/LER-2016-0052016-07-12012 July 2016 Unit 2 HPCI Manually Overridden Prior to a Manual Scram During a Plant Transient, LER 16-005-00 for Susquehanna, Unit 2, Regarding HPCI Manually Overridden Prior to a Manual Scram During a Plant Transient 05000387/LER-2016-0152016-06-15015 June 2016 Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error, LER 16-015-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error 05000387/LER-2016-0132016-06-0909 June 2016 Secondary Containment Declared Inoperable Due to Simultaneous Opening of Double Airlock Doors, LER 16-013-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Simultaneous Opening of Double Airlock Doors 05000387/LER-2016-0142016-06-0909 June 2016 Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error, LER 16-014-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error 05000387/LER-2016-0102016-05-31031 May 2016 Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Medical Emergency, LER 16-010-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Medical Emergency 05000387/LER-2016-0092016-05-26026 May 2016 Valid Primary Containment Isolation Actuation during Local Leak Rate Testing due to Human Performance Error, LER 16-009-00 for Susquehanna, Unit 1, Regarding Valid Primary Containment Isolation Actuation During Local Leak Rate Testing Due to Human Performance Error 05000387/LER-2016-0082016-05-19019 May 2016 Inoperability of Diesel Generator Due to Misalignment of MOC Switch Contacts Due to Inadequate Post Maintenance Testing, LER 16-008-00 for Susquehanna, Unit 1, Regarding Inoperability of Diesel Generator Due to Misalignment of MOC Switch Contacts Due to Inadequate Post Maintenance Testing 05000387/LER-2016-0052016-05-16016 May 2016 Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Human Performance Error, LER 16-005-00 for Susquehanna, Units 1 and 2, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Human Performance Error 05000387/LER-2016-0112016-05-16016 May 2016 Valve inoperability for a period longer than allowed by Technical Specifications, LER 16-011-00 for Susquehanna, Unit 1, Regarding Valve Inoperability for a Period Longer Than Allowed by Technical Specifications 2024-09-16
[Table view] |
comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
CONDITIONS PRIOR TO EVENT
Unit 1 — Mode 5, 0 percent Rated Thermal Power Unit 2 — Mode 1, 100 percent Rated Thermal Power There were no structures, systems, or components that were inoperable at the start of the event that contributed to the event other than the failed component itself.
EVENT DESCRIPTION
On April 1, 2016 at 20:24, Unit 2 entered Technical Specification (TS) 3.8.1 due to the A Diesel generator (DG) [EIIS System/Component Identifier: EK/DG] being inoperable due to the misaligned contacts [EIIS Component Identifier: CNTR] on the Mechanism-Operated Cell (MOC) switch. Based upon review of the history and cause, the condition likely existed since the supply breaker [EIIS Component Identifier: BKR] was replaced on July 19, 2010. A detailed timeline is provided below:
On July 19, 2010, Supply Breaker 1A20104 for the A DG was replaced during routine preventive maintenance activities.
On May 12, 2012, the timer (62X1A20104) [EIIS Component Identifier: TMR] associated with the Emergency Switchgear and Load Center Cooling Supply Fan (1V222A) [EIIS Component Identifier: FAN] immediately went to run without a time delay during performance of the Unit 1 Division I LOCA/LOOP test.
The acceptance criterion for this timer is greater than or equal to 54 seconds. The timer was replaced.
Post maintenance testing (PMT) was an abbreviated test performed by simulating the LOOP logic via a jumper and confirming the fan started after an appropriate time delay.
On April 17, 2014, during performance of Unit 1 Division I LOCA/LOOP testing, 1V222A started without a time delay. The timer was replaced. PMT was an abbreviated test to ensure the timer's delay was correct.
On April 25, 2014, during re-performance of LOCA/LOOP testing, 1V222A failed to give proper indication during bus stripping and bus re-energization, but the timing acceptance criterion was met. Possible wiring issues were investigated but none were found.
On March 23, 2016 at 13:36, Timer 62X1A20104 failed acceptance criteria during LOCA/LOOP testing as a result of 1V222A starting without a time delay. In accordance with the TS Bases, operability of the associated AC sources can be restored by rendering the affected load inoperable; Fan 1V222A was shut down by taking the hand switch to STOP. Extensive troubleshooting was performed to determine the cause, and on April 1, 2016, it was determined that the contacts on MOC Switch S1 in Breaker 1A20104 were not properly aligned.
On April 1, 2016 at 20:24, Unit 2 entered TS 3.8.1 due to the A DG being inoperable due to the misaligned contacts on the MOC switch. Unit 1 was in a refuel outage (Mode 5) and did not require the A DG; therefore, TS 3.8.2 was not entered on Unit 1.
On April 2, 2016 at 19:37, the A DG was declared Operable and Unit 2 exited TS 3.8.1 after MOC switch linkage adjustments were made and the contacts were cleaned.
comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
Based upon review of the history and cause, there is firm evidence that the condition existed since the supply breaker was replaced on July 19, 2010. As noted in the safety significance section, the A DG was still able to perform its intended safety function; however, since the condition results in inability to meet Surveillance Requirement 3.8.1.18, the A DG must be considered inoperable during periods when 1V222A would have been available to start (without a time delay). As a result, this event is reportable as a condition prohibited by Technical Specifications, in accordance with 10CFR50.73(a)(2)(i)(B), since the inoperability is assumed to have existed for a period of time greater than allowed by the Technical Specifications. A review of historical information for the last three years identified instances in which one of the other DGs (B, C, or D) was inoperable. Based on this information, this condition is also reportable as a condition that could have prevented fulfillment of a safety function in accordance with 10CFR50.73(a)(2)(v)(D).
CAUSE OF EVENT
The direct cause of the MOC switch contacts not aligning properly was mis-adjustment of the MOC switch linkage. The apparent cause of the MOC switch contacts not aligning properly is inadequate post maintenance testing (PMT) for the breaker swap because PMT did not check MOC switch contact alignment.
ANALYSIS/SAFETY SIGNIFICANCE
Actual Consequences:
As a result of declaring the A DG inoperable, Unit 2 entered a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> shutdown action in accordance with TS 3.8.1. This TS entry caused Unit 2 EOOS to be Yellow. Unit 1 was in Mode 5 and the A DG was not required for Unit 1; therefore TS 3.8.2 was not entered. Due to the minimal loading resulting from 1V222A, there was no impact on the ability of the A DG to perform its safety function. Other loads such as Core Spray and RHR were proven to have the correct time delay during the performance of Unit 1 Division I LOCA/LOOP testing on March 23, 2016.
Potential Consequences:
If the issue was not resolved within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, Unit 2 would have had to initiate shutdown activities.
CORRECTIVE ACTIONS
Key corrective actions will include the following:
1. Revising procedures to include visual inspection to ensure the MOC switch contacts are properly aligned during post maintenance testing.
COMPONENT FAILURE INFORMATION
Westinghouse Porcelain Metal Clad Switchgear Type DH-P Housing comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
PREVIOUS SIMILAR EVENTS
The following are Susquehanna MOC switch issues identified within the past 10 years:
CR-1071573 — On September 9, 2008, 13.8kV Bus 10 failed to transfer due to an open contact in the circuit, which was a MOC switch on the 13kV Breaker. Troubleshooting found that the MOC switches were preloaded and that the pantograph was not moving freely. The linkage was adjusted; pantograph was cleaned, adjusted and lubricated so that it would not bind and so that all contacts were making up properly.
CR-1308123 — On September 28, 2010, a minimum flow valve did not auto open due to MOC switch contacts not fully making up. The condition was corrected by adjusting the MOC switch operating rod in order to have the contacts make up.
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05000387/LER-2016-010 | Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Medical Emergency LER 16-010-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Medical Emergency | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000387/LER-2016-001 | Secondary Containment Declared Inoperable Due to an Airlock Doors Open Due to Random Occurrence LER 16-001-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to an Airlock Doors Open Due to Random Occurrence | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000387/LER-2016-011 | Valve inoperability for a period longer than allowed by Technical Specifications LER 16-011-00 for Susquehanna, Unit 1, Regarding Valve Inoperability for a Period Longer Than Allowed by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000388/LER-2016-001 | Secondary Containment Breach due to Simultaneous Opening of Airlock Doors Due to Degraded Latch Mechanism | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000388/LER-2016-002 | Secondary Containment Breach due to Simultaneous Opening of Airlock Doors Due to Degraded Latch Mechanism | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000387/LER-2016-012 | Secondary Containment declared inoperable due to loss of differential pressure as a result of a solenoid failure. | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000387/LER-2016-002 | Secondary Containment Declared Inoperable Due to an Airlock Doors Open Due to Random Occurrence LER 16-002-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to an Airlock Doors Open Due to Random Occurrence | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000387/LER-2016-013 | Secondary Containment Declared Inoperable Due to Simultaneous Opening of Double Airlock Doors LER 16-013-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Simultaneous Opening of Double Airlock Doors | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000388/LER-2016-003 | Secondary Containment Inoperability due to Failure to Meet Surveillance Requirement 3.6.4.1.1 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000387/LER-2016-003 | Unit 2 Zone 3 HVAC unable to maintain Zone 3 differential pressure greater than 0.25 in wg LER 16-003-00 for Susquehanna, Unit 1, Regarding Unit 2 Zone 3 HVAC Unable to Maintain Zone 3 Differential Pressure Greater Than 0.25 in wg | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000387/LER-2016-014 | Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error LER 16-014-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000388/LER-2016-004 | Unit 2 experienced an electrical transient resulting in a manual SCRAM | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000387/LER-2016-004 | Momentary Loss of Secondary Containment due to Both Airlock Doors on Elevation 779 of the Unit 2 Reactor Building being Opened at the Same Time LER 16-004-00 for Susquehanna, Unit 1, Regarding Momentary Loss of Secondary Containment Due to Both Airlock Doors on Elevation 779 of the Unit 2 Reactor Building Being Opened at the Same Time | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000387/LER-2016-015 | Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error LER 16-015-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000387/LER-2016-005 | Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Human Performance Error LER 16-005-00 for Susquehanna, Units 1 and 2, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Human Performance Error | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000388/LER-2016-005 | Unit 2 HPCI Manually Overridden Prior to a Manual Scram During a Plant Transient LER 16-005-00 for Susquehanna, Unit 2, Regarding HPCI Manually Overridden Prior to a Manual Scram During a Plant Transient | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000387/LER-2016-006 | Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 LER 16-006-00 for Susquehanna, Unit 1, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000387/LER-2016-007 | Inoperability of Swing Bus Transfer Switch Due to Deformed Bolt on Linkage LER 16-007-00 for Susquehanna, Unit 1, Regarding Inoperability of Swing Bus Transfer Switch Due to Deformed Bolt on Linkage | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000387/LER-2016-008 | Inoperability of Diesel Generator Due to Misalignment of MOC Switch Contacts Due to Inadequate Post Maintenance Testing LER 16-008-00 for Susquehanna, Unit 1, Regarding Inoperability of Diesel Generator Due to Misalignment of MOC Switch Contacts Due to Inadequate Post Maintenance Testing | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000387/LER-2016-009 | Valid Primary Containment Isolation Actuation during Local Leak Rate Testing due to Human Performance Error LER 16-009-00 for Susquehanna, Unit 1, Regarding Valid Primary Containment Isolation Actuation During Local Leak Rate Testing Due to Human Performance Error | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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