05-0-2016 | On March 5, 2016 during surveillance testing, Automatic Transfer Switch ( ATS), 1ATS229, failed to close in on the alternate supply resulting in a loss of the Division 2 Class 1 E Engineered Safeguards System (ESS) 480V Motor Control Center ( MCC) 113229 and entry into Technical Specifications 3.3.3.1, 3.5.1, and 3.6.1.3.
Based on the cause of the failure, Susquehanna believes that there is firm evidence that the transfer switch would have failed on its next actuation following testing on February 5, 2016. Based on this conclusion, the condition existed for a period longer than allowed by Technical Specifications. As a result, this condition is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications. Susquehanna also determined that work associated with the Division 1 transfer switch (1ATS219) was performed while the Division 2 switch was unknowingly inoperable resulting in simultaneous inoperability of both divisions. Since both divisions were inoperable for a period of time between February 5, 2016 and March 5, 2016, this is also considered a condition that could have prevented fulfillment of a safety function and is reportable in accordance with 10 CFR (a)(2)(v)(D).
The direct cause was determined to be a deformed bolt on the upper linkage. The apparent cause was the upper linkage rod being too long causing the deformation of the bolt. Corrective actions include revising the preventive maintenance activities for the transfer switch.
There were no actual consequences to the health and safety of the public as a result of this event. |
---|
|
---|
Category:Letter
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 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-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000388/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 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-2017-0012017-05-0505 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 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-2016-0142016-06-0909 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-2016-0132016-06-0909 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-2016-0102016-05-31031 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-2016-0112016-05-16016 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 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-2016-0062016-05-10010 May 2016 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 05000387/LER-2016-0042016-05-10010 May 2016 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 05000387/LER-2016-0032016-05-0606 May 2016 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 05000387/LER-2016-0072016-05-0303 May 2016 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 05000387/LER-2016-0012016-04-18018 April 2016 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 05000387/LER-2016-0022016-04-18018 April 2016 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 05000387/LER-2015-0062016-03-30030 March 2016 Loss of Safety Function due to Inoperability of Both Trains of the Standby Gas Treatment System and a Loss of Safety Function of the Control Room Emergency Outside Air Supply System due to Air Flow Controller found in Manual, LER 15-006-01 for Susquehanna, Unit 1, Regarding Loss of Safety Function due to Inoperability of Both Trains of the Standby Gas Treatment System and a Loss of Safety Function of the Control Room Emergency Outside Air Supply System due to Air Flow... 05000387/LER-2015-0012016-02-10010 February 2016 Inoperability of the 'B' Emergency Diesel Generator due to Fuel Oil Leakage, LER 15-001-01 for Susquehanna, Unit 1, Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Steam Dome - Low Switches 05000387/LER-2015-0032016-01-26026 January 2016 Secondary Containment Inoperability Due to Failure to Meet Technical Specification Surveillance Requirement 3.6.4.1.1, LER 15-003-01 for Susquehanna, Unit 1, Regarding Secondary Containment Inoperability Due to Failure to Meet Technical Specification Surveillance Requirement 3.6.4.1.1 05000387/LER-2015-0092016-01-11011 January 2016 Pressure Boundary Leakage From an Inadequate Weld Repair in Small Bore Pump Seal Vent Piping, LER 15-009-00 for Susquehanna, Unit 1, Regarding Pressure Boundary Leakage From an Inadequate Weld Repair in Small Bore Pump Seal Vent Piping 05000387/LER-2015-0072016-01-0808 January 2016 Unit 1 'B' Inboard Main Steam Isolation Valve, HV141F022B closed during surveillance test which caused a SCRAM on Unit 1, LER 15-007-00 for Susquehanna, Unit 1, Regarding 'B' Inboard Main Steam Isolation Valve, HV141 F022B Closed During Surveillance Test Which Caused a SCRAM PLA-7323, LER 015-001-00 for Susquehanna Regarding Inoperability of the B Emergency Diesel Generator Due to Fuel Oil Leakage2015-04-28028 April 2015 LER 015-001-00 for Susquehanna Regarding Inoperability of the B Emergency Diesel Generator Due to Fuel Oil Leakage 2018-02-02
[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 Int ocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, 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.
Susquehanna Steam Electric Station, Unit 1 05000387
CONDITIONS PRIOR TO EVENT
Unit 1 — Mode 1, approximately 87 percent Rated Thermal Power Based upon the failure mode of the transfer switch, the switch is considered to have been inoperable since the last time it was tested on February 5, 2016.
EVENT DESCRIPTION
Background Information/System Description:
Two redundant Class 1E 480 V Isolation Swing Buses (1B219 and 1B229) [EIIS System/Function Identifier:
ED/BU] provide power for the Residual Heat Removal (RHR) Injection Valves [EIIS System/Function Identifier: BO/INV], RHR Minimum Flow Valves [EIIS System/Function Identifier: BO/V], Recirculation Loop Bypass Valves [EIIS System/Function Identifier: AD/V], and Recirculation Discharge Valves [EIIS System/Function Identifier: AD/V]. The preferred power source to the isolation swing bus is from the A and B 480 VAC ESS Bus Load Groups via motor-generator set [EIIS Function Identifier: MG], and the alternate power is supplied directly from the C and D 480 VAC ESS Bus Load Groups, respectively. The transfer will occur automatically upon reduction or loss of voltage from the preferred source.
Event Timeline:
On March 5, 2016 during surveillance testing, Automatic Transfer Switch (ATS) [EIIS Function Identifier:
ASU], 1ATS229, failed to close in on the alternate supply resulting in a loss of the Division 2 Class 1 E ESS 480V MCC 1B229 and entry into Technical Specifications 3.3.3.1, 3.5.1, and 3.6.1.3.
The detailed timeline is as follows:
February 5, 2016 12:00 — 1ATS229 was successfully tested.
February 8, 2016 01:45 — Technical Specification 3.5.1 was entered for a Division 1 RHR system outage window. Work associated with 1ATS219 was performed during this window.
February 10, 2016 17:43 — The RHR system outage window was completed and Technical Specification 3.5.1 was exited.
March 5, 2016 21:25 - 1ATS229 failed to close in on the alternate supply. Testing was stopped and 1B229 was de-energized.
21:30 — The Field Unit Supervisor (FUS) reported that the ATS transfer motor was very hot to the touch and had an acrid odor.
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.
Susquehanna Steam Electric Station, Unit 1 05000387 March 6, 2016 00:45 - Electrical Maintenance personnel arrived to assess the status of 1ATS229.
04:05 - The MG set output breaker was closed and power was restored to 1B229 04:06 — Operations exited Technical Specifications 3.3.3.1 and 3.6.1.3 with valve power and indication restored. Technical Specification 3.5.1 for RHR Low Pressure Coolant Injection (LPCI) mode was maintained due to 1ATS229 still being inoperable to transfer to alternate power.
March 7, 2016 03:33 — Operations entered Technical Specifications 3.3.3.1 and 3.6.1.3 due to de-energizing 113229 for troubleshooting.
15:27 — Troubleshooting, repairs, and swing bus surveillance were satisfactorily completed.
16:57 — Operations exited Technical Specifications 3.3.3.1, 3.5.1, and 3.6.1.3.
Troubleshooting/Investigation Engineering completed a troubleshooting plan and a Failure Mode Analysis. Prior to investigating the internals of the transfer switch, Electrical Maintenance attempted to swap the transfer switch in its alternate position and as expected the switch cycled continuously without swapping. All the hardware on the transfer switch was checked for tightness, but nothing abnormal was identified. The transfer switch linkage was observed while in the upward normal position, but no abnormalities were found. The transfer switch was then manually manipulated to the alternate (down) position and the linkage was observed again. It was determined that in this position the shaft of the motor had a great deal of downward force applied to it indicating that the upper linkage rod was too long. The bolt attaching the rod to the mounting plate was removed and it was discovered that the bolt was slightly deformed. The bolt was removed and the rod was pulled up to the proper position on the mounting plate, which revealed that the rod was approximately 1/4 inch too long resulting in the continuous cycling of the switch without latching in the alternate position. An adjustment was made to the rod to align it with the mounting plate. During adjustment it was noted that all nuts attaching the upper rod were tight eliminating the possible cause of a loose connection on the upper rod linkage. The rod was reinstalled with the deformed bolt and then the transfer switch was tested. It successfully transferred to the alternate position with the deformed bolt; however, since the bolt being deformed over time in addition to the rod being too long caused the failed transfer, the bolt was replaced to eliminate any concern. No other issues were found and all additional attempts to place the transfer switch in the alternate position were successful.
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 internal 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.
Susquehanna Steam Electric Station, Unit 1 05000387 Reportability Based on the cause of the failure, Susquehanna believes that there is firm evidence that the transfer switch would have failed on its next actuation following testing on February 5, 2016. Based on this conclusion, the condition existed for a period longer than allowed by Technical Specifications. As a result, this condition is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications. Since Division 1 was inoperable from February 8, 2016 at 01:45 through February 10, 2016 at 17:43 and this timeframe is enveloped by the time that Division 2 was unknowingly inoperable, this is also considered a condition that could have prevented fulfillment of a safety function and is also reportable in accordance with 10 CFR (a)(2)(v)(D).
CAUSE OF EVENT
The direct cause was determined to be a deformed bolt on the upper linkage.
The apparent cause was the upper linkage rod being too long causing the deformation of the bolt. The previous preventive maintenance (PM) activity inspected the linkage, but did not provide criteria for the inspection specifically with regard to linkage rod length.
ANALYSIS/SAFETY SIGNIFICANCE
Actual Consequence The actual consequence was failure of 1ATS229 to transfer to its alternate supply causing ESS Swing Bus 1B229 to de-energized and resulting in entry into Technical Specifications 3.3.3.1, 3.5.1, and 3.6.1.3.
Potential Consequence In the event of a Unit 1 LOCA, LPCI would be required to inject to the Reactor Pressure Vessel (RPV). If this had occurred during the time that 1ATS229 was affected (2/5/16 to 3/5/16), and concurrent with a loss of power to the primary source for 1ATS229, then transfer to the alternate power supply would have failed and bus 16229 would have lost power. Since the LPCI injection valve HV151F0156 receives power from 16229, it would not open and LPCI injection from Division 2 RHR would not have occurred as required.
Recirculation Pump B discharge and discharge bypass valves HV143F0316 and HV143F032B also receive power from 1B229 and are required to close on a LPCI injection signal to ensure the LPCI flow is directed into the RPV. Additionally, during the period when the Division 1 transfer switch (1ATS219) was out of service for scheduled maintenance, LPCI injection from Division 1 RHR would also not have occurred.
Since HV151F015B, HV151F0176 and HV151F007B are powered from 1B229 and are used to establish the necessary RHR system alignment for Shutdown Cooling (a non-safety mode of operation), this RHR mode of operation would have been prevented.
The RHR minimum Flow valve HV151F007B receives power from 16229 and would not have closed as required after a Division 2 RHR pump start when system flow is established. This would result in diversion of some RHR flow back to the suppression pool via the minimum flow line. While this would not prevent operation of Division 2 RHR in other modes, it could result in reduced flowrate due to the flow diversion.
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 intemet 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.
CORRECTIVE ACTIONS
Revise applicable PM activities associated with the transfer switch to include the following:
1. Inspect the upper and lower linkage for any abnormalities such as deformed bolts that connect the upper and lower rods to the motor or mounting plates and replace any deformed or damaged equipment as necessary.
2. Establish criteria for rod length and adjustment.
COMPONENT FAILURE INFORMATION
Automatic Transfer Switch Information
- Manufacturer — RUSSELECTRIC
- Model Number — RMT4004CEF
- Voltage Characteristics — 480VAC, 400A, 30
PREVIOUS SIMILAR EVENTS
Condition Report 2013-03361: On November 10, 2013, 1ATS229 failed to close on the alternate supply. The cause was vibrations during monthly testing that caused the transfer switch motor mounting bolts to loosen.
|
---|
|
|
| | Reporting criterion |
---|
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 |
|