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 Start dateReporting criterionEvent description
05000271/LER-2014-00129 September 201410 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
On September 29, 2014, with reactor power operation at 96 percent power, the 'A' train Emergency Diesel Generator (EDG) did not complete the starting sequence during a scheduled Technical Specification monthly surveillance. The direct cause of the event was a hydraulic lock condition between opposing pistons on compression stroke in the #6 cylinder which prevented the EDG from turning. This condition resulted from an internal Jacket Coolant Water leak through a copper gasket that provides a sealing surface inside the cylinder. The copper gasket had been in service since installation during a cylinder liner replacement in 1992. There were no indications of a leak prior to its discovery, therefore the exact time when a hydraulic lock condition developed is unknown. The 'A' EDG was potentially inoperable since the completion of the last successful surveillance that demonstrated its capability to meet its safety function on August 25, 2014. Based on the ability of the 'A' EDG to be recovered within a few hours, the availability of the redundant 'B' train EDG, and the availability of normal and alternate off- site and onsite power sources capable of supplying power to engineered safety feature loads during and following design basis accidents, this event did not pose a threat to public health and safety.
05000271/LER-2013-0027 November 201310 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v), Loss of Safety Function
On November 6, 2013, with the plant at 100% Reactor Power, Vermont Yankee Nuclear Power Station (VY) identified a conduit containing a loose screw type conduit seal plug and another conduit with a missing seal inside electrical manhole MH-S2 located outside the Administrative Building. This was discovered during a routine preventative maintenance surveillance of flood seals. On November 7, 2013, it was identified that the missing flood seal compromised the flood design controls for the Switchgear Rooms. The conditions were corrected by installing silicone elastomer seals in the two affected spare conduits, thus removing the potential flood paths. The causes of the incorrect and missing flood seals were due to not completing the appropriate corrective actions following a similar event reported in LER 2013-001-00, dated May 16, 2013. Plant procedure requires inspection of the Switchgear Rooms during a flood event and includes actions that would have mitigated any flooding; therefore, this event did not pose a threat to public health and safety.
05000271/LER-2011-0022 December 201110 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident

On December 2, 2011, with the plant at 100 percent power, Vermont Yankee (VY) was modifying the tagging lineup on the "B" Emergency Diesel Generator (EDG) that was out of service for scheduled maintenance.

During the tagging evolution, an operator mistakenly entered the "A" EDG room and tripped the "A" EDG fuel rack making the "A" EDG inoperable. This resulted in both EDGs being inoperable requiring entry into a 24 hour limiting condition for operation. This event is reported in accordance with 10CFR50.73(a)(2)(v)(D) as an event or condition that could have prevented the fulfillment of a safety function since both EDGs were inoperable.

The investigation determined that this event was caused by a lack of adherence to procedures that provide administrative controls over tagging evolutions and direct the use of human performance tools to prevent occurrence of this type of an event. The condition was immediately identified by operations personnel due to alarms received in the main control room and the "A" EDG was returned to operable status in two minutes.

There were other sources of AC power available and therefore, this event did not pose a threat to public health and safety.

05000271/LER-2011-00116 February 201110 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

On February 16, 2011 with the plant at 100 percent power, Vermont Yankee was preparing to perform a scheduled quarterly surveillance on the High Pressure Coolant Injection (HPCI) system. During initial startup of the system, audible and visual indications of steam leakage were observed. The investigation determined that a flanged connection associated with steam trap ST-23-3 was the source of the leak. This steam trap is on a line that maintains the steam supply piping to the HPCI turbine free of accumulated water. The event was attributed to a maintenance activity that was performed on February 1, 2011 where the steam trap was disassembled to facilitate a piping weld repair. The cause of this event was a failure to follow procedures that resulted in incorrect gasket material being used as a replacement for spiral wound gasket material. This event was determined to be reportable per 10CFR50.73(a)(2)(v)(D) as an event or condition that could have prevented fulfillment of a safety function and under 10CFR50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications. The Automatic Depressurization System (ADS) serves as a backup to the HPCI system. If the HPCI System does not operate and one of the low pressure coolant injection pumps is available, the Nuclear System is depressurized using ADS to permit the Low Pressure Coolant Injection (LPCI) and Core Spray (CS) systems to operate to protect the fuel barrier. This event did potentially affect the ability of HPCI to perform its safety function from February 1, 2011 through February 19, 2011 when the system was returned to service.

During that time period, ADS and either LCPI or CS were available to perform the required safety functions.

Therefore, this event did not pose a threat to public health and safety.

05000271/LER-2010-00110 CFR 50.73(a)(2)(iv)(A), System Actuation

On May 26, 2010, at approximately 1526 hours, a generator lockout and automatic reactor trip occurred on differential current between a current transformer (CT) installed in the newly commissioned switchyard and a CT installed in the plant. During startup, when the plant reached 72% power, both channels of the reactor protection system (RPS) actuated and all control rods inserted. Following the reactor trip reactor vessel level decreased causing primary containment isolation system (PCIS) actuation for groups 2, 3, 4, and 5.. All associated valves functioned correctly. Additionally, both trains of standby gas treatment system actuated.

Immediate plant actions included entering appropriate trip response procedures. The operators stabilized the plant and reset both RPS and PCIS. During RFO 28, Vermont Yankee (VY) and the Vermont Electric Power Company (VELCO) commissioned a new 345kV switchyard. The direct cause of the trip was that VELCO changed the CT ratio settings within the 345kV Switchyard and failed to communicate the new ratio setting to VY. As power was increased, the differential current caused by the difference in CT ratio settings resulted in the generator lockout. Corrective actions include adjustment of the VY CT to the correct settings and establishment of the necessary programmatic controls to preclude recurrence. This event is reportable as a licensee event report (LER) per 10CFR50.73(a)(2)(iv)(A) as an event or condition that resulted in actuation of the any of the systems listed in 10 CFR 50.73(a)(2)(iv)(B), which includes RPS and PCIS.

05000271/LER-1998-019, Forwards LER 98-019-01,as Defined by NUREG-1022,rev 1, Section 2.9.Rept Is Being Reissued Due to Typo on Cover Ltr Submitted with Rept on 981105.Cover Ltr Provided Incorrect LER Number.Encl Rept Date Also Changed to 98111212 November 1998
05000271/LER-1997-012, Forwards LER 97-012-00,previously Submitted W/Incorrect Revision Number on Pages Two & Three6 June 1997
05000271/LER-1996-012, Forwards LER 96-012-01,previously Submitted on 970729.LER Contained Error Re Supplemental Rept & Expected Submission Date6 August 1997
05000271/LER-1995-019, Notifies of Cancellation of LER 95-019.Util Determined That Classification of Reactor Bldg Doors as Vital Fire Doors in Error.Design Basis of Reactor Bldg Doors as Airlock Doors, Not Vital Fire Doors5 June 1996
05000271/LER-1993-0127 October 1993
05000271/LER-1993-01031 August 1993
05000271/LER-1993-00913 August 1993
05000271/LER-1993-00513 August 1993
05000271/LER-1993-00419 August 1993
05000271/LER-1990-00829 June 1990
05000271/LER-1987-003, :on 880412,personnel Found Functional Testing Not Been Tested in Accordance W/Tech Spec Requirements. Caused by Programmatic Tracking Program.Programmatic Tracking Sys Revised as Described in LER 87-0310 May 1988
05000271/LER-1983-012, Forwards LER 83-012/01P-012 April 1983
05000271/LER-1983-010, Forwards LER 83-010/03L-021 April 1983
05000271/LER-1983-009, Followup LER 83-009/01T-0:on 830321,primary Containment Isolation Sys Isolation of Containment Ventilation Sys Occurred.Caused by Mods to Reactor Protection Sys Motor Generator.Fuel Handling Activities Suspended1 April 1983
05000271/LER-1983-008, Forwards LER 83-008/03L-018 April 1983
05000271/LER-1983-007, Forwards LER 83-007/03L-025 March 1983
05000271/LER-1983-006, Forwards Updated LER 83-006/01X-017 March 1983
05000271/LER-1983-005, Forwards LER 83-005/01P-04 February 1983
05000271/LER-1983-004, Forwards LER 83-004/03L-018 February 1983
05000271/LER-1983-003, Forwards LER 83-003/03L-09 February 1983
05000271/LER-1983-001, Forwards LER 83-001/01T-021 January 1983
05000271/LER-1982-025, Forwards LER 82-025/03L-029 December 1982
05000271/LER-1982-024, Forwards LER 82-024/03L-013 December 1982
05000271/LER-1982-023, Forwards LER 82-023/03L-018 November 1982
05000271/LER-1982-021, Forwards LER 82-021/03L-012 October 1982
05000271/LER-1982-020, Forwards LER 82-020/03L-05 October 1982
05000271/LER-1982-019, Forwards LER 82-019/03L-015 September 1982
05000271/LER-1982-018, Forwards LER 82-018/03L-015 September 1982
05000271/LER-1982-017, Forwards LER 82-017/03L-025 August 1982
05000271/LER-1982-016, Forwards LER 82-016/03L-022 July 1982
05000271/LER-1982-014, Forwards LER 82-014/03L-014 July 1982
05000271/LER-1982-013, Forwards LER 82-013/03L-01 July 1982
05000271/LER-1982-012, Forwards LER 82-012/03L-023 June 1982
05000271/LER-1982-011, Forwards LER 82-011/03L-030 June 1982
05000271/LER-1982-010, Forwards LER 82-010/03L-011 June 1982
05000271/LER-1982-009, Forwards LER 82-009/03L-011 June 1982
05000271/LER-1981-030, Updated LER 81-030/03L-1:cracks Found on Internal Surface of Valve Bodies & Seating Surfaces of Reactor Water Cleanup Valves Attributed to Surface Shrinking of Casting & Intergranular Stress Corrosion Cracking,Respectively1 July 1982
05000271/LER-1981-0263 November 1981
05000271/LER-1978-030, Forwards LER 78-030/03L-026 October 1978
05000271/LER-1976-020, Forwards Updated LER 76-020/01X-016 February 1983
05000271/LER-1976-005, Telecopy LER 76-005:on 760217,portion of Procedure Associated W/Securing Plant from Shutdown Cooling Mode Not Performed.Caused by Failure of Plant Personnel to Follow Appropriate Plant Procedure18 February 1976
05000271/LER-1975-003, Corrected LER 75-003:on 750204,core Spray Sys Pump Discharge Pressure Sensor PS-14-44A Actuated at 82 Psig.Caused by Setpoint Drift.Sensor replaced.W/750218 Ltr14 February 1975
05000029/LER-2001-00110 CFR 50.73(a)(2)(i)(B), Prohibited by Technical SpecificationsYankee Nuclear Power Station ceased power operation in February 1992 and is being decommissioned. On 06/26/01 during the conduct of a Nuclear Safety (Quality Assurance) Audit a discrepancy regarding the alarm setpoints for the Spent Fuel Pit (SFP) Area Radiation Monitor (ARM) was identified. The SFP ARM is an instrument required by Technical Specification 3.3 to ensure early detection of inadvertent criticality during fuel handling activities. The Technical Specification requires the alarm setpoints for the ARM be set at less than 5 mr/hr or two times the background radiation level, whichever is greater, while moving irradiated fuel, control rods or sources. The discrepancy identified was that the background radiation level annotated on procedure OP-4816, "Functional Test and Alarm Setting of the Area Radiation Monitoring System" was 2 mr/hr while the alarm setpoint for both the alert and high alarms was set at 7 mr/hr, thus greater than the Technical Specification requirement. As such, this LER is submitted in accordance with 10CFR50.73(a)(2)(i)(B) as a condition of non-compliance with a Technical Specification. No fuel handling evolutions were in progress at the time of discovery of this issue.