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| Entered date | Event description | |
|---|---|---|
| ENS 52664 | 4 April 2017 11:32:00 | On April 4, 2017, at 0735 (EDT), the HPCI System was inadvertently isolated during the performance of l&C (Instrument and Control) testing. Technicians were in the process of performing instrument surveillance tests for the HPCI (high pressure coolant injection) System (using Allowed Out of Service Times) when a trip signal was applied to the incorrect instrument. This caused a HPCI System isolation signal on High Area Temperature, resulting in the closure of the HPCI steam isolation valves and rendering the system inoperable and unavailable. RCIC was immediately verified to be operable. The surveillance testing was aborted and system restoration is in progress. This condition is being reported as a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident per 10CFR50.72(b)(3)(v)(D). This placed the plant in a 14-day LCO action statement under Technical Specification 3.5.1. The licensee has notified the NRC Resident Inspector. |
| ENS 52490 | 14 January 2017 13:09:00 | At 0613 EST on 1/14/2017, with the unit in Mode 2 at 0 percent power at the start of Refueling Outage 22, Drywell inspection identified a through-wall leak on the 3/4-inch vent line off the bonnet of valve 02MOV-43A, Reactor Water Recirc Pump A Suction Isolation Valve, in the Reactor Coolant System (RCS) loop inside the Primary Containment. This condition constitutes a defect in the primary coolant system. This event notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) as a condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. The licensee has notified the NRC Resident Inspector. |
| ENS 51613 | 19 December 2015 00:44:00 | On December 18, 2015 at 1722 EST, with James A. FitzPatrick Nuclear Power Plant (JAF) operating at 100 percent power, JAF received a notification pursuit to 10 CFR 21.21(d)(3)(ii) related to Moore Industries RTD temperature transmitters. Specifically, wire insulation in T2 transformer was damaged during assembly which reduced the insulation resistance and dielectric breakdown between the windings of the transformer. This equipment is in both redundant trains (A and B) of the Containment Atmosphere Dilution (CAD) System. Preliminary review by Operations and Engineering, which was completed on 12/18/15 at 2100 EST, determined the Part 21 results in both trains of CAD being inoperable and the applicable Technical Specification (TS) for both redundant trains of CAD being inoperable was entered. Per TS 3.6.3.2 Condition B, this places the unit in a 7-day shutdown LCO, provided the hydrogen control function is maintained. Per the TS Bases, the alternate hydrogen control capabilities are provided by the Primary Containment lnerting System, which is unaffected. The event is reportable pursuant to 10 CFR 50.72(b)(3)(v)(D), as an event or condition that could prevent fulfillment of a safety function. The licensee notified the NRC Resident Inspector. |
| ENS 50210 | 18 June 2014 21:20:00 | At 1545 (EDT), while testing of the Emergency Service Water system (ST-8Q) was being performed at the James A. FitzPatrick Nuclear Power Plant (JAF), two of five unit coolers (66UC-22H and 66UC-22K) in the East Crescent were found with indicated flow of 0 gpm. The other three unit coolers in the East Crescent Area were found with sufficient flow. At least four unit coolers are required to support the functionality of the East Crescent Area Ventilation Subsystem (TRO 3.7.C). The East and West Crescent Area Ventilation Subsystems support the Operability of the Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC) system by removing heat from the areas, in the event that ECCS and RCIC were used to mitigate the consequences of an accident. The West Crescent Area Ventilation Subsystem remained functional. The accident mitigating function of the division of ECCS and RCIC located in the West Crescent Area were unaffected by this condition. However, this condition could have prevented the function of one division of the ECCS, including the single train of High Pressure Coolant Injection (HPCI), located in the East Crescent. Therefore, this condition could have prevented fulfillment of the safety function of HPCI and it is being reported under 10 CFR 50.72(b)(3)(v)(D). As part of the testing, the throttle valves to the unit coolers (66UC-22H and 66UC-22K) were cycled and normal flow was restored. This condition no longer exists. The licensee is investigating the loss of flow to the "H" and "K" unit coolers and the restoration of flow by cycling the unit cooler supply throttle valves. The licensee will be notifying the NRC Resident Inspector.
FitzPatrick is retracting EN # 50210 made on June 18, 2014 at 2120 EDT. The plant was at 86% power at the time. The ENS notification was an 8-Hr non-emergency notification to 10 CFR 50.72(b)(3)(v)(D) when it was discovered that two of five unit coolers in the East Crescent (66UC-22H and 66UC-22K) were found with indicated flow of 0 gpm while testing. The other three unit coolers in the East Crescent (66UC-22B, 66UC-22D, 66UC-22F) were found with sufficient flow. At least four unit coolers are required to support the functionality of the East Crescent Area Ventilation subsystem (TRO 3.7.C). The East and West Crescent Area Ventilation subsystems support the Operability of the Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC) system by removing heat from these areas in the event that ECCS and RCIC are used to mitigate the consequences of an accident. As part of testing, throttle valves to unit coolers 66UC-22H and 66UC-22K were cycled and normal flow was restored. The West Crescent Area Ventilation subsystem remained functional. The accident mitigating function of the division of the ECCS and RCIC located in the West Crescent Area were unaffected by this condition. Initial review of this condition determined that it could have prevented the function of one division of the ECCS, including the single train of High Pressure Coolant Injection (HPCI), located in the East Crescent. Therefore, this condition was initially reported under 10 CFR 50.72 (b)(3)(v)(D) as a condition that could have prevented fulfillment of the Safety function of HPCI. This EN# 50210 is being retracted based upon a subsequent engineering analysis that determined that there is reasonable assurance that the three unit coolers with sufficient flow (66UC-22B, 66UC-22D, and 66UC-22F) would have been capable of removing accident heat loads as a function of time to maintain East Crescent area temperatures at a value which ensures operability of supported equipment. The analysis considered unit cooler heat transfer capability at the modified design condition flow of 22 gpm for historically observed lake temperatures and for flow at tested conditions. Additional margin in flow at the tested condition provided increased heat removal capability and provided added assurance that accident heat load would have been removed. The East Crescent Area Ventilation subsystem was, therefore, functional with three unit coolers (functionality never was lost) and the supported ECCS remained Operable. The Operability determination for the condition has subsequently been revised based upon the engineering analysis, to state the condition was not immediately reportable per 10 CFR 50.72. The licensee has notified the NRC Resident Inspector Notified R1DO (Kennedy) |
| ENS 48581 | 12 December 2012 12:30:00 | Event Summary: On October 13, 2012, at approximately 0218 (EST), a full reactor scram signal was received in the James A. FitzPatrick (JAF) control room. At the time of this event, the plant was in cold shutdown (Mode 4) and refueling outage 20 (R20) was in progress. The scram signal occurred because Reactor Vessel Scram & Primary Containment Isolation Level Transmitter (02-3LT-101C) and Reactor Vessel Scram & Primary Containment Isolation Level Transmitter EQ (02-3LT-101D) momentarily failed downscale, and then immediately recovered. 02-3LT-101C is an 'A' division component and 02-3LT-101D is a 'B' division component. Therefore, both the 'A' and 'B' divisions of reactor protection actuated providing a full reactor scram and outboard primary containment isolation signal. AOP-15, 'Isolation Verification and Recovery' verified that the proper containment isolation response was received. This event is reportable under 10 CFR 50.73(a)(2)(iv)(A) because it resulted in the invalid actuation of the reactor protection system while the reactor was already shut down. Apparent Cause: A Failure Mode Analysis and Apparent Cause Evaluation were performed to determine the most likely cause of both level transmitters to momentarily spike downscale. It was concluded that the most probable cause was due to a worker inadvertently coming into contact with the level transmitters' exposed sensing lines. Contributing to this event was the misjudgment by the Operations individual reviewing the work package, on the risk significance of the instrumentation in the vicinity of the work area. As a result, the work area was not constructed in a manner to preclude interference with the level transmitters or associated sensing lines. Corrective Actions: Immediate corrective actions were to walk down the affected instrument lines to ensure no damage had been caused. Additional corrective actions were to install signs near the level transmitters and exposed sensing lines. The signs denote that sensitive instrument lines are present. Future corrective actions include a walk down by engineering and operations to identify other areas in the plant where sensitive instrument lines are present and place additional signs or barriers as appropriate. The licensee notified the NRC Resident Inspector. |
| ENS 40289 | 2 November 2003 20:47:00 | The Tone Alert System (Radio/EAS) has been out of service for greater than 1 hour. The Tone Alert Radio/EAS was returned to service. The licensee has notified the NRC Resident Inspector. |