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| Entered date | Event description | |
|---|---|---|
| ENS 52352 | 7 November 2016 20:44:00 | On November 7, 2016, at 1609 (EST), with the reactor at 100 percent core thermal power and steady state conditions, the High Pressure Coolant Injection (HPCI) system was declared inoperable. Pilgrim Nuclear Power Station (PNPS) was performing planned quarterly testing per Technical Specifications 4.13.A.1. During a review of the HPCI pump data taken during the test, it was determined that the recorded vibration reading on the Main Pump Outboard horizontal point (P4H) was 0.8335 in./sec which exceeds the IST required action range high limit of less than or equal to 0.830 in./sec. Accordingly, the HPCI pump was declared inoperable. The Limiting Condition for Operation Action Statement 3.5.C.2 has been entered and planned troubleshooting Into the cause of the high vibration is in progress. In accordance with 10 CFR 50.72(b)(3)(v)(D), PNPS is providing an 8-hour non-emergency notification that the HPCI System is inoperable. This event had no impact on the health and/or safety of the public. The NRC Resident Inspector has been notified. The licensee will be notifying the State of Massachusetts regarding the event. |
| ENS 49201 | 17 July 2013 17:42:00 | On Wednesday, July 17, 2013 at 1054 hours EDT, with the reactor at 100% core thermal power (CTP) the Pilgrim Nuclear Power Station (PNPS) entered a 24-hour shutdown Limiting Condition for Operation (LCO) for Salt Service Water (SSW) inlet temperature exceeding the Technical Specification (TS) limit in TS 3.5.B.4. The LCO was subsequently exited at 1625 hours when the temperature of SSW trended to below the TS limit. Under certain accident conditions the SSW system is required to provide cooling water to the Reactor Building Closed Cooling Water (RBCCW) system heat exchanger. When the inlet temperature to this supplied load exceeds the 75 (degrees) F limit established in the TS, the SSW system is declared inoperable until the temperature trends below this value. This condition existed for approximately 5-1/2 hours and the SSW system was declared operable and the LCO exited. A maximum temperature of 75.5 (degrees) F was recorded during this period. At 1230 hours a power reduction was conducted to improve secondary plant parameters and Rx power is currently 85%. The SSW temperature is being closely monitored and trended on a continuous basis. This event has no impact on the health and safety of the public. The licensee has notified the NRC Senior Resident Inspector." The licensee will notify the Commonwealth of Massachusetts. |
| ENS 48766 | 18 February 2013 16:30:00 | On February 18, 2013 at 0515 hours, with the reactor at 100% core thermal power, a scram discharge volume valve, CV-302-22B was declared inoperable as required by station procedural direction due to an observed degradation in opening stroke time during performance of quarterly surveillance testing of the Scram Discharge Instrument Volume Vent and Drain Valves. This action was taken consistent with NRC IE Bulletin 80-14. Currently, station engineering is evaluating the valve stroke time trend data of CV-302-22B and a plan to address this issue will be developed as part of the Corrective Action Program. Pilgrim Technical Specification 3.3.G applies due to the inoperability of CV-302-22B. This notification is being made in accordance with NRC IE Bulletin 80-14, 'Degradation of BWR Scram Discharge Volume Capability,' Part A.3, which states, 'By procedures, require that the SDV (scram discharge volume) vent and drain valves be normally operable, open and periodically tested. If these valves are not operable or are closed for more than 1 hour in any 24 hour period during operation, the reason shall be logged and the NRC notified within 24 hours (Prompt Notification). This event has no impact on the health and safety of the public. The NRC Senior Resident Inspector has been informed. The licensee will inform the State. |
| ENS 47288 | 22 September 2011 22:20:00 | On Thursday, September 22, 2011 at 1452 (EDT), with the reactor at 100% core thermal power and steady state conditions, Pilgrim Nuclear Power Station (PNPS) conservatively declared both Salt Service Water (SSW) subsystems inoperable when engineering analysis determined that inrush current on pump restart may exceed the thermal overload trip relay settings during certain degraded voltage conditions. A 24-hour Limiting Condition for Operation action statement was entered. Entergy/Pilgrim is in the process of implementing temporary modifications to correct this issue. This potential concern has no impact on public health and safety. This 8-hour notification is being conservatively reported in accordance with 10 CFR50.72(b)(3)(ii)(B). The NRC Resident Inspector has been notified. The licensee will notify the Massachusetts Emergency Management Center.
Event Notification 47288 was conservatively made to ensure that the Eight-Hour Non-Emergency reporting requirements of 10 CFR 50.72 were satisfied pending further evaluation of Salt Service Water (SSW) subsystem operability during certain degraded voltage conditions. Pilgrim Station has subsequently evaluated the impact of the Salt Service Water (SSW) pump motor operating load; potential degraded voltage conditions on thermal overload settings; and pump motor restart requirements; and determined that reasonable assurance of SSW subsystem operability existed. Both SSW subsystems were evaluated to be capable of satisfying the system safety function of providing cooling water to the Reactor Building Closed Cooling Water System heat exchangers during accident and transient conditions. Pilgrim 's evaluation considered manufacturer's data for the thermal overload relays, site specific shop testing, and reliable grid conditions which minimize the potential for extended operation with 4 kV buses operating at just above degraded voltage relay trip settings. This past operability evaluation concluded that the SSW pumps would support continuous operation of the SSW subsystems. Therefore, the initial 50.72 report is being retracted. The licensee will notify the NRC Resident Inspector. Notified the R1DO (Caruso). |