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 Entered dateSiteRegionReactor typeEvent description
ENS 541995 August 2019 01:28:00Nine Mile PointNRC Region 1On August 4, 2019 at 1745 (EDT), Reactor Recirculation Pump (RRP) 11 tripped. The cause for the trip is under investigation. Following the RRP trip, the Average Power Range Monitors (APRMs) flow bias trips are inoperable due to reverse flow through RRP 11. The APRMs were restored to operable on August 4, 2019 at 1807, when the RRP 11 Discharge Blocking Valve was closed. This 8-hour non-emergency report is being made based upon requirements of 10CFR50.72(b)(3)(v)(A) which states: 'Licensee shall notify the NRC of any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (A) Shut down the reactor and maintain it in a safe shutdown condition.' The licensee has notified the NRC Resident Inspector.
ENS 5408925 May 2019 00:30:00Nine Mile PointNRC Region 1A licensed employee was determined to be under the influence of alcohol during a random (fitness-for-duty) test. The employee's access to the plant has been canceled. The licensee notified the NRC Resident Inspector.
ENS 5399814 April 2019 03:21:00Nine Mile PointNRC Region 1On April 14, 2019 at 0003 (EDT), Nine Mile Point Unit 1 experienced an automatic reactor scram during reactor startup. The cause of the automatic scram was due to high (Reactor Pressure Vessel) pressure following closure of the turbine stop valves. All control rods fully inserted and all plant systems responded per design following the scram. Following the automatic scram, the High Pressure Coolant Injection (HPCI) System automatically initiated as expected. At Nine Mile Point Unit 1, a HPCI System actuation signal on low Reactor Pressure Vessel (RPV) level is normally received following a reactor scram, due to level shrink. HPCI is a flow control mode of the normal feedwater systems, and is not an Emergency Core Cooling System. At 0004, RPV level was restored above the HPCI System low level actuation set point and the HPCI System initiation signal was reset. Pressure control was established on the Turbine Bypass Valves, the preferred system. No Electromatic Relief Valves actuated due to this scram. Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor water level and pressure maintained within normal bands. The offsite grid is stable with no grid restrictions or warnings in effect. The unit is currently implementing post scram recovery procedures. The NRC Resident Inspector has been notified. The Licensee will notify the State of New York.
ENS 537652 December 2018 06:17:00Nine Mile PointNRC Region 1

During the post-maintenance testing run of the Division III Emergency Diesel Generator (EDG), (a field operator) reported smoke coming from the diesel and an emergency shutdown was required. After the EDG was shutdown, significant damage (thrown rod) to the EDG was observed. Emergency Action Level HA 2.1 (an Alert) was declared at 0530 (EST). Currently, the plant is stable and operating at 100 percent power. All safety systems are available. The damage occurred approximately 20 minutes into the required 1 hour run. The licensee's emergency response organization has been activated. No offsite assistance was required or requested. There is a 14-day shutdown limiting condition for operation (LCO) in effect under technical specification 3.5.1 for the high pressure core spray system. Notified DHS Senior Watch Officer, FEMA Operations Center, DHS NICC Watch Officer, HHS Operations Center, DOE Operations Center, EPA Emergency Operations Center, FDA EOC (email), FEMA NWC (email) and DHS Nuclear SSA (email). The licensee has notified state and local authorities and the NRC Resident Inspector.

  • * * UPDATE ON 12/2/18 AT 0737 EST FROM TODD DAVIS TO HOWIE CROUCH * * *

The licensee terminated the Alert at 0731 EST on 12/2/18. The basis for termination was that the licensee has met all procedural requirements to terminate the emergency and on-shift personnel can operate the unit without further assistance. Notified R1DO (Burritt), NRR EO (Miller), IRD MOC (Gott), HQPAO (Couret), ERDS Activation Group, DHS Senior Watch Officer, FEMA Operations Center, DHS NICC Watch Officer, HHS Operations Center, DOE Operations Center, EPA Emergency Operations Center, FDA EOC (email), FEMA NWC (email) and DHS Nuclear SSA (email).

ENS 535846 September 2018 17:18:00Nine Mile PointNRC Region 1Pursuant to 50.73(a)(1) the following information is provided as a sixty (60) day telephone notification to the NRC. This notification, reported under 50.73(a)(2)(iv), is being provided in lieu of the submittal of a written LER (Licensee Event Report) to report a condition that resulted in an invalid actuation of the high pressure coolant injection (HPCI). At Nine Mile Point Unit 1, HPCI is a flow control mode of the normal feedwater system and is not an emergency core cooling system. On March 19, 2018 Nine Mile Point Unit 1 (NMP1) was at 0 percent power and in cold shutdown in support of a planned maintenance outage. At approximately 0118 (EDT), a reactor water level transient initiated by the fill and vent of 12 Reactor Recirculation Pump (12 RRP) occurred. During the fill and vent, Reactor Pressure Vessel (RPV) level lowered quickly from the initial level of 68 inches and a low level alarm was received. Control Room Operators reduced Reactor Water Clean-Up (RWCU) reject flow to turn the level trend and clear the low level alarm generated off of the compensated, GEMAC, level instrumentation. RWCU reject flow was reduced by 50 percent which caused RPV level to start to rise. RPV level was raised to approximately 72 inches at which time the Reactor Operator began to raise reject flow to reestablish the normal level band. During the RPV level transient, with actual water level at 74 inches on the GEMAC, the Yarway level instrumentation, which is not density compensated and therefore invalid, reached 92 inches causing an invalid high RPV water level turbine trip signal and associated invalid HPCI initiation signal. At no point in time did actual RPV water level reach the high RPV water level turbine trip set point of 92 inches. The potential for a turbine trip signal to occur due to shutdown activities was understood and tags were hung to lockout the Feedwater Pumps to prevent the HPCI start signal. Therefore, no HPCI injection occurred. The Licensee has notified the NRC Resident Inspector."
ENS 5356527 August 2018 03:12:00Nine Mile PointNRC Region 1

EN Revision Text: AUTOMATIC SCRAM DUE TO A GENERATOR TRIP At 0033 EDT Nine Mile Point Unit 2 experienced an automatic scram on high reactor pressure due to a turbine trip. The cause of the turbine trip was due to a generator trip. All control rods inserted. There were no safety system actuations. The cause of the generator trip is being investigated. This is a 4-Hour report for 10CFR50.72(b)(2)(iv)(B) RPS Actuation. The NRC Resident Inspector has been notified. Decay heat is being removed via the main condenser. Reactor vessel water level is being maintained by the condensate and feedwater systems. The licensee will be notifying the state of New York.

  • * * UPDATE FROM DANIEL CIFONELLI TO HOWIE CROUCH AT 1653 EDT ON 8/28/18 * * *

After further review, the licensee has determined that the cause of automatic scram was due to turbine control valve fast closure as a result of the turbine trip, not high reactor pressure, as originally reported. The licensee has notified the NRC Resident Inspector. Notified R1DO (Lilliendahl).

ENS 5339510 May 2018 08:59:00Nine Mile PointNRC Region 1GE-5At 0248 (EDT), with the plant shutdown in Mode 4, Nine Mile Point Unit 2 experienced a partial loss of off-site power during relay testing that resulted in an automatic start of the Division 2 Emergency Diesel Generator. All systems responded as expected for the event. The cause is being investigated. The station responded in accordance with appropriate Special Operating Procedures and restored impacted systems. This event is being reported in accordance with 10CFR50.72(b)(3)(iv)(A) At the time of the report, the emergency diesel generators are loaded and supplying plant safety equipment. The licensee has notified the state of New York Emergency Management Agency and the NRC Resident Inspector.
ENS 531901 February 2018 11:59:00Nine Mile PointNRC Region 1GE-5

Nine Mile Point unit 2 experienced an unusual event due to a small fire in the turbine building that was immediately extinguished and then reflashed. The fire was declared out at 1119 (EST), 2/1/18. The fire was caused when steam leak repair injection equipment failed and leaked onto hot piping. There was no equipment damage or impact to plant operation. The fire was extinguished by the fire brigade. Offsite assistance was not required. The fire resulted from Furmanite repair of a Moisture Separator Reheater inlet flow control valve. The unusual event will be terminated when sufficient lagging is removed to verify the extent of leaked fluid. The licensee notified the NRC Resident Inspector. Notified DHS SWO, FEMA, DHS NICC, and NNSA (via e-mail).

  • * * UPDATE AT 1240 EST ON 2/1/2018 FROM ANTHONY PETRELLI TO MARK ABRAMOVITZ * * *

The unusual event was terminated at 1211 EST. The licensee notified the NRC Resident Inspector. Notified the R1DO (Janda), NRR EO (Miller), IRD MOC (Grant), DHS SWO, FEMA, DHS NICC, and NNSA (via e-mail).

ENS 5299630 September 2017 09:06:00Nine Mile PointNRC Region 1GE-5At 0134 (EDT) on September 30, 2017, Nine Mile Point Unit 2 entered Tech Spec 3.6.4.1 when secondary containment was declared inoperable due to secondary containment differential pressure being above the Tech Spec Surveillance Requirement of -0.25 inches vacuum water gauge. The Division II Standby Gas Treatment System was started to restore differential pressure at 0135 (EDT) on September 30, 2017 the differential pressure was restored, the secondary containment was declared operable and the Tech Spec3.6.4.1 exited. Secondary containment being inoperable is a 8-hour report for 10 CFR 50.72(b)(3)(v)(C), Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. The cause of this condition is being investigated. The NRC Resident Inspector has been notified. The licensee will also inform the State of New York.
ENS 529506 September 2017 15:41:00Nine Mile PointNRC Region 1GE-2On September 6, 2017 at 1157 (EDT), Nine Mile Point Unit 1 experienced an automatic reactor scram with a Main Steam Isolation Valve (MSIV) and Containment isolation. The scram was due to reactor vessel low water level. The cause of the reactor vessel low water level is under investigation. All control rods fully inserted. Following the scram, pressure was momentarily controlled through the use of the Emergency Condenser (EC) system. At 1205, pressure control was established through the main steam lines to the condenser through the turbine bypass valves. All plant systems responded per design following the scram. The reactor scram is a 4-hour report per 10 CFR 50.72(b)(2)(iv)(B). The following systems automatically actuated after the scram as expected. These system actuations are an 8-hour report per 10 CFR 50.72(b)(3)(iv)(A): 1. The High Pressure Coolant Injection (HPCI) system. HPCI initiated at 1157 and was reset at 1158 when RPV level was restored above the HPCI system low level actuation set point. HPCI is a flow control mode of the normal feedwater systems, and is not an Emergency Core Cooling System. 2. The Core Spray system actuated, but did not discharge to the Reactor Coolant system. The Core Spray system was secured at 1216. 3. Containment and MSIV isolation on reactor vessel low-low water level signal. Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor vessel water level and pressure maintained within normal bands. Decay heat is being removed via steam to the main condenser using the turbine bypass valves. The offsite grid is stable with no grid restrictions or warnings in effect. The licensee has notified the NRC Resident Inspector. No safety relief valves lifted during the transient. The main steam isolation valves were opened after the isolation signal cleared to facilitate decay heat removal. Offsite power is supplying all plant loads. There was no effect on Unit 2. The licensee notified New York State Department of Environmental Protection and will be issuing a press release.
ENS 528896 August 2017 00:26:00Nine Mile PointNRC Region 1GE-5At 2235 (EDT) Nine Mile Point Unit 2 experienced an automatic scram on high reactor pressure. Turbine stop valve testing was in progress at the time of the scram. All control rods inserted. Pressure control is via the turbine bypass valves. The cause of the scram is being investigated. This is a 4-Hour report for 10CFR50.72(b)(2)(iv)(B) RPS (Reactor Protection System) Actuation. The NRC Resident Inspector has been notified. Reactor water level is being maintained with normal feedwater flow. No safety or relief valves lifted. The plant is in its normal shutdown electrical lineup.
ENS 5274711 May 2017 13:21:00Nine Mile PointNRC Region 1GE-2Pursuant to 50.73(a)(1) the following information is provided as a sixty (60) day telephone notification to the NRC. This notification, reported under 50.73(a)(2)(iv), is being provided in lieu of the submittal of a written LER to report a condition that resulted in an invalid actuation of the high pressure coolant injection (HPCI). At Nine Mile Point Unit 1, HPCI is a flow control mode of the normal feedwater system and is not an emergency core cooling system. On March 20, 2017 at 0216 EDT, Nine Mile Point Unit 1 reactor shutdown was in progress. The Unit 1 generator was off line, the 100 percent capacity 13 feedwater pump (13 FW) was removed from service, and the Unit 1 main turbine had been tripped appropriately per procedure while entering a planned refueling outage. At approximately 4 percent reactor power, a clearance tagging evolution was in progress to support shutdown activities. During this evolution a tag was applied that caused an unanticipated activation of a lock out (86) relay due to the failure to bypass this relay prior to the tag application. This 86 relay activation in turn resulted in a generator trip signal followed by a turbine trip signal. With the generator off line and the turbine already tripped there was no actual change in any plant parameter or condition that would have created a valid turbine trip signal and the associated HPCI initiation. The plant configuration at the time of the main turbine trip signal had one motor operated feedwater pump, 12 Feedwater Pump (12 FW), in service and providing normal reactor level control. HPCI did initiate as designed upon receiving the generator and main turbine trip signals caused by the activation of the 86 relay. The 12 FW pump, which was providing normal reactor level control, transitioned the level control from automatic mode into HPCI mode of operation. Per design, the 11 FW pump automatically started but was not required to and did not flow water since 12 FW pump was in operation. The 11 FW pump was subsequently secured by operations. At no point in time did the HPCI system receive a valid initiation signal (due to high DW pressure, low reactor water level, or a valid turbine trip with loss of the turbine driven 13 FW pump). Operators reset HPCI and returned water level to Automatic Control at 0218. The Licensee has notified the NRC Resident Inspector.
ENS 5262420 March 2017 04:40:00Nine Mile PointNRC Region 1GE-2On March 20, 2017 at 0227, Nine Mile Point Unit1 was manually scrammed due to pressure oscillations. The Unit was offline and reactor shutdown was in-progress at the time of the scram. The scram was inserted at approximately 4% reactor power when pressure oscillations occurred exceeding the procedurally required limit for pressure oscillations. The cause of the scram was due to Operators manually inserting the scram. The cause of the pressure oscillations is being investigated. The licensee notified the NRC Resident Inspector. Notified the R1DO (Gray).
ENS 5242510 December 2016 12:31:00Nine Mile PointNRC Region 1GE-2On December 10, 2016 at 0848 EST, (operators at) Nine Mile Point Unit 1 manually scrammed the reactor due to high vibrations on the Main Turbine. Cause of the high vibrations is being investigated. Following the scram, the High Pressure Coolant Injection (HPCI) system automatically initiated as expected. At Nine Mile Point Unit 1, a HPCI system actuation signal on low reactor pressure vessel (RPV) level is normally received following a reactor scram, due to level shrink. HPCI is a flow control mode of the normal feedwater system and is not an emergency core cooling system. At 0849, RPV level was restored above the HPCI system low level actuation set point and the HPCI system initiation signal was reset. Pressure control was established on the turbine bypass valves, the preferred system. No Electromatic relief valves actuated due to this scram. Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor water level and pressure maintained within normal bands. Decay heat is being removed via steam to the main condenser using the bypass valves. The offsite grid is stable with no grid restrictions or warnings in effect. The unit is currently implementing post scram recovery procedures. The licensee has notified the state of New York Public Service Commission and the NRC Resident Inspector.
ENS 5213329 July 2016 06:51:00Nine Mile PointNRC Region 1GE-2On 7/28/2016 at 2357 EDT, Nine Mile Point Nuclear Station Unit 1 experienced a fault in the in-service 11 RPS UPS (Reactor Protective System Ultimate Power Supply), resulting in an isolation of both emergency condensers. Emergency condenser 12 was returned to standby on 7/29/2016 at 0041 EDT and emergency condenser 11 was returned to standby on 7/29/2016 at 0045 EDT. This 8-hour non-emergency report is being made based upon requirements of 10CFR50.72(b)(3)(v)(B) which states, 'Licensee shall notify the NRC of any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (B) Remove residual heat.' The state of New York and the NRC Senior Resident Inspector were informed.
ENS 5209618 July 2016 14:48:00Nine Mile PointNRC Region 1GE-2
GE-5

This 8-hour non-emergency report is being made based upon requirements of 10 CFR 50.72(b)(3)(xiii) which states, 'The licensee shall notify the NRC as soon as practical and in all cases within eight hours of the occurrence of any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).' On 07-18-2016 at 0730 (EDT), both Control Rooms were notified by the Emergency Preparedness Manager, that the Everbridge Emergency Response Organization (ERO) Notification System may not notify all ERO individuals within the required 10 minutes of system initiation. This constitutes a loss of offsite communications capability. The Everbridge vendor is working to resolve the issue. Compensatory measures are in place. All ERO personnel received the page but not all received the notification within the required ten minutes. The licensee notified the NRC Resident Inspector and the State.

  • * * UPDATE AT 1728 EDT ON 7/20/2016 FROM CLARK WILLETT TO MARK ABRAMOVITZ * * *

The Everbridge System was restored and retested at 1930 EDT on 7-19-2016 to provide offsite communications capability. The licensee notified the NRC Resident Inspector and the state. Notified the R1DO (DeFrancisco).

ENS 519691 June 2016 14:33:00Nine Mile PointNRC Region 1GE-2Nine Mile Point Unit 1 (NMP1) experienced a momentary loss of Secondary Containment due to both Reactor Building (RB) airlock doors being opened at the same time. At 1046 (EDT) on 06/01/16, both RB airlock doors were opened simultaneously for less than 5 seconds. This resulted in Secondary Containment being declared Inoperable (TS 3.4.3). The airlock doors were closed and Secondary Containment was restored to Operable. The event is reportable in accordance with 10 CFR 50.72(b)(3)(v)(c), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.' The condition has been entered into the station's corrective action program and the NRC Resident Inspector has been notified. The licensee notified the State of New York.
ENS 518961 May 2016 12:25:00Nine Mile PointNRC Region 1GE-2
GE-5
On May 1, 2016, at 0847 (EDT), an individual experienced a personal medical emergency during a break. The onsite fire brigade and emergency medical technicians administered first aid, but the individual was unresponsive. The individual was transported to the local hospital. The station was notified at 1008 that the hospital has declared the individual deceased. The individual was outside of the radiological controlled area and not contaminated. Nine Mile Point Unit 2 is shut down for the scheduled refueling outage. The individual was a contractor employee. The licensee has notified the NRC Resident Inspector. The State of New York will be notified.
ENS 518567 April 2016 22:32:00Nine Mile PointNRC Region 1GE-5Nine Mile Point Unit 2 (NMP2) experienced a momentary loss of Secondary Containment due to both Reactor Building (RB) airlock doors being opened at the same time. At 1730 (EDT) on 04/07/16, both RB airlock doors were opened simultaneously for less than 5 seconds. This resulted in Secondary Containment being declared Inoperable (TS 3.6.4.1). Secondary Containment was restored to Operable when the doors were closed. The event is reportable in accordance with 10 CFR 50.72(b)(3)(v)(C), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.' The condition has been entered into the station's corrective action program and the NRC Resident Inspector has been notified. There is no interlock on these doors, just lights to verify the opposite door is open or shut. An Operator was entering secondary containment as another Operator was leaving.
ENS 5172310 February 2016 06:29:00Nine Mile PointNRC Region 1GE-2
GE-5
At approximately 0354 (EST) on 2/10/2016, the Nine Mile Point Unit 1 Control Room was notified by Exelon Emergency Preparedness of the inadvertent actuation of one Oswego County Notification Siren at approximately 0247 on 2/10/2016. It is unknown at this time why the inadvertent alarm occurred. Siren repair personnel (ANS Services) have been dispatched to isolate the siren and begin repair work. The siren has been silenced. Alternate notification of the public in the area is through Hyper Reach. The Oswego County Emergency Management Office has issued a news release identifying the inadvertent actuation of the emergency siren. The licensee has notified the NRC Resident Inspector.
ENS 513694 September 2015 12:58:00Nine Mile PointNRC Region 1GE-2On September 4, 2015, at 0916 (EDT), Nine Mile Point Unit 1 experienced an automatic reactor scram following Main Steam Isolation Valve (MSIV) closure and isolation of both main steam lines. The cause of the MSIV closure is not known at this time. All control rods fully inserted. Following the scram, pressure was momentarily controlled through the use of the Emergency Condenser system. At 0950, pressure control was established through the main steam lines to the condenser through Main Steam Isolation Valves (MSIVs) 01-02 and 01-04. MSIV 01-03 would not reopen. All other plant systems responded per design following the scram. The reactor scram is a 4-hour report per 10 CFR 50.72(b)(2)(iv)(B)." The following systems automatically actuated after the scram as expected. These system actuations are an 8-hour report per 10 CFR 50.72(b)(3)(iv)(A). 1. The High Pressure Coolant Injection (HPCI) system. HPCI initiated at 0916 and reset at 0917 when RPV level was restored above the HPCI system low level actuation set point. HPCI initiated and was reset a second time at 0922. HPCI is a flow control mode of the normal feedwater systems, and is not an Emergency Core Cooling System. 2. The Core Spray system actuated, but did not discharge to the Reactor Coolant system. The Core Spray system was secured at 1033. 3. The Emergency Condenser (EC) system actuated to control pressure. EC-11 was secured at 0917. EC-12 was secured at 0921 . The maximum shell temperature of EC system was 193 degrees Fahrenheit. 4. Containment Isolation actuation. Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor water level and pressure maintained within normal bands. Since the scram, there have been no anomalies observed with feedwater system operation. Decay heat is being removed via steam to the main condenser using the turbine bypass valves. The offsite grid is stable with no grid restrictions or warnings in effect. The Reactor is being supplied by the normal feedwater system and there was indication of a partial lift/reset on one Electrometric Relief Valve (ERV). The licensee notified the NRC Resident Inspector and the State of New York Public Service Commission.
ENS 512895 August 2015 16:22:00Nine Mile PointNRC Region 1GE-2Nine Mile Point Unit 1 (NMP1) experienced a momentary loss of Secondary Containment due to both Reactor Building (RB) airlock doors being opened at the same time. At 1252 (EDT) on 08/05/15, both RB airlock doors were opened simultaneously for less than 5 seconds. This resulted in Secondary Containment being declared inoperable (TS 3.4.3). Secondary Containment was restored to operable when the doors were closed. The event is reportable in accordance with 10 CFR 50.72(b)(3)(v)(c), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.' The condition has been entered into the station's corrective action program and the NRC Resident Inspector has been notified. The licensee also notified the State of New York Public Service Commission.
ENS 5090919 March 2015 22:45:00Nine Mile PointNRC Region 1GE-2This 60-Day telephone notification is being made per the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation signal affecting containment isolation valves. On January 21, 2015, Nine Mile Point Unit 1 (NMP1) received a partial primary containment isolation signal which resulted in the closure of primary containment isolation valves (PCIVs) in the following systems: Containment Monitoring System Drywell floor drain sump and Drywell equipment drain sump All affected PCIVs responded as designed. The containment isolation signal was generated due to the failure of a relay for Hi Drywell Pressure on Channel 11 during surveillance testing of the same relay on Channel 12. Drywell pressure was reading normal at the time of the relay failure. Since the isolation signal was not initiated in response to actual plant conditions or parameters satisfying the requirements for initiation, the isolation signal was determined to be invalid. The event was entered into the corrective action program as Issue Report 02440213. The moveable contacts on the failed relay were replaced and retested satisfactorily. There were no safety consequences and no impact to the health and safety of the public as a result of this event. The NRC Resident Inspector was notified.
ENS 508603 March 2015 15:18:00Nine Mile PointNRC Region 1GE-2Nine Mile Point Unit 1 (NMP1) had a momentary loss of Secondary Containment due to both Reactor Building Airlock doors being opened at the same time. At 0837 (EST) on 03/03/2015, both Reactor Building Airlock doors at NMP1 were opened simultaneously for approximately 2 seconds. This results in a momentary loss of Secondary Containment operability (TS 3.4.3). The doors were closed and operability was restored. Secondary Containment being inoperable is an 8 hour notification per 10CFR50.72(b)(3)(v)(C), 'any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.' The condition has been entered into the station's corrective action program and the Senior Resident NRC Inspector was notified. The licensee notified the State of New York.
ENS 5083018 February 2015 16:01:00Nine Mile PointNRC Region 1GE-5At 1406 (EST) Nine Mile Point Unit 2 inserted a manual scram due to rapidly rising reactor water level. The cause of the rapidly rising water prior to the manual scram is unknown and under investigation. Reactor water level is currently being maintained in normal control band post scram. The reactor scram is reportable in accordance with 10 CFR 50.72(b)(2)(iv)(B) as, 'Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical.' The NRC Resident has been notified. All rods fully inserted. Nine Mile Point Unit 2 is in a normal electrical shutdown configuration. The licensee reported no impact on Unit 1. The New York State Public Service Commission was also notified.
ENS 5081311 February 2015 23:15:00Nine Mile PointNRC Region 1GE-2Nine Mile Point Unit 1 (NMP1) had a momentary loss of Secondary Containment due to both Reactor Building Airlock doors being opened at the same time. At 1941 EST on 02/11/2015, both Reactor Building Airlock doors at NMP1 were opened simultaneously for approximately 1 second. This results in a momentary loss of Secondary Containment operability (TS 3.4.3). The doors were closed and operability was restored. Secondary Containment being inoperable is an 8 hour notification per 10 CFR 50.72(b)(3)(v)(C), 'any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.' The condition has been entered into the station's corrective action program and the Senior Resident NRC Inspector was notified.
ENS 5073212 January 2015 23:17:00Nine Mile PointNRC Region 1GE-5At 1939 (EST) on January 12, 2015, Nine Mile Point Unit 2 entered Tech Spec 3.6.4.1 when secondary containment was declared inoperable due to secondary containment differential pressure being above the Tech Spec Surveillance Requirement of -0.25 inches vacuum water gauge. This condition is related to sustained high winds. At 1956 on January 12, 2015 the differential pressure was restored, the secondary containment was declared operable and the Tech Spec 3.6.4.1 exited. Secondary containment being inoperable is a 8-hour report for 10 CFR 50.72(b)(3)(v)(c), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident'. The NRC Resident Inspector has been notified. The licensee notified the New York Public Service Commission.
ENS 5060612 November 2014 14:42:00Nine Mile PointNRC Region 1GE-2
GE-5
A non-licensed supervisor tested positive for alcohol on a follow-up fitness-for-duty test. His access to the facility was terminated. The licensee has notified the NRC Resident Inspector.
ENS 5055320 October 2014 16:32:00Nine Mile PointNRC Region 1GE-2At 1353 EDT on 10/20/2014, both Reactor Building Airlock doors at NMP1 were opened simultaneously for a few seconds. This results in a momentary loss of Secondary Containment operability (TS 3.4.3). The doors were closed and operability was restored. Secondary Containment being inoperable is an 8 hour notification per 10CFR50.73(b)(3)(v)(C), 'any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.' The condition has been entered into the station's corrective action program and the NRC Resident Inspector was notified.
ENS 5054216 October 2014 13:14:00Nine Mile PointNRC Region 1GE-2Nine Mile Point Unit 1 (NMP1) had a momentary loss of Secondary Containment due to both Reactor Building airlock doors being opened at the same time. At 1042 EDT on 10/16/2014, both Reactor Building airlock doors at NMP1 were opened simultaneously for less than 5 seconds. This results in a momentary loss of Secondary Containment operability (TS 3.4.3). The doors were closed and operability was restored. Secondary Containment being inoperable is an 8 hour notification per 10 CFR 50.72(b)(3)(v)(C), 'any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.' The condition has been entered into the station's corrective action program and the NRC Senior Resident Inspector was notified. The licensee will be notifying the State of New York Public Service Commission.
ENS 5039021 August 2014 12:04:00Nine Mile PointNRC Region 1GE-2

One of the 37 Prompt Notification System sirens surrounding the James A Fitzpatrick (JAF) / Nine Mile Point (NMP) sites spuriously activated at 0850 EDT. The Oswego County Emergency Operations Center notified Nine Mile Point via RECS (Radiological Emergency Communications System) that siren #13 had inadvertently activated. Repair technicians have de-activated and silenced the faulty siren as of 0943 EDT. Siren #13 is currently out of service and the backup method for siren #13 has been verified to be functional. The cause of the inadvertent siren activation is believed to be a lightning strike. The issue has been entered into the site's Corrective Action Program. The Oswego County Emergency Management Office issued a News Release identifying the inadvertent actuation of the emergency siren. The NRC Resident Inspector has been notified.

  • * * UPDATE AT 1247 EDT ON 8/23/14 FROM MARK GREER TO MARK ABRAMOVITZ * * *

As of 0928 EDT on 08/23/2014, siren #13 has been repaired and returned to service. The NRC Resident Inspector has been notified. Notified the R1DO (McKinley).

ENS 5036314 August 2014 01:16:00Nine Mile PointNRC Region 1GE-2Nine Mile Point Unit 1 (NMP1) had a momentary loss of Secondary Containment due to both Reactor Building Airlock doors being opened at the same time. At 2318 (EDT) on 8/13/2014, both Reactor Building Airlock doors at NMP1 were open simultaneously for less than 5 seconds. This results in a momentary loss of Secondary Containment operability (TS 3.4.3). The doors were closed and operability was restored. Secondary Containment being inoperable is an 8 hour notification per 10 CFR 50.72(b)(3)(v)(C), 'any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.' The condition has been entered into the station's corrective action program and the NRC Senior Resident Inspector was notified.
ENS 5029622 July 2014 21:36:00Nine Mile PointNRC Region 1GE-5

This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to Mitigate the Consequences of an Accident. During the conduct of the Unit 2 Division 3 High Pressure Core Spray (HPCS) Diesel Generator (DG) surveillance test, one of 2 Cooling Water Outlet Valves failed to automatically open. The Division 3 Diesel is supplied by two redundant trains of cooling water one from each Service Water Divisional Header. Although the redundant cooling water supply was fully available and supplied adequate cooling to the diesel generator, the DG was at reduced margin to have adequate cooling water supply, if required during a loss of offsite power. Due to this loss of margin and inoperable condition, it has been determined that this failure could potentially affect the safety function of this system, and is being reported as an 8 hour ENS notification. The licensee has attributed the failure to high resistance in a relay which is currently being replaced. This places Unit 2 in the Technical Specification Action Statement 3.8.1, which requires restoration of Diesel Generator within 72 hours or commence a Reactor Shutdown. All other ECCS Systems have been verified operable. The licensee informed the NRC Resident Inspector and will inform the State of New York.

  • * * RETRACTION AT 1940 EDT ON 9/2/2014 FROM ANTHONY PETRELLI TO MARK ABRAMOVITZ * * *

This update retracts Event Notification #50296, which reported an event or condition that could have potentially prevented fulfillment of a Safety Function needed to mitigate the consequences of an accident. Upon further review, it was determined that the ability of the HPCS system (single supported train) remained operable and capable of performing its safety function as evaluated by the NMP Unit 2 Safety Function Determination Process (TS 5.5.11). The NRC Resident Inspector has been notified. Notified the R1DO (Ferdas).

ENS 5021620 June 2014 07:31:00Nine Mile PointNRC Region 1GE-5

At 0110 (EDT) on June 20, 2014, Nine Mile Point Unit 2 lost communication to the DRMS (Digital Radiation Monitor System Computer). The DRMS provides the Control Room alarm functions for Offgas Pretreatment Process Radiation Monitors 2OFG-CAB13A/13B and Cooling Tower Blowdown Effluent Radiation Monitor 2CWS-CAB157. Due to the loss of the Control Room alarm function, 2OFG-CAB13A, 2OFG-CAB13B, and 2CWS-CAB157 have been declared non-functional. Compensatory measures (i.e. collect and analyze grab samples) have been implemented per the requirements of the Offsite Dose Calculation Manual (ODCM). The non-functional radiation monitors are necessary for accident assessment and are credited for Emergency Action Level (EAL) classification. The inability to classify an EAL due to the out of service radiation monitors is considered a loss of assessment capability per 10 CFR 50.72(b)(3)(xiii). The NRC Resident Inspector has been notified. The licensee has notified the State.

  • * * UPDATE PROVIDED BY CHRIS SKINNER TO JEFF ROTTON AT 1313 EDT ON 06/24/2014 * * *

At 1208 (EDT) on June 21, the DRMS was declared functional. With the alarm functions restored, radiation monitors 2OFG-CAB13A, 2OFG-CAB13B, and 2CWS-CAB157 were declared functional and compensatory actions per the ODCM have been discontinued. The licensee notified the NRC Resident Inspector and the State of New York. Notified R1DO (Bickett).

.. .  .
ENS 5018711 June 2014 00:23:00Nine Mile PointNRC Region 1GE-5Nine Mile Point Unit 2 Secondary Containment was declared inoperable on 6/10/14 from 2032 EDT until 2036 EDT during the restoration of Reactor Building Ventilation System to a normal lineup. While performing actions to restore ventilation fans the Above Refuel Floor Exhaust Fan, 2HVR-FN5A, tripped when started resulting in building differential pressure becoming less negative than -0.25 inches. Tech Spec 3.6.4.1 Secondary Containment, Action A.1 to restore within 4 hours was entered at 2032 EDT on 6/10/14. The standby Above Refuel Floor Exhaust Fan, 2HVR-FN5B, was started per procedure and building differential pressure was restored. Secondary Containment was declared operable at 2036 EDT on 6/10/14 and Tech Spec 3.6.4.1 action was exited. Secondary containment being inoperable is a 8-hour report for 10 CFR 50.72(b)(3)(v)(c), Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector and will notify the State of New York.
ENS 5013022 May 2014 09:31:00Nine Mile PointNRC Region 1GE-5At 0210 (EDT) on May 22, 2014, Nine Mile Point Unit 2, the reactor building vent radiation monitor (Vent WRGMS) was removed from service due to a problem with the check source. The unplanned isolation of Vent WRGMS is a 8-hour report for 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability. Until the equipment is restored, Chemistry will perform sampling requirements per the ODCM. The NRC Resident Inspector has been notified. The licensee notified the State of New York Public Service Commission.
ENS 500988 May 2014 20:57:00Nine Mile PointNRC Region 1GE-2A review of industry operating experience regarding the potential for secondary fires being caused by DC Motor control circuit wiring has determined the described condition to be applicable to Nine Mile Point Unit 1 resulting in a potentially unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. The original plant wiring design and configuration for the containment isolation valve IV-33-04 does not include separate over current protection for the power and control wiring. The only protection for the control circuit wiring is provided by the power circuit fuses. In the postulated event, a fire in the reactor building at the DC MOV could cause one of the control circuit wires to short and potentially over heat creating a secondary fire in the raceway system in a different fire zone. The secondary fire could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R. This event entered into the Nine Mile Point corrective action program as Condition Report (CR) 2014-004630. This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures (i.e., fire zone inspections) have been implemented for affected areas of the plant. The licensee has notified the State and the NRC Resident Inspector.
ENS 499964 April 2014 08:58:00Nine Mile PointNRC Region 1GE-5Nine Mile Point Unit 2 Ventilation Wide Range Gaseous Monitoring System was removed from service on 4/1/2014 at 1140 EDT to support isolation of the Unit 2 Reactor Building Ventilation during a Division 2 electrical bus outage. The monitoring system will be out of service for greater than 72 hours due to the planned maintenance window. NMP2 is in Mode 5, refueling. Compensatory actions remain in effect in accordance with the Off-Site Dose Calculation Manual. Expected return to service is 4/5/14. This event is being reported in accordance with 10 CFR 50.72 (b)(3)(xiii) due to a loss of assessment capability. The licensee notified the NRC Resident Inspector.
ENS 499852 April 2014 08:42:00Nine Mile PointNRC Region 1GE-5At 0123 EDT on April 2, 2014, Nine Mile Point Unit 2 was in Mode 5, Refueling, and in the other specified condition of Operations with Potential for Draining the Reactor Vessel. During this condition both redundant personnel airlock doors were open at the same time in an airlock penetration of the reactor building. This condition represents a loss of Secondary Containment safety function. Technical Specification 3.6.4.1, Action A.1 was entered for the loss of Secondary Containment and was promptly exited when the doors were closed. Secondary containment being inoperable is an 8-hour report per 10 CFR 50.72(b)(3)(v)(C), Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. The NRC Resident Inspector has been notified.
ENS 4994824 March 2014 05:14:00Nine Mile PointNRC Region 1GE-5At 0031 (EDT) on March 24, 2014, Nine Mile Point Unit 2 was lowering power for the planned refueling outage. The loss of reactor building heating resulted in the isolation of the reactor building to maintain building temperature. Isolation of the reactor building resulted in the isolation of the reactor building vent radiation monitor (Vent WRGMS) which is a loss of emergency assessment capability. The isolation of the reactor building also resulted in declaring secondary containment inoperable due to secondary containment differential pressure being positive. Secondary containment was declared operable at 0034 (EDT) when differential pressure was restored to greater than negative 0.25 inches water gauge. Secondary containment being inoperable is a 8-hour report for 10 CFR 50.72(b)(3)(v)(c), any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. The unplanned isolation of Vent WRGMS is a 8-hour report for 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability. The NRC Resident Inspector has been notified. The licensee will notify the New York Public Service Commission.
ENS 4990612 March 2014 21:18:00Nine Mile PointNRC Region 1GE-5At 1422 EDT on March 12, 2014, Nine Mile Point Unit 2 declared secondary containment inoperable due to secondary containment differential pressure being positive. The positive differential pressure was related to sustained high winds from the northeast associated with Winter Storm Vulcan. The reactor building was isolated at 1630 EDT and secondary containment declared operable at 1700 EDT when Secondary Containment Vacuum was restored to greater than 0.25 inch of vacuum water gauge. The isolation of the reactor building resulted in the isolation of the reactor building vent rad monitor (Vent WRGMS (Wide Range Gas Monitors)) which is a loss of emergency assessment capability. Secondary containment being inoperable is an 8-hour report for 10 CFR 50.72(b)(3)(v)(c), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control radioactive release.' The unplanned isolation of the Vent WRGMS is an 8-hour report for 10 CFR 50.72(b)(3)(xiii), 'Any event that results in a major loss of emergency assessment capability.' The NRC Resident Inspector has been informed. The licensee will notify the state.
ENS 4988810 March 2014 19:20:00Nine Mile PointNRC Region 1GE-5At 1628 EDT Nine Mile Point (NMP) Unit 2 experienced an actuation of the Alternate Rod Insertion (ARI) system which resulted in a reactor scram. Coincident with the scram, the Reactor Core Isolation Cooling (RCIC) system initiated. Prior to the event, maintenance personnel were working in the vicinity of a reactor vessel level instrumentation rack and may have agitated the common drain line of the transmitters. A prompt investigation is underway to investigate the incident. The actuation signal for the RCIC system was invalid because reactor vessel level did not reach level two and the actuation was not in response to actual plant conditions or parameters. The reactor scram is reportable in accordance with 10 CFR 50.72(b)(2)(iv)(B) as, 'Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical.' The event has been entered into the NMP corrective action program as CR-2014-001963. The NRC Resident Inspector has been notified. The licensee has notified the State of New York. The reactor is shutdown with all rods inserted. Decay heat is being rejected to the condenser and reactor water level is being maintained by condensate, feedwater, reactor water clean up, and control rod drive systems.
ENS 498684 March 2014 05:05:00Nine Mile PointNRC Region 1GE-5At 0137 EST Nine Mile Point Unit 2 experienced a loss of an uninterruptible power supply 2VBB-UPS3B which resulted in a half scram and half isolations. This caused a loss of cooling water to the Reactor Recirculation Pumps and other indications for the loss of power. At 0143 EST a Manual Reactor Scram was inserted due to the rise of temperatures on the Reactor Recirculation Pump seal cavity temperature and motor winding temperature. The reactor building ventilation radiation monitor went non-functional when the reactor building isolated on the loss of UPS power. The standby gas treatment system was started as required and restored the reactor building differential pressure. This is a 4-Hour report for 10CFR50.72(b)(2)(iv)(B) RPS Actuation and 8-Hour report for 10CFR50.72(b)(3)(xiii) Loss of Emergency Assessment Capability. The NRC Resident inspector has been notified. All systems functioned as required following the manual scram. All control rods fully inserted. The cause of the loss of the UPS is under investigation.
ENS 4985927 February 2014 03:37:00Nine Mile PointNRC Region 1GE-5

On February 24th at 0400 (EST), the Division 3 diesel (HPCS diesel) was declared inoperable for planned maintenance. Technical Specification (TS) 3.8.1 condition B was entered with a required action to restore the diesel to operable status within 72 hours. Shortly after starting the diesel for post maintenance testing, operations observed erratic voltage regulator operation. The diesel was secured at 1621 on 2/24/14 before completing the required post maintenance operability test and troubleshooting is ongoing. At 0330 on 2/27/14, the High Pressure Core Spray System (HPCS) was declared inoperable and TS 3.5.1 condition B was entered. With the HPCS system declared inoperable, TS 3.8.1 condition B was exited in accordance with the following note modifying TS 3.8.1: 'Division 3 AC electrical power sources are not required to be OPERABLE when High Pressure Core Spray (HPCS) System is inoperable.' The HPCS system is a single train system that is discussed in Chapters 6 and 15 of the Final Safety Analysis Report. The unplanned inoperability of the HPCS system is reportable in accordance with 10 CFR 50.72(b)(3)(v)(D) as, 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (D) Mitigate the consequences of an accident.' The condition has been entered into the NMP corrective action program as CR-2014-001623. The NRC Resident Inspector has been notified.

  • * * UPDATE FROM RODGER ORZELL TO JOHN SHOEMAKER AT 1210 EST ON 2/27/14 * * *

The NMP Unit 2 Division 3 diesel testing was completed satisfactorily. The licensee declared the Division 3 diesel and HPCS systems operable at 1013 EST on 2/27/14 and exited TS 3.8.1 and 3.5.1. The licensee has notified the NRC Resident Inspector. Notified the R1DO (DeFrancisco).

ENS 4983216 February 2014 18:21:00Nine Mile PointNRC Region 1GE-5

An automatic initiation of Emergency Diesel Generators was received due to a loss of one of two off-site power sources. On February 16, 2014 at 1216 (EST), Nine Mile Point Unit 2 experienced an automatic initiation of the Division 1 and 3 Emergency Diesel Generators (EDGs) due to a loss of Line 5. Line 5 is one of the two 115KV offsite power sources. Line 5 was lost due to an offsite event that is currently being evaluated by the grid operator. During the electrical transient, Nine Mile Point Unit 2 also experienced a feedwater level control lockup, requiring manual control. No Emergency Core Cooling Systems actuated, and feedwater level control was returned to automatic. Nine Mile Point Unit 2 remained at 100% power during the loss of Line 5, one of the offsite power sources. The NRC resident has been notified. The licensee also notified the State of New York. Unit 2 is currently in a 24-hour Technical Specification Limiting Condition of Operation (TS LCO) Action Statement 3.8.1.A3. Once Division III is realigned to the "B" side Line 6 offsite power, Unit 2 will be in a 72-hour LCO. Both EDGs are currently running. There was no effect on Unit 1.

  • * * UPDATE PROVIDED BY MARK GREER TO JEFF ROTTON AT 1727 EST ON 2/17/2014 * * *

In addition to the initiation of Division 1 and 3 Emergency Diesel Generators, Service Water Radiation Monitor 2SWP*RE146A and Radwaste/Reactor Building Vent Gaseous Effluent Monitoring Systems were also lost. Compensatory actions were established as required by station procedures and the Offsite Dose Calculation Manual. The loss of these instruments is reportable as a major loss of Emergency Assessment Capability per 10CFR50.72(b)(3)(xiii). The Service Water Radiation Monitor 2SWP*RE146A was restored to service on February 16, 2014 at 1450 EST. The Radwaste/Reactor Building Vent Gaseous Effluent Monitoring Systems were restored to service on February 17, 2014 at 0240. It is recognized that this notification is not within eight hours of the event. Line 5 is restored to OPERABLE February 17, 2014 at 1628. The NRC Resident Inspector has been informed of this additional reportable condition (and the update on the lost off-site power source). The condition has been entered into the corrective action program. The licensee also notified the State of New York Public Service Commission. The licensee exited the 72-hour LCO for the lost off-site power at 1628 on February 17, 2014. Notified R1DO(Krohn), NRREO (Monninger) and ILTAB (Whitney).

ENS 497955 February 2014 15:28:00Nine Mile PointNRC Region 1GE-2
GE-5
On Wednesday, February 5, 2014, at 1130 EST, Oswego County notified Nine Mile Point (NMP) of a loss of the tone alert system at approximately 1000. The loss of the tone alert was identified by the National Weather Service - Binghamton forecast office when it was determined that the phone line to the site was out of service. Site Emergency Procedures define a loss of the tone alert system for greater than one hour as a significant loss of emergency communications. This impacts the ability to readily notify a portion of the Emergency Planning Zone (EPZ) population for the NMP and JAF (James A. FitzPatrick) nuclear power plants. This failure meets NRC 8-Hour reporting criteria 10 CFR 50.72(b)(3)(xiii). Compensatory measures were verified to be available should the Prompt Notification System be needed. This consists of utilizing the hyper-reach system, which is a reverse 911 feature available from the county 911 center. The county alert sirens, which also function as part of the public prompt notification system, remain operable. At 1328 on February 5, 2014, Nine Mile Point was notified by Oswego County that the tone alert system was returned to service, effective as of 1325. The licensee informed the NRC Resident Inspector and the State of New York.
ENS 4967726 December 2013 16:29:00Nine Mile PointNRC Region 1GE-2On December 26, 2013 at 1301 EST, Nine Mile Point Unit 1 (NMP1) commenced a reactor shutdown in accordance with Technical Specification (TS) 3.2.7.c as a result of Main Steam Isolation Valve (MSIV) 111 being declared inoperable due to a surveillance test failure when power was lost to the control circuit. The cause of the power loss was a blown fuse due to a short in the test circuitry. TS 3.2.7.c requires that a normal orderly shutdown be initiated within one hour and have the reactor in cold shutdown condition within ten hours. The blown fuse was replaced, test circuit isolated, power to the control circuit restored and MSIV 111 was declared operable at 1549 EST. Power ascension is in progress. Post maintenance operability test have been completed and the surveillance will be completed at a later time. The licensee has notified the NRC Resident Inspector and the State of New York.
ENS 495962 December 2013 16:52:00Nine Mile PointNRC Region 1GE-2
GE-5
A non-licensed employee supervisor had a confirmed positive for alcohol during a for-cause fitness-for-duty test. The employee's unescorted access to the plant has been terminated. The NRC Resident Inspector has been notified.
ENS 495932 December 2013 11:03:00Nine Mile PointNRC Region 1GE-5At 0904 (EST) on Monday, December 2, 2013, Nine Mile Point Unit 2 was manually scrammed from approximately 40% thermal power due to the loss of both reactor recirculation pumps during a planned downpower evolution. Manual scram of the unit is procedurally required upon loss of both recirculation pumps to avoid potential power/flow oscillations. The reactor recirculation pumps failed to transfer to the low frequency motor generators when downshifted from fast speed. The cause of the loss of both reactor recirculation pumps is not known at this time. (Nine Mile Point Unit 2) NMP2 has commenced cooldown in preparation for the forced outage to investigate and commence repairs. 10 CFR 50.72(b)(2)(iv)(B) requires reporting within 4 hours of any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical. All control rods fully inserted. No safety systems actuated. Decay heat is being removed via the main condenser. The "A" recirculation pump was restarted in low speed at 1045 EST. Unit 2 is in a normal shutdown electrical lineup. The licensee informed the NRC Resident Inspector and will inform the New York State Public Services Commission.
ENS 4955018 November 2013 12:04:00Nine Mile PointNRC Region 1GE-2
GE-5
Nine Mile Point Nuclear Station (NMP1 and NMP2) was notified at 0512 (EST) by New York State (NYS) Watch Center that the Radiological Emergency Communications System (RECS) and commercial telephones were not available. The unavailability of the communications systems was a result of the relocation of personnel from the NYS Watch Center to an alternate location as a result of an unplanned computer server outage affecting the center network and some communications systems. While the RECS line remained operational, it was unavailable due to the relocation. An alternate method of communication was established via cell phone at the time of notification. The cause of the server loss is not known. This condition is reportable as a major loss of emergency offsite communications capability under 10CFR50.72(b)(3)(xiii). The NYS Watch Center network and communications systems have been restored and the facility staffed as of 0757 (EST). The condition has been entered into the station's corrective action program. The licensee has notified the NRC Resident Inspector.