Semantic search

Jump to: navigation, search
Search

Edit query Show embed code

The query [[Category:ENS Notification]] [[Site::Harris]] [[Scram::+]] was answered by the SMWSQLStore3 in 0.4366 seconds.


Results 1 – 10    (Previous 50 | Next 50)   (20 | 50 | 100 | 250 | 500)   (JSON | CSV | RSS | RDF)
 Entered dateSiteRegionScramReactor typeEvent description
ENS 4974218 January 2014 10:47:00HarrisNRC Region 2Manual ScramWestinghouse PWR 3-Loop

(At 1016 EST, an) Alert (was declared) based on EAL # HA 2.1 Fire or explosion resulting in either: visible damage to any table H-1 structure or system/component required for safe shutdown of the plant, or control room indication of degraded performance of any safe shutdown structure, system, or component within any table H-1 area. Fire in 480V bus 1D2. Reactor was manually tripped 480 VAC safety related transformer fire in switchgear room. Plant reduced power and tripped the reactor manually. Reactor trip was uncomplicated. Fire was extinguished when the 480 VAC bus was de-energized. The licensee has notified the NRC Resident Inspector, the State of North Carolina, and other local authorities. Notified DHS SWO, DOE Ops Center, FEMA Operations Center, HHS Ops Center, NICC Watch Officer, USDA Ops Center, EPA EOC, and NuclearSSA via e-mail.

  • * * UPDATE FROM JOEL DUHON TO JOHN SHOEMAKER AT 1602 EST ON 1/18/14 * * *

Harris Nuclear Plant secured from the Alert at 1551 EST, on 1/18/14. The plant is stable, the fire is out, the TSC and EOF have been secured and plant recovery has been transferred to the outage control center. There were no personnel injuries or radiological releases. Radiation monitor RM-*1TS-3653C (Technical Support Center Radiation Monitor) is out of service. The licensee has notified the NRC Resident Inspector. Notified the R2DO (King), R2RA (McCree), NRR (Leeds), IRD MOC (Grant), OPA (Brenner), NRR EO (Lee) Notified DHS SWO, DOE Ops Center, FEMA Operations Center, HHS Ops Center, NICC Watch Officer, USDA Ops Center, EPA EOC, and NuclearSSA via e-mail.

ENS 464678 December 2010 16:51:00HarrisNRC Region 2Manual ScramWestinghouse PWR 3-LoopText provided by the licensee. Quotations omitted for readability. Report Type: This 60-day telephone notification is being made under 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1). Description: On October 28, 2010, during the performance of MST I0073, "Train 'B' 18 Month Manual Reactor Trip, Solid State Protection System Actuation Logic & Master Relay Test", two sequential errors resulted in the inappropriate activation of the 'B' ESW pump. During night shift on October 27/28th, the Master Relay Selector Switch was not returned to the required OFF position. This caused day shift to find one of the two general warning lights to be lit. During the troubleshooting for the light, a technician discovered the Master Relay Selector Switch out of the expected OFF position as required by the procedure. A technician moved the switch to the OFF position outside of procedural guidance, resulting in the partial activation of the Reactor Protection System, including the 'B' ESW pump. The plant was in Mode 6 due to refueling outage 16 during the event. Actual plant conditions and parameters did not exist that required an automatic start of the 'B' ESW Pump. Therefore, this actuation is classified as invalid. The system started and functioned successfully. This invalid actuation was entered into the corrective action program as NCR 430289. Cause: Poor performance of task by the individual. The licensee informed the NRC Resident Inspector.
ENS 4549916 November 2009 02:24:00HarrisNRC Region 2Manual ScramWestinghouse PWR 3-LoopAt 2242 (EST) on 11/15/09, the reactor was manually scrammed from 100% power due to a large oil leak on the main generator seal oil system. Condenser vacuum was broken immediately following the reactor trip, and the main turbine stopped rotating at 2324 (EST). Following the reactor trip, the 'B' steam generator Main Steam Isolation Valve (MSIV) failed to fully close on demand, but was closed due to field actions at 2303 (EST). The reactor remained stable at NOP/NOT following the reactor trip. Offsite power remained available throughout the event. This condition is being reported as actuation of the reactor protection system in accordance with 10CFR 50.72(b)(2)(iv)(B). All control rods fully inserted and decay heat is being removed through the S/G relief valves to the atmospheric dumps. No known primary to secondary leakage exists. The plant remains stable in Mode 3. The licensee notified the NRC Resident Inspector.
ENS 4442319 August 2008 15:07:00HarrisNRC Region 2Manual ScramWestinghouse PWR 3-LoopOn August 19, 2008, with the Unit shut down in Mode 3, post maintenance testing was being performed for the Digital Rod Position Indication System. While performing this test, a 'Rod Control Urgent Failure' alarm was received upon initial withdrawal of Control Bank-C. All other control and shutdown banks remained fully inserted in the core. Local inspection revealed a phase failure on movable gripper coils in a power cabinet. In accordance with plant procedures, at 0905 hours, a manual reactor trip was initiated by operators opening the reactor trip breakers. All Safety Systems functioned as designed and Rod Control System repairs are in progress. This event posed no significant safety implications because the reactor was subcritical when the reactor trip breakers were opened. Compliance with all Technical Specification requirements was maintained. The health and safety of the public were not affected by this event. The NRC Resident Inspector was notified.
ENS 4440411 August 2008 04:21:00HarrisNRC Region 2Manual ScramWestinghouse PWR 3-LoopAt 0049 EDT on 8/11/2008, the Harris Nuclear Plant was manually scrammed from 21% power due to indications of degrading condenser vacuum. At the time, a reactor shutdown was in progress with indications of a degraded condenser boot seal. The unit was stabilized in Mode 3 with no additional equipment failures or other complications. The reactor is currently at normal operating pressure and temperature. The highest vacuum observed was 8". All rods inserted into the core after the manual trip. Auxiliary feed water did not start as a result of the trip. Steam generator level is being maintained via normal feed water flow path. Decay heat is being removed via the steam dumps to atmosphere. There is no known primary to secondary leakage. No power-operated or manual reliefs lifted during the transient. The grid is stable and loads are being supplied via the station start-up transformer. The licensee has notified the NRC Resident Inspector.
ENS 4367629 September 2007 02:19:00HarrisNRC Region 2Automatic ScramWestinghouse PWR 3-LoopOn September 28, 2007, while reducing power for a planned refueling outage with the reactor at approximately 30 percent power in MODE 1, an unplanned actuation of the reactor protection system occurred. At 2232 a fault pressure trip signal was received on the A Startup Transformer (SUT), causing a loss of power to Aux Buses D, A & C electrical buses as well as the A-SA safety bus. The loss of A & C buses initiated the RCP underfrequency trip which tripped the Reactor and all three RCPs as designed. The A Diesel Generator automatically started and reenergized bus A-SA as designed. The auxiliary feedwater system actuated as expected due to undervoltage on the A-SA safety bus and loss of the main feedwater pumps. All control rods inserted on the reactor trip. The operations staff responded to the event in accordance with applicable plant procedures. The plant stabilized at normal operating no-load reactor coolant system temperature and pressure following the reactor trip. Steam generator water levels are being maintained using auxiliary feedwater. All emergency core cooling system equipment is available. The plant electrical system is being restored at this time. The A SUT remains out of service. The cause of the loss of power from A SUT is under investigation. This condition is being reported as an unplanned reactor protection system actuation and specified system actuation in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector was notified of this event by the licensee. The plant was in natural circulation for approximately 1 hour. The Main Steam Isolation Valves (MSIVs) were manually isolated per procedure due to loss of EHC indication. Presently the B RCP has been restored to service, MSIVs are still closed, and the motor driven auxiliary feedwater pumps are feeding the Main Steam Generators. There are not any leaking steam generator tubes. The A EDG will be secured after backfeeding of the deenergized buses have been established.
ENS 4284819 September 2006 13:09:00HarrisNRC Region 2Automatic ScramWestinghouse PWR 3-LoopAt approximately 1000 EDT on September 19, 2006, with the reactor at 100 percent power in Mode 1, the reactor was automatically tripped from a turbine trip due to a generator lockout signal. The cause of this signal is under investigation. The auxiliary feedwater system actuated as expected to stabilize steam generator levels. All systems functioned as required and no other safety systems were actuated. All control rods inserted (fully) on the reactor trip. The operations staff responded to the event in accordance with applicable plant procedures. The plant stabilized at normal operating no-load reactor coolant system temperature and pressure following the reactor trip. Steam generator water levels are being maintained using normal feedwater. All emergency core cooling system equipment is available. The plant electrical system is available and in a normal configuration. This condition is being reported as an unplanned reactor protection system actuation and specified system actuation in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)." The MSIVs are open with the steam generators discharging steam to the main condenser using the steam dump valves. The licensee notified the NRC Resident Inspector.
ENS 416541 May 2005 04:08:00HarrisNRC Region 2Manual ScramWestinghouse PWR 3-LoopThe plant was in Mode 1 at 100% power. At 0021 (EDT) the reactor was manually tripped following a loss of 1B Condensate pump per AOP-010, Feedwater Malfunctions. The cause of the 1B Condensate pump trip is not known at the present time. The plant is stable in Mode 3 at normal temperature and pressure. All safety systems functioned as expected; AFW automatically actuated due to low level in the steam generators to provide continued decay heat removal. All control rods fully inserted on the manual reactor trip. Secondary PORVs opened on the trip and reclosed. Steam generators are discharging steam to the main condenser using the turbine steam dump valves. AFW has been secured and main feedwater is operating to maintain SG levels. The licensee notified the NRC Resident Inspector.
ENS 407306 May 2004 16:25:00HarrisNRC Region 2Automatic ScramWestinghouse PWR 3-LoopThe following information was received from the licensee via facsimile: On May 6, 2004, with the reactor at 100 percent power in MODE 1, an unplanned actuation of the reactor protection system occurred. At 1252 (EDT) the reactor was automatically tripped from a power range negative flux rate trip signal. The auxiliary feedwater system actuated as expected to stabilize steam generator levels. All systems functioned as required and no other safety systems were actuated. All control rods inserted on the reactor trip. The operations staff responded to the event in accordance with applicable plant procedures. The plant stabilized at normal operating no-load reactor coolant system temperature and pressure following the reactor trip. Steam generator water levels are being maintained using normal main feedwater. All emergency core cooling system equipment is available. The plant electrical system is available and in a normal configuration. The cause of the plant trip is under investigation. This condition is being reported as an unplanned reactor protection system actuation and specified system actuation in accordance with 10 CFR 50.72(b)(2)(iv)(B) and10 CFR 50.72(b)(3)(iv)(A) . During the transient, a steam generator power-operated relief valve lifted momentarily and then re-seated. No reportable radiological release occurred during the event. The licensee notified the NRC Resident Inspector.
ENS 4008418 August 2003 00:40:00HarrisNRC Region 2Manual ScramWestinghouse PWR 3-LoopAt 3:51 PM EDT, on August 17, 2003, with the reactor at 100% in Mode 1, the reactor was manually tripped in response to a trip of the A condensate pump and subsequent trip of the A main feed pump. Both motor-driven auxiliary feedwater pumps and the turbine driven auxiliary feedwater pump started automatically due to Lo-Lo steam generator level. The operations crew responded to the event in accordance with the applicable plant procedures. The plant was stabilized at a normal operating no-load Reactor Coolant System (RCS) temperature and pressure following the reactor trip. The condensate pump electrical supply breaker tripped due to instantaneous overcurrent, possibly related to a severe electrical storm in the area at the time. The feed pump tripped due to the loss of the condensate pump. Offsite power remained available throughout the transient. A local fire department responded to a downed power line in the vicinity of the Harris plant but the response was not related to any onsite activities. This condition is being reported as actuation of the reactor protection system and AFW in accordance with 10CFR50.72(b)(2)(iv)(B), and 10CFR50.72(b)(3)(iv)(A). 10CFR50.72 requires an 8-hour report for "Any condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation." In this case, the AFW pumps start signal was due to Lo-Lo Steam Generator Level. A root cause team is being formed to identify the cause and corrective actions Due to low decay heat in the core, the Main Steam Isolation Valves were closed and the Steam Generator PORVs are being used to maintain the plant in a Hot Standby condition. No known leaking steam generator tubes are known. Both motor-driven and the turbine driven auxiliary feedwater pumps were secured after main feedwater was returned to service. All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed. The electrical grid is stable. The NRC Resident Inspector was notified of this event by the licensee.