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The query [[Category:ENS Notification]] [[Site::Oyster Creek]] [[Scram::+]] was answered by the SMWSQLStore3 in 0.4436 seconds.


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 Entered dateSiteRegionScramReactor typeEvent description
ENS 528393 July 2017 12:32:00Oyster CreekNRC Region 1Manual Scram
Automatic Scram
GE-2At 1015 (EDT) a manual reactor scram was inserted due to degrading main condenser vacuum. All rods inserted into the core as expected and all systems functioned as expected during the scram. This event is reportable within 4 hours per 10 CFR 50.72(b)(2)(iv)(B) 'any event or condition that results in actuation of the Reactor Protection System (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' At 1033 (EDT) an automatic reactor scram occurred on low reactor water level. Due to the previous manual reactor scram, all rods were (already) inserted. This event is reportable within 8 hours per 10 CFR 50.72(b)(3)(iv)(A) 'any event or 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 preplanned sequence during testing or reactor operation. (1) Reactor protection system (RPS) including : Reactor scram and reactor trip.' Decay heat is being removed using main feedwater and the turbine bypass valves. The licensee notified the NRC Resident Inspector. This event was characterized as a "configuration control event" where a valve misposition allowed the offgas line to flood.
ENS 5238120 November 2016 06:01:00Oyster CreekNRC Region 1Automatic ScramGE-2At 0342 EST, an automatic reactor scram was processed during turbine valve testing. All rods inserted into the core as expected and all systems functioned as expected during the scram. The event is reportable within 4 hours per 10 CFR 50.72(b)(2)(iv)(B) - any event or condition that results in actuation of the Reactor Protection System (RPS) when the reactor is critical except when the actuation results from and is part of a preplanned sequence during testing or reactor operation. The plant response to the reactor scram was uncomplicated. The main feedwater system is maintaining reactor water level and decay heat is being removed by the main turbine bypass valves to the main condenser. The unit is in a normal shutdown electrical lineup. No SRVs lifted during the scram. The licensee was testing the main turbine trip function just prior to the scram. The cause is under investigation. The licensee notified the NRC Resident Inspector.
ENS 5189530 April 2016 19:14:00Oyster CreekNRC Region 1Manual ScramGE-2Today at 1804 EDT, a manual scram was processed during startup due to rising unidentified leak rate. The rise in unidentified leak rate was identified to be coming from the D Reactor Recirc Pump seal cavity. All rods inserted into the core and all systems functioned as expected during the scram. The event is reportable within 4 hours per 10 CFR 50.72(b)(2)(iv)(B) - any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. The reactor is stable in hot shutdown. The licensee notified the NRC Resident Inspector.
ENS 510557 May 2015 18:55:00Oyster CreekNRC Region 1Automatic ScramGE-2Today at 1727 EDT, an automatic scram from a turbine trip occurred. The cause of the turbine trip is currently under investigation. All rods inserted into the core and all systems functioned as expected during the scram. The event is reportable within 4 hours per 10CFR50.72(b)(2)(iv)(B) - any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. Plant response to the scram was uncomplicated and the plant is stable in Mode 3. The licensee has notified the NRC Resident Inspector.
ENS 5052412 October 2014 05:22:00Oyster CreekNRC Region 1Manual Scram
Automatic Scram
GE-2

Today at approximately 0250 (EDT) (on 10/12/14), during a planned reactor power ascension with reactor power at approximately 1% of rated thermal power, reactor water level began lowering. Operators inserted a manual SCRAM at 0251 (EDT) in accordance with station procedures. The cause of the lowering reactor level is currently under investigation. All rods inserted into the core and all systems functioned as expected during the scram. No electromatic (EMRVs) or safety relief valves lifted during the transient. The plant is currently shutdown and plant parameters are stable. This event is reportable per 10CFR50.72(b)(2)(iv)(B) - 'any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' Decay heat is being released to the main condenser and normal offsite power is being maintained. The licensee has notified the NRC Resident Inspector.

  • * * UPDATE PROVIDED BY JOSH MCGUIRE TO JEFF ROTTON AT 1520 EDT ON 10/17/2014 * * *

An automatic SCRAM occurred at 0251 EDT, moments before operators inserted a manual SCRAM in accordance with station procedures. The licensee notified the NRC Resident Inspector. Notified R1DO (Cook).

ENS 5027011 July 2014 05:17:00Oyster CreekNRC Region 1Manual ScramGE-2Today at approximately 0312 (EDT on 7/11/14), during a planned reactor power ascension with reactor power at approximately 55 percent of rated thermal power, main condenser vacuum began to lower. In accordance with the abnormal operating procedure for degrading vacuum, Operators inserted a manual scram of the reactor at 0314 (EDT). The cause of the degraded vacuum is currently under investigation. All rods inserted into the core and all systems functioned as expected during the scram. No electromatic (EMRVs) or safety relief valves lifted during the transient. This event is reportable within 4 hours per 10CFR50.72(b)(2)(iv)(B) - any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. The scram was uncomplicated, normal offsite power is available, and plant is being cooled down to cold shutdown. The cause of the degraded condenser vacuum is suspected condenser boot degradation. The licensee has informed the NRC Resident Inspector.
ENS 4963314 December 2013 06:57:00Oyster CreekNRC Region 1Manual ScramGE-2Today at approximately 0337 (EST), during quarterly turbine valve testing with reactor power at 100% of rated thermal power, the plant experienced reactor pressure control abnormalities. Reactor pressure rose to 1042 psig (at which point) the Operators inserted a manual SCRAM. The cause of the rise in reactor pressure is currently under investigation. All control rods inserted into the core. Main steam isolation valves remained open, (however), bypass valves did not open as expected. The plant is in its normal electrical lineup and decay heat is being removed via isolation condensers. No electronic (EMRVs) or safety valves lifted during the transient. The plant is currently shutdown and all parameters are stable. This event is reportable within 4 hours per 10CFR50.72(b)(2)(iv)(B) - 'any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' The licensee notified the NRC Resident Inspector and will be notifying the State.
ENS 494146 October 2013 14:26:00Oyster CreekNRC Region 1Manual ScramGE-2Today at approximately 1040 (EDT), during a planned reactor power ascension with reactor power at approximately 20% of rated thermal power, main condenser vacuum began to lower. In accordance with the abnormal operating procedure for degrading vacuum, Operators inserted a manual scram of the reactor at 1130 (EDT). The cause of the degraded vacuum is currently under investigation. All rods inserted into the core and all systems functioned as expected during the scram. No electromatic (EMRVs) or safety relief valves lifted during the transient. The plant is currently shutdown and parameters are stable. The plant is in its normal shutdown electrical lineup and decay heat is being removed via steam bypass valves to the main condenser. This event is reportable within 4 hours per 10CFR50.72(b)(2)(iv)(B) - any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. The licensee has notified the NRC Resident Inspector and will be notifying state authorities.
ENS 494043 October 2013 09:20:00Oyster CreekNRC Region 1Automatic ScramGE-2At 0643 EDT (on 10/03/13), during reactor startup, with the reactor critical and power in the intermediate range, an automatic reactor scram occurred due to an invalid (noise) intermediate range monitor (IRM) scram signal processed on both RPS trip systems. All control rods fully inserted and plant response was as expected. This notification is in accordance with 10CFR50.72(b)(2)(iv)(B). The reactor is currently subcritical. When the reactor scram occurred, reactor power was below the Point of Adding Heat and had minimal effect on the plant. Normal offsite power is being maintained. Decay heat is being maintained via normal shutdown cooling. The Licensee has notified the NRC Resident Inspector.
ENS 4650723 December 2010 16:40:00Oyster CreekNRC Region 1Automatic ScramGE-2At 1407 EST, during reactor startup at a RCS (Reactor Coolant System) pressure of 570 psig and with the turbine off-line, a Low Condenser Vacuum trip signal from both RPS (Reactor Protection System) channels resulted in an automatic reactor scram. All control rods fully inserted and plant response was as expected. This notification is in accordance with 10CFR50.72(b)(2)(iv)(B). The reactor is currently subcritical. The licensee notified the NRC Resident Inspector.
ENS 4502125 April 2009 20:50:00Oyster CreekNRC Region 1Manual ScramGE-2Oyster Creek inserted a manual reactor scram due to a loss of cooling to one of its main transformers. All systems responded normally during the reactor scram. The NRC Resident Inspector has been notified. " The manual scram was described as uncomplicated. All control rods fully inserted. No safeties or PORVs lifted during the transient. There were no electrical power issues besides the problem associated with the main transformer cooling. Normal feedwater cooling was maintained to the reactor and decay heat removal is to the main condenser. There were no ESF actions during the transient. The loss of cooling was to one of Oyster Creeks' two main transformers. Power to the transformer cooling system components (oil cooling pumps and cooling fans) was lost when the control power transformer to the cooling system components failed. The licensee manually scrammed because sustained operation at power would not be possible with loss of cooling to the main transformer and operation with one of the main transformers de-energized is also not possible. The licensee will continue to cold shutdown to perform other maintenance activities while shutdown. The NRC Resident Inspector has been notified.
ENS 4468828 November 2008 23:04:00Oyster CreekNRC Region 1Automatic ScramGE-2

At 98% power, a reactor scram occurred due to a Main Transformer fault. The plant is currently stable in the Hot Shutdown Mode. Isolation Condensers initiated as part of this event are currently in Standby Mode. This event is reportable in accordance with 10CFR50.72(b)(2) and (b)(3) and the Station Reportability Manual section SAF 1.6 and SAF 1.7. The cause of the transformer fault is unknown and under investigation. There was no fire or explosion associated with the fault. All rods inserted during the scram. As a result of the transient, one electromatic relief valve lifted and subsequently reseated. There were no other isolations or safety equipment actuations during the transient. The station electrical system is in its normal shutdown lineup with offsite power available. Decay heat is being removed via the turbine bypass valves to the main condenser. Pressure is currently at 700 psi with water level being maintained at 160" via the main feed system. The licensee has notified the NRC Resident Inspector and will be notifying the State of New Jersey.

  • * * * UPDATE FROM CARL SUCHTING TO JOHN KNOKE AT 0017 EDT ON 11/29/08 * * * *
Notification performed to NJDEP of fish mortality following a reactor scram.  As of this report, one dead bluefish spotted and three distressed bluefish spotted.

Licensee has notified the NRC Resident Inspector. Notified R1DO (Doerflein).

ENS 4385419 December 2007 14:57:00Oyster CreekNRC Region 1Manual ScramGE-2At 1145 hrs. EST, operators inserted a manual reactor scram due to lowering reactor water level after the 'A' main feedwater pump tripped. Prior to the scram, the plant was operating at reduced power due to removing the 'B' main feedwater pump from service for planned maintenance. Reactor water level was at 155" when the scram was initiated and lowered to 100" during the transient. Currently, reactor water level is at the normal operating band and is being maintained by the feedwater system. After the scram, all safety systems functioned as expected. There were no system isolations due to the transient. Electrical power is being provided by normal offsite sources via the startup transformer. Decay heat is being removed via the normal path through bypasses to the main condensers. Additionally, the licensee made an offsite notification to the New Jersey Department of Environmental Protection due to approximately 300 dead or distressed fish in the discharge canal. The licensee has notified the NRC Resident Inspector.
ENS 4349517 July 2007 06:30:00Oyster CreekNRC Region 1Automatic ScramGE-2

An automatic reactor scram occurred at 0522 on 07/17/07 due to a low reactor water level, following a trip of the 'C' Reactor Feed Pump. Reactor water level lowered to the low-low level setpoint and a reactor isolation occurred. Reactor level has been returned to the normal band and a reactor cooldown has been initiated using isolation condensers. The cause of the "C" RFP trip is attributed to an electrical fault as sensed on ground sensing and differential sensing instrumentation. No flames or smoke was observed, however, operators reported an acrid smell of insulation. Following the automatic scram on low reactor water level (138" above top of active fuel (TAF)), level continued to decrease to the low-low setpoint of 86" TAF resulting in a reactor isolation signal. The reactor isolation signal initiates closure of the Main Steam Isolation Valves (MSIVs), trip of the Recirc Pumps and actuation of the Isolation Condensers. Current reactor pressure is 520 psig with a cooldown rate of 82F/hr. The licensee plans to issue a press release and will take the Unit to cold shutdown for repairs. The licensee informed the NRC Resident Inspector.

  • * * UPDATE AT 1000 EDT ON 07/17/07 FROM STEVE FULLER TO S. SANDIN * * *

The following information reported under 10CFR50.72(b)(3)(iv)(A) was provided as an update: The following systems actuated upon receipt of a lo-lo reactor water level signal, subsequent to the reactor scram, reported under EN #43495, which occurred at 0522 on 07/17/07: MSIVs - Isolation Isolation Condensers - Initiation Standby Gas Treatment - Initiation Recirc Pumps - Trip Containment Valves - Isolation Core Spray - Start, but no injection Containment Spray - Manual initiation only, following use of EMRVs to control Rx pressure, causing elevated Torus water temperature. The licensee informed the NRC Resident Inspector. Notified R1DO (Krafty).

  • * * UPDATE AT 1122 EDT ON 7/17/07 FROM STEVE FULLER TO S. SANDIN * * *

The following information reported under 10CFR50.72(b)(2)(xi) was provided as an update: Notified the New Jersey D.E.P. of an unplanned plant shutdown which occurred at 0522 07/17/07. There was no environmental impact from the plant shutdown. This notification is required to be made within 12 hours of an unplanned plant shutdown. The licensee informed the NRC Resident Inspector. Notified R1DO (Krafty).

ENS 425586 May 2006 12:31:00Oyster CreekNRC Region 1Manual ScramGE-2A manual reactor scram was inserted to expedite a reactor shutdown. The reactor was subcritical at the time of the manual scram. All control rods inserted to less than or equal to position 02 as required. The unit entered a forced outage for necessary repairs including replacement of the "B" recirc pump motor. All systems functioned as required for the manual reactor scram. The licensee informed the NRC Resident Inspector.
ENS 4077827 May 2004 01:21:00Oyster CreekNRC Region 1ScramGE-2During a reactor shutdown for scheduled maintenance, a full reactor scram was generated from the Nuclear Instrumentation System. IRMs (Intermediate Range Monitoring detectors) 13, 14 and 18 spiked causing scram signals in both RPS (Reactor Protection Systems). All systems functioned properly post scram, all operator actions were correct. Holding reactor pressure at 900 psig to perform leakage inspection. Following (the leakage) inspection (operations intend) to proceed to cold shutdown. All control rods inserted fully into the core and excess decay heat is currently being diverted to the main condenser, as necessary. The licensee notified the NRC Resident Inspector.
ENS 4009522 August 2003 09:05:00Oyster CreekNRC Region 1Automatic ScramGE-2The licensee reported that an automatic reactor scram occurred at 0259 due to a turbine generator trip from a hi-hi moisture separator water level. One control rod indicated position 02; however, the remainder of the control rods indicated full in. All other systems and components functioned as designed. The licensee is cooling the plant down to cold shutdown. The licensee notified the NRC Resident Inspector.