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 Entered dateSiteRegionScramReactor typeEvent description
ENS 5417519 July 2019 13:05:00VogtleNRC Region 2Automatic ScramAt 0945 (EDT) on July 19, 2019, with Unit 2 in Mode 1 and 100 percent power, the reactor automatically tripped due to Loop 2 'B' Main Steam Isolation Valve failing shut. The Auxiliary Feedwater system (AFW) started automatically as a result of the automatic reactor trip. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Due to the valid AFW actuation from the reactor trip, this event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A). Unit 1 was not affected. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspectors have been notified. All control rods fully inserted.
ENS 5396731 March 2019 00:17:00VogtleNRC Region 2Manual ScramAt 2130 (EDT) on March 30, 2019, with Unit 2 in Mode 1 at 30 percent reactor power, the reactor was manually tripped due to a main steam isolation valve failing closed. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser. The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A). Unit 1 was not affected. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspectors have been notified."
ENS 536434 October 2018 07:57:00VogtleNRC Region 2Manual Scram

EN Revision Text: MANUAL REACTOR TRIP DURING LOW POWER PHYSICS TESTING At 0544 EDT on October 4, 2018, with Unit 1 in Mode 2 with reactor power in the intermediate range performing low power physics testing, the reactor was manually tripped due to a rod control urgent failure alarm. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam system. Unit 2 was not affected. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspectors have been notified. All control rods inserted as expected. The cause of the rod control urgent failure is being investigated.

  • * * UPDATE FROM KEVIN LOWE TO DONALD NORWOOD AT 1408 EDT ON 10/19/2018 * * *

This Event Notification is being updated to clarify that the reactor was not critical when this event occurred. Therefore, the reporting requirement is changed from 10 CFR 50.72(b)(2)(iv)(B) to 10 CFR 50.72 (b)(3)(iv)(A). During Dynamic Rod Worth Measurement testing, Control Bank Charlie was inserted approximately 153 steps when the urgent failure occurred (CBC positioned at 75 steps out). Following the scram, additional analysis concluded that the reactor was subcritical when the Reactor Protection System was actuated." The licensee notified the NRC Resident Inspector. Notified the R2DO (McCoy).

ENS 534843 July 2018 12:00:00VogtleNRC Region 2Manual ScramAt 0954 (EDT) on July 3, 2018, with Unit 1 in Mode 1 at 100 percent power, the reactor was manually tripped due to high steam generator water level. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser. The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A). Unit 2 was not affected. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspectors have been notified. All control rods inserted and Unit 1 is in an electrical shutdown lineup. The cause of the high steam generator water level transient is being investigated.
ENS 525343 February 2017 18:56:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopAt 1545 EST on 2/3/17, Vogtle Unit 1 was manually tripped from 100% power when loop 1 Main Steam Isolation Valve (MSIV) started to fail closed. Non-Safety Related 4160V bus 1NA01 failed to transfer to alternate incoming power supply automatically and was successfully manually energized. All control rods fully inserted and AFW (Auxiliary Feedwater) and FWI (Feedwater Isolation) actuated as expected. Unit 1 is in Mode 3 and stable with decay heat being removed by AFW. The licensee informed the NRC Resident Inspector.
ENS 5195625 May 2016 04:54:00VogtleNRC Region 2Automatic ScramWestinghouse PWR 4-LoopAt 0206 EDT 5/25/16, Vogtle Unit 2 tripped from 100% when SG (Steam Generator) #1 Level began to lower for an unknown reason. Cause for level issue is under investigation. All control rods fully inserted and AFW (Auxiliary Feedwater) and FWI (Feedwater Isolation) actuated as expected. Unit 2 is in Mode 3 and stable with decay heat being removed by Aux Feedwater. Prior to the trip, I & C (Instrumentation & Calibration) was performing a loop #1 narrow range instrument calibration. Unit 2 is in a normal post trip electrical lineup with all source of offsite power available. The licensee informed the NRC Resident Inspector.
ENS 5089314 March 2015 08:07:00VogtleNRC Region 2Automatic ScramWestinghouse PWR 4-LoopVogtle Unit 2 was operating in Mode 1 at 100% rated thermal power. At 0429 EDT a Unit 2 automatic Reactor Trip and Safety Injection / Steamline Isolation occurred. All systems operated as expected and all control rods fully inserted. The Safety Injection was terminated at 0447 EDT and the emergency operating procedures were exited at 0522 EDT. Unit 2 is stable in Mode 3 with decay heat removal via the Auxiliary Feedwater system and the atmospheric relief valves. A response team is investigating the cause of the event. Unit 1 was unaffected by the event. NRC Senior Resident Inspector was notified and is at plant site for investigation.
ENS 5052612 October 2014 12:41:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopVEGP (Vogtle Electric Generating Plant) Unit 2 was performing startup and had taken reactor critical at 0929 EDT. When attempting to stabilize power to collect critical data, control rods were inserted with Control Bank D the expected group to insert. Control Bank A inserted instead of Control Bank D. Power had reached 6 E-2 percent as indicated by IR (intermediate range) indication when control room crew performed a manual reactor trip. AFW (auxiliary feed water) was in service to support plant conditions prior to the trip and did not receive any actuation signal. All equipment operated as expected. Unit 2 is currently stable in Mode 3 at normal operating temperature and pressure. The licensee has notified the NRC Resident Inspector.
ENS 5031427 July 2014 15:22:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopVEGP (Vogtle Electric Generation Plant) Unit One was at 100 percent power, with a Main Feed Pump (MFP) Turbine A trip mechanism test in-progress, when MFP A Trip alarm was received in the Main Control Room. Control Room crew identified MFP A speed and steam generator levels lowering and initiated a manual reactor trip. All control rods fully inserted and nothing unusual was noted. Auxiliary feed water and feedwater isolation actuated as expected. The unit is currently stable in MODE 3 at normal operating temperature and pressure. A forced outage response team has been formed to determine the cause of the MFP A trip and determine restart criteria and time of restart. The unit is in a normal shutdown electric plant lineup. No effect on Unit 2. The licensee notified the NRC Resident Inspector.
ENS 5003112 April 2014 23:20:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopAt 2008 EDT, Vogtle Unit One was manually tripped in response to loop 1 outboard Main Steam Isolation Valve failing shut. All systems operated correctly in response to the reactor trip. All control rods fully inserted. System response allowed for an uncomplicated reactor trip response. Unit 1 is stable in Mode 3 and cause investigation is in progress. The NRC Senior Resident Inspector was notified. There was a normal post trip feedwater isolation due to low Tave. Offsite power remains available. Decay heat is being removed by the main condenser. The plant is stable in Mode 3. There was no impact on Unit 2.
ENS 500068 April 2014 05:21:00VogtleNRC Region 2Automatic ScramWestinghouse PWR 4-LoopVEGP Unit 2 was at 100% power, normal activities, when digital feedwater trouble alarms were received on all 4 steam generators (SG) with level stable in all generators. Operating crew entered abnormal operating procedure for feedwater malfunction when SG #3 level began rapidly lowering. Operators attempted to take manual control of SG #3 main feedwater regulating valve and were unable to raise SG #3 level. SG #3 level lowered to the Lo-Lo Level setpoint causing an automatic reactor trip. All control rods fully inserted and SG #3 level remained off scale low on narrow range indications. Auxiliary feedwater and feedwater isolation actuated as expected. (Unit 2) is currently stable in Mode 3 at normal operating temperature and pressure. A forced outage response team has been formed to determine the cause of the low SG water level and determine restart criteria and time of restart. All control rods fully inserted on the trip. Decay heat is being removed via auxiliary feedwater to steam generators steaming to the condenser steam dumps. The licensee has notified the NRC Resident Inspector.
ENS 4946122 October 2013 13:18:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopAt 1144 EDT, Vogtle Unit Two was manually tripped in response to lowering Main Condenser vacuum. The Unit 2 Bravo Main Feed Pump was tagged out for scheduled maintenance and the casing was being removed when condenser vacuum started lower due to isolation valve not holding pressure. Main Condenser vacuum lowered to less than procedural limits for continued plant operation. All systems operated correctly in response to the reactor trip. All control rods fully inserted. AFW was placed in service to control Steam Generator levels. System response allowed for an uncomplicated reactor trip response. Plant is stable in Mode 3 while performing a cause investigation. The NRC Senior Resident Inspector was notified and at plant site. The plant is in a normal post-trip electrical line-up. Decay heat is being removed via the steam dumps to the Main Condenser.
ENS 4945319 October 2013 09:36:00VogtleNRC Region 2Automatic ScramWestinghouse PWR 4-LoopVEGP (Vogtle Electric Generating Plant) unit two was at 100% power, normal activities, when the unit two turbine tripped causing an automatic reactor trip. All control rods fully inserted and nothing unusual was noted. Auxiliary feed water and feedwater isolation actuated as expected. The unit is currently stable in Mode 3 at normal operating temperature and pressure. A forced outage response team has been formed to determine the cause of the turbine trip and determine restart criteria and time of restart. During the transient, no relief valves lifted. The electrical grid is stable and supplying plant safety loads. Decay heat is being removed via steam dumps to the condenser. The licensee has notified the NRC Resident Inspector.
ENS 4878827 February 2013 02:07:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopAt 2302 EST, Vogtle Unit Two was manually tripped in response to excessive Reactor Coolant Pump #4, seal #1 leakoff flow. Seal leakoff flow exceeded the procedural limits for continued operation of the pump. Following the reactor trip, RCP #4 was shutdown per procedure guidance. All systems operated correctly in response to the reactor trip. All control rods fully inserted. The Auxiliary Feed Water (AFW) system automatically actuated as expected. System responses allowed for an uncomplicated reactor trip response. The plant is stable in Mode 3 during cause investigation. The NRC Senior Resident was notified and is enroute to the plant for investigation. AFW is supplying the steam generators and decay heat removal is to the condenser via steam dumps. No safety valves or relief valves lifted during the transient. The unit is in a normal post-trip electrical line-up. There was no impact on Unit One.
ENS 4783614 April 2012 16:12:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopAt 1346 EDT, Vogtle Unit 1 reactor was manually tripped from 100% power due to Main Feedwater Pump 'B' discharge flow lowering unexpectedly. All control rods fully inserted. AFW system automatically actuated as expected. System responses allowed for an uncomplicated reactor trip response. Plant is stable in Mode 3 during cause investigation. The electrical lineup remained normal. No safety valves lifted due to the trip. Decay heat is being removed via the steam dumps to the main condenser. The licensee has notified the NRC Resident Inspectors.
ENS 4722431 August 2011 12:02:00VogtleNRC Region 2Automatic ScramWestinghouse PWR 4-LoopWhile preparing Loop 2 Main Feed Reg Valve (MFRV) for maintenance, it was placed on its 'air gag' that maintained the MFRV in position, while any small changes in feed flow would be modulated by the associated Bypass Feed Reg Valve (BFRV). Approximately 5 minutes after the MFRV was placed on the air gag, with Steam Generator (S/G) level stable, control room operators observed S/G level start to increase. The operators observed for a short time to see if the associated BFRV would control the level change. When it became apparent that level was not being controlled automatically, the operators took manual control of the BFRV, eventually closing it all the way, and observed that S/G level was then increasing very slowly. While level was still slowly rising, two hi-hi level bistables actuated, generating a P-14 (hi-hi S/G level trip) signal which tripped the main turbine, which then caused an automatic reactor trip. As a result of the reactor trip, all systems functioned as required and there was nothing unusual or not understood. During the transient, no safeties, primary relief valves or secondary relief valves lifted. All control rods inserted into the core. Auxiliary Feed Water automatically initiated and is supplying the steam generators. Decay heat is being removed via the steam dumps to condenser. The grid is stable with all safety buses powered from offsite power via a normal shutdown electrical lineup. Unit 2 was unaffected by the trip. The licensee will be issuing a press release. The NRC Resident Inspector has been notified.
ENS 4558823 December 2009 17:18:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopAt 1525 EST, Vogtle Unit 2 was manually tripped from 100% power due to a loss of instrument air to the turbine building. System operators were releasing a tagout and restoring one of two instrument air dryers that had been isolated for maintenance. Instrument air low pressure alarms were received in the control room and secondary side valves were responding to the loss of instrument air. Control room operators responded according to procedures. Main feed pump 'B' tripped on a loss of suction pressure and operators manually tripped the reactor. The reactor was manually tripped in anticipation of a loss of feed water to the steam generators. All systems responded as required. AFW (Auxiliary Feed Water) actuated as required for loss of feed water. All control rods fully inserted on the reactor trip. Instrument air has been restored to the turbine building and steam dumps are controlling RCS temperatures. Cause of the loss of instrument air is being investigated. (The NRC) Senior Resident (Inspector) was notified.
ENS 4555710 December 2009 01:38:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopAt 2310 EST, Vogtle Unit 1 was manually tripped from 24% reactor power while the main turbine was rolling at 1800 rpm, preparing for synchronization to the grid. As Vogtle 1 was preparing to bring the Unit 1 generator on line following a forced outage, high vibration levels were experienced on the HP turbine bearings while the Turbine was at rated speed and synchronization preparations were in progress. The Turbine was manually tripped in accordance with plant procedures. Vibrations continued to increase as the Turbine began to coast down, warranting that vacuum be broken in accordance with procedures. The reactor was manually tripped in anticipation of trip of the main feedwater pump (due to loss of condenser vacuum) and condenser vacuum was broken to slow the turbine. When condenser vacuum was broken, the in-service Main Feedwater Pump auto tripped as expected, causing an automatic actuation of the Motor Driven Auxiliary Feedwater system. The cause of high vibrations on the Turbine is being investigated. All systems responded as expected on the trip. All control rods fully inserted into the core following the reactor trip. Atmospheric relief valves are being used to remove decay heat. There is no known primary to secondary leakage. The plant is in a normal post-trip electrical line-up. The licensee notified the NRC Resident Inspector.
ENS 455477 December 2009 20:07:00VogtleNRC Region 2Automatic ScramWestinghouse PWR 4-LoopVogtle Unit 1 tripped from 100% power due to a (turbine trip/ reactor trip) RPS (reactor protection system) actuation. The turbine tripped due to low condenser vacuum. Initial investigation indicates that a loss of a non-1E electrical switchgear initiated the event. All systems responded as expected. The AFW (auxiliary feedwater) systems responded as required. Reactor temperature (and decay heat removal) is being maintained on SG (steam generator) ARVs (atmospheric relief valves). Both NRC Resident Inspectors were notified of the trip. There were no complications. All rods inserted during the trip and there was no primary to secondary leakage. There was no impact on Unit 2.
ENS 4331323 April 2007 11:25:00VogtleNRC Region 2Automatic ScramWestinghouse PWR 4-LoopVogtle Unit 2 tripped from 53% power due to a turbine trip /P9 reactor trip RPS actuation during power ascension following completion of refueling outage 2R12. Initial investigation indicates that a generator neutral ground relay actuated causing an automatic main generator turbine trip. No visual damage is apparent on any plant equipment. All systems responded as expected. Both motor driven auxiliary feedwater pumps and the turbine driven started on lo-lo steam generator level and AMSAC. The NRC Resident Inspector was notified. All control rods fully inserted upon RPS actuation, the atmospheric relief valves lifted momentarily and reseated as expected, and no safety valves lifted. After the trip, steam generator level was being maintained with auxiliary feed pumps and steam was being dumped to the condenser. The plant was placed in the normal shutdown electrical lineup.
ENS 4280627 August 2006 09:20:00VogtleNRC Region 2Automatic ScramWestinghouse PWR 4-LoopOn Sunday, August 27, 2006 at 0631 EDST, Unit Two was at 99.7% RTP when RCP #4 tripped generating a Low Flow Reactor Trip. All systems functioned as required. AFWAS (Aux Feedwater Actuation Signal) was actuated as expected due to lo-lo Steam Generators levels. RCS Letdown isolated on a momentary low level signal on one channel of Pressurizer level, and has since been restored. The reactor is currently stable in Mode 3 while the cause of the trip of the RCP is investigated. Decay heat is being rejected to the condenser via the steam dumps. ESF systems remain operable and the electrical grid is stable. The licensee notified the NRC Resident Inspector.
ENS 4250617 April 2006 01:20:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopUnit 1 reactor was manually tripped from 33% RTP due to the Loop 3 Main Feed Regulating Valve (MFRV) 1LV-0530 not controlling steam generator level in manual or AUTO. A unit shutdown was in progress at the time of the trip due to concerns with the Loop 3 MFRV. The unit shutdown had commenced from 100% power on 04/16/2006 at 1603 hrs. All systems functioned as required on the reactor trip including a feedwater isolation and the Loop 3 MFRV closing as expected. The unit is presently in Mode 3 at normal operating temperature and pressure. An investigation team is being assembled concerning the Loop 3 MFRV. All control rods fully inserted. No primary or secondary reliefs/safeties lifted during the transient. Unit 1 is currently in Mode 3 Hot Standby controlling Steam Generator Water Level using Auxiliary Feedwater supplied by both Motor Driven and the Steam Driven pumps. Decay Heat is being removed via the Bypass Valves to the Main Condenser. Offsite power is stable and all EDGs are available, if necessary. The licensee informed the NRC Resident Inspector.
ENS 4205817 October 2005 19:18:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopAt 1816 EDT on 10/17/2005 Vogtle Unit 1 was manually tripped from 100% power due to lowering Steam Generator level on Loop 2. The Main Feedwater Regulating Valve for Loop 2 failed closed and operator attempts to re-open it were unsuccessful. The operators initiated a manual reactor trip when it was apparent that Steam Generator level would not be restored. Following the manual reactor trip, an automatic actuation of the Motor Driven and Turbine Driven Auxiliary Feedwater Pumps occurred due to low level in the Steam Generators. The Main Feedwater Regulating Valve for Loop 1 did not close as expected for the feedwater isolation signal (P-4 / Tavg 564 degrees F) that resulted from the manual trip. The Loop 1 Main Feedwater Regulating Valve was manually closed by the operators. All control rods are fully inserted. This incident did not affect Unit 2. Unit 1 is stable in Mode 3 and removing heat by dumping steam to the condensers. All safety related systems or equipment are available and functioning as required. The licensee notified the NRC Resident Inspector.
ENS 4165330 April 2005 00:00:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopAt 2155 EDT on 4/29/2005, Vogtle Unit 1 was manually tripped from 100% power due to lowering steam generator level on loop #1. The main feedwater regulating valve was in manual control and a repair plan was in progress to replace a controlling card which failed earlier in the day. The manual reactor trip caused an automatic aux. feedwater actuation of the motor driven and turbine driven feedwater pumps. All other equipment responded as expected on the trip. At approximately 1600, the loop #1 main feed regulating valve had failed shut while in the automatic mode of operation. The operator shifted control to manual and opened the valve, preventing a reactor trip. At 2155 the recovery plan was being implemented using a plant procedure. While performing the procedure, the loop #1 feed regulating valve shut. The reactor was manually tripped on lowering steam generator level. All rods fully inserted after the manual reactor trip. Decay heat removal is to the main condenser with steam generator level being maintained using the motor driven aux. feedwater pumps. The plant is in its normal shutdown electrical lineup. The licensee notified the NRC Resident Inspector.
ENS 4132311 January 2005 09:20:00VogtleNRC Region 2Automatic ScramWestinghouse PWR 4-LoopAt 0719 EST, Vogtle Unit 1 tripped from 100% power due to a Turbine Trip/P9 Reactor Trip, RPS actuation. Initial investigation indicates that Generator relaying was involved. The investigation is ongoing. As expected for the trip, both Motor Driven Auxiliary Feedwater pumps and the Turbine Driven pump started on Lo-Lo Steam Generator level and AMSAC. All equipment actuated as expected except the Group A Pressurizer Heaters tripped. Technical Specification 3.4.9 Condition B was entered. All control rods fully inserted. Decay heat is being removed via the steam dumps to the main condenser. The electrical grid is stable. The licensee notified the NRC Resident Inspectors.
ENS 4121320 November 2004 14:56:00VogtleNRC Region 2Automatic ScramWestinghouse PWR 4-LoopOn 11/20/2004 at 1140 EST during the performance of 14421-2 'Solid State Protection System And Reactor Trip Breaker Train B Operability Test' an automatic Reactor Trip occurred and a Safety Injection occurred a short time thereafter. The Reactor Trip was caused by an error made in the performance of the 14421-2 procedure. The operator working with a peer checker mistakenly placed the 'A' train multiplexer test switch in the 'A + B' position instead of the 'B' train one. The 'B' train multiplexer test switch was still in the inhibit position. When the 'A' Train multiplexer switch went through the inhibit position, it caused the second general warning which tripped the reactor. The Safety Injection is believed to have been caused by a failure of the loop 2 Reactor Coolant Average Temperature which impacted the Steam Dump control system. The Steam Dumps did not close as expected during the Reactor Trip response and Pressurizer pressure lowered below the Safety Injection System setpoint and a Safety Injection was actuated. All systems operated as expected during the Safety Injection and Reactor Trip. All the Control Rods fully inserted on the Reactor Trip. The Main Steam Lines were isolated by the operator due to the lower than expected decrease of the Reactor Coolant System Average Temperature. Both Motor Driven AFW pumps started as expected as did the Turbine Driven AFW pump. All ECCS pumps started as expected on the Safety Injection. The Containment Coolers all started in low speed on the Safety Injection as expected. Both Diesel Generators started on the Safety Injection actuation. The Containment Isolation systems isolated containment as expected. During the recovery from the Safety Injection pressurizer level did reach 100%, but the Pressurizer PORVs were not required to open to control Pressurizer pressure. Unit 2 is currently stable in mode 3 removing decay heat via the Atmospheric Steam Dumps. The licensee informed the NRC Resident Inspector.
ENS 4061528 March 2004 00:30:00VogtleNRC Region 2Manual ScramWestinghouse PWR 4-LoopOn 3/27/2004, the Unit 1 Reactor was manually tripped when the 1B Main Feedwater Pump speed could not be controlled in automatic or manual. An unexpected increase in Main Feedwater Pump speed was observed which increased the Main Feedwater header pressure to higher than expected values. An attempt was made to manually control the speed of the 1B Main Feedwater Pump from the various controllers in the Main Control Room. Preparations to start the 1A Main Feedwater Pump were initiated. The speed of the 1B Main Feedwater Pump continued to increase to a point where level control of the Steam Generators and overspeed of the 1B Main Feedwater Pump became a concern. At this point the Reactor was manually tripped and the 1B Main Feedwater Pump was tripped. An Auxiliary Feedwater System automatic actuation occurred on the trip a the 1B Main Feedwater Pump as expected because the 1A Main Feedwater Pump was also tripped at the time due to being at a low power level. All systems responded as expected on the Reactor Trip. The plant is currently stable in Mode 3. An Event Review Team will be performing a review of the event and making recommendations related to restarting the Reactor. All control rods fully inserted. Decay heat is being removed using the steam dumps and auxiliary feedwater. Plant pressure is 2235 psig and temperature is 557 degrees F. The licensee notified the NRC Resident Inspector.