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The query [[Category:ENS Notification]] [[Site::Palisades]] [[Scram::+]] was answered by the SMWSQLStore3 in 0.7660 seconds.


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 Entered dateSiteRegionScramReactor typeEvent description
ENS 538199 January 2019 13:23:00PalisadesNRC Region 3Automatic ScramAt 1034 EST on January 9, 2019, with the reactor at 100% power, an automatic reactor trip was initiated. The trip occurred while Reactor Protection System testing was in progress. The trip was uncomplicated with all systems responding normally following the rip. Troubleshooting and investigation of the cause is ongoing. All full-length control rods inserted fully. Auxiliary Feedwater System actuated as designed in response to low steam generator water levels. Operations stabilized the plant in Mode 3 (hot standby). Decay heat is being removed by the turbine bypass valve. This condition has no impact to the health and safety of the public. The licensee notified the NRC Resident Inspector.
ENS 538133 January 2019 23:57:00PalisadesNRC Region 3Manual ScramAt 2028 (EST) on January 3, 2019, with the reactor at 85% power, the reactor was manually tripped due to cycling of Turbine Governor Valve #4. The trip was uncomplicated with all systems responding normally following the trip. Investigation of the cause of the valve cycling is ongoing. All full-length control rods inserted fully. Auxiliary Feedwater System actuated as designed in response to low steam generator water levels. Operations stabilized the plant in Mode 3 (hot standby). Decay heat is being removed by atmospheric dump valves. This condition has no impact to the health and safety of the public. The licensee notified the NRC Senior Resident Inspector. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
ENS 5139716 September 2015 03:59:00PalisadesNRC Region 3Automatic ScramCEAt 0117 (EDT) on 9/16/2015 a reactor trip occurred (4-hr non-emergency). The plant was at approximately 85% power performing a coastdown in preparation for a refueling outage when a Digital Electro-Hydraulic (DEH) alarm was received in the control room. Shortly following receipt of the alarm the turbine tripped. This resulted in an RPS actuation and a reactor trip on Loss of Load. The crew entered EOP-1 Standard Post Trip Actions and completed all required actions. The crew subsequently entered EOP-2 Reactor Trip Recovery. All full-length control rods inserted fully. Auxiliary Feedwater System actuated in response to low steam generator water levels (8-hr non-emergency). Steam generator water levels are in progress of being returned to normal operating levels. No known primary to secondary leakage. Atmospheric Steam Dump Valves lifted after the trip and subsequently reseated. The plant is currently stable in Mode 3 at NOP/NOT being maintained by the Turbine Bypass Valve. Initial investigation into the cause of the turbine trip appears to be from a DEH power supply failure. The NRC Resident Inspector was notified of the reactor trip at 0139 on 9/16/2015.
ENS 4752314 December 2011 16:40:00PalisadesNRC Region 3Manual ScramCEThe reactor was manually tripped at 1510 EST on 12/14/11 due to loss of both main feedpumps. Both feedpumps tripped on low suction pressure due to an apparent unplanned opening of the 'A' main feedpump recirculation valve. The cause of the main feedpump recirculation valve opening has not been determined. All full length control rods fully inserted. Auxiliary feed pump P-8A automatically started at 1511 EST on steam generator level as designed (10CFR50.72(b)(3)(iv)(A)). The turbine bypass valve is in service maintaining reactor coolant system temperature (by directing steam flow to the main condenser). The plant is stable in mode 3 (and the reactor trip was considered uncomplicated). The Van Buren County Sherriff was notified (per other plant requirements) concerning use of the atmospheric steam dump causing excessive noise in the vicinity of the plant (immediately following the plant trip). The plant electric power is in the normal shutdown configuration. There was no primary to secondary leakage. A press release is planned for the local media. The licensee notified the NRC Resident Inspector.
ENS 473225 October 2011 18:00:00PalisadesNRC Region 3Automatic ScramCEAn Appendix R non-compliance issue was identified. When the plant automatically tripped on September 25, 2011, an unexpected automatic trip was identified in DC shunt trip breakers 72-01 and 72-02. This automatic trip function was not considered in the Appendix R electrical coordination evaluation. Preliminary analysis has shown that if the shunt trip breaker would have automatically opened due to fire induced fault currents, then Appendix R credited equipment may have been lost unexpectedly. The operability evaluation performed, resulted in increasing the shunt trip settings to maximum, and implementing compensatory measures to isolate some non-safety related electrical loads, which restored compliance with 10 CFR 50 Appendix R. The licensee notified the NRC Senior Resident Inspector. CR# PLP2011-04835
ENS 4727116 September 2011 15:04:00PalisadesNRC Region 3Manual ScramCE

The Licensee declared an Unusual Event for Palisades Unit 1 on 09/16/2011 at 1450 EDT based on EAL SU 8.1, RCS (Reactor Coolant System) leakage exceeding 10 gallons per minute (gpm). The licensee was monitoring an increase in RCS leakage, and at a rate of 3.5 gpm entered their off normal procedure and began shutting down the plant. Technical Specification requires the plant to be in Mode 3 within 6 hours. Leakage increased to greater than 10 gpm, and at 1454 EDT the reactor was manually tripped from 79% power. All control rods fully inserted, and the shutdown was described by the licensee as uncomplicated. Unit 1 is stable in Mode 3. No safety injection was required since two charging pumps (B&C) were able to keep up with RCS leakage estimated to be between 14 and 15 gpm. Pressurizer level was restored to 43% and rising. RCS pressure was greater than 2000 psi and RCS temperature was being maintained at no load Tave of 535F on the turbine bypass valves. There is no indication of any primary-to-secondary leakage and all equipment is available except for charging pump 'A', which was tagged out of service for planned maintenance. An entry into containment had been made and the licensee had identified the source of the RCS leakage as being in the vicinity of the 'A' pressurizer spray control valve #1057. This was based on a steam plume seen from below the pressurizer looking up through grating towards this valve. The licensee has notified the NRC Resident Inspector.

* * * UPDATE FROM JAMES BYRD TO JOHN KNOKE AT 1952 EDT ON 09/16/11 * * *

At 1934 EDT the licensee terminated from their Unusual Event due to EAL SU 8.1. The plant is still in Mode 3 with a leak rate of 0.324 gpm..The licensee has confirmed that the leak is a result of the packing gland backing out of pressurizer spray valve #1057. The licensee has notified the NRC Resident Inspector. The R3DO (Bloomer) was notified. Notified FEMA (Eiscoe) and DHS (Flinter).

ENS 4656422 January 2011 18:24:00PalisadesNRC Region 3Automatic ScramCEThe licensee reported a loss of main generator load at full power resulting in a generator trip, turbine trip, and reactor trip. All rods fully inserted. All safety systems functioned as required. The reactor is stable at no-load temperature and pressure in Hot Standby. Auxiliary feedwater started as expected and is currently supplying cooling water to the steam generators. Decay heat is being removed via the atmospheric steam dumps because the turbine bypass system did not respond as expected. There is no known primary to secondary generator leakage The grid is stable and the plant is in a normal post-trip electrical lineup. The reactor trip was characterized as uncomplicated. The cause of the loss of generator load is not yet know and under investigation. The licensee has notified the NRC Resident Inspector. The local County Sheriff was notified of the use of the atmospheric steam dumps to alleviate any concern from local population in the vicinity of the plant.
ENS 4423723 May 2008 16:06:00PalisadesNRC Region 3Automatic ScramCEThe reactor automatically tripped at 1249 EDT on 05/23/08. The cause of the reactor trip signal is not positively known, but it is believed to be related to trip of the 346 negative sequence relay which caused a trip of the 386C generator independent trip (coastdown) lockout relay. All plant systems performed as designed with minor deficiencies noted. EOP-1, 'Standard Post Trip Actions', and EOP-2, 'Reactor Trip Recovery', performed. All control rods fully inserted. All atmospheric steam dump valves lifted and reseated. CV-0780 (B Steam Generator ASDV) was identified as leaking and was manually isolated. There is no known primary to secondary leakage. Auxiliary feedwater system actuated automatically as designed in response to low steam generator water levels. AFW actuation consisted on AFW pump P-8A auto start and AFW valve operation. Steam generator water levels were subsequently restored to normal and are being maintained for primary coolant system heat removal via main steam isolation valves to main condenser (via the turbine bypass valves). Plant is at Normal Operating Pressure (2060 psia) and Temperature (533 degrees F). Grid is stable with safety bus station power being provided from Safeguards transformer. The licensee notified the NRC Resident Inspector.
ENS 4390013 January 2008 09:11:00PalisadesNRC Region 3Manual Scram
Automatic Scram
CEPalisades Operations staff manually tripped the reactor in accordance with their station's Off-Normal Operating Procedure, after an automatic trip of the "B" Main Feedwater Pump (MFP). The cause of the MFP auto-trip is unknown and being investigated. During the trip, all systems performed as designed. During the transient resulting from the trip, the atmospheric steam dump valves did open momentarily and properly reseated. There is no known primary-to-secondary leakage therefore no release was known to have occurred. All control rods inserted fully as a result of the trip. Auxiliary feedwater pump (AFW) 8A started, as expected, in response to low steam generator water levels experienced during the transient and supplied both steam generators. Decay heat is being removed via the main steam isolation valves to the condenser with the 8A AFW pump supplying feedwater to the steam generators. The plant is at normal temperatures and pressures for this mode. The electrical grid is stable with the station start-up transformer supplying station loads. The licensee has notified the NRC Resident Inspector.
ENS 433518 May 2007 15:23:00PalisadesNRC Region 3Automatic ScramCEOn May 8, 2007 at 1322 hours, the reactor automatically tripped from approximately 100% power due to low level in the 'B' Steam Generator. The low level condition resulted from spurious closure of the 'B' feedwater regulating valve. The feedwater regulating valve closure appears related to an instrument and control troubleshooting work activity that was in progress at the time of the event. Investigation into the cause is continuing. In additions an automatic actuation of the auxiliary feedwater system occurred, as designed, to restore steam generator levels. All systems functioned as designed. Decay heat is being removed via steaming through the turbine bypass valve to the main condenser. All control rods fully inserted. The licensee informed the NRC Resident Inspector.
ENS 4256911 May 2006 17:35:00PalisadesNRC Region 3Manual ScramCEFollowing a startup from a refueling outage with the plant at approximately 24% power, it was determined that one control rod appeared to be fully inserted in the core as determined by both incore and excore flux tilts. The Off Normal Procedure for a dropped control rod was entered. The decision was made to take the plant offline to troubleshoot and correct the apparent condition. The Off Normal Procedure does not allow operation in Mode 2 with a dropped control rod. At 1514 hours EDT the reactor was manually tripped from 8% power. The reactor trip was uncomplicated. This is reportable under 10 CFR 50.72(b)(2)(iv)(B) as a manual Reactor Protection System actuation while critical. Decay heat is being discharged to the condenser via the turbine bypass valves and cooling is being supplied from AFW. All systems besides the control rod in question functioned as required. It appears that the control rod in question may have been inserted since startup. The rod position indicators were showing a normal rod position. The licensee believes that the rod may not be coupled. This rod has had a previous history of being difficult to couple. The licensee stated that normal rod testing was conducted prior to startup along with low power physics testing which did not indicate anything significantly out of spec. The licensee notified the NRC Resident Inspector.
ENS 419671 September 2005 11:23:00PalisadesNRC Region 3Manual ScramCEThe Palisades reactor was manually tripped from approximately 100% power at 1025 hours EDT due to a hydrogen leak from main generator. At 1027 hours, an automatic actuation of the auxiliary feedwater system occurred, as designed, to maintain steam generator levels. The atmospheric steam dump valves opened and reseated per design on reactor trip. Reactor decay heat is being removed via steaming through the turbine bypass valve to the main condenser. The source of the hydrogen leak was determined earlier to be a cracked weld that could not be repaired on line. The main generator must be purged in order to repair the weld. This is reportable under 10 CFR 50.72(b)(2)(iv)(B) and (b)(3)(iv)(A). All control rods fully inserted. There are no known Steam Generator tube leaks. The licensee notified the NRC Resident Inspector.
ENS 413199 January 2005 13:42:00PalisadesNRC Region 3Manual ScramCEThe Palisades reactor was manually tripped from approximately 75% power at 1127 hours EST due to lowering main condenser vacuum. Prior to the reactor trip, power was lowered from 100% to 75% in accordance with off-normal procedures in an effort to restore condenser vacuum. The reason for the loss of condenser vacuum is not understood and is being investigated. At 1135 hours an automatic actuation of the auxiliary feedwater system occurred, as designed, to maintain steam generator levels. The atmospheric steam dump valves opened per design on reactor trip, however one dump valve did not fully re-close until instrument air was manually isolated to it. Reactor decay heat is being removed via steaming through the turbine bypass valve to the main condenser. Reportable under 10CFR50.72(b)(2)(iv)(B) and (b)(3)(iv)(A). After the reactor trip, Main Condenser vacuum rose to 25 inches - sufficient for using the Turbine Bypass valves for removing decay heat. All rods inserted on the manual reactor trip. The electric grid is stable. Licensee notified NRC Resident Inspector.
ENS 4100231 August 2004 09:38:00PalisadesNRC Region 3Manual ScramCEAt 0718 EDT, the reactor was manually tripped from approximately 95% power following notification to the control room of a fire associated with condensate pump 2B. Initially, upon notification of smoke at the condensate pump, a rapid down power had been commenced, wherein reactor power was reduced from 100% to approximately 95% power. An automatic actuation of the auxiliary feedwater system also occurred as designed to maintain steam generator water level following the reactor trip. The fire was extinguished in less than 10 minutes. The local fire department was notified, responded to the site as a precautionary measure, but was not used in extinguishing the fire. All systems functioned as designed. The reactor is stable in mode 3. Decay heat is being removed with the steam generators discharging steam to the main condenser. The licensee notified the NRC Resident Inspector.