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Category:Licensee Event Report (LER)
MONTHYEARML22021B5512022-01-21021 January 2022 Compensatory Measures Not Implemented Per Site'S Physical Security Plan Due to Multiplexer (Mux) Power Supply Failure 05000219/LER-2017-0052018-01-0303 January 2018 1 OF 3, LER 17-005-00 for Oyster Creek Nuclear Generating Station Regarding Failure of the Emergency Diesel Generator #2 During Surveillance Testing Due to a Broken Electrical Connector 05000219/LER-2017-0032017-08-31031 August 2017 Automatic Scram while Suberitical due to Low Reactor Level, LER 17-003-00 for Oyster Creek Regarding Automatic Scram while Subcritical due to Low Reactor Level 05000219/LER-2017-0022017-08-31031 August 2017 Manual Reactor Scram due to Degrading Main Condenser Vacuum, LER 17-002-00 for Oyster Creek Regarding Manual Scram due to Degraded Main Condenser Vacuum 05000219/LER-2016-0022017-06-23023 June 2017 Control Rod Drive Cooling Water System Isolation Scram Time Testing Was Not Performed, LER 16-002-01 for Oyster Creek Regarding Control Rod Drive Cooling Water System Isolation Scram Time Testing Was Not Performed 05000219/LER-2017-0012017-05-0303 May 2017 Automatic SCRAM due to APRM High Flux during Turbine Valve Testing, LER 17-001-01 for Oyster Creek, Regarding Transfer of Automatic SCRAM due to APRM High Flux during Turbine Valve Testing ML17129A6032017-05-0303 May 2017 LER 16-S01-01 for Oyster Creek, Regarding Special Nuclear Material Discovered Outside of Material Access Area 05000219/LER-2016-0012017-01-24024 January 2017 1 OF 4, LER 16-001-01 for Oyster Creek Nuclear Generating Station Regarding Failure of the #1 Emergency Diesel Generator During Surveillance Testing due to a Cooling Water System Leak RA-16-107, LER 16-S01-00 for Oyster Creek Nuclear Generating Station Regarding Special Nuclear Material Discovered Outside of Material Access Area2016-12-0505 December 2016 LER 16-S01-00 for Oyster Creek Nuclear Generating Station Regarding Special Nuclear Material Discovered Outside of Material Access Area 05000219/LER-2016-0052016-11-17017 November 2016 Technical Specification Prohibited Condition Caused by One Electromatic Relief Valve Inoperable for Greater than Allowed Outage Time, LER 16-005-00 for Oyster Creek Nuclear Generating Station Regarding Technical Specification Prohibited Condition Caused by One Electromatic Relief Valve Inoperable for Greater than Allowed Outage Time 05000219/LER-2016-0032016-06-29029 June 2016 Manual SCRAM Inserted due to Leakage from the D' Reactor Recirculation Pump Seal, LER 16-003-00 for Oyster Creek, Unit 1, Regarding Manual SCRAM Inserted due to Leakage from the 'D' Reactor Recirculation Pump Seal RA-16-001, Special Report for Inoperability of the Turbine Building High Range Radioactive Noble Gas Monitor2016-01-15015 January 2016 Special Report for Inoperability of the Turbine Building High Range Radioactive Noble Gas Monitor ML1015505702009-08-26026 August 2009 Event Notification for Oyster Creek on Offsite Notification Due to a Water Leak Containing Tritium ML0932006252009-07-24024 July 2009 NRC Operations Center Event Report - Oyster Creek ML1015505672009-04-15015 April 2009 Event Notification for Oyster Creek on Offsite Notification Due to Potential Release of Tritium ML0506107132005-02-16016 February 2005 LER 04-03-001 Oyster Creek, Unit 1, Regarding Actuation of Reactor Protection System Due to Spurious Hi-Hi Trip Signals on Intermediate Range Monitors Caused by Electromagnetic Interference 2022-01-21
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0712412009 U.S. Nuclear Regulatory Commission Operations Center Event Report Paze I Power Reactor Event# 45196 Site: OYSTER CREEK Notification Date / Time: 07/12/2009 02:11 (EDT)
Unit: 1 Region: 1 State: NJ Event Date /Time: 07/12/2009 01:48 (EDT)
Reactor Type: [1] GE-2 Last Modification: 07/13/2009 Containment Type: MARK I NRC Notified by: HERB TRITT Notifications: GLENN DENTEL R1DO HQ Ops Officer: STEVE SANDIN BRIAN HOLIAN NRR EO Emergency Class: UNUSUAL EVENT BILL GOTT IRD 10 CFR Section: SAM COLLINS R1 RA 50.72(a) (1) (i) EMERGENCY DECLARED JIM WIGGINS NRR ET 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICAL AL AUSTIN FEMA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD MIKE INZER DHS 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUATION Unit Scram Code RX Crit Init Power Initial RX Mode Curr Power Current RX Mode 1 A/R Yes 100 Power Operation 0 Hot Shutdown UNUSUAL EVENT DECLARED DUE TO A LOSS OF OFFSITE POWER At 0135 EDT on 07/12 both Startup Transformers "SA" and "SB" were deenergized due to the loss of the 34.5kV power distribution lines (offsite power). The licensee declared an Unusual Event at 0148 EDT based on the loss of power to both transformers for greater than 15 minutes (EAL MU1).
As a result of the loss of offsite power, the Unit automatically scrammed with all control rods fully inserting. Both Emergency Diesel Generators EDG #1 and EDG #2 auto started and are carrying vital loads. The Unit is stable in Hot Shutdown with decay heat removal via the Isolation Condenser. The licensee reported that the transient may be due to a possible lightning strike caused by adverse weather.
The licensee informed the NJ State Police and the NRC Resident Inspector.
- At 0405 EDT on 07/12 the licensee terminated the Unusual Event based on restoration of offsite power and reenergizing both Startup Transformers.
The licensee informed the NJ State Police and the NRC Resident Inspector. Notified R1 (Lew), EO (Holian), IRD (Gott), FEMA (Austin) and DHS (Inzer).
- ** UPDATE AT 0413 EDT ON 07/13/09 FROM CALVIN TAYLOR TO DONALD NORWOOD **
- 07/24/2009 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Pa-ee 2 Power Reactor Event# 45196 Licensee changed one reporting requirement from 50.72(b)(3)(v)(B) to 50.72(b)(3)(iv)(A).
Notified R1 DO (Dentel).