| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/20/2009 - 04/21/2009 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 44999 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MIKE HIMEBAUCH
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/19/2009
Notification Time: 23:38 [ET]
Event Date: 04/19/2009
Event Time: 23:15 [EDT]
Last Update Date: 04/20/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
LAURA KOZAK (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text SAFETY PARAMETER DISPLAY SYSTEM AND EMERGENCY RESPONSE DATA SYSTEM OUT OF SERVICE FOR PLANNED MAINTENANCE
"On 4/19/09 at 2315 EDT, Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service to support activities for a planned maintenance outage on the UPS vital bus power supply. The duration of work is expected to be approximately 24 hours. During this time, the majority of the Control Room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems, if needed. The plant is currently in Mode 5, and will remain in Mode 5, for the duration of the SPDS and ERDS unavailability. Since the unavailability will last greater than 8 hours, this is considered a Loss of Emergency Assessment Capability, and reportable under 10CFR50.72(b)(3)(xiii).
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM MIKE HIMEBAUCH TO HOWIE CROUCH ON 4/20/09 @ 2301 EDT * * *
"Update to Event #44999 regarding SPDS and ERDS being removed from service to support planned maintenance on the UPS vital bus power supply. Maintenance is complete, and SPDS and ERDS were returned to service on 4/20/09 at 2230 EDT. The NRC Resident Inspector has been notified."
Notified R3DO (Cameron). |
| Power Reactor | Event Number: 45000 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: GEORGE E. STOROLIS
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/20/2009
Notification Time: 05:09 [ET]
Event Date: 04/20/2009
Event Time: 01:15 [EDT]
Last Update Date: 04/20/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RAY POWELL (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text AUXILIARY FEEDWATER ACTUATION ON VALID STEAM GENERATOR HI-HI SIGNAL DURING SHUTDOWN
"On April 20,2009 at 0115 during Beaver Valley Power Station Unit 1 shutdown and cooldown in support of the 19th refueling outage, Unit 1 experienced an Engineered Safety Feature (ESF) actuation P-14 due to Steam Generator (SG) HI-HI water level in the 'B' Steam Generator. This ESF actuation initiated automatic actions resulting in full feedwater isolation, trip of the only operating 'B' main feed and the start of two Auxiliary Feedwater System pumps. The unplanned automatic initiation of the Auxiliary Feedwater system [was] due to the Main Feedwater pump trip. The P-14 automatic ESF features properly closed the main and bypass feedwater regulating valves and [caused the] closure of the Feedwater Containment Isolation valves. A turbine trip signal was generated but the turbine was not on-line. The automatic start of the MDAFW pumps from this valid signal is reportable under 10CFR50.72(b)(3)(iv)(A).
"The cause of the steam generator high level transient is the failure of the FCV-1FW-489, 'B' steam generator feed water bypass level control to automatically maintain level. Attempts to control the level manually were not successful. Additional investigation is in progress.
"P-14 ESF actuation reset actions are being performed. Unit one cooldown continues using the MDAFW pumps and controls. AFW continues to be injected into the steam generators.
"The licensee notified the NRC resident Inspector." |
| Power Reactor | Event Number: 45001 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: GEORGE E. STOROLIS
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/20/2009
Notification Time: 05:09 [ET]
Event Date: 04/20/2009
Event Time: 01:53 [EDT]
Last Update Date: 04/20/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RAY POWELL (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text UNEXPECTED START OF THE STEAM DRIVEN AUXILIARY FEEDWATER PUMP DURING PLANT COOLDOWN
"On 4/20/09 at 0153 hours, while in Mode 3 performing a plant cooldown for a refueling outage, a control room operator noted that the 'B' train steam supply (TV-1MS-105B) to the steam driven auxiliary feedwater pump, FW-P-2, was open. This caused the steam driven auxiliary feedwater pump to start and inject auxiliary feedwater into the steam generators. This was an unexpected condition. The start of the FW-P-2 auxiliary turbine driven feedwater pump is reportable under 10CFR50.72(b)(3)(iv)(A).
"At 0209, TV-1MS-105B was closed. The steam driven auxiliary feedwater pump was declared inoperable and Technical Specification action statements were entered. Technical Specification 3.7.5 Condition B requires the pump to be restored to operable status within 72 hours or be in Mode 4 within the following 18 hours.
"Mode 4 was entered on 4/20/09 at 0347 hours. The steam drive auxiliary feedwater pump is not required to be operable in Mode 4. Technical Specification 3.7.5 Condition B was exited on 4/20/09 at 0347.
"Investigation is in progress to determine the cause of TV-1MS-105B opening.
"The licensee notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 45002 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN OSBORNE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/20/2009
Notification Time: 15:43 [ET]
Event Date: 04/20/2009
Event Time: 12:50 [EDT]
Last Update Date: 04/20/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
PAUL KROHN (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text INADVERTENT ACTUATION OF ONE AUTOMATIC NOTIFICATION SYSTEM SIREN
"At approximately 1242 on April 20, 2009, three New Jersey Emergency Planning Zone (EPZ) Alert Notification System sirens went into AC power failure. This caused an automatic swap of the power supply from an AC source to a back up DC battery source. When this auto swap occurred, the Salem County 9-1-1 Center received an alarm which the dispatcher acknowledged. Sirens 127 and 114 were successfully acknowledged but when the dispatcher went to acknowledge Siren 128 he inadvertently selected 'alert with report' at 12:50:34 which when selected, initiated the siren. An ANS Services technician immediately received notification of the siren system actuation and called the Salem County 9-1-1 Center to provide direction to cancel the actuation. The siren actuation was cancelled at 12:52:21. Salem County officials notified the Lower Alloways Creek (LAC) Public Safety director and the New Jersey State Police (NJSP). The NJSP was notifying the NJ Regional Operation Intelligence Center (ROIC), LAC Police, and making a courtesy call to the LAC elementary school which is located in the vicinity of the siren. This event is being reported to NRC in accordance with the requirements of 10CFR50.72(b)(2)(xi)."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45003 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By:
HQ OPS Officer: KARL DIEDERICH | Notification Date: 04/20/2009
Notification Time: 17:02 [ET]
Event Date: 04/20/2009
Event Time: 12:08 [EDT]
Last Update Date: 04/20/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
MALCOLM WIDMANN (R2)
TIM McGINTY (NRR)
BRIAN McDERMOTT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Refueling | 0 | Refueling | Event Text INJURED PERSON TRANSPORTED OFF SITE WITH CLOTHING CONTAMINATION
"At 1208 on 4/20/2009, the control room was notified of an injured person inside the Unit 3 Containment. It was immediately reported that this person fell about 4 feet off of the Reactor Head (while the Reactor Head was on the head stand) and potentially had head/back trauma. At 1210, Miami Metro Dade Fire and Rescue (911) was called. At 1218, Medical and Safety personnel arrived in containment and began preparation to transport the individual outside of containment. At 1225, Metro Dade Fire and Rescue arrived on site. At 1240, the individual was transported outside of containment via the equipment hatch. At 1253, FPL Radiation Protection reported to the control room that due to the individual's injuries and the difficulty in completing a full frisk, the individual would be transported offsite as a potentially contaminated-injured person. At 1255, security contacted the control room and stated that Metro Dade Fire and Rescue received the individual and began transport offsite to Baptist Hospital, Miami, Florida. At 1408,an FPL Radiation Protection representative that traveled to Baptist Hospital reported that the individual's clothing (protected clothing and modesty garments) was contaminated at 200 corrected cps > background. No skin contamination was found. An FPL Radiation Protection representative at Baptist Hospital took physical control of all material brought to the hospital from the site and are transporting all material back to site."
The ambulance, other equipment, people, and structures with whom the contaminated individual and his clothing made contact between the containment control point and the hospital were surveyed, showed no contamination, and released. The individual was an FPL employee, and was staging equipment at a work site.
The licensee has notified the NRC Resident Inspector. | |