Event Notification Report for March 06, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/05/2013 - 03/06/2013
Power Reactor
Event Number: 48808
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN GRAHAM
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN GRAHAM
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/06/2013
Notification Time: 11:00 [ET]
Event Date: 03/06/2013
Event Time: 08:45 [EST]
Last Update Date: 03/06/2013
Notification Time: 11:00 [ET]
Event Date: 03/06/2013
Event Time: 08:45 [EST]
Last Update Date: 03/06/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BLAKE WELLING (R1DO)
BLAKE WELLING (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
OFFSITE NOTIFICATION DUE TO OIL SHEEN ON HUDSON RIVER
"Indian Point 3 is in Mode 5. At approximately 0845 [EST] on 3/6/2013, an oil sheen was observed in the discharge canal and Hudson River. Minor volume of oil is unknown at this time. The source of oil was from an overflowing barrel associated with a waste oil skimmer in the turbine building. Source of oil has been secured. There is no adverse impact on the plant. Notifications to New York State Department of Environmental Conservation, Westchester County Department of Health and U.S. Coast Guard National Response Center have been completed.
"NRC Resident Inspector has been informed."
"Indian Point 3 is in Mode 5. At approximately 0845 [EST] on 3/6/2013, an oil sheen was observed in the discharge canal and Hudson River. Minor volume of oil is unknown at this time. The source of oil was from an overflowing barrel associated with a waste oil skimmer in the turbine building. Source of oil has been secured. There is no adverse impact on the plant. Notifications to New York State Department of Environmental Conservation, Westchester County Department of Health and U.S. Coast Guard National Response Center have been completed.
"NRC Resident Inspector has been informed."
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 48809
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JACK EARSLEY
HQ OPS Officer: VINCE KLCO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JACK EARSLEY
HQ OPS Officer: VINCE KLCO
Notification Date: 03/06/2013
Notification Time: 12:52 [ET]
Event Date: 03/06/2013
Event Time: 04:01 [CST]
Last Update Date: 04/11/2013
Notification Time: 12:52 [ET]
Event Date: 03/06/2013
Event Time: 04:01 [CST]
Last Update Date: 04/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
NICK VALOS (R3DO)
NICK VALOS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
MOMENTARY LOSS OF SHUTDOWN COOLING
"At 0401 CST on 3/6/2013, while in RHR-High [Residual Heat Removal-High] water level the plant experienced a momentary Loss of Shutdown Cooling which resulted in a loss of safety function for Residual Heat Capability. Division 2 RHR shutdown cooling was restored within approximately 90 seconds without issue. No changes were experienced in refuel volume temperature or level during the loss of RHR shutdown cooling. This occurred shortly after a flow adjustment on the system was made utilizing the outboard valve. The inboard valve was reopened and an investigation is in progress. At the time of the valve closure, decay heat removal continued from Reactor Water Cleanup in heat reject mode and fuel pool cooling (with the fuel pool gates removed) is in service. Division 1 RHR (Shutdown Cooling) was available (not Operable) at the time of the loss. It is not currently understood why the injection valve closed. All systems functioned as required except for the spurious closing of MO-2015 (the Div 2 RHR inboard injection valve). The following make-up sources are available: Divisions 1 and 2 RHR, Divisions 1 and 2 Core Spray, CRD [Control Rod Drive], CST [Condensate Storage Tank] via a Core Spray with pressurizing station bypassed."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION AT 1419 EDT ON 4/11/2013 FROM RYAN RICHARDS TO MARK ABRAMOVITZ * * *
"On March 6, 2013 (Notification No. 48809) NSPM [Northern States Power Monticello] reported in accordance with 10 CFR 50.72 (b)(3)(v)(B), a momentary closure of valve MO-2015 in the operating Residual Heat Removal (RHR) subsystem as an event or condition that at the time of discovery could have prevented the fulfillment of a safety function. Following the event, the RHR SDC [shut down cooling] subsystem was removed from operation for equipment forensics and troubleshooting. Results validated that valve MO-2015 was operable and no issues were identified with the associated electrical circuitry, or the RHR SDC subsystem. The decay heat removal requirements of LCO 3.9.7, RHR - High Water Level, were met and there was not a loss of safety function. Therefore, NSPM retracts the March 6, 2013 notification for this event."
The licensee notified the NRC Resident Inspector, state and local authorities, and may make a press release.
Notified the R3DO (Passehl).
"At 0401 CST on 3/6/2013, while in RHR-High [Residual Heat Removal-High] water level the plant experienced a momentary Loss of Shutdown Cooling which resulted in a loss of safety function for Residual Heat Capability. Division 2 RHR shutdown cooling was restored within approximately 90 seconds without issue. No changes were experienced in refuel volume temperature or level during the loss of RHR shutdown cooling. This occurred shortly after a flow adjustment on the system was made utilizing the outboard valve. The inboard valve was reopened and an investigation is in progress. At the time of the valve closure, decay heat removal continued from Reactor Water Cleanup in heat reject mode and fuel pool cooling (with the fuel pool gates removed) is in service. Division 1 RHR (Shutdown Cooling) was available (not Operable) at the time of the loss. It is not currently understood why the injection valve closed. All systems functioned as required except for the spurious closing of MO-2015 (the Div 2 RHR inboard injection valve). The following make-up sources are available: Divisions 1 and 2 RHR, Divisions 1 and 2 Core Spray, CRD [Control Rod Drive], CST [Condensate Storage Tank] via a Core Spray with pressurizing station bypassed."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION AT 1419 EDT ON 4/11/2013 FROM RYAN RICHARDS TO MARK ABRAMOVITZ * * *
"On March 6, 2013 (Notification No. 48809) NSPM [Northern States Power Monticello] reported in accordance with 10 CFR 50.72 (b)(3)(v)(B), a momentary closure of valve MO-2015 in the operating Residual Heat Removal (RHR) subsystem as an event or condition that at the time of discovery could have prevented the fulfillment of a safety function. Following the event, the RHR SDC [shut down cooling] subsystem was removed from operation for equipment forensics and troubleshooting. Results validated that valve MO-2015 was operable and no issues were identified with the associated electrical circuitry, or the RHR SDC subsystem. The decay heat removal requirements of LCO 3.9.7, RHR - High Water Level, were met and there was not a loss of safety function. Therefore, NSPM retracts the March 6, 2013 notification for this event."
The licensee notified the NRC Resident Inspector, state and local authorities, and may make a press release.
Notified the R3DO (Passehl).
Agreement State
Event Number: 48825
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: ARENA PHARMACEUTICAL
Region: 4
City: SAN DIEGO State: CA
County:
License #: 6434-37
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: DONG HWA PARK
Licensee: ARENA PHARMACEUTICAL
Region: 4
City: SAN DIEGO State: CA
County:
License #: 6434-37
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/15/2013
Notification Time: 20:43 [ET]
Event Date: 03/06/2013
Event Time: 00:00 [PDT]
Last Update Date: 03/15/2013
Notification Time: 20:43 [ET]
Event Date: 03/06/2013
Event Time: 00:00 [PDT]
Last Update Date: 03/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DALE POWERS (R4DO)
FSME EVENTS RESOURCE (EMAI)
DALE POWERS (R4DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - DAMAGED TRITIUM EXIT SIGN
The following information was received from the California Radiologic Health Branch via e-mail:
"[The Radiation Safety Officer] RSO reported that a tritium exit sign (approximately 20 Ci of H-3) was broken when a forklift hit the sign on 3/6/13. The forklift driver did not report the damaged sign to the RSO until 3/13/13. Initial wipe surveys showed contamination up to 130,000 dpm. The area is not routinely occupied and, since being reported, access has been restricted. The forklift is also secured. A consultant will be used to decontaminate the area and the forklift. A urine sample was collected of the forklift driver on 3/14/13."
California Report 031513
The following information was received from the California Radiologic Health Branch via e-mail:
"[The Radiation Safety Officer] RSO reported that a tritium exit sign (approximately 20 Ci of H-3) was broken when a forklift hit the sign on 3/6/13. The forklift driver did not report the damaged sign to the RSO until 3/13/13. Initial wipe surveys showed contamination up to 130,000 dpm. The area is not routinely occupied and, since being reported, access has been restricted. The forklift is also secured. A consultant will be used to decontaminate the area and the forklift. A urine sample was collected of the forklift driver on 3/14/13."
California Report 031513