| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/17/2010 - 05/18/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45923 | Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: THE OHIO STATE UNIVERSITY
Region: 3
City: COLUMBUS State: OH
County:
License #: 02110250037
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: VINCE KLCO | Notification Date: 05/13/2010
Notification Time: 16:04 [ET]
Event Date: 05/11/2010
Event Time: [EDT]
Last Update Date: 05/13/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARK RING (R3DO)
KEITH McCONNELL (FSME)
| Event Text AGREEMENT STATE REPORT - REPORT OF LEAKING SEALED SOURCE
The following information was received by e-mail:
"On Tuesday May 11, 2010, the licensee discovered during a routine leak test that a Ni-63 source in a Shimadzu GC-14A gas chromatograph was leaking, presenting 0.0142 microCi. The source was identified as an NRD model N-100, serial number 616355, with an original activity of 9.98 mCi on 3/23/03 and a current activity of 9.50 mCi.
"A second leak test confirmed that this was not a false positive. Surveys of the instrument and area presented no evidence that contamination had spread.
"The device containing the Ni-63 source was removed from service and taken to the licensee's radioactive waste storage facility."
Ohio Report: OH100006 |
| Power Reactor | Event Number: 45931 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: BOB KASTNER
HQ OPS Officer: JOE O'HARA | Notification Date: 05/17/2010
Notification Time: 12:27 [ET]
Event Date: 05/17/2010
Event Time: 10:17 [EDT]
Last Update Date: 05/17/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
MARIE MILLER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | A/R | Y | 17 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO LOW STEAM GENERATOR WATER LEVEL
"System Affected: RPS actuation and reactor trip. Actuation Initiation Signals: AFW auto initiation. Cause: Low level 'C' steam generator. Effect of event on Plant: Reactor and turbine trip. Actions taken or Planned: Standard post trip actions. Additional information: Plant stabilized at NOP/NOT."
The licensee experienced a feedwater transient which initiated the event. All safety systems are available. All control rods fully inserted. The electrical lineup is normal. The decay heat path is through the condenser steam dumps. There were no relief valve or safety valve lifted during the transient. Primary plant temperature is 555 degrees Fahrenheit, and primary plant pressure is 2250 psig. The licensee is investigating the cause of the feed transient.
The licensee notified the NRC Resident Inspector, the Waterford Dispatch, and the State Department of Environmental Protection, | |