| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/20/2008 - 05/21/2008 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 44214 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: BOSTON UNIVERSITY
Region: 1
City: BOSTON State: MA
County:
License #: GL - 0671
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: BILL HUFFMAN | Notification Date: 05/15/2008
Notification Time: 09:54 [ET]
Event Date: 03/25/2008
Event Time: [EDT]
Last Update Date: 05/15/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PAUL KROHN (R1)
RON ZELAC (FSME)
| Event Text AGREEMENT STATE - MASSACHUSETTS - LEAKING CS-137 CHECK SOURCE
The State provided the following information via facsimile:
"This facsimile serves as initial notification of an event of a leaking Cs-137 check source found inside a generally licensed device - Beckman Coulter Model 3801 LSC - at Boston University, Boston, MA. The event was reported by Beckman Coulter to the Massachusetts Radiation via letter dated April 25, 2008. The preliminary information of this event [is as follows:]
"On March 25, 2008, a Field Service Engineer (FSE) for Beckman Coulter performed a service call on a Beckman Coulter LS 3801 liquid scintillation counter (LSC) at Boston University in Boston, MA. At the time the service was performed, the FSE discovered an elevated radiation reading inside the LSC. Upon further investigation, the FSE discovered elevated radiation reading originated from a metal base plate used to support lead shielding inside the LSC. A wipe test of this base plate revealed removable contamination of ~ 0.03 microcuries. Upon discovery of the contamination, the FSE immediately notified Beckman Coulter's RSO and Boston University personnel. The contamination was limited to the metal base plate inside the LSC and no personnel were contaminated. Due to the position of the base plate, directly beneath lead shielding, no additional exposure to the user of the LSC would have resulted. The LSC was being decommissioned at the time and it is out of service. The dislodged Cs-137 source (currently 18 microcuries) was recovered from the LSC by the FSE and it is currently being held by Boston University. Beckman Coulter is investigating how the source holder may have been damaged. No contamination was found outside of the LSC, thus no additional decontamination measures were necessary as a result of this event."
MA Report 05 - 7780 |
| Power Reactor | Event Number: 44226 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GLENN SAXON
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/20/2008
Notification Time: 17:40 [ET]
Event Date: 05/20/2008
Event Time: 16:00 [EDT]
Last Update Date: 05/20/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
STEVEN VIAS (R2)
|
| 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 | 98 | Power Operation | 98 | Power Operation | Event Text LOSS OF FUNCTIONALITY TO TECHNICAL SUPPORT CENTER
"A condition is being reported per Technical Requirements Manual 13.13.1 Emergency Response Facilities Action 8.2. The functionality of the Technical Support Center [TSC] has been lost due to the failure of the TSC Chiller to maintain chilled water within the normal control band. Alternate facilities are available to provide emergency response functions and actions are proceeding to return the TSC to FUNCTIONAL status with high priority."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44227 | Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: SUSAN GARDNER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/20/2008
Notification Time: 18:44 [ET]
Event Date: 05/20/2008
Event Time: 13:10 [PDT]
Last Update Date: 05/20/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID PROULX (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 99 | Power Operation | 99 | Power Operation | | 3 | N | Y | 80 | Power Operation | 80 | Power Operation | Event Text OFFSITE POWER GRID DISTURBANCE
"On Tuesday, May 20, 2008, at approximately 1310 PDT, the offsite power grid connected to San Onofre experienced a momentary system disturbance. Control Room indicators alerted Operators that the grid frequency dipped to approximately 59.69 Hz. Because frequency dipped below 59.7 Hz, SCE is reporting this event in accordance with 10CFR50.72(b)(3)(v)(D).
"The frequency dip lasted approximately 10 seconds, reportedly due to a high voltage DC transmission line disturbance in Oregon. The grid is currently operating at nominal frequency.
"At the time of the event, San Onofre Unit 2 was operating in Mode 1 at approximately 99 percent power and Unit 3 was operating in Mode 1 at approximately 80 percent power. The NRC Senior Resident Inspector has been notified of this event and provided a copy of this report." |
| Power Reactor | Event Number: 44228 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: SCOTT LINDQUIST
HQ OPS Officer: PETE SNYDER | Notification Date: 05/21/2008
Notification Time: 02:29 [ET]
Event Date: 05/20/2008
Event Time: 19:56 [CDT]
Last Update Date: 05/21/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
DAVID PROULX (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text DECAY HEAT REMOVAL COOLING INTERUPTED DURING CORE RELOAD
"At 1956, during reactor core reload with a full refueling cavity, power was lost to the #2 non-vital instrument bus. This power loss resulted in closure of the shutdown cooling temperature control valve, HCV-341. The closure of HCV-341 interrupted the cooling capability of the in service shutdown cooling loop.
"While cycling a condenser motor operated valve a 480 volt ground occurred which resulted in tripping the feeder breaker to motor control center MCC-4B2. MCC-4B2 was supplying power to Instrument Bus 2 via the Inverter 2 test transformer. The test transformer was powering Instrument Bus 2 due to Inverter 2 replacement per plant modification. The loss of the #2 Instrument Bus resulted in HCV-341, the shutdown cooling heat exchangers temperature control valve, failing closed. HCV-341 was manually opened to restore cooling at 2019. At 2049 power was restored to Instrument Bus 2 and the shutdown cooling system was returned to automatic operation. Flow through the core was maintained throughout the event, as the shutdown cooling heat exchanger bypass valve responded by opening to maintain flow. At the time shutdown cooling was lost, 44 of 133 assemblies had been loaded into the vessel and shutdown cooling temperature was approximately 88 degrees F. Time to boil was conservatively calculated to be 22.5 hours per plant procedures which assume decay heat from all 133 assemblies. Shutdown cooling temperature rose approximately one degree during this event.
"Technical Specification 2.8.1(3)(1) was entered due to no Shutdown Cooling loop in Operation. No reactor coolant boron reductions were in progress. Irradiated fuel assembly loading into the reactor core was secured and actions to restore a Shutdown Cooling loop were been initiated. [Ft. Calhoun] enter[ed] a 4 hour LCO to close all containment penetrations providing direct access from the containment to the outside atmosphere."
The licensee notified the NRC Resident Inspector. | |