| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/28/2008 - 05/29/2008 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 44239 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MICHAEL MOUSER
HQ OPS Officer: JOE O'HARA | Notification Date: 05/24/2008
Notification Time: 15:06 [ET]
Event Date: 05/24/2008
Event Time: 09:38 [EDT]
Last Update Date: 05/28/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
MEL GRAY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 15 | Power Operation | 15 | Power Operation | Event Text STEAM GENERATOR LEVEL EXCURSION
"On 5/24/2008 at 0938, with Beaver Valley Power Station Unit 2 (BVPS U2) in Mode 1 at 15% power during preparations for turbine startup, the unit experienced a steam generator level excursion. Attempts to manually control steam generator water level were unsuccessful.
"Steam Generator narrow range levels exceeded the setpoint for P-14, Steam Generator Level High High Turbine Trip. The actuation of P-14 automatically actuated the following: trip of the running Main Feedwater pump, closure of the Main and Bypass Feedwater regulating valves, and closure of the Feedwater Containment isolation valves. In addition to these signals, a turbine trip signal is generated but the turbine was not yet on-line.
"The feedwater isolation signal has been reset and normal feedwater flow has been established. Preliminary investigation has revealed that a broken air line caused the 'A' Main Feedwater pump recirculation flow control valve to fail open. This initiated the steam generator level transient. Additional investigation is in progress.
"The trip of the Main Feedwater pumps automatically started both Motor Driven Auxiliary Feedwater pumps (MDAFW). The automatic start of the MDAFW pumps from this valid system actuation is reportable under 10CFR50.72(b)(3)(iv)(A).
"The plant is currently stable in Mode 1 at 15% reactor power." AFW injected into the core.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM MORGAN TO SNYDER ON 5/28/08 * * *
The last sentence of the original report text should read "AFW injected into the Steam Generators" since AFW does not inject into the core. |
| Power Reactor | Event Number: 44244 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WILLIAM J. BAKER
HQ OPS Officer: PETE SNYDER | Notification Date: 05/28/2008
Notification Time: 20:02 [ET]
Event Date: 05/28/2008
Event Time: 16:30 [CDT]
Last Update Date: 05/28/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MALCOLM WIDMANN (R2)
WILLIAM JONES (R4)
WILLIAM GOTT (IRD)
KING STABLEIN (NMSS)
TERRANCE REIS (FSME)
SNOWDEN (DOT-)
ROBERT TURNER (DOE)
MARYANN DOYLE (DHS)
MISS. EMER. MGMT. ()
|
| 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 | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TRANSPORTATION ACCIDENT INVOLVING A RADIOACTIVE MATERIAL SHIPMENT
"On May 28,2008 at 1630 CDT Browns Ferry was informed that a tractor trailer transporting a shipment of radioactive material from Browns Ferry Nuclear Plant (shipment # 080518) was involved in a 2 car traffic accident near Corinth, Mississippi. Local law enforcement responded to the accident. The Mississippi Emergency Management System was notified as well as the Local CMA in Alcorn County, Mississippi. Investigation into the accident concluded that no personnel injuries occurred and there was no damage to the radioactive material shipment container. Presently another tractor is in route to the area to continue transportation of the shipment.
"The licensee notified the NRC Resident Inspector.
"This event is reportable as a 4 hour Non-Emergency Notification report in accordance with 10 CFR 50.72(b)(2)(xi), 'Any event or situation, related to the heath and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.'" |
| Power Reactor | Event Number: 44245 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: TONY MCGOWAN
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/28/2008
Notification Time: 22:03 [ET]
Event Date: 05/28/2008
Event Time: 17:30 [EDT]
Last Update Date: 05/28/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
KENNETH O'BRIEN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HIGH PRESSURE CORE SPRAY INOPERABLE
"On May 28, 2008, at 1730 hours, control room operators determined after testing, that the Emergency Service Water (ESW) Division 3 subsystem was inoperable due to a condition that will not allow the subsystem to maintain 'keep-fill' pressure in the event of a loss of offsite power. Technical Specification (TS) Limiting Condition for Operation (LCO) 3.7.2 requires that the High Pressure Core Spray (HPCS) System (a single train safety system) be declared inoperable immediately when the ESW Division 3 Subsystem is inoperable. The plant immediately entered TS LCO 3.5.1 Condition B, HPCS System inoperable. TS LCO 3.5.1, Required Action B.1, verify by administrative means that the Reactor Core Isolation Cooling System is operable within one hour, was completed at 1730 hours. Required Action B.2 requires that the HPCS System be restored to operable status within 14 days. Maintenance/troubleshooting activities are in progress to determine the cause of the ESW Division 3 Subsystem condition.
"This event is being reported as a condition that could have prevented the safety function of structures or systems required to mitigate the consequences of an accident. The resident inspector has been notified." |
| Power Reactor | Event Number: 44246 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JIM MORELAND
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/29/2008
Notification Time: 02:40 [ET]
Event Date: 05/28/2008
Event Time: 21:34 [MST]
Last Update Date: 05/29/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
WILLIAM JONES (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 0 | Startup | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO IMPROPER MOVEMENT OF CEA'S
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10 CFR 50.73.
"On May 28, 2008, at approximately 2134 Mountain Standard Time (MST) Palo Verde Unit 2 operators manually tripped the reactor, as directed by procedures, when four Control Element Assembly (CEAs 7, 9, 11 &13) of shutdown bank A slipped to the fully inserted position while conducting low power physics testing following Unit 2's fourteenth refueling outage. Unit 2 was critical [Intermediate Range 5.0E-2]and at normal operating temperature and pressure prior to the trip. Following the manual reactor trip all remaining CEAs inserted fully into the reactor core. This was an uncomplicated reactor trip. No emergency classification was required per the Emergency Plan. No automatic ESF actuations occurred and none were required. Safety related buses remained energized during and following the reactor trip. The Emergency Diesel Generators did not start and were not required. The offsite power grid is stable. No LCOs have been entered as a result of this event. No major equipment was inoperable prior to the event that contributed to the event.
"Unit 2 is stable at normal operating temperature and pressure in Mode 3. The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The event did not adversely affect the safe operation of the plant or the health and safety of the public.
"The cause of the slipped CEAs is not known at this time and is under investigation.
"The Senior Resident Inspector was informed of the Unit 2 reactor trip." | |