| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/01/2009 - 05/04/2009 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 44984 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: ROBERT MATUSZAK
HQ OPS Officer: DONALD NORWOOD | Notification Date: 04/11/2009
Notification Time: 14:27 [ET]
Event Date: 04/11/2009
Event Time: 12:10 [EDT]
Last Update Date: 05/01/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ROBERT DALEY (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 LOSS OF EMERGENCY ASSESSMENT CAPABILITY - TECHNICAL SUPPORT CENTER VENTILATION UNAVAILABLE
"Notified by Engineering that Technical Support Center (TSC) emergency charcoal sample failed acceptance criteria. Declared TSC ventilation unavailable at 12:10 PM EDT, 4/11/09. TSC ventilation supports RERP radiological habitability function and as such represents a major loss of emergency assessment capability, offsite response capability, or offsite communications capability in accordance with 10CFR50.72(b)(3)(xiii). Notified all Shift Managers if an emergency event is declared (Alert or higher), Shift Managers will need to modify emergency call out service so that TSC staffing report to Emergency Operating Facility (EOF). The use of the EOF as a backup facility for the TSC is included in Fermi's RERP Plan. Fermi will notify the NRC upon completion of corrective maintenance."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM ROBERT MATUSZAK TO DONALD NORWOOD ON 5/1/09 AT 1621 EDT * * *
"Regarding Technical Support Center (TSC) ventilation unavailability: Corrective maintenance to restore HVAC system has been completed satisfactorily. TSC has been restored as an Emergency Response facility."
The TSC was declared operable at 1457 EDT. Corrective maintenance included replacing the out-of-spec charcoal filters and satisfactory follow-up tests.
The licensee notified the NRC Resident Inspector. Notified R3DO (Hills). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 45035 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JIM KONRAD
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/30/2009
Notification Time: 17:39 [ET]
Event Date: 04/30/2009
Event Time: 10:39 [EDT]
Last Update Date: 05/01/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID HILLS (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 10 | Startup | 0 | Startup | Event Text HPCI DECLARED INOPERABLE DUE TO FAILURE OF TEST LINE PRESSURE CONTROL VALVE DURING SURVEILLANCE TEST
"During plant startup on 4/29/09 at 2239 [EDT], the startup had progressed to the point where plant conditions were adequate to allow performance of SR 3.5.1.9, High Pressure Coolant Injection (HPCI) System flow testing against system head corresponding to reactor pressure. A Note to SR 3.5.1.9 allows 12 hours to perform this test after adequate reactor steam dome pressure and flow have been established for test performance.
"During the test performance, the test line pressure control valve did not properly operate to establish the required system head. The HPCI system was shutdown and returned to Standby. Earlier, on 4/29/09, SR 3.5.1.10, low pressure HPCI flow testing was successfully completed. Troubleshooting of the test line pressure control valve was begun.
"At 1039 [EDT] on 4/30/09, the 12 hour allowance of the Note to SR 4.5.1.9 expired and the HPCI system was declared inoperable for failure to complete the required surveillance. The HPCI system remains in Standby and is configured to perform its safety function.
"However, this event represents a potential loss of a single train safety system pending repair of the test line pressure control valve and completion of flow testing."
With HPCI inoperable, the Unit is in the 14-day Tech. Spec. Action Statement 3.5.1. The licensee is revising their surveillance procedure to allow for manual operation of the failed control valve and estimates that the required testing will be completed within 4 hours. The Unit will remain in Mode 2 pending completion of this test.
The licensee informed the NRC Resident Inspector.
* * * RETRACTION PROVIDED BY D. DUNCAN TO JASON KOZAL 05/01/09 AT 1128 * * *
"High Pressure Coolant Injection (HPCI) Surveillance Requirement 3.5.1.9, HPCI system flow testing against system head corresponding to reactor pressure, was satisfactorily completed and HPCI declared OPERABLE May 1, 2009 at 0221 hours. There was no loss of HPCl safety function. Therefore this event is retracted."
Notified R3DO (Hills). |
| Power Reactor | Event Number: 45036 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: COLE EHRHARDT
HQ OPS Officer: JOE O'HARA | Notification Date: 05/02/2009
Notification Time: 08:18 [ET]
Event Date: 05/02/2009
Event Time: 00:02 [CDT]
Last Update Date: 05/02/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
WAYNE WALKER (R4DO)
|
| 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 EMERGENCY OPERATIONS FACILITY POWER INTERRUPTION
"The Emergency Operations Facility lost power due to a fault on the site power loop. The licensee has not been able to restore power to the facility. The emergency generator also failed to operate.
"This call is required due to not being able to promptly restore the facility in the event of an accident as noted in NUREG 1022 Section 3.2.13. Maintenance is ongoing.
"The backup EOF is available and the EOF team will be notified."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45038 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: CRYSTAL GARBE
HQ OPS Officer: STEVE SANDIN | Notification Date: 05/03/2009
Notification Time: 14:32 [ET]
Event Date: 05/03/2009
Event Time: 07:45 [CDT]
Last Update Date: 05/03/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
WAYNE WALKER (R4DO)
|
| 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 LOSS OF EOF COMMUNICATION CAPABILITY DUE TO EQUIPMENT FAILURE
"At approximately 0745 [CDT] it was determined that the ANO telephone system communications for outgoing and incoming calls had been lost. An ENS phone check was performed satisfactory with the NRC. Two alternate dedicated outside lines located in the Control Rooms and five alternate NRC lines in the TSC were operating satisfactory.
"However, when E-plan personnel evaluated the EOF located in the nearby training center, there was only one outside line that was functioning and in addition to a lack of external phone lines, there was no internal phone communications available between the EOF and the plant. The impairment to the EOF due to the lack of communications was considered a major loss of emergency assessment capability per 50.72(b)(3)(xiii).
"Phone service to the site was returned at 1031 [CDT]. Phone service to the EOF was verified at 1145 [CDT]."
This event was the result of an offsite power outage on 05/02/09. Following the loss of power, the onsite telephone equipment transferred automatically to battery supplied backup power. When the affected offsite power was restored, the telephone equipment power supply failed to automatically realign (auto transfer). No alarms were available to operators to detect the power supply misalignment.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45039 | Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: ARNIE CRIB
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/03/2009
Notification Time: 18:29 [ET]
Event Date: 05/03/2009
Event Time: 03:10 [EDT]
Last Update Date: 05/03/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
RESPONSE-BULLETIN
| Person (Organization):
MIKE ERNSTES (R2DO)
|
| 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 24-HOUR NRC BULLETIN 80-24 REPORT DUE TO POSSIBLE SERVICE WATER SYSTEM LEAKAGE INTO CONTAINMENT
"V.C. Summer Nuclear Station is notifying the NRC in accordance with NRC Bulletin 80-24, regarding Service Water System leakage into containment.
"At approximately 0310 on 05/03/09, Reactor Building sump sample analyses, in response to increasing sump level, indicated a probable leak from the Industrial Cooling Water System at 0.38 gpm.
"In accordance with Bulletin 80-24, a 14 day written report will be submitted."
The licensee is continuing to monitor at this time. A corrective action plan to definitively identify where the leak is coming from will be developed.
The licensee notified the NRC Resident Inspector. The licensee plans on notifying State of South Carolina and the counties of Fairfield, Richland, Lexington, and Newberry EP representatives. | |