| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/15/2011 - 11/16/2011 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 47441 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: MIKE STODICK
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/15/2011
Notification Time: 20:54 [ET]
Event Date: 11/05/2011
Event Time: 12:30 [PST]
Last Update Date: 11/15/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BLAIR SPITZBERG (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text MAJOR LOSS OF EMERGENCY PREPAREDNESS CAPABILITY DUE TO NETWORK ISOLATION DEVICE FAILURE
"At 12:30 PDT on 11-5-2011, a network isolation device failed, resulting in interruption of the feed of plant data to emergency response facilities as well as loss of Emergency Response Data System (ERDS) transmission capabilities. At approximately 05:00 PST on 11-6-11, actions were initiated to reboot the system and capability was restored at 06:30 PST on 11-6-11. On 11-15-11, the time of the original device failure was identified and it was determined the total outage time was approximately 19 hours (including accounting for the change from daylight to standard time). It was further concluded this represents a major loss of emergency preparedness capability. Emergency assessment equipment in the control room was available throughout the event."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47442 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [ ] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: GARY GAESSER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/15/2011
Notification Time: 22:19 [ET]
Event Date: 11/15/2011
Event Time: 19:52 [EST]
Last Update Date: 11/15/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JOHN CARUSO (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HIGH PRESSURE COOLANT INJECTION STEAM SUPPLY VALVE CABLE UNPROTECTED DURING POSTULATED FIRE
"On 11/15/2011 at 1952 [EST], while performing a Fire Protection Program review, it was determined that one of the 'Multiple Spurious Operation' (MSO) modifications implemented during the P3R18 refueling outage adversely impacted Peach Bottom's fire safe shutdown analysis conclusions. New cabling that was routed for the Unit 3 High Pressure Coolant Injection (HPCI) system steam supply valve lacks appropriate fire barrier protection in the event of a postulated fire-induced damage to this cable. This cable is routed through a fire area in which the only credited and protected method of reactor level control for a fire in this area is HPCI. Postulated fire-induced damage in the cable could prevent the steam supply valve from opening, thereby causing the HPCI pump to be unavailable for an Appendix R fire. An hourly fire watch has been established as a compensatory action."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47443 | Facility: DAVIS-BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: TOM COBBLEDICK
HQ OPS Officer: JOHN KNOKE | Notification Date: 11/16/2011
Notification Time: 03:04 [ET]
Event Date: 11/16/2011
Event Time: 02:22 [EST]
Last Update Date: 11/16/2011 | Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
DAVID HILLS (R3DO)
JANE MARSHALL (IRD)
CINDY PEDERSON (RA)
BRUCE BOGER (ET)
JENNIFIER UHLE (DRA)
MICHAEL INZER (DHS)
DAVID BARDON (FEMA)
DANIEL GUNN (DOE)
ART WOOD (USDA)
DANIEL CONNALLY (HHS)
|
| 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 ALERT DUE TO FIRE IN ELECTRICAL BUS AFFECTING SAFETY RELATED EQUIPMENT
At 0222 EST on November 16, 2011, an ALERT was declared due to an electrical fire in the auxiliary building which houses safety related equipment. The apparent cause of the fire was due to an unknown source of water leaking on a breaker, thus causing an arc. The electrical fire is out. The plant was at 0% power and will remain shutdown in Mode 5. There was no impact on core cooling, or emergency power supplies.
The licensee has notified the NRC Resident Inspector and state and local agencies.
* * * UPDATE FROM JANE MALLERNEE TO JOHN KNOKE AT 0449 EST ON 11/16/11 * * *
At 0443 EST on November 16, 2011, Davis Besse, Unit 1 exited their ALERT. The electrical short affected the Control Room Emergency Ventilation Fan #1 Damper.
The licensee has notified the NRC Resident Inspector. Notified R3DO (Hills) and Canada Nuclear Safety Commission (Jim Sandlef). |
| Power Reactor | Event Number: 47444 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVID FASHCHER
HQ OPS Officer: JOHN KNOKE | Notification Date: 11/16/2011
Notification Time: 03:33 [ET]
Event Date: 11/16/2011
Event Time: 03:01 [EST]
Last Update Date: 11/16/2011 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
STEVEN VIAS (R2DO)
JANE MARSHALL (IRD)
VICTOR MCCREE (RA)
BRUCE BOGER (NRR)
MICHAEL INZER (DHS)
DAVID BARDON (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 7 | Power Operation | 0 | Hot Shutdown | Event Text UNUSUAL EVENT DUE TO DRYWELL LEAKAGE GREATER THAN 10 GPM
"On 11/16111 at 0208 EST, Brunswick Nuclear Plant, Unit 2 calculated a drywall floor drain 42 minute leak rate of 5.88 gpm, following several hours of gradually rising floor drain leakage during a plant startup. Tech Spec 3.4.4 A was entered. requiring floor drain leakage to be restored below 5 gpm within 8 hours. At 0253 EST, a 45 minute leak rate of 10.11 gpm was calculated. At 0301 EST, Unusual Event SU 6.1 was declared for unidentified leakage exceeding 10 gpm, and at 0309 EST, a manual reactor scram was inserted from approximately 7% power [10 CFR 50.72(b)(2)(iv)(B)]. Following the scram, the reactor was depressurized at a maximum cooldown rate of 92.5 deg F/hr, and the unidentified leak rate fell less than 10 gpm within 1 hour and less than 5 gpm within 2 hours. Leak rate at 0614 EST on 11/16/11 is 3.82 gpm with reactor pressure at 228 psig.
"The exact nature of the leak is unknown at this time. The current plan is to continue to depressurize and cool down the reactor to Mode 4, such that a full drywall inspection can commence. At present, Brunswick has not terminated the Unusual Event."
Level control is currently being maintained with control rod drives (CRD). The MSIVs were manually closed to control cooldown. The maximum cooldown was observed to be 92.5 F/hour. The plant plans to reopen MISIVs and depressurized to condensate booster pump injection pressure of 350 psig. The plan is to achieve Mode 4 for a leak inspection.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM DAVID FASHCHER TO CHARLES TEAL AT 0550 EST ON 11/16/11 * * *
The leakage rate is currently 3.73 gpm. The decrease is due to lower pressure which is currently at 258 psig. There are no additional changes. The leakage source is not identified at this time. The licensee has notified the NRC Resident Inspector.
Notified R2DO (Vias).
* * * UPDATE FROM DUSTIN LUPTON TO JOHN SHOEMAKER AT 0648 EST ON 11/16/11 * * *
The leakage rate is currently below the T.S. limit due to lower pressure which is currently at 210 psig. There are no additional changes. The plant will remain in an Unusual Event (UE) until further notice. The licensee has notified the NRC Resident Inspector.
Notified R2DO (Vias).
* * * UPDATE FROM DUSTIN LUPTON TO CHARLES TEAL AT 0749 EST ON 11/16/11 * * *
The leakage rate is stable. The leak rate is calculated at 3.04 gpm at 183 psig at 0708 EST. The current reactor pressure is 162 psig. The licensee has notified the NRC Resident Inspector.
Notified R2DO (Vias).
* * * UPDATE FROM DUSTIN LUPTON TO JOHN KNOKE AT 0832 EST ON 11/16/11 * * *
The licensee terminated from their Unusual Event at 0815 EST. The leakage is still unidentified.
The licensee has notified the NRC Resident Inspector.
Notified R2DO (Vias). | |