Event Notification Report for May 11, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/10/2012 - 05/11/2012
EVENT NUMBERS
47919479174792547915
Power Reactor
Event Number: 47919
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RON FRY
HQ OPS Officer: DONG HWA PARK
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RON FRY
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/11/2012
Notification Time: 21:27 [ET]
Event Date: 05/11/2012
Event Time: 16:03 [EDT]
Last Update Date: 05/11/2012
Notification Time: 21:27 [ET]
Event Date: 05/11/2012
Event Time: 16:03 [EDT]
Last Update Date: 05/11/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
PAMELA HENDERSON (R1DO)
PAMELA HENDERSON (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF CONTROL ROOM FLOOR COOLING
"At 16:03 hours on 5/11/12, Susquehanna Steam Electric Station Unit 2 entered LCO 3.0.3 due to two control room floor cooling systems being inoperable.
"A discharge damper for the 'A' train of control room floor cooling had failed earlier during the same day at 05:23 hours, rendering the associated 'A' fan inoperable. The redundant 'B' train fans and associated Control Structure Chiller automatically started as a result of a fan low flow interlock. The 'A' train logic was left in 'Start' and the 'B' train logic was left in 'Auto' as directed by an alarm response procedure.
"During application of a clearance order for repair of the failed 'A' fan damper, the 'A' control room cooling fan switch was placed in 'Stop' position. This resulted in an automatic start of the 'A' Control Structure Chiller and all the associated 'A' fans except for the control room cooling fan, and a trip of the 'B' train fans and chiller. This condition caused a loss of both control room cooling fans.
"The control room operators immediately recognized the loss of cooling and took manual action to restart the 'B' train.
"LCO 3.0.3 was exited at 16:18 hours without a reactor power reduction. This condition is reportable as loss of entire safety function under 10CFR50.72(b)(3)(v) & (vi)."
The licensee has notified the NRC Resident Inspector.
"At 16:03 hours on 5/11/12, Susquehanna Steam Electric Station Unit 2 entered LCO 3.0.3 due to two control room floor cooling systems being inoperable.
"A discharge damper for the 'A' train of control room floor cooling had failed earlier during the same day at 05:23 hours, rendering the associated 'A' fan inoperable. The redundant 'B' train fans and associated Control Structure Chiller automatically started as a result of a fan low flow interlock. The 'A' train logic was left in 'Start' and the 'B' train logic was left in 'Auto' as directed by an alarm response procedure.
"During application of a clearance order for repair of the failed 'A' fan damper, the 'A' control room cooling fan switch was placed in 'Stop' position. This resulted in an automatic start of the 'A' Control Structure Chiller and all the associated 'A' fans except for the control room cooling fan, and a trip of the 'B' train fans and chiller. This condition caused a loss of both control room cooling fans.
"The control room operators immediately recognized the loss of cooling and took manual action to restart the 'B' train.
"LCO 3.0.3 was exited at 16:18 hours without a reactor power reduction. This condition is reportable as loss of entire safety function under 10CFR50.72(b)(3)(v) & (vi)."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 47917
Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: ROBERT DUARTE
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: ROBERT DUARTE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/11/2012
Notification Time: 09:20 [ET]
Event Date: 05/11/2012
Event Time: 05:15 [EDT]
Last Update Date: 05/11/2012
Notification Time: 09:20 [ET]
Event Date: 05/11/2012
Event Time: 05:15 [EDT]
Last Update Date: 05/11/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
PAMELA HENDERSON (R1DO)
PAMELA HENDERSON (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 85 | Power Operation | 85 | Power Operation |
BRIEF LOSS OF THE EMERGENCY NOTIFICATION SYSTEM PHONE
"At approximately 0515 EDT today, Seabrook experienced a brief loss of the Emergency Notification System (ENS). The ENS was inoperable for approximately four minutes due to an unknown cause. During this time, commercial telephone lines were available as a means of communication with the NRC. A subsequent communications check using the ENS phone was satisfactory.
"This event is being reported as an eight-hour notification in accordance with 10CFR50.72(b)(3)(xiii) for a loss of offsite ENS communications capability. Investigation into the cause continues and will be documented via the corrective action process."
The licensee has notified the NRC Resident Inspector.
"At approximately 0515 EDT today, Seabrook experienced a brief loss of the Emergency Notification System (ENS). The ENS was inoperable for approximately four minutes due to an unknown cause. During this time, commercial telephone lines were available as a means of communication with the NRC. A subsequent communications check using the ENS phone was satisfactory.
"This event is being reported as an eight-hour notification in accordance with 10CFR50.72(b)(3)(xiii) for a loss of offsite ENS communications capability. Investigation into the cause continues and will be documented via the corrective action process."
The licensee has notified the NRC Resident Inspector.
Agreement State
Event Number: 47925
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: BUDINGER AND ASSOCIATES
Region: 4
City: SPOKANE State: WA
County:
License #: I0139
Agreement: Y
Docket:
NRC Notified By: BRANDY KETTER
HQ OPS Officer: PETE SNYDER
Licensee: BUDINGER AND ASSOCIATES
Region: 4
City: SPOKANE State: WA
County:
License #: I0139
Agreement: Y
Docket:
NRC Notified By: BRANDY KETTER
HQ OPS Officer: PETE SNYDER
Notification Date: 05/16/2012
Notification Time: 17:45 [ET]
Event Date: 05/11/2012
Event Time: 00:00 [PDT]
Last Update Date: 05/16/2012
Notification Time: 17:45 [ET]
Event Date: 05/11/2012
Event Time: 00:00 [PDT]
Last Update Date: 05/16/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DALE POWERS (R4DO)
ANGELA MCINTOSH (FSME)
DALE POWERS (R4DO)
ANGELA MCINTOSH (FSME)
AGREEMENT STATE REPORT - FRONT END LOADER RAN OVER A PORTABLE NUCLEAR GAUGE
The following information was received from the State of Washington via email:
On 5/11/2012 a front end loader ran over a Troxler moisture density gauge. The gauge contained a 0.37 GBq Cs-137 source and a 1.85 GBq Am-241 source.
The cause was identified as inattention to detail.
WA Item: WA12034
The following information was received from the State of Washington via email:
On 5/11/2012 a front end loader ran over a Troxler moisture density gauge. The gauge contained a 0.37 GBq Cs-137 source and a 1.85 GBq Am-241 source.
The cause was identified as inattention to detail.
WA Item: WA12034
Power Reactor
Event Number: 47915
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: TIM KUDO
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: TIM KUDO
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/11/2012
Notification Time: 07:07 [ET]
Event Date: 05/11/2012
Event Time: 03:55 [EDT]
Last Update Date: 05/11/2012
Notification Time: 07:07 [ET]
Event Date: 05/11/2012
Event Time: 03:55 [EDT]
Last Update Date: 05/11/2012
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
SCOTT FREEMAN (R2DO)
SCOTT FREEMAN (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 99 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO FEEDWATER CONTROL VALVE FAILURE
"On May 11, 2012, a failure of the High Power Feed Regulating Valve FCV-9011 resulted in '2A' S/G water level lowering. Manual operator control of the Main Feed Regulating system was unsuccessful in stabilizing S/G water level. '2A' S/G level lowered to the procedurally required manual reactor trip criteria. The crew inserted a manual trip. All CEAs fully inserted into the core. Following the trip, Auxiliary Feedwater actuated as designed and decay heat removal was via Auxiliary Feedwater and Steam Bypass to the Main Condenser. All equipment operated as expected. Currently, Unit 2 is maintaining pressurizer pressure at 2250 psia, temperature at 532 degrees F on Main Feedwater (using Low Power Feed Regulating Valves LCV-9005/9006) and Steam Bypass Control.
'Unit 1 was unaffected and remains in Mode 1 at 29% power.
"This event is reportable pursuant to 10CFR50.72(b)(2)(iv)(B) for the Reactor Trip, as well as 10CFR50.72(b)(3)(iv)(A) for specified system actuation (Auxiliary Feedwater)."
The licensee has notified the NRC Resident Inspector.
"On May 11, 2012, a failure of the High Power Feed Regulating Valve FCV-9011 resulted in '2A' S/G water level lowering. Manual operator control of the Main Feed Regulating system was unsuccessful in stabilizing S/G water level. '2A' S/G level lowered to the procedurally required manual reactor trip criteria. The crew inserted a manual trip. All CEAs fully inserted into the core. Following the trip, Auxiliary Feedwater actuated as designed and decay heat removal was via Auxiliary Feedwater and Steam Bypass to the Main Condenser. All equipment operated as expected. Currently, Unit 2 is maintaining pressurizer pressure at 2250 psia, temperature at 532 degrees F on Main Feedwater (using Low Power Feed Regulating Valves LCV-9005/9006) and Steam Bypass Control.
'Unit 1 was unaffected and remains in Mode 1 at 29% power.
"This event is reportable pursuant to 10CFR50.72(b)(2)(iv)(B) for the Reactor Trip, as well as 10CFR50.72(b)(3)(iv)(A) for specified system actuation (Auxiliary Feedwater)."
The licensee has notified the NRC Resident Inspector.