Event Notification Report for March 04, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/03/2014 - 03/04/2014
EVENT NUMBERS
49867498684986949870498714987249931
Power Reactor
Event Number: 49867
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DOUGLAS LaMARCA
HQ OPS Officer: STEVE SANDIN
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DOUGLAS LaMARCA
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/04/2014
Notification Time: 01:50 [ET]
Event Date: 03/04/2014
Event Time: 00:25 [EST]
Last Update Date: 03/04/2014
Notification Time: 01:50 [ET]
Event Date: 03/04/2014
Event Time: 00:25 [EST]
Last Update Date: 03/04/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
FRED BOWER (R1DO)
FRED BOWER (R1DO)
| 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 | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
SECONDARY CONTAINMENT DECLARED INOPERABLE DURING SURVEILLANCE TESTING
"On March 4, 2014 at 0025 EST, Secondary Containment drawdown testing surveillance failed to meet acceptance criteria of SR 3.6.4.1.5 due to maximum flow rate exceeding the allowable value. Secondary Containment drawdown testing was being performed on Reactor Building Zone 1 and Zone 3 with Zone 2 HVAC shutdown.
"Upon failure of the surveillance, Secondary Containment ventilation was realigned to a previous successfully tested and known operable alignment for Zones 1, 2 and 3. This alignment consists of all Reactor Building Zones in service and Zone 3 aligned to the Railroad Bay.
"Upon restoration of Secondary Containment ventilation to a known operable alignment, operability was restored and Secondary Containment LCO 3.6.4.1 was cleared at 0128 EST on March 4, 2014.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG-1022, Rev. 3, Section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system."
The licensee informed the NRC Resident Inspector.
"On March 4, 2014 at 0025 EST, Secondary Containment drawdown testing surveillance failed to meet acceptance criteria of SR 3.6.4.1.5 due to maximum flow rate exceeding the allowable value. Secondary Containment drawdown testing was being performed on Reactor Building Zone 1 and Zone 3 with Zone 2 HVAC shutdown.
"Upon failure of the surveillance, Secondary Containment ventilation was realigned to a previous successfully tested and known operable alignment for Zones 1, 2 and 3. This alignment consists of all Reactor Building Zones in service and Zone 3 aligned to the Railroad Bay.
"Upon restoration of Secondary Containment ventilation to a known operable alignment, operability was restored and Secondary Containment LCO 3.6.4.1 was cleared at 0128 EST on March 4, 2014.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG-1022, Rev. 3, Section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system."
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 49868
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL M. JONES
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL M. JONES
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/04/2014
Notification Time: 05:05 [ET]
Event Date: 03/04/2014
Event Time: 01:43 [EST]
Last Update Date: 03/04/2014
Notification Time: 05:05 [ET]
Event Date: 03/04/2014
Event Time: 01:43 [EST]
Last Update Date: 03/04/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
FRED BOWER (R1DO)
FRED BOWER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
UNIT 2 MANUAL REACTOR SCRAM FOLLOWING LOSS OF A UNINTERRUPTIBLE POWER SUPPLY [UPS]
"At 0137 EST Nine Mile Point Unit 2 experienced a loss of an uninterruptible power supply 2VBB-UPS3B which resulted in a half scram and half isolations. This caused a loss of cooling water to the Reactor Recirculation Pumps and other indications for the loss of power.
"At 0143 EST a Manual Reactor Scram was inserted due to the rise of temperatures on the Reactor Recirculation Pump seal cavity temperature and motor winding temperature.
"The reactor building ventilation radiation monitor went non-functional when the reactor building isolated on the loss of UPS power. The standby gas treatment system was started as required and restored the reactor building differential pressure.
"This is a 4-Hour report for 10CFR50.72(b)(2)(iv)(B) RPS Actuation and 8-Hour report for 10CFR50.72(b)(3)(xiii) Loss of Emergency Assessment Capability.
"The NRC Resident inspector has been notified."
All systems functioned as required following the manual scram. All control rods fully inserted.
The cause of the loss of the UPS is under investigation.
"At 0137 EST Nine Mile Point Unit 2 experienced a loss of an uninterruptible power supply 2VBB-UPS3B which resulted in a half scram and half isolations. This caused a loss of cooling water to the Reactor Recirculation Pumps and other indications for the loss of power.
"At 0143 EST a Manual Reactor Scram was inserted due to the rise of temperatures on the Reactor Recirculation Pump seal cavity temperature and motor winding temperature.
"The reactor building ventilation radiation monitor went non-functional when the reactor building isolated on the loss of UPS power. The standby gas treatment system was started as required and restored the reactor building differential pressure.
"This is a 4-Hour report for 10CFR50.72(b)(2)(iv)(B) RPS Actuation and 8-Hour report for 10CFR50.72(b)(3)(xiii) Loss of Emergency Assessment Capability.
"The NRC Resident inspector has been notified."
All systems functioned as required following the manual scram. All control rods fully inserted.
The cause of the loss of the UPS is under investigation.
Power Reactor
Event Number: 49869
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JIM RITCHIE
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JIM RITCHIE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/04/2014
Notification Time: 06:04 [ET]
Event Date: 03/04/2014
Event Time: 05:02 [EST]
Last Update Date: 03/06/2014
Notification Time: 06:04 [ET]
Event Date: 03/04/2014
Event Time: 05:02 [EST]
Last Update Date: 03/06/2014
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):
FRED BOWER (R1DO)
FRED BOWER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER OUT OF SERVICE FOR PLANNED MAINTENANCE
"A planned maintenance evolution at the Oyster Creek Nuclear Generating Station has removed the Technical Support Center (TSC) ventilation system from service. The TSC ventilation system will be rendered non-functional during the course of the work activities. The TSC ventilation is expected to be out of service for approximately twenty hours from 0500 [EST] to 2400, today, March 4, 2014.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures.
''This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to potential loss of the TSC. An update will be provided once the TSC ventilation has been restored to normal operation. The NRC Resident Inspector has been notified."
* * * UPDATE AT 1532 ON 3/6/14 FROM SPAGNUOLO TO SNYDER * * *
On 3/6/14 at 1532 EST the Technical Support Center was returned to service.
Notified R1DO (Bower).
"A planned maintenance evolution at the Oyster Creek Nuclear Generating Station has removed the Technical Support Center (TSC) ventilation system from service. The TSC ventilation system will be rendered non-functional during the course of the work activities. The TSC ventilation is expected to be out of service for approximately twenty hours from 0500 [EST] to 2400, today, March 4, 2014.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures.
''This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to potential loss of the TSC. An update will be provided once the TSC ventilation has been restored to normal operation. The NRC Resident Inspector has been notified."
* * * UPDATE AT 1532 ON 3/6/14 FROM SPAGNUOLO TO SNYDER * * *
On 3/6/14 at 1532 EST the Technical Support Center was returned to service.
Notified R1DO (Bower).
Power Reactor
Event Number: 49870
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: KEVIN HOLLE
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: KEVIN HOLLE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/05/2014
Notification Time: 01:37 [ET]
Event Date: 03/04/2014
Event Time: 19:17 [CST]
Last Update Date: 03/05/2014
Notification Time: 01:37 [ET]
Event Date: 03/04/2014
Event Time: 19:17 [CST]
Last Update Date: 03/05/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
ERIC DUNCAN (R3DO)
ERIC DUNCAN (R3DO)
| 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 | 95 | Power Operation | 95 | Power Operation |
MOMENTARY LOSS OF SECONDARY CONTAINMENT
"At 1917 hours [CST] on March 4, 2014, the Unit 1B fuel pool radiation monitor spiked high due to an invalid actuation which caused the U1 and U2 reactor building ventilation system to isolate (the control room ventilation system also isolated as designed). The Standby Gas Treatment system was already in operation for a scheduled surveillance as of 1900 hours on March 4, 2014. During the ensuing pressure transient, the Reactor Building differential pressure momentarily went positive. As a result, Secondary Containment was declared inoperable.
"Given the temporary loss in secondary containment, this event is reportable under 10CFR50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function.
"The NRC Resident Inspector has been notified."
After the transient, the reactor building ventilation system was shutdown for scheduled maintenance and the control room ventilation system was returned to its normal configuration. The Standby Gas Treatment system was operating to support planned reactor building ventilation system maintenance. Troubleshooting of the radiation monitor spike is underway.
"At 1917 hours [CST] on March 4, 2014, the Unit 1B fuel pool radiation monitor spiked high due to an invalid actuation which caused the U1 and U2 reactor building ventilation system to isolate (the control room ventilation system also isolated as designed). The Standby Gas Treatment system was already in operation for a scheduled surveillance as of 1900 hours on March 4, 2014. During the ensuing pressure transient, the Reactor Building differential pressure momentarily went positive. As a result, Secondary Containment was declared inoperable.
"Given the temporary loss in secondary containment, this event is reportable under 10CFR50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function.
"The NRC Resident Inspector has been notified."
After the transient, the reactor building ventilation system was shutdown for scheduled maintenance and the control room ventilation system was returned to its normal configuration. The Standby Gas Treatment system was operating to support planned reactor building ventilation system maintenance. Troubleshooting of the radiation monitor spike is underway.
Power Reactor
Event Number: 49871
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAN WILLIAMSON
HQ OPS Officer: STEVE SANDIN
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAN WILLIAMSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/05/2014
Notification Time: 02:26 [ET]
Event Date: 03/04/2014
Event Time: 23:34 [EST]
Last Update Date: 03/05/2014
Notification Time: 02:26 [ET]
Event Date: 03/04/2014
Event Time: 23:34 [EST]
Last Update Date: 03/05/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
FRED BOWER (R1DO)
FRED BOWER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
UNIT 1 MANUALLY SCRAMMED DURING A RAPID SHUTDOWN IN RESPONSE TO A TURBINE EHC FAILURE
"At 2334 EST on 3/4/14 Unit 1 was manually scammed during a Rapid Plant Shutdown. The Rapid Plant Shutdown was initiated due to an Electro Hydraulic [Control] [EHC] System failure resulting in all Low Pressure Turbine lntercept Valves failing closed.
"The shutdown was normal and the plant is stable in Hot Shutdown with normal pressure control via the Main Steam Bypass Valves to the Main Condenser and normal level control using Feedwater."
The licensee informed both State and local agencies and the NRC Resident Inspector. A press release will be issued by the licensee.
"At 2334 EST on 3/4/14 Unit 1 was manually scammed during a Rapid Plant Shutdown. The Rapid Plant Shutdown was initiated due to an Electro Hydraulic [Control] [EHC] System failure resulting in all Low Pressure Turbine lntercept Valves failing closed.
"The shutdown was normal and the plant is stable in Hot Shutdown with normal pressure control via the Main Steam Bypass Valves to the Main Condenser and normal level control using Feedwater."
The licensee informed both State and local agencies and the NRC Resident Inspector. A press release will be issued by the licensee.
Power Reactor
Event Number: 49872
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN McHUGH
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NJ
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN McHUGH
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/05/2014
Notification Time: 11:10 [ET]
Event Date: 03/04/2014
Event Time: 13:30 [EST]
Last Update Date: 03/05/2014
Notification Time: 11:10 [ET]
Event Date: 03/04/2014
Event Time: 13:30 [EST]
Last Update Date: 03/05/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
FRED BOWER (R1DO)
FRED BOWER (R1DO)
| 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 |
FITNESS-FOR-DUTY REPORT INVOLVING A LICENSED EMPLOYEE
A licensed employee had a confirmed positive for cocaine during a random fitness-for-duty test. The employee's access to the plant has been restricted.
Notified R1DO (Bower).
A licensed employee had a confirmed positive for cocaine during a random fitness-for-duty test. The employee's access to the plant has been restricted.
Notified R1DO (Bower).
Agreement State
Event Number: 49931
Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: CONFIDENTIAL
Region: 1
City: CONFIDENTIAL State: NY
County:
License #: CONFIDENTIAL
Agreement: Y
Docket:
NRC Notified By: FAX
HQ OPS Officer: DONALD NORWOOD
Licensee: CONFIDENTIAL
Region: 1
City: CONFIDENTIAL State: NY
County:
License #: CONFIDENTIAL
Agreement: Y
Docket:
NRC Notified By: FAX
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/19/2014
Notification Time: 16:03 [ET]
Event Date: 03/04/2014
Event Time: 00:00 [EDT]
Last Update Date: 03/19/2014
Notification Time: 16:03 [ET]
Event Date: 03/04/2014
Event Time: 00:00 [EDT]
Last Update Date: 03/19/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BLAKE WELLING (R1DO)
FSME EVENTS RESOURCE (EMAI)
BLAKE WELLING (R1DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - MISADMINISTRATION OF IODINE-125 SOLUTION DURING BRACHYTHERAPY
The following information was received via facsimile:
"A patient was prescribed 50 Gray to be delivered to a brain tumor bed via a GliaSite balloon inflated with 200 mCi of I-125 saline solution implanted for 66 hours. Upon removal of the balloon on March 7, 2014, it was discovered that the balloon had not inflated and no dose to the tumor bed had been delivered.
"A three position stopcock was incorrectly positioned at the time of inflation and the I-125 saline solution was diverted to another syringe rather than to the balloon. All material is accounted for and is being held for DIS. The three position stopcock is not part of the vendor's kit.
"Corrective Actions: In-service by the vendor scheduled, revision of policies and procedures to include verification of balloon via medical imaging post-infusion, and in-service to staff on new policies and procedures."
NYS Incident: #1054
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
The following information was received via facsimile:
"A patient was prescribed 50 Gray to be delivered to a brain tumor bed via a GliaSite balloon inflated with 200 mCi of I-125 saline solution implanted for 66 hours. Upon removal of the balloon on March 7, 2014, it was discovered that the balloon had not inflated and no dose to the tumor bed had been delivered.
"A three position stopcock was incorrectly positioned at the time of inflation and the I-125 saline solution was diverted to another syringe rather than to the balloon. All material is accounted for and is being held for DIS. The three position stopcock is not part of the vendor's kit.
"Corrective Actions: In-service by the vendor scheduled, revision of policies and procedures to include verification of balloon via medical imaging post-infusion, and in-service to staff on new policies and procedures."
NYS Incident: #1054
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.