Event Notification Report for March 13, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/12/2013 - 03/13/2013
EVENT NUMBERS
48820488214886548946
Power Reactor
Event Number: 48820
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: EDWARD WINN
HQ OPS Officer: VINCE KLCO
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: EDWARD WINN
HQ OPS Officer: VINCE KLCO
Notification Date: 03/13/2013
Notification Time: 03:11 [ET]
Event Date: 03/13/2013
Event Time: 01:49 [CDT]
Last Update Date: 03/14/2013
Notification Time: 03:11 [ET]
Event Date: 03/13/2013
Event Time: 01:49 [CDT]
Last Update Date: 03/14/2013
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
DALE POWERS (R4DO)
ELMO COLLINS (RA)
JOHN LUBINSKI (NRR)
JEFFERY GRANT (IRD)
DALE POWERS (R4DO)
ELMO COLLINS (RA)
JOHN LUBINSKI (NRR)
JEFFERY GRANT (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Defueled | 0 | Defueled |
UNUSUAL EVENT DECLARED DUE TO INOPERABLE EMERGENCY DIESEL GENERATORS
At 0149 CDT on 3/13/2013, Wolf Creek declared an Unusual Event due to inoperability of both on-site emergency diesel generators. While the A-EDG (Emergency Diesel Generator) was out of service due to planned maintenance, the B-EDG experienced a loss of control power. The cause is currently under investigation. Offsite power is available and providing electrical power to the Unit.
The licensee notified state and local agencies and the NRC Resident Inspector.
Notified DHS, FEMA, DHS NICC and NuclearSSA (email).
* * * UPDATE FROM MARTINSON TO KLCO ON 3/14/13 AT 0407 EDT * * *
"Repairs are complete on the 'B' EDG (Emergency Diesel Generator). The 'B' EDG has been tested and restored to operable status at 0221 [CDT] on 03/14/2013. The 'A' EDG remains out of service for scheduled maintenance. NUE (Notification of Unusual Event) terminated at 0239 CDT on 03/14/2013."
The licensee notified state and local agencies and will notify the NRC Resident Inspector. Notified the R4DO (Powers), IRD (Grant) and NRR (Lubinski).
Notified DHS, FEMA, DHS NICC and Nuclear SSA (email).
At 0149 CDT on 3/13/2013, Wolf Creek declared an Unusual Event due to inoperability of both on-site emergency diesel generators. While the A-EDG (Emergency Diesel Generator) was out of service due to planned maintenance, the B-EDG experienced a loss of control power. The cause is currently under investigation. Offsite power is available and providing electrical power to the Unit.
The licensee notified state and local agencies and the NRC Resident Inspector.
Notified DHS, FEMA, DHS NICC and NuclearSSA (email).
* * * UPDATE FROM MARTINSON TO KLCO ON 3/14/13 AT 0407 EDT * * *
"Repairs are complete on the 'B' EDG (Emergency Diesel Generator). The 'B' EDG has been tested and restored to operable status at 0221 [CDT] on 03/14/2013. The 'A' EDG remains out of service for scheduled maintenance. NUE (Notification of Unusual Event) terminated at 0239 CDT on 03/14/2013."
The licensee notified state and local agencies and will notify the NRC Resident Inspector. Notified the R4DO (Powers), IRD (Grant) and NRR (Lubinski).
Notified DHS, FEMA, DHS NICC and Nuclear SSA (email).
Power Reactor
Event Number: 48821
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: SEAN BLOOM
HQ OPS Officer: CHARLES TEAL
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: SEAN BLOOM
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/13/2013
Notification Time: 19:01 [ET]
Event Date: 03/13/2013
Event Time: 11:20 [EDT]
Last Update Date: 03/13/2013
Notification Time: 19:01 [ET]
Event Date: 03/13/2013
Event Time: 11:20 [EDT]
Last Update Date: 03/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
KATHLEEN O'DONOHUE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Hot Standby | 0 | Hot Standby |
AFW ACTUATION DUE TO TRIP OF 3B FEEDWATER PUMP
"This is a non-emergency event notification to the NRCOC [NRC Operations Center] in accordance with 10 CFR 50.72(b)(3)(iv)(A) for valid Engineered Safeguards (ESF) actuations of the Auxiliary Feedwater System (AFW).
"On 3/13/2013 at 1120 EDT, Unit 3 experienced an automatic initiation of AFW due to a trip of the 3B Steam Generator Feedwater Pump while shutdown with Rod Banks withdrawn in preparation for startup. Subsequently, at 1131 EDT, Rx Trip Breakers were opened due to a lowering Reactor Coolant System average temperature resulting from AFW operation. Unit 3 remains stable in Mode 3. The initiation of AFW is currently under investigation."
The NRC Resident Inspector has been informed.
"This is a non-emergency event notification to the NRCOC [NRC Operations Center] in accordance with 10 CFR 50.72(b)(3)(iv)(A) for valid Engineered Safeguards (ESF) actuations of the Auxiliary Feedwater System (AFW).
"On 3/13/2013 at 1120 EDT, Unit 3 experienced an automatic initiation of AFW due to a trip of the 3B Steam Generator Feedwater Pump while shutdown with Rod Banks withdrawn in preparation for startup. Subsequently, at 1131 EDT, Rx Trip Breakers were opened due to a lowering Reactor Coolant System average temperature resulting from AFW operation. Unit 3 remains stable in Mode 3. The initiation of AFW is currently under investigation."
The NRC Resident Inspector has been informed.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 48865
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BRAD BARE
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BRAD BARE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/28/2013
Notification Time: 18:39 [ET]
Event Date: 03/13/2013
Event Time: 17:26 [CDT]
Last Update Date: 05/10/2013
Notification Time: 18:39 [ET]
Event Date: 03/13/2013
Event Time: 17:26 [CDT]
Last Update Date: 05/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
GREG PICK (R4DO)
GREG PICK (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 |
LOSS OF REASONABLE ASSURANCE OF OPERABILITY FOR STANDBY LIQUID CONTROL TANK
"Information Notice IN 2012-01 on seismic qualification of Standby Liquid Control (SLC) tanks was evaluated in 2012 to assess immediate operability of the SLC system based on SLC Test Tank and Mixing Tank not being qualified to Seismic Class 1S. Based on calculation NEDC 12-015 in response to IN 2012-01, [Cooper Nuclear Station] CNS concluded that SLC was still operable with the test tank full. Long-term actions from the 2012 condition were completed by issuance of calculation NEDC 13-010 and evaluation EE 13-009. NEDC 13-010 concludes that the SLC storage tank is qualified when full and the test tank and mixing tank are qualified when empty.
"No procedure step existed in the SLC surveillances to ensure the test tank is drained prior to restoration of SLC to an operable status to ensure it remained fully qualified to its NEDC 13-010 design. Further, no Caution Order or Standing Order existed to ensure short-term control until a procedure change could be implemented. So, as a short-term action, CNS implemented a Standing Order to establish positive control of the test tank. The Standing Order directs that SLC be declared INOPERABLE if the Test Tank is filled.
"Initially, this was thought to be a conservative measure only, because CNS judged that reasonable assurance of OPERABILITY remained due to conservative assumptions in NEDC 13-010. However, on 3/19/13 at 2146 CDT, the Prompt Operability Determination was changed to credit the Standing Order as a compensatory measure needed to maintain or enhance OPERABILITY of SLC. Therefore, CNS had lost reasonable assurance of OPERABILITY as of 03/13/2013 at 1726 CDT when the Control Room was notified that NEDC 13-010 concluded the test tank and mixing tank had to be empty to preserve the required seismic qualification, and an 8-hour report should have been made prior to 0126 CDT on 03/14/2013.
"Currently the SLC Test Tank is drained and SLC is OPERABLE."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION FROM DAVID MADSEN TO JOHN SHOEMAKER ON 5/10/2013 AT 1436 EDT * * *
"This notification is being made to retract Event Notification EN #48865 which was reported on March 28, 2013 for an event occurring on March 13, 2013. This EN identified Cooper Nuclear Station had lost reasonable assurance of OPERABILITY of the Standby Liquid Control (SLC) system based on a CNS design calculation which supported that the SLC test tank was not seismically qualified when full of water.
"Subsequently, this calculation was re-evaluated specifically in support of determining OPERABILITY. This re-evaluation determined the SLC system remained OPERABLE when the consideration of nozzle loads is removed. The ability of Class IIS [ASME American Society Mechanical Engineering] seismic components to meet Class II/I [ASME] does not require the consideration of nozzle loads. The SLC test tank, which is a Class IIS [ASME] component, does not fail when filled if no nozzle loads are considered. As such, there was no loss of safety function for SLC."
The licensee will notify the NRC Resident Inspector. Notified R4DO (Drake).
"Information Notice IN 2012-01 on seismic qualification of Standby Liquid Control (SLC) tanks was evaluated in 2012 to assess immediate operability of the SLC system based on SLC Test Tank and Mixing Tank not being qualified to Seismic Class 1S. Based on calculation NEDC 12-015 in response to IN 2012-01, [Cooper Nuclear Station] CNS concluded that SLC was still operable with the test tank full. Long-term actions from the 2012 condition were completed by issuance of calculation NEDC 13-010 and evaluation EE 13-009. NEDC 13-010 concludes that the SLC storage tank is qualified when full and the test tank and mixing tank are qualified when empty.
"No procedure step existed in the SLC surveillances to ensure the test tank is drained prior to restoration of SLC to an operable status to ensure it remained fully qualified to its NEDC 13-010 design. Further, no Caution Order or Standing Order existed to ensure short-term control until a procedure change could be implemented. So, as a short-term action, CNS implemented a Standing Order to establish positive control of the test tank. The Standing Order directs that SLC be declared INOPERABLE if the Test Tank is filled.
"Initially, this was thought to be a conservative measure only, because CNS judged that reasonable assurance of OPERABILITY remained due to conservative assumptions in NEDC 13-010. However, on 3/19/13 at 2146 CDT, the Prompt Operability Determination was changed to credit the Standing Order as a compensatory measure needed to maintain or enhance OPERABILITY of SLC. Therefore, CNS had lost reasonable assurance of OPERABILITY as of 03/13/2013 at 1726 CDT when the Control Room was notified that NEDC 13-010 concluded the test tank and mixing tank had to be empty to preserve the required seismic qualification, and an 8-hour report should have been made prior to 0126 CDT on 03/14/2013.
"Currently the SLC Test Tank is drained and SLC is OPERABLE."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION FROM DAVID MADSEN TO JOHN SHOEMAKER ON 5/10/2013 AT 1436 EDT * * *
"This notification is being made to retract Event Notification EN #48865 which was reported on March 28, 2013 for an event occurring on March 13, 2013. This EN identified Cooper Nuclear Station had lost reasonable assurance of OPERABILITY of the Standby Liquid Control (SLC) system based on a CNS design calculation which supported that the SLC test tank was not seismically qualified when full of water.
"Subsequently, this calculation was re-evaluated specifically in support of determining OPERABILITY. This re-evaluation determined the SLC system remained OPERABLE when the consideration of nozzle loads is removed. The ability of Class IIS [ASME American Society Mechanical Engineering] seismic components to meet Class II/I [ASME] does not require the consideration of nozzle loads. The SLC test tank, which is a Class IIS [ASME] component, does not fail when filled if no nozzle loads are considered. As such, there was no loss of safety function for SLC."
The licensee will notify the NRC Resident Inspector. Notified R4DO (Drake).
Agreement State
Event Number: 48946
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: CORNERSTONE CHEMICAL COMPANY
Region: 4
City: WAGGAMAN State: LA
County:
License #: GL-155
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: CHARLES TEAL
Licensee: CORNERSTONE CHEMICAL COMPANY
Region: 4
City: WAGGAMAN State: LA
County:
License #: GL-155
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/19/2013
Notification Time: 14:29 [ET]
Event Date: 03/13/2013
Event Time: 00:00 [CDT]
Last Update Date: 04/19/2013
Notification Time: 14:29 [ET]
Event Date: 03/13/2013
Event Time: 00:00 [CDT]
Last Update Date: 04/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JAMES DRAKE (R4DO)
FSME EVENT RESOURCE (EMAI)
JAMES DRAKE (R4DO)
FSME EVENT RESOURCE (EMAI)
AGREEMENT STATE REPORT - STUCK SHUTTER ON KAY-RAY DENSITY METER
The following was received by the State of Louisiana via fax:
"Louisiana Dept. of Environmental Quality was notified on April 2, 2013, by a written letter from Cornerstone Chemical Company. A Kay-Ray Cs-137 50 mCi (decay corrected to 31 mCi) density meter, model number 7062BP, serial number S93C1706 was removed in order to service a pipe during a turnaround activity. After the device was removed, the shutter was discovered to be stuck in the half closed position and would not completely close. An employee who carried the density meter was calculated to receive a radiation exposure of 1.8 mR total dose. BBP Sales serviced the shutter, reinstalled the density gauge, performed a leak test, and installation survey. Notification was given to all Cornerstone Chemical maintenance planning personnel and supervision in the acid unit to contact the RSO for any activities concerning radiation sources. All activities are to be conducted by licensed contractors.
"The general license registration is in the stages of being modified to a specific license."
State event report number: LA-13-0015
The following was received by the State of Louisiana via fax:
"Louisiana Dept. of Environmental Quality was notified on April 2, 2013, by a written letter from Cornerstone Chemical Company. A Kay-Ray Cs-137 50 mCi (decay corrected to 31 mCi) density meter, model number 7062BP, serial number S93C1706 was removed in order to service a pipe during a turnaround activity. After the device was removed, the shutter was discovered to be stuck in the half closed position and would not completely close. An employee who carried the density meter was calculated to receive a radiation exposure of 1.8 mR total dose. BBP Sales serviced the shutter, reinstalled the density gauge, performed a leak test, and installation survey. Notification was given to all Cornerstone Chemical maintenance planning personnel and supervision in the acid unit to contact the RSO for any activities concerning radiation sources. All activities are to be conducted by licensed contractors.
"The general license registration is in the stages of being modified to a specific license."
State event report number: LA-13-0015