Event Notification Report for April 27, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/26/2012 - 04/27/2012
EVENT NUMBERS
47869478704787149131
Power Reactor
Event Number: 47869
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ADRIAN GONZALEZ
HQ OPS Officer: VINCE KLCO
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ADRIAN GONZALEZ
HQ OPS Officer: VINCE KLCO
Notification Date: 04/27/2012
Notification Time: 13:19 [ET]
Event Date: 04/27/2012
Event Time: 08:00 [EDT]
Last Update Date: 04/27/2012
Notification Time: 13:19 [ET]
Event Date: 04/27/2012
Event Time: 08:00 [EDT]
Last Update Date: 04/27/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
DAVID PROULX (R4DO)
DAVID PROULX (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Refueling | 0 | Refueling |
| 4 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY - NON-LICENSED CONTRACT SUPERVISOR TESTED POSITIVE FOR DRUGS
A non-licensee contract supervisor tested positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector.
A non-licensee contract supervisor tested positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 47870
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: ROBERT KROS
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: ROBERT KROS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/27/2012
Notification Time: 16:02 [ET]
Event Date: 04/27/2012
Event Time: 13:45 [CDT]
Last Update Date: 04/27/2012
Notification Time: 16:02 [ET]
Event Date: 04/27/2012
Event Time: 13:45 [CDT]
Last Update Date: 04/27/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
DAVID PROULX (R4DO)
DAVID PROULX (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
FITNESS FOR DUTY - NON-LICENSED SUPERVISOR TESTED POSITIVE FOR ILLEGAL DRUGS
A non-licensed supervisory employee was determined to be under the influence of illegal drugs during a random test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee has notified the NRC Resident Inspector.
A non-licensed supervisory employee was determined to be under the influence of illegal drugs during a random test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 47871
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: LOGAN MILLER
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: LOGAN MILLER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/27/2012
Notification Time: 22:23 [ET]
Event Date: 04/27/2012
Event Time: 17:42 [CDT]
Last Update Date: 04/27/2012
Notification Time: 22:23 [ET]
Event Date: 04/27/2012
Event Time: 17:42 [CDT]
Last Update Date: 04/27/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
JULIO LARA (R3DO)
JULIO LARA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
BOTH TRAINS OF RESIDUAL HEAT REMOVAL DECLARED INOPERABLE
"At 1742 EDT on 04/27/2012, while in Mode 5, both trains of RHR (Residual Heat Removal) were declared inoperable due to a through wall leak on a socket welded connection of ASME code class piping. Currently, with both trains of RHR in service for decay heat removal, the leakage impacts redundant equipment required to fulfill a safety function. In the current condition, both trains are required to be operable to meet Technical Specification [TS] 3.4.7, 'RCS Loops - MODE 5, Loops Filled'.
"The leakage is isolable from the reactor coolant system and is therefore not considered RCS pressure boundary leakage per LCO 3.4.13, 'RCS Operational Leakage'.
"This event is being reported under 50.72(b)(3)(v)(B), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (B) remove residual heat'.
"Action has been initiated in accordance with TS 3.4.7 required action C.2 to restore one RHR loop to operable status."
The licensee is performing engineering analysis to determine the most appropriate repair method.
The licensee has notified the NRC Resident Inspector.
"At 1742 EDT on 04/27/2012, while in Mode 5, both trains of RHR (Residual Heat Removal) were declared inoperable due to a through wall leak on a socket welded connection of ASME code class piping. Currently, with both trains of RHR in service for decay heat removal, the leakage impacts redundant equipment required to fulfill a safety function. In the current condition, both trains are required to be operable to meet Technical Specification [TS] 3.4.7, 'RCS Loops - MODE 5, Loops Filled'.
"The leakage is isolable from the reactor coolant system and is therefore not considered RCS pressure boundary leakage per LCO 3.4.13, 'RCS Operational Leakage'.
"This event is being reported under 50.72(b)(3)(v)(B), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (B) remove residual heat'.
"Action has been initiated in accordance with TS 3.4.7 required action C.2 to restore one RHR loop to operable status."
The licensee is performing engineering analysis to determine the most appropriate repair method.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 49131
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JOHN CAVES
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JOHN CAVES
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/18/2013
Notification Time: 16:42 [ET]
Event Date: 04/27/2012
Event Time: 14:33 [EDT]
Last Update Date: 06/18/2013
Notification Time: 16:42 [ET]
Event Date: 04/27/2012
Event Time: 14:33 [EDT]
Last Update Date: 06/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
BINOY DESAI (R2DO)
BINOY DESAI (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
REACTOR HEAD NOZZLE PENETRATION FLAWS IDENTIFIED
"On April 27, 2012, while the Harris Nuclear Plant was shutdown for a scheduled refueling outage, the reactor vessel head penetrations were being examined in accordance with Inservice Inspection Program requirements. Examinations were being performed to identify flaws before they grow to a size that could effect the structural integrity of the reactor vessel. Those examinations identified flaws in four head penetration nozzles that exhibited characteristics of Primary Water Stress Corrosion Cracking. The four nozzles were repaired using the inner diameter temper bead welding process. Examinations performed following the repairs confirmed the repairs were successful.
"This was originally submitted as a voluntary report on May 29, 2012 at 1511 EDT. The condition has since been determined to be reportable per 10CFR50.72(b)(3)(ii)(A).
"The NRC Resident Inspector has been informed."
"On April 27, 2012, while the Harris Nuclear Plant was shutdown for a scheduled refueling outage, the reactor vessel head penetrations were being examined in accordance with Inservice Inspection Program requirements. Examinations were being performed to identify flaws before they grow to a size that could effect the structural integrity of the reactor vessel. Those examinations identified flaws in four head penetration nozzles that exhibited characteristics of Primary Water Stress Corrosion Cracking. The four nozzles were repaired using the inner diameter temper bead welding process. Examinations performed following the repairs confirmed the repairs were successful.
"This was originally submitted as a voluntary report on May 29, 2012 at 1511 EDT. The condition has since been determined to be reportable per 10CFR50.72(b)(3)(ii)(A).
"The NRC Resident Inspector has been informed."