Event Notification Report for February 13, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/12/2013 - 02/13/2013
Power Reactor
Event Number: 48750
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: MICHAEL MCCARTHY
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: MICHAEL MCCARTHY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/13/2013
Notification Time: 16:41 [ET]
Event Date: 02/13/2013
Event Time: 13:55 [EST]
Last Update Date: 02/13/2013
Notification Time: 16:41 [ET]
Event Date: 02/13/2013
Event Time: 13:55 [EST]
Last Update Date: 02/13/2013
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):
ANTHONY DIMITRIADIS (R1DO)
ANTHONY DIMITRIADIS (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 Standby |
MANUAL REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL
"At 1352 [hrs. EST], the Unit 2 CCR [Central Control Room] noted a trip of both heater drain tank pumps and entered Abnormal Operating Procedure 2-AOP-FW-1, 'Loss of Feedwater'. Prior to the event, Instrumentation and Controls personnel were performing testing on the heater drain tank level control system. Turbine load was reduced per plant procedures, however a manual reactor trip was initiated at 1355 due to an inability to maintain steam generator water levels. The team subsequently entered E-0, 'Reactor Trip or Safety Injection'. All control rods fully inserted. All safety systems responded as expected with the exception of source range detector N-31 and intermediate range detector N-35. N-31 and N-35 were declared inoperable. The auxiliary feedwater system actuated as expected and provided feedwater to maintain steam generator water level. Decay heat removal is via the steam generators to the main condensers. Offsite power and plant electrical lineups are normal. No primary or secondary code safety relief valves lifted. The reactor is in Mode 3 and stable. Unit 3 was unaffected and remains at 100% power. An investigation is in progress."
Unit 2 is currently at normal operating pressure and temperature. The licensee plans to issue a press release on this event.
The licensee notified the State of New York Public Service Commission and the NRC Resident Inspector.
"At 1352 [hrs. EST], the Unit 2 CCR [Central Control Room] noted a trip of both heater drain tank pumps and entered Abnormal Operating Procedure 2-AOP-FW-1, 'Loss of Feedwater'. Prior to the event, Instrumentation and Controls personnel were performing testing on the heater drain tank level control system. Turbine load was reduced per plant procedures, however a manual reactor trip was initiated at 1355 due to an inability to maintain steam generator water levels. The team subsequently entered E-0, 'Reactor Trip or Safety Injection'. All control rods fully inserted. All safety systems responded as expected with the exception of source range detector N-31 and intermediate range detector N-35. N-31 and N-35 were declared inoperable. The auxiliary feedwater system actuated as expected and provided feedwater to maintain steam generator water level. Decay heat removal is via the steam generators to the main condensers. Offsite power and plant electrical lineups are normal. No primary or secondary code safety relief valves lifted. The reactor is in Mode 3 and stable. Unit 3 was unaffected and remains at 100% power. An investigation is in progress."
Unit 2 is currently at normal operating pressure and temperature. The licensee plans to issue a press release on this event.
The licensee notified the State of New York Public Service Commission and the NRC Resident Inspector.
Power Reactor
Event Number: 48751
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/13/2013
Notification Time: 17:42 [ET]
Event Date: 02/13/2013
Event Time: 15:45 [EST]
Last Update Date: 02/13/2013
Notification Time: 17:42 [ET]
Event Date: 02/13/2013
Event Time: 15:45 [EST]
Last Update Date: 02/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MICHAEL F. KING (R2DO)
MICHAEL F. KING (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
OFFSITE NOTIFICATION DUE TO TRITIUM RELEASE ONSITE
"As part of routine rounds on 2/13/13, site personnel discovered an overflow condition at a collection tank containing water with low levels of tritium (approximately 6,000 pCi/L). The discharge pump for the tank was found to be nonfunctional which resulted in the overflow condition. Following discovery, a portable pump was utilized to pump the water to the normal monitored discharge path and terminate the overflow condition. The exact volume could not be determined but it is estimated that the volume of water that overflowed to the ground was greater than the 100 gallon threshold for voluntary reporting as indicated in Nuclear Energy Institute (NEI) 07-07, 'Industry Ground Water Initiative-Final Guidance Document.' A rough estimate of the release is between 100 and 300 gallons. The tritium was contained to a small area on the plant site in the vicinity of the discharge structure, and there is no significant potential for off-site impact or impact to on-site personnel.
"Because the leak remained on site, there will be no offsite impact to drinking water sources. Furthermore, the release posed no threat to employees or the public. Southern Nuclear [SNC] will continue to monitor the affected area as required.
"In accordance with SNC's groundwater protection procedures and the NEI guidance, a voluntary notification of this discovery will be made to the State of Georgia Environmental Protection Division and other agencies to inform them of this matter. The NRC Region II Resident Inspector was also notified.
"Reference: Condition Report 589402. Event occurred at 1111 EST, decision to make offsite notifications authorized at 1545 EST."
The tank was the outfall collection tank. Environmental Protection Agency limit for tritium in drinking water is 20,000 pCi/l.
"As part of routine rounds on 2/13/13, site personnel discovered an overflow condition at a collection tank containing water with low levels of tritium (approximately 6,000 pCi/L). The discharge pump for the tank was found to be nonfunctional which resulted in the overflow condition. Following discovery, a portable pump was utilized to pump the water to the normal monitored discharge path and terminate the overflow condition. The exact volume could not be determined but it is estimated that the volume of water that overflowed to the ground was greater than the 100 gallon threshold for voluntary reporting as indicated in Nuclear Energy Institute (NEI) 07-07, 'Industry Ground Water Initiative-Final Guidance Document.' A rough estimate of the release is between 100 and 300 gallons. The tritium was contained to a small area on the plant site in the vicinity of the discharge structure, and there is no significant potential for off-site impact or impact to on-site personnel.
"Because the leak remained on site, there will be no offsite impact to drinking water sources. Furthermore, the release posed no threat to employees or the public. Southern Nuclear [SNC] will continue to monitor the affected area as required.
"In accordance with SNC's groundwater protection procedures and the NEI guidance, a voluntary notification of this discovery will be made to the State of Georgia Environmental Protection Division and other agencies to inform them of this matter. The NRC Region II Resident Inspector was also notified.
"Reference: Condition Report 589402. Event occurred at 1111 EST, decision to make offsite notifications authorized at 1545 EST."
The tank was the outfall collection tank. Environmental Protection Agency limit for tritium in drinking water is 20,000 pCi/l.