Event Notification Report for December 19, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/18/2012 - 12/19/2012
EVENT NUMBERS
48605486074860848614
Power Reactor
Event Number: 48605
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: LOGAN MILLER
HQ OPS Officer: VINCE KLCO
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: LOGAN MILLER
HQ OPS Officer: VINCE KLCO
Notification Date: 12/19/2012
Notification Time: 08:54 [ET]
Event Date: 12/19/2012
Event Time: 08:00 [CST]
Last Update Date: 12/19/2012
Notification Time: 08:54 [ET]
Event Date: 12/19/2012
Event Time: 08:00 [CST]
Last Update Date: 12/19/2012
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):
KENNETH RIEMER (R3DO)
KENNETH RIEMER (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 |
PLANNED MAINTENANCE AFFECTING THE ABILITY TO ASSESS AN EMERGENCY CLASSIFICATION
"Voluntary ENS Notification Regarding Maintenance Affecting the Ability to Assess an EAL Classification.
"Kewaunee Power Station (KPS) is preparing to perform routine planned calibrations on Wednesday, December 19, and Thursday, December 20, 2012, on the forebay level indication. This maintenance will impact the forebay level computer and Control Room indication normally used to make the Unusual Event or Alert emergency classifications in the event the lake or forebay threshold is exceeded for greater than 15 minutes.
"The maintenance is planned to occur from 0800 [CST] on 12/19/12 until 1230 [CST] on 12/20/12. There are four level transmitters each with local indication. Each transmitter will be calibrated, but only one at a time, so that the capability to locally determine forebay level using the other three transmitters will remain.
"This activity has been evaluated against the requirements of 10 CFR 50.72(b)(3)(xiii) and it has been determined that the condition does not rise to the significance necessitating an event notification since Kewaunee retains the capability to make the necessary emergency classifications. However, this information is being conservatively provided so that NRC may be aware of the condition should an emergency develop."
The licensee notified the NRC Resident Inspector.
"Voluntary ENS Notification Regarding Maintenance Affecting the Ability to Assess an EAL Classification.
"Kewaunee Power Station (KPS) is preparing to perform routine planned calibrations on Wednesday, December 19, and Thursday, December 20, 2012, on the forebay level indication. This maintenance will impact the forebay level computer and Control Room indication normally used to make the Unusual Event or Alert emergency classifications in the event the lake or forebay threshold is exceeded for greater than 15 minutes.
"The maintenance is planned to occur from 0800 [CST] on 12/19/12 until 1230 [CST] on 12/20/12. There are four level transmitters each with local indication. Each transmitter will be calibrated, but only one at a time, so that the capability to locally determine forebay level using the other three transmitters will remain.
"This activity has been evaluated against the requirements of 10 CFR 50.72(b)(3)(xiii) and it has been determined that the condition does not rise to the significance necessitating an event notification since Kewaunee retains the capability to make the necessary emergency classifications. However, this information is being conservatively provided so that NRC may be aware of the condition should an emergency develop."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 48607
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVE WALSH
HQ OPS Officer: DONG HWA PARK
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVE WALSH
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/19/2012
Notification Time: 20:29 [ET]
Event Date: 12/19/2012
Event Time: 17:31 [EST]
Last Update Date: 12/19/2012
Notification Time: 20:29 [ET]
Event Date: 12/19/2012
Event Time: 17:31 [EST]
Last Update Date: 12/19/2012
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):
GORDON HUNEGS (R1DO)
GORDON HUNEGS (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 18 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO LOW REACTOR PRESSURE VESSEL LEVEL
"At approximately 17:31 hours on December 19, 2012, Susquehanna Steam Electric Station Unit Two reactor automatically scrammed on low RPV level (Level 3, +13 inches) while transitioning the 'A' reactor feed pump from discharge pressure mode to flow control mode.
"All control rods inserted and both reactor recirculation pumps tripped. Reactor water level lowered to approximately -29 inches causing Level 3 (+13 inches) isolations. An automatic trip of the reactor recirculation pumps occurred, but is not expected at this RPV level. There were no automatic emergency core cooling system initiations. No steam relief valves opened during the event. All safety systems operated as expected. The cause of the loss of feed water flow and trip of the reactor recirculation pumps is under investigation.
"This report is being made per 10CFR50.72(b)(2)(iv)(B) for a 4 hour report, and 10CFR50.72(b)(3)(iv)(A) for an 8 hour report."
Decay heat is removed via steam to the main condenser using the bypass valves . On-site electrical power is in the normal configuration. The Unit 2 reactor is currently stable in Mode 3. Unit 1 was not affected and operates at 99% power.
The licensee will inform the Commonwealth of Pennsylvania and make a press release. The NRC Resident Inspector was notified.
"At approximately 17:31 hours on December 19, 2012, Susquehanna Steam Electric Station Unit Two reactor automatically scrammed on low RPV level (Level 3, +13 inches) while transitioning the 'A' reactor feed pump from discharge pressure mode to flow control mode.
"All control rods inserted and both reactor recirculation pumps tripped. Reactor water level lowered to approximately -29 inches causing Level 3 (+13 inches) isolations. An automatic trip of the reactor recirculation pumps occurred, but is not expected at this RPV level. There were no automatic emergency core cooling system initiations. No steam relief valves opened during the event. All safety systems operated as expected. The cause of the loss of feed water flow and trip of the reactor recirculation pumps is under investigation.
"This report is being made per 10CFR50.72(b)(2)(iv)(B) for a 4 hour report, and 10CFR50.72(b)(3)(iv)(A) for an 8 hour report."
Decay heat is removed via steam to the main condenser using the bypass valves . On-site electrical power is in the normal configuration. The Unit 2 reactor is currently stable in Mode 3. Unit 1 was not affected and operates at 99% power.
The licensee will inform the Commonwealth of Pennsylvania and make a press release. The NRC Resident Inspector was notified.
Power Reactor
Event Number: 48608
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GUY GRIFFIS
HQ OPS Officer: DONG HWA PARK
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GUY GRIFFIS
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/19/2012
Notification Time: 20:55 [ET]
Event Date: 12/19/2012
Event Time: 19:35 [EST]
Last Update Date: 12/19/2012
Notification Time: 20:55 [ET]
Event Date: 12/19/2012
Event Time: 19:35 [EST]
Last Update Date: 12/19/2012
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):
BRIAN BONSER (R2DO)
BRIAN BONSER (R2DO)
| 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 |
GROUNDWATER SAMPLES INDICATE ELEVATED TRITIUM LEVELS
"On December 19, 2012, results from routine monitoring of groundwater at Plant Hatch indicated tritium was detected above historical background levels at two sample points on site. Additional samples were taken from the same points and analysis confirmed that tritium was present at elevated levels in both samples and that tritium had not migrated out of the general area of initial discovery. Immediate actions are being taken to locate the source of the leak and actions are in progress to stop the leak. The investigation currently shows that the tritium is confined to a small area on the plant site in the vicinity of the Unit 1 Condensate Storage Tank (CST), and there is no significant potential for off-site impact. Additionally, there is no impact to on-site personnel. No tritium levels above background have been detected or migrated outside the area where the two sample points are located.
"Southern Nuclear [SNC] will continue to sample strategic locations in the ground water monitoring network to determine if there are changes in the impacted area and beyond. SNC is confident that these levels are of low safety significance and do not pose any issues to the public health and safety.
"In accordance with SNC's groundwater protection procedures and the Nuclear Energy Institute (NEI), SNC contacted the NRC Region II Resident Inspector and will be notifying the State of Georgia Environmental Protection Division and other agencies to inform them of this matter."
"On December 19, 2012, results from routine monitoring of groundwater at Plant Hatch indicated tritium was detected above historical background levels at two sample points on site. Additional samples were taken from the same points and analysis confirmed that tritium was present at elevated levels in both samples and that tritium had not migrated out of the general area of initial discovery. Immediate actions are being taken to locate the source of the leak and actions are in progress to stop the leak. The investigation currently shows that the tritium is confined to a small area on the plant site in the vicinity of the Unit 1 Condensate Storage Tank (CST), and there is no significant potential for off-site impact. Additionally, there is no impact to on-site personnel. No tritium levels above background have been detected or migrated outside the area where the two sample points are located.
"Southern Nuclear [SNC] will continue to sample strategic locations in the ground water monitoring network to determine if there are changes in the impacted area and beyond. SNC is confident that these levels are of low safety significance and do not pose any issues to the public health and safety.
"In accordance with SNC's groundwater protection procedures and the Nuclear Energy Institute (NEI), SNC contacted the NRC Region II Resident Inspector and will be notifying the State of Georgia Environmental Protection Division and other agencies to inform them of this matter."
Agreement State
Event Number: 48614
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: UNIVERSITY OF MARYLAND COLLEGE PARK
Region: 1
City: COLLEGE PARK State: MD
County: PRINCE GEORGES
License #: MD-33-004-03
Agreement: Y
Docket:
NRC Notified By: KENNETH BRENNEMAN
HQ OPS Officer: HOWIE CROUCH
Licensee: UNIVERSITY OF MARYLAND COLLEGE PARK
Region: 1
City: COLLEGE PARK State: MD
County: PRINCE GEORGES
License #: MD-33-004-03
Agreement: Y
Docket:
NRC Notified By: KENNETH BRENNEMAN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/20/2012
Notification Time: 13:46 [ET]
Event Date: 12/19/2012
Event Time: 15:00 [EST]
Last Update Date: 12/20/2012
Notification Time: 13:46 [ET]
Event Date: 12/19/2012
Event Time: 15:00 [EST]
Last Update Date: 12/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
GORDON HUNEGS (R1DO)
FSME RESOURCE (EMAI)
GORDON HUNEGS (R1DO)
FSME RESOURCE (EMAI)
MARYLAND AGREEMENT STATE REPORT - IRRADIATOR SOURCE CHAIN FAILED TO FUNCTION
The following information was obtained from the State of Maryland via fax:
On December 19, 2012 at 1500 EST, the licensee's irradiator chain became "kinked" and failed to function as required. The sources were being raised at the time of the incident. The chain was de-kinked from around the sprocket and the elevator/sources were returned to their lowest position in the pool.
The sources will remain stored at the lowest position until an internal investigation determines the cause of the event.
The following information was obtained from the State of Maryland via fax:
On December 19, 2012 at 1500 EST, the licensee's irradiator chain became "kinked" and failed to function as required. The sources were being raised at the time of the incident. The chain was de-kinked from around the sprocket and the elevator/sources were returned to their lowest position in the pool.
The sources will remain stored at the lowest position until an internal investigation determines the cause of the event.