Event Notification Report for January 07, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/06/2014 - 01/07/2014
Power Reactor
Event Number: 49699
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JACK OSBORNE
HQ OPS Officer: JEFF ROTTON
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JACK OSBORNE
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/07/2014
Notification Time: 13:12 [ET]
Event Date: 01/07/2014
Event Time: 07:45 [EST]
Last Update Date: 01/07/2014
Notification Time: 13:12 [ET]
Event Date: 01/07/2014
Event Time: 07:45 [EST]
Last Update Date: 01/07/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
WAYNE SCHMIDT (R1DO)
WAYNE SCHMIDT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNANALYZED CONDITION CAUSED BY HIGH ENERGY LINE BREAK BARRIER DOOR OPEN DURING MAINTENANCE
"At approximately 0745 on January 7, 2014, a review of maintenance activities performed on October 3, 2013 on Salem Unit 2, identified an instance in which a High Energy Line Break (HELB) barrier access door was not properly controlled during a Turbine Driven Auxiliary Feedwater Pump room maintenance activity. A HELB event occurring in a room with its barrier door open could adversely affect equipment in an adjacent room. The steam supply to the Turbine Driven Auxiliary Feedwater Pump was not isolated in support of the maintenance activities and the room HELB barrier door was not properly controlled during maintenance in the room. Consequently, a HELB event occurring in the Unit 2 Turbine Driven Auxiliary Feedwater Pump room with the impaired barrier door, could have rendered the Turbine Driven Auxiliary Feed water Pump and both of the Motor Driven Auxiliary Feedwater Pumps in the adjacent room inoperable.
"This event is being reported under the requirements of 10 CFR 50.72(b)(3)(ii)(B) as "the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety." An ENS notification is required if an unanalyzed condition occurred within 3 years of the date of discovery even if the event is not on-going at the time of discovery.
"The Licensee has notified the NRC Resident."
The licensee also will notify the Lower Alloways Creek Township.
"At approximately 0745 on January 7, 2014, a review of maintenance activities performed on October 3, 2013 on Salem Unit 2, identified an instance in which a High Energy Line Break (HELB) barrier access door was not properly controlled during a Turbine Driven Auxiliary Feedwater Pump room maintenance activity. A HELB event occurring in a room with its barrier door open could adversely affect equipment in an adjacent room. The steam supply to the Turbine Driven Auxiliary Feedwater Pump was not isolated in support of the maintenance activities and the room HELB barrier door was not properly controlled during maintenance in the room. Consequently, a HELB event occurring in the Unit 2 Turbine Driven Auxiliary Feedwater Pump room with the impaired barrier door, could have rendered the Turbine Driven Auxiliary Feed water Pump and both of the Motor Driven Auxiliary Feedwater Pumps in the adjacent room inoperable.
"This event is being reported under the requirements of 10 CFR 50.72(b)(3)(ii)(B) as "the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety." An ENS notification is required if an unanalyzed condition occurred within 3 years of the date of discovery even if the event is not on-going at the time of discovery.
"The Licensee has notified the NRC Resident."
The licensee also will notify the Lower Alloways Creek Township.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 49700
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: QUOC VO
HQ OPS Officer: DAN LIVERMORE
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: QUOC VO
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/07/2014
Notification Time: 16:07 [ET]
Event Date: 01/07/2014
Event Time: 12:10 [PST]
Last Update Date: 02/09/2015
Notification Time: 16:07 [ET]
Event Date: 01/07/2014
Event Time: 12:10 [PST]
Last Update Date: 02/09/2015
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):
BOB HAGAR (R4DO)
BOB HAGAR (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
REACTOR BUILDING STACK MONITOR TEMPORARILY OUT OF SERVICE FOR MAINTENANCE
"At 1210 PST on January 7, 2014 the Reactor Building Stack Radiation Monitor- Intermediate Range detector was declared non-functional due to scheduled maintenance on supporting equipment. The monitor is expected to be out of service for approximately 1 hour. Preplanned compensatory actions have been implemented.
"This event is being reported as a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).
"At 1238 PST on January 7, 2014 the Reactor Building Stack Radiation Monitor -Intermediate Range detector was declared functional following scheduled maintenance on supporting equipment. Emergency Assessment Capability has been restored. Preplanned compensatory actions have been secured.
"The licensee has notified the NRC Resident Inspector."
* * * RETRACTION FROM MATT REID TO DANIEL MILLS AT 1636 EST ON 02/09/2015 * * *
"Licensee is retracting this event notification based on the following: Regulatory guidance in NUREG-1022 Revision 3 allows for not reporting EP equipment outages that are planned (i.e., maintenance) when outage time is not expected to exceed or does not exceed 72 hours, and when there are viable compensatory measures in place. Verification of the Control Room Logs indicates Columbia had viable compensatory measures in place during the maintenance outage and the outage duration was less than 72 hours. Columbia met the conditions in NUREG-1022; therefore, this event did not represent a loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector.
Notified R4DO (Allen).
"At 1210 PST on January 7, 2014 the Reactor Building Stack Radiation Monitor- Intermediate Range detector was declared non-functional due to scheduled maintenance on supporting equipment. The monitor is expected to be out of service for approximately 1 hour. Preplanned compensatory actions have been implemented.
"This event is being reported as a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).
"At 1238 PST on January 7, 2014 the Reactor Building Stack Radiation Monitor -Intermediate Range detector was declared functional following scheduled maintenance on supporting equipment. Emergency Assessment Capability has been restored. Preplanned compensatory actions have been secured.
"The licensee has notified the NRC Resident Inspector."
* * * RETRACTION FROM MATT REID TO DANIEL MILLS AT 1636 EST ON 02/09/2015 * * *
"Licensee is retracting this event notification based on the following: Regulatory guidance in NUREG-1022 Revision 3 allows for not reporting EP equipment outages that are planned (i.e., maintenance) when outage time is not expected to exceed or does not exceed 72 hours, and when there are viable compensatory measures in place. Verification of the Control Room Logs indicates Columbia had viable compensatory measures in place during the maintenance outage and the outage duration was less than 72 hours. Columbia met the conditions in NUREG-1022; therefore, this event did not represent a loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector.
Notified R4DO (Allen).
Power Reactor
Event Number: 49701
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROBERT MELTON
HQ OPS Officer: GEROND GEORGE
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROBERT MELTON
HQ OPS Officer: GEROND GEORGE
Notification Date: 01/08/2014
Notification Time: 17:35 [ET]
Event Date: 01/07/2014
Event Time: 14:39 [CST]
Last Update Date: 01/08/2014
Notification Time: 17:35 [ET]
Event Date: 01/07/2014
Event Time: 14:39 [CST]
Last Update Date: 01/08/2014
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):
BOB HAGAR (R4DO)
BOB HAGAR (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 |
OFFSITE NOTIFICATION FOR SPILL IN THE RIVER BEND OWNER CONTROL AREA
"On January 8, 2014, at 1439 CST, River Bend Station management determined that a spill discovered on the morning of January 7 was reportable in accordance with NEI 07-07 (Nuclear Energy Institute), Ground Water Protection Initiative. The spill was the result of freeze damage that occurred on a valve connected to the cooling tower blow-down line. Dams were installed to prevent the water from reaching any storm drains, and the spill was confined to the owner-controlled area. Since this system has the potential to contain diluted radioactive plant effluent, samples were collected for analysis. The leak was immediately reduced to a small drip and actions are in progress to completely isolate and repair the valve. The effluent was determined today to contain 4584 pico-curies per liter of tritium, but no detectable gamma activity. The calculated volume of the leak was between 100 and 1200 gallons. This exceeds the NEI reporting criterion of 100 gallons from a source containing licensed material. The Louisiana Department of Environmental Quality was notified at 1549 CST today.
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(xi) as an event requiring notification of the state government.
"The NRC resident inspector has been notified."
"On January 8, 2014, at 1439 CST, River Bend Station management determined that a spill discovered on the morning of January 7 was reportable in accordance with NEI 07-07 (Nuclear Energy Institute), Ground Water Protection Initiative. The spill was the result of freeze damage that occurred on a valve connected to the cooling tower blow-down line. Dams were installed to prevent the water from reaching any storm drains, and the spill was confined to the owner-controlled area. Since this system has the potential to contain diluted radioactive plant effluent, samples were collected for analysis. The leak was immediately reduced to a small drip and actions are in progress to completely isolate and repair the valve. The effluent was determined today to contain 4584 pico-curies per liter of tritium, but no detectable gamma activity. The calculated volume of the leak was between 100 and 1200 gallons. This exceeds the NEI reporting criterion of 100 gallons from a source containing licensed material. The Louisiana Department of Environmental Quality was notified at 1549 CST today.
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(xi) as an event requiring notification of the state government.
"The NRC resident inspector has been notified."