Event Notification Report for April 10, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/09/2013 - 04/10/2013
EVENT NUMBERS
4890748908489094891248913
Power Reactor
Event Number: 48907
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVE RICHARDSON
HQ OPS Officer: PETE SNYDER
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVE RICHARDSON
HQ OPS Officer: PETE SNYDER
Notification Date: 04/10/2013
Notification Time: 11:06 [ET]
Event Date: 04/10/2013
Event Time: 11:30 [EDT]
Last Update Date: 04/10/2013
Notification Time: 11:06 [ET]
Event Date: 04/10/2013
Event Time: 11:30 [EDT]
Last Update Date: 04/10/2013
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):
JAMES TRAPP (R1DO)
JAMES TRAPP (R1DO)
| 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 TECHNICAL SUPPORT CENTER OUTAGE
"A planned work package (52343687-01) at the James A. FitzPatrick (JAF) Nuclear Power Plant will be performed for DOP/Freon Testing TSCVASS as required per TS 5.5.8 Ventilation Filter Testing Program. The testing requires breaking the boundary into the Technical Support Center (TSC) ventilation system to obtain a charcoal sample. Therefore, the TSC ventilation system will be rendered nonfunctional during the duration of this work activity. The TSC ventilation is expected to be out of service for approximately 6 hours.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the station Emergency Plant Manager will relocate the TSC staff to an alternate TSC location In accordance with applicable site procedures giving first consideration to the Control Room. TSC facility leads have been made aware of this contingency.
"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the potential loss of an emergency response facility (ERF). An update will be provided once the TSC ventilation has been restored to normal operation.
"The NRC Resident Inspector has been notified."
* * * UPDATE ON 4/10/13 AT 1717 EDT FROM DAVE RICHARDSON TO DONG PARK * * *
"This is an update from EN #48907. Planned maintenance has been completed on the Technical Support Center (TSC) ventilation system. The TSC filtered ventilation system has been restored to normal standby lineup.
"The NRC Resident Inspector has been informed."
"A planned work package (52343687-01) at the James A. FitzPatrick (JAF) Nuclear Power Plant will be performed for DOP/Freon Testing TSCVASS as required per TS 5.5.8 Ventilation Filter Testing Program. The testing requires breaking the boundary into the Technical Support Center (TSC) ventilation system to obtain a charcoal sample. Therefore, the TSC ventilation system will be rendered nonfunctional during the duration of this work activity. The TSC ventilation is expected to be out of service for approximately 6 hours.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the station Emergency Plant Manager will relocate the TSC staff to an alternate TSC location In accordance with applicable site procedures giving first consideration to the Control Room. TSC facility leads have been made aware of this contingency.
"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the potential loss of an emergency response facility (ERF). An update will be provided once the TSC ventilation has been restored to normal operation.
"The NRC Resident Inspector has been notified."
* * * UPDATE ON 4/10/13 AT 1717 EDT FROM DAVE RICHARDSON TO DONG PARK * * *
"This is an update from EN #48907. Planned maintenance has been completed on the Technical Support Center (TSC) ventilation system. The TSC filtered ventilation system has been restored to normal standby lineup.
"The NRC Resident Inspector has been informed."
Power Reactor
Event Number: 48908
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN PANAGOTOPULOS
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN PANAGOTOPULOS
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/10/2013
Notification Time: 13:13 [ET]
Event Date: 04/10/2013
Event Time: 09:30 [EDT]
Last Update Date: 04/10/2013
Notification Time: 13:13 [ET]
Event Date: 04/10/2013
Event Time: 09:30 [EDT]
Last Update Date: 04/10/2013
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):
JAMES TRAPP (R1DO)
JAMES TRAPP (R1DO)
| 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 EMERGENCY NOTIFICATION SYSTEM TELEPHONE
"On April 10, 2013 at 0930 [EDT] Hope Creek Operations personnel identified that the NRC ENS phone line was unavailable for Hope Creek Generating Station. The loss of the NRC ENS line was verified by the Hope Creek Shift Manager via backup land line communication to the NRC. The NRC Operations Center has an open repair ticket with the phone service provider.
"The loss of the phone line had no effect on plant operation and the unit remains at 100% power.
"Additionally, Emergency Response Data System (ERDS) capability was verified to remain intact and is available to transmit data.
"No personnel injuries resulted from the event.
"The NRC Resident Inspector has been informed."
"On April 10, 2013 at 0930 [EDT] Hope Creek Operations personnel identified that the NRC ENS phone line was unavailable for Hope Creek Generating Station. The loss of the NRC ENS line was verified by the Hope Creek Shift Manager via backup land line communication to the NRC. The NRC Operations Center has an open repair ticket with the phone service provider.
"The loss of the phone line had no effect on plant operation and the unit remains at 100% power.
"Additionally, Emergency Response Data System (ERDS) capability was verified to remain intact and is available to transmit data.
"No personnel injuries resulted from the event.
"The NRC Resident Inspector has been informed."
Power Reactor
Event Number: 48909
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JOHN OHRENBERGER
HQ OPS Officer: DONG HWA PARK
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JOHN OHRENBERGER
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/10/2013
Notification Time: 16:19 [ET]
Event Date: 04/10/2013
Event Time: 13:14 [EDT]
Last Update Date: 01/15/2014
Notification Time: 16:19 [ET]
Event Date: 04/10/2013
Event Time: 13:14 [EDT]
Last Update Date: 01/15/2014
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):
JAMES TRAPP (R1DO)
JAMES TRAPP (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 86 | Power Operation | 86 | Power Operation |
MASSACHUSETTS AGENCIES NOTIFIED REGARDING NEUTRALIZING SUMP DISCHARGE LINE INSPECTION
"At 1314 hours on Wednesday, April 10, 2013 during a boroscopic inspection of the sub-surface portions of the Neutralizing Sump Discharge Line, Pilgrim Station discovered indications of a separation in the line. The line is currently isolated and no discharges were in progress during the planned inspection. This line is used infrequently to discharge permitted liquids that have the potential to contain radiological contamination. This
notification is conservatively being made in accordance with Pilgrim site procedures with direct voluntary communications with offsite agencies.
"There is no impact on the safe operation of the plant and personnel are investigating the cause.
"The [NRC] Resident Inspector staff has been informed of this notification.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi).
"The licensee will notify the Massachusetts Emergency Management Agency (MEMA) and other state agencies."
* * * UPDATE AT 1700 EST ON 01/15/14 FROM STAN PAUL TO S. SANDIN * * *
"Entergy Pilgrim Station has twenty three (23) groundwater monitoring wells used to sample for tritium and other radioactive nuclides in accordance with the Nuclear Energy Institute's (NEI) voluntary Groundwater Protection Initiative (GPI). One of the newly installed wells, MW-219, located in the vicinity of a Catch Basin adjacent to the Reactor Building Auxiliary Bay and in the flow path of the Neutralizing Sump Discharge Line indicated an elevated level of tritium (H3), that exceed the limits established by the NEI Groundwater Protection initiative and the Nuclear Regulatory Commission's (NRC) limits for liquid effluent release. A protocol for more frequent sampling has been instituted and an investigation of the cause is underway. To date, tritium is the only isotope detected In the groundwater monitoring well samples collected at the site. This supplemental information has been voluntarily communicated to Federal, State and local stakeholders.
"The NRC Resident Inspector has been notified of this update. This is an update to the 4-hour non-emergency notification made in accordance with 50.72(b)(2)(xi) on April 10, 2013 at 1619 hours."
Notified R1DO (Rogge).
"At 1314 hours on Wednesday, April 10, 2013 during a boroscopic inspection of the sub-surface portions of the Neutralizing Sump Discharge Line, Pilgrim Station discovered indications of a separation in the line. The line is currently isolated and no discharges were in progress during the planned inspection. This line is used infrequently to discharge permitted liquids that have the potential to contain radiological contamination. This
notification is conservatively being made in accordance with Pilgrim site procedures with direct voluntary communications with offsite agencies.
"There is no impact on the safe operation of the plant and personnel are investigating the cause.
"The [NRC] Resident Inspector staff has been informed of this notification.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi).
"The licensee will notify the Massachusetts Emergency Management Agency (MEMA) and other state agencies."
* * * UPDATE AT 1700 EST ON 01/15/14 FROM STAN PAUL TO S. SANDIN * * *
"Entergy Pilgrim Station has twenty three (23) groundwater monitoring wells used to sample for tritium and other radioactive nuclides in accordance with the Nuclear Energy Institute's (NEI) voluntary Groundwater Protection Initiative (GPI). One of the newly installed wells, MW-219, located in the vicinity of a Catch Basin adjacent to the Reactor Building Auxiliary Bay and in the flow path of the Neutralizing Sump Discharge Line indicated an elevated level of tritium (H3), that exceed the limits established by the NEI Groundwater Protection initiative and the Nuclear Regulatory Commission's (NRC) limits for liquid effluent release. A protocol for more frequent sampling has been instituted and an investigation of the cause is underway. To date, tritium is the only isotope detected In the groundwater monitoring well samples collected at the site. This supplemental information has been voluntarily communicated to Federal, State and local stakeholders.
"The NRC Resident Inspector has been notified of this update. This is an update to the 4-hour non-emergency notification made in accordance with 50.72(b)(2)(xi) on April 10, 2013 at 1619 hours."
Notified R1DO (Rogge).
Power Reactor
Event Number: 48912
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: MARK MITCHELL
HQ OPS Officer: DONG HWA PARK
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: MARK MITCHELL
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/10/2013
Notification Time: 20:40 [ET]
Event Date: 04/10/2013
Event Time: 09:52 [PDT]
Last Update Date: 04/10/2013
Notification Time: 20:40 [ET]
Event Date: 04/10/2013
Event Time: 09:52 [PDT]
Last Update Date: 04/10/2013
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):
RICK DEESE (R4DO)
RICK DEESE (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 ACCESS DOOR NOT FULLY CLOSED
"On April 10, 2013, at 0952 [PDT] it was discovered that an access door to the reactor building stack was not fully closed. The door was subsequently closed by operations. On March 16, 2013, the reactor building exhaust flow rate took a step change decrease. Initially the reduction in flow was thought to be a reactor building ventilation damper issue. On April 3, 2013, after walkdown of the reactor building dampers and verification of proper system lineup, the reactor building exhaust flow rate monitor was declared inoperable and a substitute value was used for the exhaust flow rate in accordance with station procedures.
"Had an actual event involving an offsite release occurred during the time period from March 16, 2013, to April 3, 2013, an inaccurate reactor building exhaust flow rate might have been used to calculate offsite dose. This would only impact dose calculations at lower doses and potentially delay declaration of an Unusual Event. This is being reported as a major loss of assessment capability. At higher dose rates, the reactor building ventilation isolates and Standby Gas Treatment is operated. Standby Gas Treatment flow rate measurement would be unaffected. The intermediate and high range radiation monitors for the reactor building effluent remained fully functional and would have provided an accurate measure of activity concentration.
"Upon closure of the reactor building stack door, the reactor building exhaust flow rate returned to normal and emergency preparedness assessment capability was restored."
The licensee has notified the NRC Resident Inspector.
"On April 10, 2013, at 0952 [PDT] it was discovered that an access door to the reactor building stack was not fully closed. The door was subsequently closed by operations. On March 16, 2013, the reactor building exhaust flow rate took a step change decrease. Initially the reduction in flow was thought to be a reactor building ventilation damper issue. On April 3, 2013, after walkdown of the reactor building dampers and verification of proper system lineup, the reactor building exhaust flow rate monitor was declared inoperable and a substitute value was used for the exhaust flow rate in accordance with station procedures.
"Had an actual event involving an offsite release occurred during the time period from March 16, 2013, to April 3, 2013, an inaccurate reactor building exhaust flow rate might have been used to calculate offsite dose. This would only impact dose calculations at lower doses and potentially delay declaration of an Unusual Event. This is being reported as a major loss of assessment capability. At higher dose rates, the reactor building ventilation isolates and Standby Gas Treatment is operated. Standby Gas Treatment flow rate measurement would be unaffected. The intermediate and high range radiation monitors for the reactor building effluent remained fully functional and would have provided an accurate measure of activity concentration.
"Upon closure of the reactor building stack door, the reactor building exhaust flow rate returned to normal and emergency preparedness assessment capability was restored."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 48913
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: ADAM MANELLA
HQ OPS Officer: PETE SNYDER
Region: 4 State: CA
Unit: [] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: ADAM MANELLA
HQ OPS Officer: PETE SNYDER
Notification Date: 04/11/2013
Notification Time: 04:29 [ET]
Event Date: 04/10/2013
Event Time: 23:26 [PDT]
Last Update Date: 04/11/2013
Notification Time: 04:29 [ET]
Event Date: 04/10/2013
Event Time: 23:26 [PDT]
Last Update Date: 04/11/2013
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):
RICK DEESE (R4DO)
RICK DEESE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
| 3 | N | N | 0 | Defueled | 0 | Defueled |
FBI NOTIFIED DUE TO DEGRADED SECURITY RADIO COMMUNICATIONS
"At 2253 PDT on 4/10/13, SONGS experienced degraded on-site radio communications during planned maintenance on radio systems. Radio communications were restored at 2315 PDT."
The licensee will notify the NRC Resident Inspector.
"At 2253 PDT on 4/10/13, SONGS experienced degraded on-site radio communications during planned maintenance on radio systems. Radio communications were restored at 2315 PDT."
The licensee will notify the NRC Resident Inspector.