Event Notification Report for June 13, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/12/2009 - 06/13/2009
EVENT NUMBERS
45128451294513145132
Power Reactor
Event Number: 45128
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE HENRY
HQ OPS Officer: RYAN ALEXANDER
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE HENRY
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 06/13/2009
Notification Time: 09:19 [ET]
Event Date: 06/13/2009
Event Time: 09:45 [EDT]
Last Update Date: 06/19/2009
Notification Time: 09:19 [ET]
Event Date: 06/13/2009
Event Time: 09:45 [EDT]
Last Update Date: 06/19/2009
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):
GERALD MCCOY (R2DO)
GERALD MCCOY (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 |
TECHNICAL SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE
"Planned maintenance activities are being performed today (June 13, 2009) on the Vogtle Nuclear Plant's Technical Support Center (TSC) power sources. This work activity is planned to be performed and completed expeditiously within approximately 3 days (78 hours). This maintenance activity is to perform a transformer replacement, perform preventative maintenance on several circuit breakers, perform preventative maintenance on the TSC HVAC unit, repair a leak on the Back-Up D/G [diesel generator] which provides a back-up power supply to the TSC HVAC, and other minor maintenance activities.
"If an emergency condition occurs that requires activation of the Technical Support Center during this work activity, contingency plans are in place to restore the TSC to fully functional status, with the time to restoration dependent on the stage of the work activity at the time the emergency occurs. Plans are to utilize the Shift Manager's Office in the Control Room as the Backup TSC for any declared emergency during the time the work activity is being performed. Procedure 91201-C, Activation and Operation of the Technical Support Center, provides instructions to direct TSC management to the Control Room to continue TSC activities if it is necessary to relocate from the primary TSC. At the beginning of the TSC outage, the ENN [Emergency Notification Network] and ERDS [Emergency Response Data System] will not be available until temporary power is being provided. This outage for the communications equipment will last from 2-4 hours, at which time they will be available.
"This event is reportable per 10 CFR 50.72 (b)(3)(xiii) as described in NUREG-1022, Rev. 2 since this work activity affects an emergency response facility for the duration of the evolution.
"The licensee has notified the NRC Resident Inspector."
The licensee provided notification of this issue prior to initiation of the maintenance per the licensee's 10 CFR 50.54(q) evaluation for the activity. The licensee intends to update this report when the temporary modification is completed such that the ERDS system is returned to service.
* * * UPDATE FROM MIKE HENRY TO HOWIE CROUCH @ 0735 EDT ON 6/15/09 * * *
The licensee has returned the ERDS system to service using temporary power. Preventive maintenance still continues on the TSC. The licensee has notified the NRC Resident Inspector.
Notified R2DO (McCoy).
* * * UPDATE ON 6/19/2009 AT 1153 FROM RICHARD COTTY TO MARK ABRAMOVITZ * * *
The ventilation system has been returned to its normal power supply at 1121 on 6/19/2009.
The licensee will notify the NRC Resident Inspector.
Notified the R2DO (Bartley).
"Planned maintenance activities are being performed today (June 13, 2009) on the Vogtle Nuclear Plant's Technical Support Center (TSC) power sources. This work activity is planned to be performed and completed expeditiously within approximately 3 days (78 hours). This maintenance activity is to perform a transformer replacement, perform preventative maintenance on several circuit breakers, perform preventative maintenance on the TSC HVAC unit, repair a leak on the Back-Up D/G [diesel generator] which provides a back-up power supply to the TSC HVAC, and other minor maintenance activities.
"If an emergency condition occurs that requires activation of the Technical Support Center during this work activity, contingency plans are in place to restore the TSC to fully functional status, with the time to restoration dependent on the stage of the work activity at the time the emergency occurs. Plans are to utilize the Shift Manager's Office in the Control Room as the Backup TSC for any declared emergency during the time the work activity is being performed. Procedure 91201-C, Activation and Operation of the Technical Support Center, provides instructions to direct TSC management to the Control Room to continue TSC activities if it is necessary to relocate from the primary TSC. At the beginning of the TSC outage, the ENN [Emergency Notification Network] and ERDS [Emergency Response Data System] will not be available until temporary power is being provided. This outage for the communications equipment will last from 2-4 hours, at which time they will be available.
"This event is reportable per 10 CFR 50.72 (b)(3)(xiii) as described in NUREG-1022, Rev. 2 since this work activity affects an emergency response facility for the duration of the evolution.
"The licensee has notified the NRC Resident Inspector."
The licensee provided notification of this issue prior to initiation of the maintenance per the licensee's 10 CFR 50.54(q) evaluation for the activity. The licensee intends to update this report when the temporary modification is completed such that the ERDS system is returned to service.
* * * UPDATE FROM MIKE HENRY TO HOWIE CROUCH @ 0735 EDT ON 6/15/09 * * *
The licensee has returned the ERDS system to service using temporary power. Preventive maintenance still continues on the TSC. The licensee has notified the NRC Resident Inspector.
Notified R2DO (McCoy).
* * * UPDATE ON 6/19/2009 AT 1153 FROM RICHARD COTTY TO MARK ABRAMOVITZ * * *
The ventilation system has been returned to its normal power supply at 1121 on 6/19/2009.
The licensee will notify the NRC Resident Inspector.
Notified the R2DO (Bartley).
Power Reactor
Event Number: 45129
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MARK DAVIS
HQ OPS Officer: DONALD NORWOOD
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MARK DAVIS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/13/2009
Notification Time: 16:36 [ET]
Event Date: 06/13/2009
Event Time: 13:53 [CDT]
Last Update Date: 06/13/2009
Notification Time: 16:36 [ET]
Event Date: 06/13/2009
Event Time: 13:53 [CDT]
Last Update Date: 06/13/2009
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):
PATTY PELKE (R3DO)
PATTY PELKE (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO EMERGENCY SIREN ACTUATION
"At approximately 1353 (CDT), [the licensee] received notification of a single siren actuation in the Early Warning Siren System. This call came from a Pierce County 911 dispatcher after they received a call from a local resident. The siren system vendor reports the siren actuated at approximately 1310 and was inactivated by Pierce County Deputies at 1345 using the local emergency key. The siren (P14) remains out of service and is the only siren in Pierce County currently out of service. The licensee's procedural requirement to maintain at least 70% of sirens within the 10 mile EPZ is still met. Neither Pierce County nor the licensee intend on making a press release."
The licensee notified the Pierce County Emergency Government Manager.
The licensee notified the NRC Resident Inspector
"At approximately 1353 (CDT), [the licensee] received notification of a single siren actuation in the Early Warning Siren System. This call came from a Pierce County 911 dispatcher after they received a call from a local resident. The siren system vendor reports the siren actuated at approximately 1310 and was inactivated by Pierce County Deputies at 1345 using the local emergency key. The siren (P14) remains out of service and is the only siren in Pierce County currently out of service. The licensee's procedural requirement to maintain at least 70% of sirens within the 10 mile EPZ is still met. Neither Pierce County nor the licensee intend on making a press release."
The licensee notified the Pierce County Emergency Government Manager.
The licensee notified the NRC Resident Inspector
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 45131
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: NICK RULLMAN
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: NICK RULLMAN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/13/2009
Notification Time: 19:20 [ET]
Event Date: 06/13/2009
Event Time: 11:30 [PDT]
Last Update Date: 06/19/2009
Notification Time: 19:20 [ET]
Event Date: 06/13/2009
Event Time: 11:30 [PDT]
Last Update Date: 06/19/2009
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):
GEOFFREY MILLER (R4DO)
GEOFFREY MILLER (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 |
DEGRADED CONDITION DUE TO REACTOR COOLANT PRESSURE BOUNDARY LEAK
"This notification is made pursuant to 10CFR50.72(b)(3)(ii) to report degradation of a principal safety barrier. During ASME Section XI (Table 2500-1 Code Category B-P, Item Number B15.10) refuel outage system leak testing of the reactor vessel and reactor coolant pressure boundary, leakage of approximately 1 drop per minute was detected from the bonnet vent leak-off connection on the reactor recirculation pump inlet isolation valve (RRC-V-23A) in the reactor coolant recirculation loop A. This condition is consistent with example (A)(2) provided in NUREG-1022, rev. 2 'Event Reporting Guidelines 10CFR50.72 and 50.73.' This example indicates that reporting under the above criteria is required for 'Welding or material defects in the primary coolant system which cannot be found acceptable under ASME Section XI, Table IWB-3410-1, 'Acceptance Standards.'
"A cause evaluation will be performed and a 60-day follow-up report provided pursuant to the corresponding 10CFR50.73 reporting requirement."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM FRED SCHILL TO VINCE KLCO AT 1955 EDT ON 6/19/09 * * *
"Subsequent evaluation of the point where leakage was observed reveals that the 1 drop per minute leakage from RRC-V-23A was actually emanating from the packing chamber leak-off connection and not from the bonnet vent leak-off connection as reported. The packing chamber leak-off connection provides a means to monitor leakage from the packing. It does not provide a pressure containing function at its location on the valve and, therefore, is not part of the Reactor Coolant Pressure Boundary (RCPB) as defined in Part 50.2.
"Since the packing chamber leak-off connection is not a pressure-retaining structure it is not part of the RCPB, therefore the condition reported in event report #45131 is not a degradation of a principle safety barrier and is not reportable pursuant to Part 50.72(b)(3)(ii)(A). For this reason, the subject event report is hereby retracted."
The licensee notified the NRC Resident Inspector.
R4DO (Cain) notified.
"This notification is made pursuant to 10CFR50.72(b)(3)(ii) to report degradation of a principal safety barrier. During ASME Section XI (Table 2500-1 Code Category B-P, Item Number B15.10) refuel outage system leak testing of the reactor vessel and reactor coolant pressure boundary, leakage of approximately 1 drop per minute was detected from the bonnet vent leak-off connection on the reactor recirculation pump inlet isolation valve (RRC-V-23A) in the reactor coolant recirculation loop A. This condition is consistent with example (A)(2) provided in NUREG-1022, rev. 2 'Event Reporting Guidelines 10CFR50.72 and 50.73.' This example indicates that reporting under the above criteria is required for 'Welding or material defects in the primary coolant system which cannot be found acceptable under ASME Section XI, Table IWB-3410-1, 'Acceptance Standards.'
"A cause evaluation will be performed and a 60-day follow-up report provided pursuant to the corresponding 10CFR50.73 reporting requirement."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM FRED SCHILL TO VINCE KLCO AT 1955 EDT ON 6/19/09 * * *
"Subsequent evaluation of the point where leakage was observed reveals that the 1 drop per minute leakage from RRC-V-23A was actually emanating from the packing chamber leak-off connection and not from the bonnet vent leak-off connection as reported. The packing chamber leak-off connection provides a means to monitor leakage from the packing. It does not provide a pressure containing function at its location on the valve and, therefore, is not part of the Reactor Coolant Pressure Boundary (RCPB) as defined in Part 50.2.
"Since the packing chamber leak-off connection is not a pressure-retaining structure it is not part of the RCPB, therefore the condition reported in event report #45131 is not a degradation of a principle safety barrier and is not reportable pursuant to Part 50.72(b)(3)(ii)(A). For this reason, the subject event report is hereby retracted."
The licensee notified the NRC Resident Inspector.
R4DO (Cain) notified.
Other Nuclear Material
Event Number: 45132
Rep Org: ACUREN INSPECTIONS
Licensee: ACUREN INSPECTIONS
Region: 3
City: LINDEN State: IN
County:
License #: 42-27593-01
Agreement: N
Docket:
NRC Notified By: MARK RINKE
HQ OPS Officer: JOHN KNOKE
Licensee: ACUREN INSPECTIONS
Region: 3
City: LINDEN State: IN
County:
License #: 42-27593-01
Agreement: N
Docket:
NRC Notified By: MARK RINKE
HQ OPS Officer: JOHN KNOKE
Notification Date: 06/15/2009
Notification Time: 08:53 [ET]
Event Date: 06/13/2009
Event Time: 09:15 [EDT]
Last Update Date: 06/15/2009
Notification Time: 08:53 [ET]
Event Date: 06/13/2009
Event Time: 09:15 [EDT]
Last Update Date: 06/15/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
PATTY PELKE (R3DO)
ANGELA MCINTOSH (FSME)
PATTY PELKE (R3DO)
ANGELA MCINTOSH (FSME)
STUCK SOURCE IN RADIOGRAPHY CAMERA
Two radiographers were examining welds on a tank when the magnetic stand that was attached to the side of the tank fell. The Amersham radiography camera (model 660B) was secured to the tank by a shackle and swung freely. This mishap damaged the guide tube extension and crimped the guide tube at the source connect. When the radiographers realized the source (65.2 Ci Ir-192) was stuck they followed O&E (Radiographic Operating & Emergency) procedures and notified the FRSO (Facility Radiation Safety Officer). At that same time the radiographers reassessed the area and established appropriate boundaries.
The tank being examined was in an area away from the general public, therefore the public was not exposed. The FRSO, in retrieving the stuck source, was not over exposed.
Both individuals on the job-site, as well as the FRSO are carded radiographers. FRSO is also trained in source retrieval.
Corrective actions planned by the licensee to prevent recurrence of this incident is to use two lifts instead of one, which should prevent the stand from falling to its farthest point.
Two radiographers were examining welds on a tank when the magnetic stand that was attached to the side of the tank fell. The Amersham radiography camera (model 660B) was secured to the tank by a shackle and swung freely. This mishap damaged the guide tube extension and crimped the guide tube at the source connect. When the radiographers realized the source (65.2 Ci Ir-192) was stuck they followed O&E (Radiographic Operating & Emergency) procedures and notified the FRSO (Facility Radiation Safety Officer). At that same time the radiographers reassessed the area and established appropriate boundaries.
The tank being examined was in an area away from the general public, therefore the public was not exposed. The FRSO, in retrieving the stuck source, was not over exposed.
Both individuals on the job-site, as well as the FRSO are carded radiographers. FRSO is also trained in source retrieval.
Corrective actions planned by the licensee to prevent recurrence of this incident is to use two lifts instead of one, which should prevent the stand from falling to its farthest point.