Event Notification Report for July 10, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/09/2014 - 07/10/2014
EVENT NUMBERS
50265502665026950369
Power Reactor
Event Number: 50265
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WESLEY CONKLE
HQ OPS Officer: JOHN SHOEMAKER
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WESLEY CONKLE
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 07/10/2014
Notification Time: 09:17 [ET]
Event Date: 07/10/2014
Event Time: 04:45 [CDT]
Last Update Date: 07/10/2014
Notification Time: 09:17 [ET]
Event Date: 07/10/2014
Event Time: 04:45 [CDT]
Last Update Date: 07/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
ANTHONY MASTERS (R2DO)
ANTHONY MASTERS (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 98 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
"At 0445 [CDT] on July 10, 2014, Browns Ferry Unit 2 initiated actions to commence a reactor shutdown to comply with TS LCO 3.0.3. TS LCO 3.0.3 was entered at 0355 [CDT] and was required due to the 'C' Emergency Diesel Generator becoming inoperable after isolating a leak on the Emergency Equipment Cooling Water System. Currently, a 7 day TS LCO Action 3.5.1.A is in effect due to ongoing scheduled Core Spray Loop I maintenance outage. The declaration of inoperability of the equipment supported by the 'C' Emergency Diesel Generator, Core Spray Loop II, along with the redundant Core Spray system inoperable for maintenance resulted in TS LCO 3.0.3 for Unit 2. TS LCO 3.0.3 requires actions to be initiated within one hour; to place the unit in MODE 2 within 10 hours; MODE 3 within 13 hours; and MODE 4 within 37 hours.
"This event requires a 4 hour report lAW 50.72(b)(2)(i), 'The initiation of any nuclear plant shutdown required by the plant's Technical Specifications.'
"Actions were taken to restore the Core Spray System to Operable status and LCO 3.0.3 was exited at 0735 [CDT] on July 10, 2014.
"The NRC Resident Inspector has been notified.
"This event was entered into the Corrective Action Program."
Browns Ferry Unit 2 had reduced power to 98% when LCO 3.0.3 was exited, the power reduction was suspended, and preparations are being made to return power to 100%. There is no impact on Units 1 or 3.
"At 0445 [CDT] on July 10, 2014, Browns Ferry Unit 2 initiated actions to commence a reactor shutdown to comply with TS LCO 3.0.3. TS LCO 3.0.3 was entered at 0355 [CDT] and was required due to the 'C' Emergency Diesel Generator becoming inoperable after isolating a leak on the Emergency Equipment Cooling Water System. Currently, a 7 day TS LCO Action 3.5.1.A is in effect due to ongoing scheduled Core Spray Loop I maintenance outage. The declaration of inoperability of the equipment supported by the 'C' Emergency Diesel Generator, Core Spray Loop II, along with the redundant Core Spray system inoperable for maintenance resulted in TS LCO 3.0.3 for Unit 2. TS LCO 3.0.3 requires actions to be initiated within one hour; to place the unit in MODE 2 within 10 hours; MODE 3 within 13 hours; and MODE 4 within 37 hours.
"This event requires a 4 hour report lAW 50.72(b)(2)(i), 'The initiation of any nuclear plant shutdown required by the plant's Technical Specifications.'
"Actions were taken to restore the Core Spray System to Operable status and LCO 3.0.3 was exited at 0735 [CDT] on July 10, 2014.
"The NRC Resident Inspector has been notified.
"This event was entered into the Corrective Action Program."
Browns Ferry Unit 2 had reduced power to 98% when LCO 3.0.3 was exited, the power reduction was suspended, and preparations are being made to return power to 100%. There is no impact on Units 1 or 3.
Power Reactor
Event Number: 50266
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: GENE DAMMANN
HQ OPS Officer: DONG HWA PARK
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: GENE DAMMANN
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/10/2014
Notification Time: 13:29 [ET]
Event Date: 07/10/2014
Event Time: 08:38 [CDT]
Last Update Date: 07/10/2014
Notification Time: 13:29 [ET]
Event Date: 07/10/2014
Event Time: 08:38 [CDT]
Last Update Date: 07/10/2014
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):
DAVID HILLS (R3DO)
DAVID HILLS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH RANGE SHIELD BUILDING VENT STACK GAS MONITOR REMOVED FROM SERVICE FOR MAINTENANCE
"At 0830 CDT on July 10, 2014, 2R-50 High Range Shield Building Vent Stack Gas Monitor was removed from service for planned maintenance. 2R-50 was planned for an out of service time of approximately 8 hours. The clearance order associated with the work isolated the flow path to the sample pump. Subsequent to the execution of the clearance order, it was discovered that the flow path to the alternate sample pump was also unavailable inhibiting the ability to implement compensatory measures. With 2R-50 rad monitor sample pump out of service and no alternate sampling available, timely classification of two Emergency Action Levels (EALs), SAE (Notification of Site Area Emergency) and General Emergency classifications would not be achievable. This results in a Loss of Emergency Assessment Capability while 2R-50 is out of service. This is a reportable condition in accordance with 10 CFR 50.72(b)(3)(xiii).
"Unit 2 Shield Building Ventilation Stack is also monitored by the Shield Building Vent Gas Monitor, 2R-22, which is used for the same purpose in NUE (Notification of Unusual Event) and Alert classifications. 2R-22 is being monitored and is indicating normal values. There are no radioactive leaks that will impact the Shield Building as evidenced by normal readings on 2R-22 prior to removing 2R-50 from service. This planned maintenance will not result in the unplanned release of radioactivity to the environment and will not adversely affect the safe operation
of the plant or health and safety of the public.
"The licensee has notified the NRC Resident Inspector."
"At 0830 CDT on July 10, 2014, 2R-50 High Range Shield Building Vent Stack Gas Monitor was removed from service for planned maintenance. 2R-50 was planned for an out of service time of approximately 8 hours. The clearance order associated with the work isolated the flow path to the sample pump. Subsequent to the execution of the clearance order, it was discovered that the flow path to the alternate sample pump was also unavailable inhibiting the ability to implement compensatory measures. With 2R-50 rad monitor sample pump out of service and no alternate sampling available, timely classification of two Emergency Action Levels (EALs), SAE (Notification of Site Area Emergency) and General Emergency classifications would not be achievable. This results in a Loss of Emergency Assessment Capability while 2R-50 is out of service. This is a reportable condition in accordance with 10 CFR 50.72(b)(3)(xiii).
"Unit 2 Shield Building Ventilation Stack is also monitored by the Shield Building Vent Gas Monitor, 2R-22, which is used for the same purpose in NUE (Notification of Unusual Event) and Alert classifications. 2R-22 is being monitored and is indicating normal values. There are no radioactive leaks that will impact the Shield Building as evidenced by normal readings on 2R-22 prior to removing 2R-50 from service. This planned maintenance will not result in the unplanned release of radioactivity to the environment and will not adversely affect the safe operation
of the plant or health and safety of the public.
"The licensee has notified the NRC Resident Inspector."
Power Reactor
Event Number: 50269
Facility: CRYSTAL RIVER
Region: 1 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: WILLIAM G. CARR
HQ OPS Officer: DONG HWA PARK
Region: 1 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: WILLIAM G. CARR
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/10/2014
Notification Time: 16:41 [ET]
Event Date: 07/10/2014
Event Time: 09:59 [EDT]
Last Update Date: 07/10/2014
Notification Time: 16:41 [ET]
Event Date: 07/10/2014
Event Time: 09:59 [EDT]
Last Update Date: 07/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
ANNE DeFRANCISCO (R1DO)
ANNE DeFRANCISCO (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | 0 |
NON-LICENSED EMPLOYEE SUPERVISOR FOUND IN VIOLATION OF FITNESS-FOR-DUTY POLICY
"A non-licensed employee supervisor has been found in violation of the Duke Energy Fitness for Duty Policy. The individual's access to the plant has been suspended. The licensee has notified the NRC Region 1 [Hammann]."
"A non-licensed employee supervisor has been found in violation of the Duke Energy Fitness for Duty Policy. The individual's access to the plant has been suspended. The licensee has notified the NRC Region 1 [Hammann]."
Non-Agreement State
Event Number: 50369
Rep Org: BOTSFORD HOSPITAL
Licensee: BOTSFORD HOSPITAL
Region: 3
City: FARMINGTON HILLS State: MI
County:
License #: 21-08892-01
Agreement: N
Docket:
NRC Notified By: TEAMOUR NURUSHEV
HQ OPS Officer: CHARLES TEAL
Licensee: BOTSFORD HOSPITAL
Region: 3
City: FARMINGTON HILLS State: MI
County:
License #: 21-08892-01
Agreement: N
Docket:
NRC Notified By: TEAMOUR NURUSHEV
HQ OPS Officer: CHARLES TEAL
Notification Date: 08/14/2014
Notification Time: 17:17 [ET]
Event Date: 07/10/2014
Event Time: 13:20 [EDT]
Last Update Date: 08/14/2014
Notification Time: 17:17 [ET]
Event Date: 07/10/2014
Event Time: 13:20 [EDT]
Last Update Date: 08/14/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
10 CFR Section:
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
Person (Organization):
MICHAEL KUNOWSKI (R3DO)
FSME EVENTS RESOURCE (EMAI)
MICHAEL KUNOWSKI (R3DO)
FSME EVENTS RESOURCE (EMAI)
PATIENT RECEIVED LESS THAN PRESCRIBED DOSE
A patient undergoing High Dose Rate Brachytherapy using Ir-192 was prescribed 700 cGy per fraction and only received 700 cGy to 60% of the planned volume.
The patient was scheduled for two treatments. The first treatment was successfully administered to the patient on 6/26/14. When the patient returned for the second treatment on 7/10/14 the HDR afterloader was loaded with the treatment plan for the original treatment instead of the second treatment. This resulted in the patient not receiving the full prescribed treatment.
The licensee discovered the problem during an audit when the number of catheters did not match.
There are no adverse health effects expected as a result of this treatment.
The licensee has contacted the vender to determine a way to remove old treatment plans from the machine to ensure this does not happen in the future.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
A patient undergoing High Dose Rate Brachytherapy using Ir-192 was prescribed 700 cGy per fraction and only received 700 cGy to 60% of the planned volume.
The patient was scheduled for two treatments. The first treatment was successfully administered to the patient on 6/26/14. When the patient returned for the second treatment on 7/10/14 the HDR afterloader was loaded with the treatment plan for the original treatment instead of the second treatment. This resulted in the patient not receiving the full prescribed treatment.
The licensee discovered the problem during an audit when the number of catheters did not match.
There are no adverse health effects expected as a result of this treatment.
The licensee has contacted the vender to determine a way to remove old treatment plans from the machine to ensure this does not happen in the future.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.