Event Notification Report for March 22, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/21/2016 - 03/22/2016
EVENT NUMBERS
5181751818518125181451815
Power Reactor
Event Number: 51817
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM BERNARD
HQ OPS Officer: DONG HWA PARK
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM BERNARD
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/22/2016
Notification Time: 23:33 [ET]
Event Date: 03/22/2016
Event Time: 19:34 [EDT]
Last Update Date: 03/22/2016
Notification Time: 23:33 [ET]
Event Date: 03/22/2016
Event Time: 19:34 [EDT]
Last Update Date: 03/22/2016
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):
DAVID AYRES (R2DO)
DAVID AYRES (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
DEGRADED CONDITION FOUND IN REACTOR COOLANT SYSTEM PIPING
"On Tuesday, March 22, 2016, while performing planned inspections of Unit 1 Reactor Coolant System piping welds, a flaw indication was identified on a 3 inch Charging Line connection to the Reactor Coolant System piping.
"NDE [Non-Destructive Evaluation] results showed a change in the flaw since the previous outage inspection and the condition is now determined as not meeting the acceptance criteria specified in ASME Code Section XI. As such, this indication is reportable under 10 CFR 50.72(b)(3)(ii)(A) as a degraded condition.
"An action plan is being developed. There is no impact on current Unit 1 refueling operations. This condition and the action plan have no impact to the health and safety of the public or employees.
"The NRC Resident [Inspector] has been notified."
"On Tuesday, March 22, 2016, while performing planned inspections of Unit 1 Reactor Coolant System piping welds, a flaw indication was identified on a 3 inch Charging Line connection to the Reactor Coolant System piping.
"NDE [Non-Destructive Evaluation] results showed a change in the flaw since the previous outage inspection and the condition is now determined as not meeting the acceptance criteria specified in ASME Code Section XI. As such, this indication is reportable under 10 CFR 50.72(b)(3)(ii)(A) as a degraded condition.
"An action plan is being developed. There is no impact on current Unit 1 refueling operations. This condition and the action plan have no impact to the health and safety of the public or employees.
"The NRC Resident [Inspector] has been notified."
Non-Agreement State
Event Number: 51818
Rep Org: BOTSFORD CANCER CENTER
Licensee: BOTSFORD CANCER CENTER
Region: 3
City: FARMINGTON HILLS State: MI
County:
License #: 21-08892-01
Agreement: N
Docket:
NRC Notified By: MISBAH GULAM
HQ OPS Officer: DONG HWA PARK
Licensee: BOTSFORD CANCER CENTER
Region: 3
City: FARMINGTON HILLS State: MI
County:
License #: 21-08892-01
Agreement: N
Docket:
NRC Notified By: MISBAH GULAM
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/23/2016
Notification Time: 16:12 [ET]
Event Date: 03/22/2016
Event Time: 00:00 [EDT]
Last Update Date: 03/23/2016
Notification Time: 16:12 [ET]
Event Date: 03/22/2016
Event Time: 00:00 [EDT]
Last Update Date: 03/23/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
ROBERT DALEY (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
ROBERT DALEY (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
BRACHYTHERAPY EQUIPMENT MALFUNCTION
On 3/22/16, a medical event occurred from a high dose rate brachytherapy treatment of the prostate. After the first catheter was delivered, the treatment console reported an error. The medical physicist went inside the treatment room with the survey meter to verify that the source retracted and the connections were fine.
The vendor was called out to the facility, and parts had to be replaced. The treatment was stopped, and the patient was notified.
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.
On 3/22/16, a medical event occurred from a high dose rate brachytherapy treatment of the prostate. After the first catheter was delivered, the treatment console reported an error. The medical physicist went inside the treatment room with the survey meter to verify that the source retracted and the connections were fine.
The vendor was called out to the facility, and parts had to be replaced. The treatment was stopped, and the patient was notified.
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.
Power Reactor
Event Number: 51812
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/22/2016
Notification Time: 06:38 [ET]
Event Date: 03/22/2016
Event Time: 01:04 [CDT]
Last Update Date: 03/22/2016
Notification Time: 06:38 [ET]
Event Date: 03/22/2016
Event Time: 01:04 [CDT]
Last Update Date: 03/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ROBERT DALEY (R3DO)
ROBERT DALEY (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 |
HIGH PRESSURE COOLANT INJECTION (HPCI) OIL LEAK
"On 3/22/2016 during performance of HPCI FLOW CONTROL SYSTEM DYNAMIC TEST PROCEDURE, an oil leak was discovered on the hydraulic control oil piping. HPCI had previously been declared INOPERABLE due to planned maintenance, however as a result of the oil leak HPCI remains INOPERABLE. This oil leak would have cause HPCI to be declared INOPERABLE had it been found outside of the planned maintenance. The plant remains at 100% power with no challenges to the health and safety of the public."
HPCI is in a 14 day technical specification to repair the oil leak.
The licensee notified the NRC Resident Inspector.
"On 3/22/2016 during performance of HPCI FLOW CONTROL SYSTEM DYNAMIC TEST PROCEDURE, an oil leak was discovered on the hydraulic control oil piping. HPCI had previously been declared INOPERABLE due to planned maintenance, however as a result of the oil leak HPCI remains INOPERABLE. This oil leak would have cause HPCI to be declared INOPERABLE had it been found outside of the planned maintenance. The plant remains at 100% power with no challenges to the health and safety of the public."
HPCI is in a 14 day technical specification to repair the oil leak.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 51814
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JIM SOUTHERTON
HQ OPS Officer: DONG HWA PARK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JIM SOUTHERTON
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/22/2016
Notification Time: 12:43 [ET]
Event Date: 03/22/2016
Event Time: 09:14 [EDT]
Last Update Date: 03/22/2016
Notification Time: 12:43 [ET]
Event Date: 03/22/2016
Event Time: 09:14 [EDT]
Last Update Date: 03/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
RAY MCKINLEY (R1DO)
FFD GROUP (EMAI)
RAY MCKINLEY (R1DO)
FFD GROUP (EMAI)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY - NON-LICENSED SUPERVISOR TESTED POSITIVE DURING RANDOM TESTING
"A non-licensed supervisor tested positive for alcohol during a random fitness for duty test. The individual's access to the facility has been denied.
"The licensee has notified the NRC Resident Inspector."
"A non-licensed supervisor tested positive for alcohol during a random fitness for duty test. The individual's access to the facility has been denied.
"The licensee has notified the NRC Resident Inspector."
Power Reactor
Event Number: 51815
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW ROBERTSON
HQ OPS Officer: KARL DIEDERICH
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW ROBERTSON
HQ OPS Officer: KARL DIEDERICH
Notification Date: 03/22/2016
Notification Time: 13:59 [ET]
Event Date: 03/22/2016
Event Time: 11:31 [EDT]
Last Update Date: 03/22/2016
Notification Time: 13:59 [ET]
Event Date: 03/22/2016
Event Time: 11:31 [EDT]
Last Update Date: 03/22/2016
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):
DAVID AYRES (R2DO)
DAVID AYRES (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
WATTS BAR AUTOMATIC REACTOR TRIP
"On March 22, 2016, at 1131 EDT, the Watts Bar Nuclear Plant Unit 1 (WBN1) reactor tripped due to the actuation of the Over Temperature Delta Temperature bistables. Concurrent with the reactor trip, the Auxiliary Feedwater (AFW) system actuated. All control rods inserted upon the reactor trip. Engineered Safety Function systems functioned as expected.
"WBN1 is currently stable in Mode 3. The Reactor Coolant system is being maintained at normal operating pressure and no-load temperature with decay heat removal via the Main Condenser steam dumps and the AFW system. The station is in a normal shutdown electrical alignment. Watts Bar Unit 2 is in mode 4 preparing for power ascension testing and was unaffected by the WBN1 event.
"The cause of the event is under investigation. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
The NRC Resident Inspector has been notified.
"On March 22, 2016, at 1131 EDT, the Watts Bar Nuclear Plant Unit 1 (WBN1) reactor tripped due to the actuation of the Over Temperature Delta Temperature bistables. Concurrent with the reactor trip, the Auxiliary Feedwater (AFW) system actuated. All control rods inserted upon the reactor trip. Engineered Safety Function systems functioned as expected.
"WBN1 is currently stable in Mode 3. The Reactor Coolant system is being maintained at normal operating pressure and no-load temperature with decay heat removal via the Main Condenser steam dumps and the AFW system. The station is in a normal shutdown electrical alignment. Watts Bar Unit 2 is in mode 4 preparing for power ascension testing and was unaffected by the WBN1 event.
"The cause of the event is under investigation. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
The NRC Resident Inspector has been notified.