Event Notification Report for January 04, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/03/2018 - 01/04/2018
Power Reactor
Event Number: 53147
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MICHAEL MCDONNELL
HQ OPS Officer: DAVID AIRD
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MICHAEL MCDONNELL
HQ OPS Officer: DAVID AIRD
Notification Date: 01/04/2018
Notification Time: 17:57 [ET]
Event Date: 01/04/2018
Event Time: 14:10 [EST]
Last Update Date: 01/04/2018
Notification Time: 17:57 [ET]
Event Date: 01/04/2018
Event Time: 14:10 [EST]
Last Update Date: 01/04/2018
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):
DAVE WERKHEISER (R1DO)
MICHAEL F. KING (NRR)
WILLIAM GOTT (IRD)
DAVE WERKHEISER (R1DO)
MICHAEL F. KING (NRR)
WILLIAM GOTT (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 81 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO PARTIAL LOSS OF OFFSITE POWER DURING WINTER STORM
"On January 4, 2018, at 1410 hours EST, with the reactor at approximately 100 percent power and steady state conditions, the winter storm across the Northeast caused the loss of offsite 345 kV Line 342. Reactor power was reduced to approximately 81 percent and a procedurally required manual reactor scram was initiated. All control rods fully inserted.
"As a result of the reactor scram, indicated reactor water level decreased, as expected, to less than +12 inches resulting in automatic actuation of the Primary Containment Isolation Systems for Group II - Primary Containment Isolation and Reactor Building Isolation System, and Group VI - Reactor Water Cleanup System.
"Reactor Water Level was restored to the normal operating band. The Primary Containment Isolation Systems have been reset. The Reactor Protection System signal has been reset.
"Following the reactor scram, the non-safety related Control Rod Drive Pump "B" tripped on low suction pressure. Control Rod Drive Pump "A" was placed in service. All other systems operated as expected, in accordance with design.
"This event is reportable per the requirements of Title 10, Code of Federal Regulations (CFR) 50.72 (b)(2)(iv)(B) - "RPS Actuation" and 10 CFR 50.72 (b)(3)(iv)(A) - "Specified System Actuation."
"This event had no impact on the health and/or safety of the public.
"The NRC Resident Inspector has been notified."
The main steam isolation valves are open with decay heat being removed via steam to the main condenser.
Offsite power is still available from 345kV line 355. As a contingency, emergency diesel generators are running and powering safety busses per licensee procedure.
The licensee notified the Commonwealth of Massachusetts. The licensee will be notifying the town of Plymouth as part of their local notifications. The licensee will be issuing a press release.
"On January 4, 2018, at 1410 hours EST, with the reactor at approximately 100 percent power and steady state conditions, the winter storm across the Northeast caused the loss of offsite 345 kV Line 342. Reactor power was reduced to approximately 81 percent and a procedurally required manual reactor scram was initiated. All control rods fully inserted.
"As a result of the reactor scram, indicated reactor water level decreased, as expected, to less than +12 inches resulting in automatic actuation of the Primary Containment Isolation Systems for Group II - Primary Containment Isolation and Reactor Building Isolation System, and Group VI - Reactor Water Cleanup System.
"Reactor Water Level was restored to the normal operating band. The Primary Containment Isolation Systems have been reset. The Reactor Protection System signal has been reset.
"Following the reactor scram, the non-safety related Control Rod Drive Pump "B" tripped on low suction pressure. Control Rod Drive Pump "A" was placed in service. All other systems operated as expected, in accordance with design.
"This event is reportable per the requirements of Title 10, Code of Federal Regulations (CFR) 50.72 (b)(2)(iv)(B) - "RPS Actuation" and 10 CFR 50.72 (b)(3)(iv)(A) - "Specified System Actuation."
"This event had no impact on the health and/or safety of the public.
"The NRC Resident Inspector has been notified."
The main steam isolation valves are open with decay heat being removed via steam to the main condenser.
Offsite power is still available from 345kV line 355. As a contingency, emergency diesel generators are running and powering safety busses per licensee procedure.
The licensee notified the Commonwealth of Massachusetts. The licensee will be notifying the town of Plymouth as part of their local notifications. The licensee will be issuing a press release.
Agreement State
Event Number: 53148
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: ASPIRUS-WAUSAU HOSPITAL
Region: 3
City: WAUSAU State: IL
County:
License #: 073-1342-01
Agreement: Y
Docket:
NRC Notified By: KRISTA KUHLMAN
HQ OPS Officer: ANDREW WAUGH
Licensee: ASPIRUS-WAUSAU HOSPITAL
Region: 3
City: WAUSAU State: IL
County:
License #: 073-1342-01
Agreement: Y
Docket:
NRC Notified By: KRISTA KUHLMAN
HQ OPS Officer: ANDREW WAUGH
Notification Date: 01/05/2018
Notification Time: 08:30 [ET]
Event Date: 01/04/2018
Event Time: 00:00 [CST]
Last Update Date: 01/05/2018
Notification Time: 08:30 [ET]
Event Date: 01/04/2018
Event Time: 00:00 [CST]
Last Update Date: 01/05/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ROBERT DALEY (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
ROBERT DALEY (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
AGREEMENT STATE REPORT - DELIVERED DOSAGE DIFFERENT FROM PRESCRIBED
The following was received from the State of Wisconsin:
"On January 4, 2018, the Department [Wisconsin Radiation Protection Section] received a telephone call and email from the licensee's medical physicist that a medical event of a prostate brachytherapy procedure was identified on January 4, 2018. The total dose delivered differs from the prescribed dose by 20% or more. This is a medical event as described in DHS [Department of Health Services] 157.72(1)(a)1.a. The prescribed dose was 145 Gy; the dose delivered was 105 Gy. The licensee uses D90 (dose delivered to 90% of the clinical target volume) < 80% for determining medical events. Using the licensee's dose based criteria; the dose received by the prostate was 75% of the intended dose. The post-implant computed tomography scan occurred on December 6, 2017. The subsequent dosimetric analysis was on January 3, 2018. The department will perform a site investigation to determine the root cause of this medical event.
"DHS inspectors will investigate this medical event."
Wisconsin Event: WI180001
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.
The following was received from the State of Wisconsin:
"On January 4, 2018, the Department [Wisconsin Radiation Protection Section] received a telephone call and email from the licensee's medical physicist that a medical event of a prostate brachytherapy procedure was identified on January 4, 2018. The total dose delivered differs from the prescribed dose by 20% or more. This is a medical event as described in DHS [Department of Health Services] 157.72(1)(a)1.a. The prescribed dose was 145 Gy; the dose delivered was 105 Gy. The licensee uses D90 (dose delivered to 90% of the clinical target volume) < 80% for determining medical events. Using the licensee's dose based criteria; the dose received by the prostate was 75% of the intended dose. The post-implant computed tomography scan occurred on December 6, 2017. The subsequent dosimetric analysis was on January 3, 2018. The department will perform a site investigation to determine the root cause of this medical event.
"DHS inspectors will investigate this medical event."
Wisconsin Event: WI180001
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.
Agreement State
Event Number: 53149
Rep Org: VIRGINIA OFFICE OF RAD HEALTH
Licensee: OLD DOMINION ELECTRIC COOPERATIVE/VIRGINIA POWER
Region: 1
City: CLOVER State: VA
County:
License #: 083-388-1
Agreement: Y
Docket:
NRC Notified By: STEVE HARRISON
HQ OPS Officer: DAVID AIRD
Licensee: OLD DOMINION ELECTRIC COOPERATIVE/VIRGINIA POWER
Region: 1
City: CLOVER State: VA
County:
License #: 083-388-1
Agreement: Y
Docket:
NRC Notified By: STEVE HARRISON
HQ OPS Officer: DAVID AIRD
Notification Date: 01/05/2018
Notification Time: 12:16 [ET]
Event Date: 01/04/2018
Event Time: 00:00 [EST]
Last Update Date: 01/05/2018
Notification Time: 12:16 [ET]
Event Date: 01/04/2018
Event Time: 00:00 [EST]
Last Update Date: 01/05/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DAVE WERKHEISER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
DAVE WERKHEISER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
AGREEMENT STATE REPORT - STUCK SOURCE IN DENSITY GAUGE
The following report was received via email from the Virginia Office of Radiological Health:
"On January 4, 2018, the Radiation Safety Officer of the licensee reported that the metal (insertion) rod that enables the source holder to move to its 'ON' position (moves the source in and out of the vessel) broke during routine periodic maintenance. The gauge is a Texas Nuclear Model 50315, serial number B0047, with a 100 milliCurie Cesium-137 source (effective 1993). The gauge is used to measure the density of material inside a process vessel. The gauge is currently in its normal operative state, which is to send a signal to the detector to control density in the vessel. The source was pushed back into the vessel to allow for normal operation after the rod broke, but it is not able to be removed. The licensee has contacted ThermoFisher Scientific for further actions."
Virginia Event Report ID No.: VA-18-001
The following report was received via email from the Virginia Office of Radiological Health:
"On January 4, 2018, the Radiation Safety Officer of the licensee reported that the metal (insertion) rod that enables the source holder to move to its 'ON' position (moves the source in and out of the vessel) broke during routine periodic maintenance. The gauge is a Texas Nuclear Model 50315, serial number B0047, with a 100 milliCurie Cesium-137 source (effective 1993). The gauge is used to measure the density of material inside a process vessel. The gauge is currently in its normal operative state, which is to send a signal to the detector to control density in the vessel. The source was pushed back into the vessel to allow for normal operation after the rod broke, but it is not able to be removed. The licensee has contacted ThermoFisher Scientific for further actions."
Virginia Event Report ID No.: VA-18-001