Event Notification Report for February 11, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/10/2016 - 02/11/2016
EVENT NUMBERS
51728517295173051731
Agreement State
Event Number: 51728
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: CLARA MAASS MEDICAL CENTER
Region: 1
City: BELLEVILLE State: NJ
County:
License #: NJ PI ID # 42
Agreement: Y
Docket:
NRC Notified By: RICHARD PEROS
HQ OPS Officer: STEVE SANDIN
Licensee: CLARA MAASS MEDICAL CENTER
Region: 1
City: BELLEVILLE State: NJ
County:
License #: NJ PI ID # 42
Agreement: Y
Docket:
NRC Notified By: RICHARD PEROS
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/11/2016
Notification Time: 15:38 [ET]
Event Date: 02/11/2016
Event Time: 00:00 [EST]
Last Update Date: 02/11/2016
Notification Time: 15:38 [ET]
Event Date: 02/11/2016
Event Time: 00:00 [EST]
Last Update Date: 02/11/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAY POWELL (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
RAY POWELL (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
AGREEMENT STATE REPORT - BRACHYTHERAPY DEVICE MALFUNCTION RESULTING IN UNDERDOSE
The following information was received from the State of New Jersey via fax:
"One of the hospital's authorized medical physicists reported that a patient was due to receive a therapeutic treatment from the center's HDR [High Dose Rate] unit. During administration of the fraction, there was a device malfunction. The source was safely returned to the shielded position, but the patient did not receive the prescribed dose for the fraction. There was an underdose. The patient and the patient's physician have been informed. The unit is a Nucletron MicroSelectron Model 106.990. Additional details will be forthcoming from the hospital."
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 information was received from the State of New Jersey via fax:
"One of the hospital's authorized medical physicists reported that a patient was due to receive a therapeutic treatment from the center's HDR [High Dose Rate] unit. During administration of the fraction, there was a device malfunction. The source was safely returned to the shielded position, but the patient did not receive the prescribed dose for the fraction. There was an underdose. The patient and the patient's physician have been informed. The unit is a Nucletron MicroSelectron Model 106.990. Additional details will be forthcoming from the hospital."
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: 51729
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: TONY KLEDZIK
HQ OPS Officer: DONALD NORWOOD
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: TONY KLEDZIK
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/11/2016
Notification Time: 19:38 [ET]
Event Date: 02/11/2016
Event Time: 15:04 [EST]
Last Update Date: 02/11/2016
Notification Time: 19:38 [ET]
Event Date: 02/11/2016
Event Time: 15:04 [EST]
Last Update Date: 02/11/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVID HILLS (R3DO)
DAVID HILLS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
AUTOMATIC START OF EMERGENCY DIESEL GENERATOR AND LOSS OF SHUTDOWN COOLING
"At 1504 EST on February 11, 2016, with the plant shutdown in a forced outage, the Division 1, 4.16 Kv Safety Bus (EH11) lost power. Division 1 Shutdown Cooling was in service at the time and the Division 1 Shutdown Cooling pump A tripped. The Division 1 Emergency Diesel Generator (EDG) started and loaded EH11 as designed. However, the Emergency Service Water (ESW) A pump, which supplies cooling water to the EDG did not start. Due to the absence of cooling water to the EDG, operators took manual action to secure the Division 1 EDG. Division 2 Shutdown Cooling was operable during this transient and was subsequently started. The Division 1 Shutdown Cooling common suction isolation valve (1E12F0008) had previously been de-energized in the open position to support planned maintenance. The Division 2 Shutdown Cooling isolation valve was not affected by the loss of bus EH11. Shutdown Cooling was re-established at 1544 EST using the Division 2 Shutdown Cooling pump. Reactor coolant temperature rose from approximately 89 degrees Fahrenheit to 115 degrees Fahrenheit during the event. The cause of the loss of EH11 and subsequent failure of ESW A pump to start are currently under investigation.
"This event is being reported under 10 CFR 50.72(b)(3)(iv)(A) as a specific system actuation due to the auto start of the Division 1 EDG on a valid signal.
"The plant remains shutdown with Division 2 Shutdown Cooling in operation. The plant is in a normal electrical line up with the exception of bus EH11 being de-energized."
The licensee notified the NRC Resident Inspector.
"At 1504 EST on February 11, 2016, with the plant shutdown in a forced outage, the Division 1, 4.16 Kv Safety Bus (EH11) lost power. Division 1 Shutdown Cooling was in service at the time and the Division 1 Shutdown Cooling pump A tripped. The Division 1 Emergency Diesel Generator (EDG) started and loaded EH11 as designed. However, the Emergency Service Water (ESW) A pump, which supplies cooling water to the EDG did not start. Due to the absence of cooling water to the EDG, operators took manual action to secure the Division 1 EDG. Division 2 Shutdown Cooling was operable during this transient and was subsequently started. The Division 1 Shutdown Cooling common suction isolation valve (1E12F0008) had previously been de-energized in the open position to support planned maintenance. The Division 2 Shutdown Cooling isolation valve was not affected by the loss of bus EH11. Shutdown Cooling was re-established at 1544 EST using the Division 2 Shutdown Cooling pump. Reactor coolant temperature rose from approximately 89 degrees Fahrenheit to 115 degrees Fahrenheit during the event. The cause of the loss of EH11 and subsequent failure of ESW A pump to start are currently under investigation.
"This event is being reported under 10 CFR 50.72(b)(3)(iv)(A) as a specific system actuation due to the auto start of the Division 1 EDG on a valid signal.
"The plant remains shutdown with Division 2 Shutdown Cooling in operation. The plant is in a normal electrical line up with the exception of bus EH11 being de-energized."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 51730
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: KENNETH CORL
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: KENNETH CORL
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/12/2016
Notification Time: 03:51 [ET]
Event Date: 02/11/2016
Event Time: 23:05 [EST]
Last Update Date: 02/12/2016
Notification Time: 03:51 [ET]
Event Date: 02/11/2016
Event Time: 23:05 [EST]
Last Update Date: 02/12/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RAY POWELL (R1DO)
RAY POWELL (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 |
EMERGENCY DIESEL GENERATOR AUTO-STARTED DUE TO THE LOSS OF A STATION SERVICE TRANSFORMER
"On 02/11/2016, at 2305 [EST], Ginna Station experienced a loss of Station Service Transformer 12A causing Emergency Diesel Generator 1A to automatically start due to under-voltage signals to safeguards buses 14 and 18. All plant systems responded as designed. Control room operators stabilized the plant per abnormal operating procedures. The plant is currently in a 100/0 electrical lineup [supplied by the 12B Service Station Transformer] on the off site circuit 767 with the 1A Emergency Diesel Generator secured. The loss of the station service transformer is currently under investigation.
"This is reportable as a valid system actuation that was not part of a pre-planned sequence during testing.
"The NRC Resident Inspector has been notified."
"On 02/11/2016, at 2305 [EST], Ginna Station experienced a loss of Station Service Transformer 12A causing Emergency Diesel Generator 1A to automatically start due to under-voltage signals to safeguards buses 14 and 18. All plant systems responded as designed. Control room operators stabilized the plant per abnormal operating procedures. The plant is currently in a 100/0 electrical lineup [supplied by the 12B Service Station Transformer] on the off site circuit 767 with the 1A Emergency Diesel Generator secured. The loss of the station service transformer is currently under investigation.
"This is reportable as a valid system actuation that was not part of a pre-planned sequence during testing.
"The NRC Resident Inspector has been notified."
Agreement State
Event Number: 51731
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: COVESTRO LLC
Region: 4
City: BAYTOWN State: TX
County:
License #: 01577
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN
Licensee: COVESTRO LLC
Region: 4
City: BAYTOWN State: TX
County:
License #: 01577
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/12/2016
Notification Time: 13:07 [ET]
Event Date: 02/11/2016
Event Time: 00:00 [CST]
Last Update Date: 02/12/2016
Notification Time: 13:07 [ET]
Event Date: 02/11/2016
Event Time: 00:00 [CST]
Last Update Date: 02/12/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
NEIL OKEEFE (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
NEIL OKEEFE (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
AGREEMENT STATE REPORT - FIXED GAUGE SHUTTER FOUND IN STUCK OPEN POSITION
The following information was provided by the State of Texas via email:
"On February 12, 2016, the Agency [Texas Department of State Health Services] was notified by the licensee's radiation safety officer (RSO) that on February 11, 2016, while performing a routine inspection of a Berthold model LB 300 l nuclear gauge, they found the source shutter was stuck in the open position. Open is the normal position for the gauge shutter. The gauge contains a one millicurie (original activity, current activity 0.07 mCi.) Cobalt-60 source. The RSO stated the dose rates at and around the gauge are normal. He [the RSO] stated no individuals, including members of the general public, will be exposed to any additional radiation due to the failure. The RSO stated the manufacturer has been contacted and will be at the licensee's facility the week of February 15, 2016 to fix or replace the gauge. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-9378
The following information was provided by the State of Texas via email:
"On February 12, 2016, the Agency [Texas Department of State Health Services] was notified by the licensee's radiation safety officer (RSO) that on February 11, 2016, while performing a routine inspection of a Berthold model LB 300 l nuclear gauge, they found the source shutter was stuck in the open position. Open is the normal position for the gauge shutter. The gauge contains a one millicurie (original activity, current activity 0.07 mCi.) Cobalt-60 source. The RSO stated the dose rates at and around the gauge are normal. He [the RSO] stated no individuals, including members of the general public, will be exposed to any additional radiation due to the failure. The RSO stated the manufacturer has been contacted and will be at the licensee's facility the week of February 15, 2016 to fix or replace the gauge. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-9378