| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/26/2018 - 01/29/2018 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 53175 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: ST. FRANCIS MEDICAL CENTER
Region: 3
City: PEORIA State: IL
County:
License #: IL-01361-01
Agreement: Y
Docket:
NRC Notified By: GARY FORSEE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/18/2018
Notification Time: 12:39 [ET]
Event Date: 01/09/2018
Event Time: [CST]
Last Update Date: 01/18/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID HILLS (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text ILLINOIS AGREEMENT STATE REPORT - MEDICAL EVENT
The following information was received from the State of Illinois via email:
"The agency [Illinois Emergency Management Agency, Bureau of Radiation Safety] was notified on 1/16/18 of a medical event that occurred on 1/9/18. Agency personnel were able to contact the licensee and obtain details on 1/17/18. The licensee's RSO advised that he was out of state for a training class and was not informed by his staff until he returned.
"Licensee administered Y-90 Theraspheres to a patient in 2 doses, each treating a separate lobe of the liver. The physician wrote two prescriptions, one for each lobe. One lobe required 10 mCi, in which the entire 10 mCi dose was delivered. The second prescribed dose was for 7 mCi. Upon performing residual measurements, it was discovered that the delivered dose was 28 percent less than the 7mCi specified in the written directive. There were no equipment malfunctions reported, nor were there any medical reasons for the underdose (stasis was not reached). The AU [Authorized User] was notified, as was the referring physician.
"When considering the organ as a whole, three separate fractions were prescribed, under three separate written directives (34 mCi + 10 mCi +7 mCi), yielding a total dose of 94.44 Gy. The administered dose was 93.94 Gy. The resultant composite differential is 50 rem, with 99.5% of the desired dose administered to the organ. A written report is pending from the licensee."
Illinois Item No.: IL180012
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: 53180 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RYAN CRAGG
HQ OPS Officer: VINCE KLCO | Notification Date: 01/23/2018
Notification Time: 05:02 [ET]
Event Date: 01/23/2018
Event Time: 04:00 [CST]
Last Update Date: 01/26/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JAMNES CAMERON (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 | Event Text LOSS OF ASSESSMENT CAPABILITY DUE TO TECHNICAL SUPPORT CENTER PLANNED MAINTENANCE
"At 0400 [CST] on 1/23/2018 the Braidwood Technical Support Center (TSC) HVAC [Heating, Ventilation and Air Conditioning] Emergency Makeup Air Filter train was taken out of service to perform a planned Makeup Air Filter charcoal replacement. The TSC HVAC Makeup Air Filter train will be rendered nonfunctional during the charcoal replacement. Subsequent charcoal and HEPA filter testing will restore functionality of the TSC HVAC Makeup Air Filter train. The expected duration of the charcoal replacement and subsequent testing is 30 hours.
"If an emergency is declared requiring TSC activation during the time TSC HVAC is non-functional, the TSC will be staffed and activated using existing emergency planning procedure unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to a major loss of emergency preparedness capability. An update will be provided once the TSC HVAC Emergency Makeup Air Filter train functionality has been restored.
"The licensee has notified the NRC Resident Inspector."
* * * UPDATE AT 1645 EST ON 01/26/2018 FROM PAUL ARTUSA TO JEFF HERRERA * * *
"On 1/26/18 at time 1539 EST, the TSC HVAC Emergency Makeup Air Filter train was returned to service following the planned Makeup Alr Filter charcoal replacement. Functionality was verified by charcoal and HEPA filter post maintenance testing.
"The licensee has notified the NRC Resident Inspector."
Notified the R3DO (Cameron). |
| Power Reactor | Event Number: 53184 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC THOMAS
HQ OPS Officer: DAVID AIRD | Notification Date: 01/26/2018
Notification Time: 01:37 [ET]
Event Date: 01/25/2018
Event Time: 19:01 [PST]
Last Update Date: 01/26/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GREG PICK (R4DO)
|
| 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 | Event Text OFFSITE NOTIFICATION DUE TO SCREEN WASH PUMP MOTOR FIRE
"At 1901 PST on January 25, 2018, the Control Room received a fire alarm, followed by screen wash and 480v load center alarms a few minutes later. The intake operator and on-site fire department personnel were promptly dispatched to the scene and confirmed within 15 minutes there was no active fire. As a conservative measure, off-site fire assistance was initially requested, however [this request] was canceled a short time later. While on-site fire personnel were locally assessing the damage to screen wash pump 1-2, a brief flare-up occurred at the pump motor which was immediately extinguished. Units 1 and 2 remained stable and two screen wash pumps remain available. There is no risk to plant safety or personnel and both units continue to operate at power. Current efforts are focused on determining the cause of the situation."
The licensee notified the NRC Resident Inspector and CAL FIRE. The licensee issued a media/press release. |
| Power Reactor | Event Number: 53185 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: JUSTIN KNOWLES
HQ OPS Officer: JEFF HERRERA | Notification Date: 01/26/2018
Notification Time: 13:06 [ET]
Event Date: 01/26/2018
Event Time: 08:53 [EST]
Last Update Date: 01/26/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
HAROLD GRAY (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 | Event Text REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE
"On January 26, 2018, a containment entry was made to identify the source of elevated Unidentified Reactor Coolant System (RCS) operational leakage. A through-wall leak was identified on a Class 1 piping weld on the letdown line at 0853 EST. It was determined that the leak was RCS pressure boundary leakage. Ginna entered Technical Specification (TS) LCO [Limiting Condition for Operation] 3.4.13, RCS Operational Leakage, Condition B. for the existence of pressure boundary leakage. This condition requires the plant to be in MODE 3 within 6 hours and MODE 5 within 36 hours. The leak was isolated and TS LCO 3.4.13 exited at 1015 EST.
"This event is reportable within 8 hours in accordance with 10CFR50.72(b)(3)(ii)(A) for 'Any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded'.
"The Station [Ginna] is developing an evaluation and a repair plan at this time.
"This condition has no impact on public health and safety.
"The licensee has informed the NRC Resident Inspector." | |