| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/15/2015 - 12/16/2015 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51590 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: GEISINGER HEALTH SYSTEM
Region: 1
City: Danville State: PA
County:
License #: PA-0006
Agreement: Y
Docket:
NRC Notified By: JOE MELNIC
HQ OPS Officer: JEFF HERRERA | Notification Date: 12/07/2015
Notification Time: 14:39 [ET]
Event Date: 12/04/2015
Event Time: [EST]
Last Update Date: 12/07/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GLENN DENTEL (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - DELIVERED DOSE OF YTTRIUM-90 LESS THAN PRESCRIBED DOSE
The following report was received from the Pennsylvania Department of Environmental Protection via facsimile:
"On 12/4/2015, a patient was scheduled for a yttrium-90 (Y-90) Sirsphere procedure. The prescribed dose on the written directive was 10 mCi. The ion chamber measurements indicated a delivered dose of 7.72 mCi (-22.8% of prescribed dose). Both the patient and referring physician were notified. No harm is expected to the patient.
"A reactive inspection is planned by the Pennsylvania Department of Environmental Protection."
Pennsylvania Event Report ID No: PA150032
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: 51591 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: US STEEL
Region: 1
City: WEST MIFFLIN State: PA
County:
License #: PA-G0309
Agreement: Y
Docket:
NRC Notified By: JOE M. MELNIC
HQ OPS Officer: JEFF HERRERA | Notification Date: 12/07/2015
Notification Time: 15:08 [ET]
Event Date: 12/04/2015
Event Time: [EST]
Last Update Date: 12/07/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GLENN DENTEL (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE - TWO GAUGE SHUTTERS FAILED TO CLOSE
The following report was provided by the Pennsylvania Department of Environmental Protection via facsimile:
"Two separate shutter issues occurred during gauge standardization procedures on December 4, 2015. The shutters failed to close completely. All proper lock out procedures were followed and leak tests and survey data revealed no elevated radiation levels. A service provider has been contacted for repairs.
"Gauge #1
Radionuclide: Am-241
Manufacturer: Accu-Ray
Source Model#: S-16
Source SN#: AM-109
Device Model: U-3
Device SN#: 6631901
Activity: 1 Ci
"Gauge #2
Radionuclide: Am-241
Manufacturer: IRMS
Source Model#: S-16
Source SN#: AM-1149
Device Model: TG-2
Device SN#: OOM0397 -15
Activity: 3 Ci
"A reactive inspection is planned by the Pennsylvania Department of Environmental Protection. More information will be provided upon receipt."
Pennsylvania Event Report ID No: PA150033 |
| Power Reactor | Event Number: 51607 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: THERON ROWBOTHAM
HQ OPS Officer: JEFF ROTTON | Notification Date: 12/15/2015
Notification Time: 10:24 [ET]
Event Date: 12/15/2015
Event Time: 05:44 [CST]
Last Update Date: 12/15/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RAY AZUA (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 43 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO LOSS OF FEED TO ONE STEAM GENERATOR
"This is a 4-hour Non-Emergency 10 CFR 50.72(b)(2)(iv)(B) notification due to a Reactor Protection System (RPS) actuation. Arkansas Nuclear One, Unit 1, was manually tripped from 43 percent power at 0544 CST. The reactor was manually tripped due to operator judgement during control issues with the Integrated Control System (ICS) during a planned downpower for Electro-Hydraulic Control (EHC) system maintenance. CV-2672 B, low load control valve, failed to close. Subsequently, CV-2674 B, low load block valve, began to close and caused a loss of feed to E-24B Steam Generator.
"No additional equipment issues were noted. All control rods fully inserted. Emergency Feedwater (EFW) actuated and was utilized to maintain Steam Generator (SG) levels. This [EFW actuation] meets the 8 hour Non-Emergency Immediate Notification Criteria [(10CFR50.72(b)(3)(iv)(A)]. No Primary safety valves lifted. Main Steam Safety Valves (MSSVs) did lift initially after the trip.
"The NRC Resident [Inspector] has been notified."
Decay heat is being removed via the steam dump valves to the main condenser. Unit 1 is in a normal shutdown electrical lineup. Unit 2 was not affected by the transient on Unit 1. The licensee notified the State of Arkansas. | |