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Event Notification Report for December 16, 2015

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/15/2015 - 12/16/2015

** EVENT NUMBERS **


51590 51591 51607

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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.

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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

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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.

Page Last Reviewed/Updated Wednesday, December 16, 2015
Wednesday, December 16, 2015