| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/14/2015 - 12/15/2015 ** 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 |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 51601 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: KATE COLIAS
HQ OPS Officer: DANIEL MILLS | Notification Date: 12/13/2015
Notification Time: 10:41 [ET]
Event Date: 12/13/2015
Event Time: 03:07 [EST]
Last Update Date: 12/14/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
EUGENE GUTHRIE (R2DO)
|
| 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 ESSENTIAL SERVICES CHILLED WATER SYSTEM INOPERABLE
"This is a non-emergency eight hour notification for a condition that could have prevented fulfillment of a safety function in a system needed to remove decay heat and to mitigate the consequences of an accident.
"At approximately 0307 EST on December 13, 2015, the 'A' and 'B' trains of the essential services chilled water (ESCW) system were inoperable for a time period of 23 minutes. The 'B' train of the ESCW system was being tested at the time that the 'A' train of the ESCW system became inoperable. The 'B' train of the ESCW system was returned to operable status at approximately 0330 EST and remains operable.
"The ESCW system provides cooling support functions to remove decay heat and mitigate the consequences of an accident. There were no safety system actuations during this time period and the plant is stable.
"This condition does not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified."
The 'A' ESCW pump tripped on low lube oil pressure.
* * * RETRACTION FROM JOHN CAVES TO JOHN SHOEMAKER AT 1756 EST ON 12/14/15 * * *
"Upon further review of the condition, it was determined that the 'A' train of the ESCW system was capable of performing its safety function throughout the time period previously reported, and the 'A' train of the ESCW system was operable. Therefore, there was no loss of safety function. Event notification 51601 is retracted. The NRC Resident Inspector has been informed of this notification retraction."
Notified the R2DO (Guthrie). |
| Power Reactor | Event Number: 51602 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PAXTON FAYSSOUX
HQ OPS Officer: HOWIE CROUCH | Notification Date: 12/14/2015
Notification Time: 12:30 [ET]
Event Date: 12/14/2015
Event Time: 10:11 [EST]
Last Update Date: 12/14/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
EUGENE GUTHRIE (R2DO)
FFD GROUP (EMAI)
|
| 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 FITNESS FOR DUTY REPORT - NON-LICENSED SUPERVISOR TEST POSITIVE FOR ILLEGAL SUBSTANCES
A non-licensed supervisor tested positive for drugs on a random fitness-for-duty test. The individual's access to the facility has been terminated.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 51603 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: CRAIG MINARICH
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 12/14/2015
Notification Time: 13:10 [ET]
Event Date: 12/14/2015
Event Time: 09:04 [EST]
Last Update Date: 12/14/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
MARC FERDAS (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 FITNESS FOR DUTY - NON-LICENSED SUPERVISOR TESTED POSITIVE DURING FOR CAUSE TESTING
A non-licensed supervisor tested positive for alcohol during a for-cause fitness-for-duty test. The individual's access to the facility has been denied.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 51604 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: THOMAS JOACHIMCZYK
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 12/14/2015
Notification Time: 14:32 [ET]
Event Date: 10/21/2015
Event Time: 00:29 [EST]
Last Update Date: 12/14/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
MARC FERDAS (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text DIESEL GENERATOR START DUE TO INVALID SIGNAL
"This report is being made per paragraphs 50.73(a)(1) and 50.73(a)(2)(iv)(A) to address an actuation of Emergency Diesel Generator 'A' on October 21, 2015, during the performance of a Diesel Generator Load and Safeguard Sequence Test. The Emergency AC Electrical Power system, including Diesel Generators is a system named in 50.73(a)(2)(iv)(B).
"During the performance of the Diesel Generator Load and Safeguard Sequence Test restoration steps a human performance error, while taking resistance readings on a relay, resulted in the unintentional start of the 'A' Emergency Diesel Generator. The testing was aborted and the affected Diesel Generator was restored to standby service in accordance with plant procedures. This is defined as an 'invalid signal' in that the 'A' Diesel Generator did not start as the result of an actual initiating condition.
"The start signal is considered an INVALID signal with respect to 50.73(a)(2)(iv)(A), however the system was not fully removed from service. The 'B' train was not affected by this event. The actuation signal was considered complete since all necessary components responded as would have been expected if there had been a valid signal.
"The NRC Resident Inspector was notified."
The licensee has determined that shorter test probe tips, when taking resistance readings, are necessary to prevent reoccurrence of this event. |
| Power Reactor | Event Number: 51606 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: BRETT ULRICH
HQ OPS Officer: HOWIE CROUCH | Notification Date: 12/14/2015
Notification Time: 19:49 [ET]
Event Date: 12/14/2015
Event Time: 19:06 [EST]
Last Update Date: 12/14/2015 | 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
| Person (Organization):
MARC FERDAS (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO MAIN GENERATOR LOCKOUT
"At 1906 [EST] on 12/14/2015, Indian Point Unit 3 received a Main Generator Lockout trip signal, and the reactor automatically tripped. Site personnel reported seeing arcing on a 345kV output transmission line tower. At the time of the trip, there was moderate rain and fog in the area. The site fire brigade leader investigated the reports of arcing and found no evidence of fire; fire brigade response was not required.
"All automatic systems functioned as designed and all control rods inserted automatically. Auxiliary Feedwater Pumps started automatically due to expected low steam generator levels following a reactor trip from 100% power. Unit 3 is being maintained in Mode 3 with decay heat removal via steam dumps to the condenser. Offsite power remains available and in service from 138kV to the 480V safeguards buses. The cause of the Main Generator Lockout signal is being investigated.
"Unit 2 was not impacted and continues to operate at 100% power.
"The NRC Resident Inspector has been notified."
After the trip, operators observed high vibrations on the 33 reactor coolant pump which eventually returned to normal range.
The licensee will be notifying the New York Public Service Commission and their local Independent System Operator. A press release will be issued by the Communications Department. | |