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Event Notification Report for November 6, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/03/2017 - 11/06/2017

** EVENT NUMBERS **


53039 53040 53051 53052 53053 53054

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Agreement State Event Number: 53039
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: PANHANDLE GEOTECHNICAL & ENVIRONMENTAL, INC.
Region: 4
City: KIMBALL State: NE
County:
License #: 21-06-01
Agreement: Y
Docket:
NRC Notified By: LARRY HARISIS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/27/2017
Notification Time: 12:11 [ET]
Event Date: 10/27/2017
Event Time: 10:20 [CDT]
Last Update Date: 10/27/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

NEBRASKA AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following information was obtained from the state of Nebraska via email:

"Nebraska Department of Health and Human Services, Office of Radiological Health was notified on October 27, 2017, by the Radiation Safety Officer (RSO) from Panhandle Geotechnical and Environmental, of a loss of control and damage to a portable gauge (licensed material) on Friday, October 27, 2017 outside of a temporary jobsite located near Kimball, Nebraska. The licensed material is a Troxler 3400 series moisture density gauge, serial number 30894, containing 9 mCi of Cs-137 and 44 mCi of Am-241:Be. The licensee reported to the State that an employee placed the license material on the standardization block performing the normal gauge standardization behind the pickup truck. The source rod was not extended during this time. When the employee was told to move the vehicle in order to move a shipping container to the job site, the employee placed the vehicle in reverse and backed into the gauge. The employee pulled forward after hearing the damage to the gauge and placed the pickup in park. The employee got out of the vehicle and assessed the situation. After noticing the damage to the gauge, the employee called the RSO and alerted nearby personnel to stay away from the area. No personnel were injured and the nearest person was at least 50 feet away. The employee moved the pickup further away (~20 feet from the gauge) and caution taped the area, prohibiting access. The RSO arrived at 1240 hrs. (Central Daylight Time) and performed a radiation survey and a wipe test. The RSO did not find any elevated readings and the sources were not leaking. The RSO and employee placed the gauge back in the shipping container and will deliver the gauge to licensed facility for repairs. A 30 day written report is to follow."

State Event Report ID No.: NE-17-0006

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Non-Agreement State Event Number: 53040
Rep Org: SAINT VINCENT HOSPITAL
Licensee: SAINT VINCENT HOSPITAL
Region: 3
City: INDIANAPOLIS State: IN
County:
License #: 13-00133-02
Agreement: N
Docket:
NRC Notified By: EDWARD ROBLEWSKI
HQ OPS Officer: VINCE KLCO
Notification Date: 10/28/2017
Notification Time: 13:29 [ET]
Event Date: 10/27/2017
Event Time: 15:28 [EDT]
Last Update Date: 10/28/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
ANN MARIE STONE (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

MEDICAL EVENT - DOSE MISADMINISTRATION

A patient receiving treatment for a liver disease was prescribed 60 milliCuries of Y-90 SIR-Spheres. The delivered dose was calculated to be 11 milliCuries and stasis was not achieved. The patient was notified of the misadministration and is scheduled to receive the fully prescribed dose.

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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Power Reactor Event Number: 53051
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: TOM COBBLEDICK
HQ OPS Officer: JEFF HERRERA
Notification Date: 11/03/2017
Notification Time: 14:20 [ET]
Event Date: 11/03/2017
Event Time: 10:45 [EDT]
Last Update Date: 11/03/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
HIRONORI PETERSON (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

Event Text

STATION VENT RADIATION MONITOR EFFICIENCY FACTOR NON CONSERVATIVE

"On 11/3/17, with the unit operating in Mode 1 at approximately 100 percent power, an issue was identified with the Station Vent Radiation Monitors. The noble gas channels utilize an efficiency factor for isotope Kr-85 instead of the required Xe-133. For the normal range radiation monitors, the efficiency factor is non-conservative, resulting in both monitors being declared inoperable at 1045 hours EDT. As a result, the Normal Control Room Ventilation System was shut down and isolated, and the Control Room Emergency Ventilation System started in accordance with Technical Specification Required Actions at 1122 hours.

"The inoperability of both Station Vent Normal Range Radiation Monitors represents a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident. The Station Vent Accident Range Monitors also utilize an efficiency factor for Kr-85 instead of Xe-133, but for the Accident Range Monitors the efficiency factor is conservative. Because alternate means exist to determine release rate, which include use of grab samples and field surveys, this degraded capability does not represent a major loss of emergency assessment capability.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 53052
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: OVIDIO RAMIREZ
HQ OPS Officer: JEFF HERRERA
Notification Date: 11/03/2017
Notification Time: 21:08 [ET]
Event Date: 11/03/2017
Event Time: 20:22 [EDT]
Last Update Date: 11/03/2017
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):
RAY MCKINLEY (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

INDIAN POINT UNIT 3 REACTOR TRIP ON LOW STEAM GENERATOR LEVEL

"On November 3rd, 2017 at 2022 EDT, the Indian Point Unit 3 Reactor Protection system automatically actuated at 100 percent power. Annunciator first out indication was from 33 SG [Steam Generator] Low Level. This automatic reactor trip is reportable to the NRC under 10 CFR 50.72(b)(2)(iv)(B). All control rods fully inserted on the reactor trip. All safety systems responded as expected. The Auxiliary Feedwater System actuated as expected. Offsite power and plant electrical lineups are normal. All plant equipment responded normally to the unit trip. No primary or secondary code safeties lifted during the trip.

"The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). The Emergency Diesel Generators did not start as offsite power remained available and stable. The Unit remains on offsite power and all electrical loads are stable. Unit 3 is in Hot Standby at normal operating temperature and pressure with decay heat removal using auxiliary feedwater to the steam generators and normal heat removal through the condenser via the high pressure steam dumps. Unit 2 was unaffected and remains at 100 percent power.

"A post trip investigation is in progress."

The licensee indicated that Radiation Monitor number 14 spiked twice during the transient, however, is currently not indicating any signs of radiation.

The licensee will notify the NRC Resident Inspector and the NY Public Service Commission.

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Power Reactor Event Number: 53053
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: SARAH AFARIAN
HQ OPS Officer: JEFF HERRERA
Notification Date: 11/04/2017
Notification Time: 14:00 [ET]
Event Date: 11/03/2017
Event Time: 16:49 [EDT]
Last Update Date: 11/04/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
RAY MCKINLEY (R1DO)
FFD GROUP (EMAI)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
3 N N 0 Refueling 0 Refueling

Event Text

FITNESS FOR DUTY - LICENSED EMPLOYEE CONFIRMED POSITIVE FOR FITNESS FOR DUTY

A licensed employee had a confirmed positive test for a controlled substance during a random fitness-for-duty test. The employees plant access has been placed on administrative hold.

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 53054
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: SETH STROPE
HQ OPS Officer: JEFF HERRERA
Notification Date: 11/05/2017
Notification Time: 17:11 [ET]
Event Date: 11/05/2017
Event Time: 12:40 [CST]
Last Update Date: 11/05/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
HIRONORI PETERSON (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 98 Power Operation 98 Power Operation

Event Text

LOSS OF SECONDARY CONTAINMENT PRESSURE DUE TO VOLTAGE TRANSIENT

"At approximately 1240 CST on 11/05/17, the Main Control Room received numerous annunciators that indicated a trip of the Emergency Reserve Auxiliary Transformer (ERAT) Static VAR [volt-ampere reactive] Compensator (SVC) caused by a voltage transient on the 138 kV feed due to thunderstorms in the area. As a result of the voltage transient, the Division 1 Fuel Building ventilation (VF) system isolation dampers closed causing a trip of VF supply and exhaust fans. With no running VF fans, secondary containment differential pressure rose to slightly greater than 0 inches water gauge which exceeded the Technical Specification requirement of greater than 0.25 inches vacuum water gauge at 1241. The Control Room entered EOP-8, Secondary Containment Control. This event is being reported as a Condition that Could Have Prevented Fulfillment of a Safety Function under 10CFR50.72(b)(3)(v)(C). Secondary Containment differential pressure was restored within Technical Specification requirements at 1242 by starting the Standby Gas Treatment HVAC (VG) system.

"The NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Monday, November 06, 2017
Monday, November 06, 2017