United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2017 > November 7

Event Notification Report for November 7, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/06/2017 - 11/07/2017

** EVENT NUMBERS **


53039 53040 53045 53052

To top of page
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

To top of page
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.

To top of page
Agreement State Event Number: 53045
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: KRAZAN & ASSOCIATES, INC.
Region: 4
City: MODESTO State: CA
County:
License #: 4247-10
Agreement: Y
Docket:
NRC Notified By: K. ARUNIKA HEWADIKARAM
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/30/2017
Notification Time: 19:25 [ET]
Event Date: 10/30/2017
Event Time: [PDT]
Last Update Date: 10/30/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG WERNER (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
ILTAB (EMAI)
CNSNS (MEXICO) (EMAI)

This material event contains a "Less than Cat 3 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TROXLER MOISTURE DENSITY GAUGE

The following information was received from the State of California via email:

"On 10/30/17, California Office of Emergency Services contacted RHB [Radiologic Health Branch] to report a lost moisture density gauge. The lost gauge is a Troxler Model 3440, S/N 23171, containing 9 mCi of Cs-137 and 44 mCi of Am241/Be. According to the RSO [Radiation Safety Officer], the gauge user left the gauge on the tailgate of his truck without properly securing it, and drove off to the next job site. A passing driver alerted the gauge user of a falling object from his truck at the intersection of Floyd Street and Oakdale Street in Modesto, CA. The user immediately went back to the intersection, but was unable to locate the gauge. The RSO has notified the Modesto Police Department of this incident. He will be posting a reward for the safe return of the gauge on Craigslist. The RHB will be following up on this investigation.

"5010 Number: 103017"

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

To top of page
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: 11/06/2017
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.

* * * UPDATE AT 1523 EST ON 11/06/17 FROM RAMIREZ OVIDIO TO JEFF HERRERA * * *

"The initial notification stated that Indian Point Unit 3 Reactor Tripped on 33 SG [Steam Generator] Low Level, this is incorrect. Indian Point Unit 3 Reactor Tripped on a Turbine Trip. The Turbine Trip was caused by a Generator Back-up Lockout Relay. The Turbine Trip was the 'first' annunciator first-out but was acknowledged instead of silenced during initial operator actions. The Turbine Trip first-out being acknowledged allowed a Low Steam Generator first-out to later annunciate. A Low Steam Generator Level is an expected condition post trip.

"This update does not change any actions taken by the operating team or required notifications under 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).

"A post trip investigation remains in progress.

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

Notified the R1DO(Cook)

Page Last Reviewed/Updated Tuesday, November 07, 2017
Tuesday, November 07, 2017