United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2017 > July 25

Event Notification Report for July 25, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/24/2017 - 07/25/2017

** EVENT NUMBERS **


52858 52860 52869 52870 52871

To top of page
Agreement State Event Number: 52858
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: GEOTEK INSITE, INC.
Region: 4
City: PHOENIX State: AZ
County:
License #: AZ 07-495
Agreement: Y
Docket:
NRC Notified By: BRIAN GORETZKI
HQ OPS Officer: VINCE KLCO
Notification Date: 07/14/2017
Notification Time: 11:13 [ET]
Event Date: 07/13/2017
Event Time: [MST]
Last Update Date: 07/14/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID PROULX (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - DAMAGED SHUTTER

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

"This First Notice constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received WITHOUT verification or evaluation, and is basically all that is known by the Agency [Arizona Radiation Regulatory Agency] Staff at this time.

"During an inspection of the licensee on July 13, 2017, an inspector found one portable gauge where the radiation source exposure shutter would not close when moved to the closed position. The inspector's dose measurement at contact with the device was approximately 100 mR/hr. The gauge is a Troxler model 3430, Serial Number 30302, containing 8 milliCuries of Cesium-137 and 40 milliCuries of Americium-241. The licensee has contacted a repair company to fix the gauge as soon as possible.

"The Agency is investigating the event.

"The Governor's office and U.S. NRC are being notified of this event. "

Arizona First Notice: 17-009

To top of page
Agreement State Event Number: 52860
Rep Org: NV DIV OF RAD HEALTH
Licensee: LAS VEGAS PAVING CORP
Region: 4
City: LAS VEGAS State: NV
County:
License #: 00-11-0255-01
Agreement: Y
Docket:
NRC Notified By: MICHAEL W. SCHMIDT
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/14/2017
Notification Time: 16:36 [ET]
Event Date: 07/14/2017
Event Time: [PDT]
Last Update Date: 07/14/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID PROULX (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

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

Event Text

AGREEMENT STATE REPORT - LOST AND RECOVERED PORTABLE GAUGE

The following was received from the State of Nevada via email:

"It was reported to the Nevada Radiation Control Program duty officer that a portable gauge had been recovered at a temporary job site in Las Vegas, Nevada. The individual who reported the event is a Nevada radioactive material licensee and said on 7/14/2017, at approximately 0735 [PDT], 'a nuclear density gauge was found in North Las Vegas at Cheyenne Ave and Berg St on the road. The gauge was recovered by an employee and quickly brought it to a secure storage location. The gauge was found in good condition and not damaged or source exposed.' At 0930 [PDT] on 7/14/2017, it was reported to the Nevada Radiation Control Program, by the ARSO from the company who lost the gauge, the gauge fell off the tailgate of a transport vehicle at a temporary jobsite, and the operator realized the loss and returned to the site within 5 minutes, but the gauge had already been recovered by [the reporting licensee]. The operator from [the licensee who lost the gauge] was informed that the gauge was recovered by [the reporting licensee] and relayed that information to the ARSO at [the licensee who lost the gauge]. The gauge was intact, no damage, transported back to the owner's storage location, and taken out of service. An investigation of the event will commence [on] 07/17/2017."

Item Number: NV170006

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: 52869
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: SANDRA CHRISTIANSON
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/24/2017
Notification Time: 13:36 [ET]
Event Date: 05/25/2017
Event Time: 16:47 [PDT]
Last Update Date: 07/24/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
MICHAEL HAY (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

INVALID HIGH PRESSURE CORE SPRAY (HPCS) SYSTEM ACTUATION IN MODE 5

"At 1647 [PDT] on May 25, 2017, during the performance of a post-maintenance test for replacement of a Reactor Pressure Vessel (RPV) low water level 3 indicator switch (MS-LIS-24A), a pressure perturbation in the common pressure reference line resulted in tripping of the RPV Level 2 instruments and an unplanned start of High Pressure Core Spray (HPCS) pump (HPCS-P-1) and its supporting emergency diesel (DG3). The Reactor Pressure Vessel was flooded up during the refueling outage, thus, the actuations of the HPCS pump and its supporting emergency diesel (DG3) were unplanned and invalid. The HPCS pump did not inject into the RPV due to the RPV level being above Level 8 which is an interlock to close the HPCS RPV injection valve (HPCS-V-4).

"During the event, the single train HPCS system initiated normally but did not inject into the reactor pressure vessel as expected due to flooded-up conditions of the reactor pressure vessel for refueling outage activities. The emergency diesel generator started normally in response to the initiation signal of HPCS. Both HPCS and the emergency diesel generator functioned successfully. All systems responded in conformance with their design and there was no safety significance associated with this event.

"At the time of the event, the licensee notified the NRC Resident [Inspector]."

To top of page
Power Reactor Event Number: 52870
Facility: OCONEE
Region: 2 State: SC
Unit: [ ] [ ] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: ROBERT SHAW
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/24/2017
Notification Time: 19:25 [ET]
Event Date: 07/24/2017
Event Time: 16:38 [EDT]
Last Update Date: 07/24/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
ALAN BLAMEY (R2DO)

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 LOAD REJECTION

"At 1638 [EDT] on 7/24/2017, Oconee Unit 3 experienced an automatic reactor trip due to a load rejection when the generator output breakers both tripped open unexpectedly while 525kV switchyard maintenance was being performed. The trip was uncomplicated with all systems responding normally post-trip. Due to the RPS [Reactor Protection System] actuation while critical, this event is being reported as a 4-hour non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B).

"The plant responded normally to the reactor trip, and there was no impact on the health and safety of the public or plant personnel.

"Operations responded using the Emergency Operating Procedure and stabilized Unit 3 in MODE 3.

"The NRC Senior Resident Inspector has been notified."

Decay heat is removed by discharging steam to the main condenser using the turbine bypass valves. Unit 1 and 2 are not affected.

To top of page
Power Reactor Event Number: 52871
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MATTHEW BONANNO
HQ OPS Officer: VINCE KLCO
Notification Date: 07/24/2017
Notification Time: 23:50 [ET]
Event Date: 07/24/2017
Event Time: 20:44 [EDT]
Last Update Date: 07/25/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DAN SCHROEDER (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION TO THE PENNSYLVANIA DEPARTMENT OF ENVIRONMENTAL PROTECTION

"At time [2044 EDT], Limerick Generating Station notified the Pennsylvania DEP [Department of Environmental Protection] that there was an imminent overflow of our plant waste water pond (holding pond) due to heavy rainfall in the area. Level in the plant waste water pond was approximately " from the overflow. Prior to overflowing, plant alignment changes enabled us to lower level in the hold pond to prevent the overflow. PADEP was subsequently notified that an actual overflow condition did not occur."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Tuesday, July 25, 2017
Tuesday, July 25, 2017