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Event Notification Report for April 14, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/11/2014 - 04/14/2014

** EVENT NUMBERS **


49999 50000 50030 50031 50032

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Agreement State Event Number: 49999
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: DESERT NDT LLC
Region: 4
City: ABILENE State: TX
County:
License #: 06462
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: VINCE KLCO
Notification Date: 04/04/2014
Notification Time: 16:37 [ET]
Event Date: 04/04/2014
Event Time: [CDT]
Last Update Date: 04/04/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME RESOURCES (EMAI)

Event Text

AGREEMENT STATE REPORT - CAMERA SOURCE DISCONNECT

The following information was received by facsimile from the State of Texas:

"On April 14, 2014, the Agency [Texas Department of State Health Services] was notified by the licensee's Corporate Radiation Safety Officer (CRSO) that one of their radiography crews had experienced source disconnect while using an INC IR 100 exposure device. The device contains a 70 curie iridium - 192 source. The CRSO stated the radiographers had completed a shot and noted the dose rates on the camera had not returned to normal after retracting the source. The radiographers increased the barriers around the exposure device and contacted their supervisor for assistance. The CRSO stated the source had been recovered by an individual listed on their license to retrieve sources. The CRSO stated he did not believe any individual received an exposure which exceeded any limits. The CRSO stated no member of the general public received any exposure. The CRSO stated he had just learned of the event and was beginning his investigation and would provide the Agency with additional information as it was obtained. This Agency will provide additional information as it is received in accordance with SA-300."

Texas Incident: I-9178

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Agreement State Event Number: 50000
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: HI-TECH TESTING SERVICES
Region: 4
City: BEEVILLE State: TX
County:
License #: L05021
Agreement: Y
Docket:
NRC Notified By: ROBERT FREE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/04/2014
Notification Time: 18:18 [ET]
Event Date: 04/03/2014
Event Time: [CDT]
Last Update Date: 04/04/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

TEXAS AGREEMENT STATE REPORT - STUCK RADIOGRAPHY SOURCE

The following information was obtained from the State of Texas via email:

"The licensee called to report that a radiography crew had damaged the source guide tube of their QSA 880D industrial radiography camera. The incident occurred at a temporary job site near Beeville, Texas. The crew was working in some elevated pipe racks and had used a rope to suspend the camera. The knot on the rope came loose, dropping the camera to the ground. The camera landed on the source guide tube crimping it and preventing the retraction of the radiography source which was extended into the collimator. A second radiography crew on the site secured their camera and placed it on the collimator to shield the source. The radiographers then called an RSO in Deer Park, Texas and another in Corpus Christi, Texas to get advice and instruction to secure the source. The crew then dragged the camera to a shielded location behind a concrete pillar. Two radiographer trainees were assigned to maintain a perimeter around the camera to prevent access by unmonitored individuals. The radiographers were able to use pliers to un-crimp the source guide tube and return the source to its shielded position."

No radiography personnel received overexposures due to this event.

Texas Incident # I-9177

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Power Reactor Event Number: 50030
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: RYAN CHAMBERLIN
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/12/2014
Notification Time: 13:24 [ET]
Event Date: 04/12/2014
Event Time: 10:12 [CDT]
Last Update Date: 04/12/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
PATTY PELKE (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TO TRANSFORMER SUDDEN PRESSURE RELAY ACTUATION

"At 1012 CDT on April 12, 2014, Dresden Unit 2 automatically scrammed on TR-2 sudden pressure relay actuation. All rods inserted to their full-in positions.

"Following the reactor scram, the 'A' reactor recirculation pump did not run back to minimum speed automatically. Operators took action to run the recirculation pump to minimum speed manually. All other systems operated as expected. Reactor vessel inventory and pressure are being maintained in automatic.

"The cause of the scram was due to a trip of the sudden pressure relay for Main Power Transformer 2. Troubleshooting is in progress to determine the cause [of the trip of the sudden pressure relay].

"This condition is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B), any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical."

Normal offsite power remains available. There was no impact on Unit 3.

The NRC Resident Inspector has been informed.

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Power Reactor Event Number: 50031
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE BRILL
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/12/2014
Notification Time: 23:20 [ET]
Event Date: 04/12/2014
Event Time: 20:08 [EDT]
Last Update Date: 04/12/2014
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):
MALCOLM WIDMANN (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 30 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO MAIN STEAM ISOLATION VALVE FAILING SHUT

"At 2008 EDT, Vogtle Unit One was manually tripped in response to loop 1 outboard Main Steam Isolation Valve failing shut. All systems operated correctly in response to the reactor trip. All control rods fully inserted. System response allowed for an uncomplicated reactor trip response. Unit 1 is stable in Mode 3 and cause investigation is in progress."

"The NRC Senior Resident Inspector was notified."

There was a normal post trip feedwater isolation due to low Tave.

Offsite power remains available. Decay heat is being removed by the main condenser. The plant is stable in Mode 3. There was no impact on Unit 2.

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Power Reactor Event Number: 50032
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WILLIAM MUFFLEY
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/13/2014
Notification Time: 23:49 [ET]
Event Date: 04/13/2014
Event Time: 21:13 [EDT]
Last Update Date: 04/14/2014
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 POWELL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

REACTOR TRIP DUE TO ACTUATION OF MAIN GENERATOR PROTECTION RELAY

"This 4 and 8 hour notification is being made to report that Salem Unit 1 experienced an unplanned automatic reactor trip and subsequent Auxiliary Feedwater system actuation. The automatic trip was initiated from a generator protection relay. A walkdown of the main generator and all protection circuitry has been completed with no visible problems identified. A troubleshooting team is being assembled to determine the exact cause for the generator protection actuation. 11, 12, and 13 Aux Feedwater Pumps automatically started as expected on low Steam Generator water level following the reactor trip. All control rods inserted on the reactor trip. All ECCS and ESF systems functioned as expected.

"Salem Unit 1 is currently in Mode 3. Reactor Coolant System pressure is at 2235 psig and temperature is 547 degrees F with decay heat removal via the main steam dumps and Auxiliary Feedwater Systems.

"There was no major primary or secondary equipment tagged for maintenance prior to this event. Condenser vacuum and Steam Generator Feed Pumps were available for the duration of the event. No personnel were injured during this event."

The licensee notified the NRC Resident Inspector and the Lower Alloways Creek Township.

Unit 1 is in a normal shutdown electrical lineup. Unit 2 is in a refueling outage and was unaffected by the Unit 1 trip.

Page Last Reviewed/Updated Wednesday, May 14, 2014
Wednesday, May 14, 2014