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Event Notification Report for January 26, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/25/2016 - 01/26/2016

** EVENT NUMBERS **


51657 51658 51682 51683 51684

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Agreement State Event Number: 51657
Rep Org: PA DEP BUREAU OF RAD PROTECTION
Licensee: UNIVERSAL WELL SERVICES, INC
Region: 1
City: MEADVILLE State: PA
County:
License #: PA1446
Agreement: Y
Docket:
NRC Notified By: JOE MELNIC
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/15/2016
Notification Time: 08:55 [ET]
Event Date: 01/14/2016
Event Time: [EST]
Last Update Date: 01/15/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MEL GRAY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - SHUTTER MALFUNCTION

The following was received from Pennsylvania via fax:

"On January 14, 2016, the Department [PA DEP Bureau of Radiation Protection] was notified by Universal Well Services that a malfunction of a roll pin on a shutter handle occurred at the Hop Bottom, Pennsylvania temporary job site. It is reportable per 10 CFR 30.50(b)(2).

"A roll pin, which holds the shutter handle to the shutter shaft, on an in-line density gauge, became dislodged rendering the gauge unusable. The shutter is in the closed position and out of service awaiting repair from a service provider. No exposures occurred.

"Radionuclide: Cs-137
"Manufacturer: Berthold
"Model: LB 8010
"Serial Number: 10059
"Activity: 20 mCi

"The shutter is in the closed position and the gauge is out of service and secure. There was no other damage to the gauge. A reactive inspection is planned by the Department."

PA Event ID # PA160002

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Agreement State Event Number: 51658
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: LA PIGMENT COMPANY, L.P.
Region: 4
City: WESTLAKE State: LA
County:
License #: LA-6491-L01
Agreement: Y
Docket:
NRC Notified By: JOSEPH NOBLE
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/15/2016
Notification Time: 17:09 [ET]
Event Date: 01/14/2016
Event Time: 12:01 [CST]
Last Update Date: 01/15/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - FIXED GAUGE WITH SHUTTER STUCK IN OPEN POSITION

The following Agreement State Report was received from the State of Louisiana via email:

"The RSO [Radiation Safety Officer], called to report that a gauge installed on a process at the licensee's Westlake, LA facility, had a shutter malfunction. The gauge is installed on a routing process for material at the facility. The gauge shutter is stuck in the open position.

"The Gauge is a Berthold Technologies, Model: Berthold Systems, LB-330 utilizing a 12 mCi Cs-137 source, Model: Lab. Prof. Dr. Berthold Dwg. #2653.100-001. The source and gauge will remain on the process in operation until the Berthold Technician arrives over the weekend service the gauge. This will be either make the necessary repairs to the shutter or remove the gauge from service and perform the disposal. Due to the age of the gauge, if it cannot be repaired, disposal is the resolution. This will be determined by the Berthold personnel performing the repair. The service order request has the repairs scheduled to be made over this weekend.

"There are no exposure or health and safety issues involved with this event. The gauge and rod source will remain installed on the functioning process. The resolution of the situation will be directed by the ability to be repaired or if the gauge should be de-installed and sent for disposal.

"The corrective action: Will be determined by the ability of the Berthold Technician to repair the shutters on the gauge or if the gauge needs to be de-installed and sent for disposal. The repairs and or corrective actions will be determined by a site visit and assessment by Berthold Technologies."

The State of Louisiana considers this event to be closed.

State Event Report ID No: LA 160002

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Power Reactor Event Number: 51682
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MARK STROLLO
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/25/2016
Notification Time: 03:21 [ET]
Event Date: 01/25/2016
Event Time: 01:47 [EST]
Last Update Date: 01/25/2016
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):
HAROLD GRAY (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 REACTOR COOLANT PUMP TRIP

At 0147 EST on 1/25/16, the 'B' Reactor Coolant Pump (RCP) tripped offline. This caused a reactor trip on low coolant flow. As expected, the Aux Feedwater System (AFW) initiated on the reactor trip. The trip was uncomplicated and the plant is currently shutdown in Mode 3 with a normal electrical lineup and decay heat is being removed via steam dumps to the condenser. The cause of the 'B' RCP trip is under investigation. A containment entry is planned for dayshift on 1/25/16 to inspect and troubleshoot the 'B' RCP.

The Licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 51683
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: ERVIN LYSON
HQ OPS Officer: DANIEL MILLS
Notification Date: 01/25/2016
Notification Time: 05:45 [ET]
Event Date: 01/25/2016
Event Time: 03:15 [EST]
Last Update Date: 01/25/2016
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):
HAROLD GRAY (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 10 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO ELEVATED CONDENSER SODIUM LEVELS

At 0315 EST on 1/25/16, Calvert Cliffs Unit 1 was manually tripped from 10 percent power due to elevated condenser sodium levels. All systems responded per design. Main Feed was secured and auxiliary feed water was initiated. The elevated sodium levels are believed to be due to a condenser tube leak. The reactor is currently shutdown and stable in Mode 3 and will remain in Mode 3 until repairs are effected. Unit 2 was not affected and remains at full power.

The Licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 51684
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TERRY ODOMS
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/25/2016
Notification Time: 15:26 [ET]
Event Date: 01/25/2016
Event Time: 10:30 [EST]
Last Update Date: 01/25/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GERALD MCCOY (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE DUE TO DISCOVERED CONDITION

"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability.

"This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as the discovered condition affects the functionality of an emergency response facility.

"A condition impacting functionality due to a loss of cooling of the TSC (Technical Support Center) Ventilation system was discovered on 1/25/2016. At 1030 [EST], maintenance personnel reported the compressor local power breaker was tripped open and that all 3 phases of the compressor indicated grounded. Maintenance will begin repairs as soon as parts are made available. Estimated time to repair is unknown at this time.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable. If relocation of the TSC becomes necessary, the Emergency Coordinator will relocate the TSC staff to an alternate location in accordance with applicable emergency plan implementing procedures. The Emergency Response Organization team will be notified of the condition and the possible need to relocate during an emergency. This condition does not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Tuesday, January 26, 2016
Tuesday, January 26, 2016