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Event Notification Report for March 11, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/10/2014 - 03/11/2014

** EVENT NUMBERS **


49863 49888 49889 49890

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Agreement State Event Number: 49863
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: CALFRAC WELL SERVICES CORP
Region: 4
City: SAN ANTONIO State: TX
County:
License #: 02439
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: CHARLES TEAL
Notification Date: 02/28/2014
Notification Time: 16:35 [ET]
Event Date: 02/24/2014
Event Time: [CST]
Last Update Date: 02/28/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BOB HAGAR (R4DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - OPERATING ARM FOR NUCLEAR GAUGE BROKEN

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

"On February 28, 2014, the Agency [State of Texas] received a reciprocity request from a company from the State of Tennessee to perform emergency repairs on a Berthold model LB 8010 nuclear gauge containing a 20 milliCurie cesium-137 source at a generally licensed facility in Texas. The Agency [State of Texas] contacted the Texas licensee and asked if there had been a shutter problem with the gauge. The licensee stated on February 24, 2014, while they were moving the gauge from one location to another, one of their employees noted the operating arm on the shutter appeared bent. The employee attempted to straighten the operating arm and it broke off the gauge. The gauge was placed in the licensee's storage location. The licensee contacted the manufacturer who repaired the gauge shutter on February 25, 2014. The licensee stated no personnel received any significant exposure from the event. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident #: I-9159

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Power Reactor Event Number: 49888
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: RYAN HAMILTON
HQ OPS Officer: DANIEL MILLS
Notification Date: 03/10/2014
Notification Time: 19:20 [ET]
Event Date: 03/10/2014
Event Time: 16:28 [EDT]
Last Update Date: 03/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
MARC FERDAS (R1DO)

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

REACTOR SCRAM DUE TO ACTUATION OF THE ALTERNATE ROD INSERTION SYSTEM

"At 1628 EDT Nine Mile Point (NMP) Unit 2 experienced an actuation of the Alternate Rod Insertion (ARI) system which resulted in a reactor scram. Coincident with the scram, the Reactor Core Isolation Cooling (RCIC) system initiated.

"Prior to the event, maintenance personnel were working in the vicinity of a reactor vessel level instrumentation rack and may have agitated the common drain line of the transmitters. A prompt investigation is underway to investigate the incident.

"The actuation signal for the RCIC system was invalid because reactor vessel level did not reach level two and the actuation was not in response to actual plant conditions or parameters.

"The reactor scram is reportable in accordance with 10 CFR 50.72(b)(2)(iv)(B) as, 'Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical.'

"The event has been entered into the NMP corrective action program as CR-2014-001963.

"The NRC Resident Inspector has been notified."

The licensee has notified the State of New York.

The reactor is shutdown with all rods inserted. Decay heat is being rejected to the condenser and reactor water level is being maintained by condensate, feedwater, reactor water clean up, and control rod drive systems.

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Power Reactor Event Number: 49889
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JAMES GROOMS
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/10/2014
Notification Time: 22:43 [ET]
Event Date: 03/10/2014
Event Time: 16:53 [EDT]
Last Update Date: 03/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
MARC FERDAS (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown
2 N Y 100 Power Operation 100 Power Operation

Event Text

POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT

"An extent of condition review identified that there were unfused 250 VDC circuits for the battery charger ammeters and the control circuits for various DC lube oil pumps which left the turbine building and went through the respective cable spreading room and up into the Control Room. These circuits are protected by 200 amp fuses and in some cases 100 amp fuses. The concern is that under the fire safe shutdown rules, it is postulated that a fire in one fire area can damage these circuits and cause short circuits without protection that would overheat the cables and possibly result in secondary fires in other fire areas where the cables are routed. The secondary fires could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R.

"This condition is reportable as an 8-hour ENS report in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition. Compensatory measures (fire watches) have been implemented for affected areas of the plant."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49890
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JOHN PANAGOTOPULOS
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/11/2014
Notification Time: 03:38 [ET]
Event Date: 03/11/2014
Event Time: 03:00 [EDT]
Last Update Date: 03/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARC FERDAS (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

Event Text

TECHNICAL SUPPORT CENTER VENTILATION REMOVED FROM SERVICE FOR PLANNED MAINTENANCE

"On March 11, 2014 at 0300 [EDT], the Hope Creek Technical Support Center (TSC) ventilation system was removed from service to perform planned maintenance. The removal of the ventilation potentially affects the TSC habitability during a declared emergency requiring activation. Appropriate compensatory measures are in place while the ventilation is out of service. The Emergency Response organization duty team has been notified of the maintenance and the possible need to activate the TSC in an alternate location. The ventilation system is scheduled to be out of service for approximately 78 hours."

The licensee will be notifying the NRC Resident Inspector and the Lower Alloways Creek Township.

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