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Event Notification Report for January 13, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/10/2014 - 01/13/2014

** EVENT NUMBERS **


49531 49679 49689 49702 49707 49708 49709 49710 49712 49713 49714 49715
49716 49717 49718

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 49531
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARTIN LICHTNER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/13/2013
Notification Time: 09:53 [ET]
Event Date: 11/13/2013
Event Time: 02:26 [EST]
Last Update Date: 01/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
J LILLIENDAHL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 99 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

SECONDARY CONTAINMENT ZONE II DIFFERENTIAL PRESSURE LOST DURING RECOVERY FROM VENTILATION DRAWDOWN TEST

"On November 13, 2013 at 0226 [EST], Secondary Containment Zone II (Unit 2 Reactor Building) differential pressure was lost during restoration of a ventilation drawdown test. During restoration Unit 2 'A' Train Reactor Building Ventilation fans tripped. The 'B' Train fans were placed in service and secondary containment was restored. Zone I (Unit 1 Reactor Building) and III (Common Refuel Floor Area) ventilation remained in service and stable.

"Zone II differential pressure recovered within a few minutes and was verified to be stable. LCO 3.6.4.1 was exited for both units at 0257 [EST]. Tech Spec Secondary Containment Operability requires a negative pressure of at least 0.25 inches water gauge.

"There have been no further perturbations in differential pressure and secondary containment remains operable.

"This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System."

The cause of the Unit 2 "A" Train Reactor Building ventilation fans tripping is still under investigation.

The licensee has notified the NRC Resident Inspector.

* * * RETRACTION ON 1/10/14 AT 1657 EST FROM DOUG LAMARCA TO NESTOR MAKRIS * * *

"NUREG-1022, Revision 3 states, ' reports are not required when systems are declared inoperable as part of a planned evolution for maintenance or surveillance testing when done in accordance with an approved procedure and the plant's TS (unless a condition is discovered that would have resulted in the system being declared inoperable).'

"The event reported in this event notification occurred during a pre-planned evolution for surveillance testing that was done in accordance with an approved procedure and the Susquehanna Technical Specifications. The loss of differential pressure occurred during restoration from the surveillance test and occurred prior to completing the planned evolution and declaring the system OPERABLE. Specifically, the trip of the fans occurred when restoring the Reactor Building normal ventilation after a Zone 1, 2, and 3 isolation (returning back to normal ventilation from the Standby Gas Treatment System). The secondary containment boundary and standby gas treatment system were unaffected. This event occurred as a result of the testing process and would not have occurred during normal operation of the system. There was no discovered condition that would have resulted in the safety function of the system being declared inoperable under normal, non-testing conditions.

"Based on the above additional information, PPL is retracting this report. Susquehanna was in a planned evolution and did not discover a condition that could have prevented performing a safety function."

The licensee has notified the NRC Resident Inspector. Notified the R1DO (Schmidt).

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Agreement State Event Number: 49679
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: WELDSONIX, INC.
Region: 4
City: HOUSTON State: TX
County:
License #: 05718
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/30/2013
Notification Time: 06:18 [ET]
Event Date: 12/30/2013
Event Time: 04:25 [CST]
Last Update Date: 12/30/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JACK WHITTEN (R4DO)
ANGELA MCINTOSH (FSME)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)

Event Text

AGREEMENT STATE REPORT - ATTEMPTED THEFT OF LICENSED NUCLEAR MATERIAL

The following information was provided by the State of Texas via email:

"On December 30, 2013, the Agency [Texas Department of Health] was notified by the licensee's Radiation Safety Officer (RSO) they had received a call from their security company stating the alarm at their facility had activated. The security company also called local law enforcement (LLE) who had responded. The RSO stated when they arrived at the location, they found a hole had been cut in the side of the metal building where the storage area for their exposure devices is located. The lock on the outer storage vault had been cut, but the lock on the inner vault was still intact. The RSO stated it appeared no radioactive material was removed from the facility. The RSO stated the building lights, which are always on, were off when he arrived. The RSO stated LLE is sending a team to take finger prints in the area. The RSO stated the hoods off of six of their trucks had been removed and are missing. The RSO stated he was waiting for LLE to complete their work before he opens the storage vault. The RSO stated he will update this Agency as soon as they complete their inspection of the facility. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident #: I-9144

* * * UPDATE AT 0716 EST ON 12/30/13 FROM ART TUCKER TO S. SANDIN * * *

The following update was received via email:

"On December 30,2013, at 0552 hours, the licensee's Radiation Safety Officer (RSO) contacted the Agency and stated they had accounted for all of their sources, none were missing. The RSO stated Local Law Enforcement (LLE) had completed processing the scene. The RSO stated one of their trucks had been stolen. The truck has a tracking device on it and they had located the truck using the device. The RSO stated the truck was located about five mile from the licensee's address. Local Law enforcement is investigating. Additional information will be provided as it is received in accordance with SA-300."

Notified R4DO (Whitten), FSME (McIntosh), FSME Events Resource (email) and ILTAB (email).

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Non-Agreement State Event Number: 49689
Rep Org: WAUPACA FOUNDRY
Licensee: WAUPACA FOUNDRY
Region: 3
City: TELL CITY State: IN
County:
License #: 48-15031-01
Agreement: N
Docket:
NRC Notified By: GARY GREUBEL
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 01/02/2014
Notification Time: 20:41 [ET]
Event Date: 01/02/2014
Event Time: 15:30 [EST]
Last Update Date: 01/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
MICHAEL KUNOWSKI (R3DO)
FSME RESOURCES (EMAI)

Event Text

FIXED SOURCE SHIELDING FAILURE

"This letter is a follow up to our phone conversation dated January 2, 2014, with a contact time of 2041 EST which involved damage to one of our fixed nuclear sources (Model TN5200 s/n B3493). This report is being filed in compliance to 10 CFR 30.50(b)(2)(ii).

"On January 2, 2014, on or about 1535 pm CST it was noted that the shell of our #2 cupola had overheated during startup of the equipment. Previously at 1130 CST, the shell temperature was noted at 145 degrees F. At the time of the event, the shell temperature was noted at 990 degrees F. The person taking the temperatures was using a hand held laser temperature device and took the temperature remote to the shell. The person taking the temperatures immediately contacted a Radiation Safety Officer (RSO). The RSO then conducted a visual inspection of the gauge and noted a puddle in front of the gauge. All personnel were evacuated from the vicinity of the cupola shell. An additional RSO was contacted at 1602 CST via phone. He then proceeded to conduct an evaluation of the area at approximately 1630 CST.

"The nuclear source noted above is used to measure scrap metal level in the cupola and is located directly against the cupola shell, down in an enclosed moat. This in turn resulted in the high ambient temperatures causing the lead shielding of the nuclear source to melt out the front of the gauge. The amount of lead melted out is estimated to be the equivalent of shot glass.

"The manufacturer of the gauge was contacted at 1732 CST and informed of the event. The RSO will contact the manufacturer again tomorrow during normal business hours to arrange for the removal and replacement of the gauge.

"The gauge is a Thermal Fisher Model TN5200, serial number B3493 containing Cs-137 with an activity of 100 mCi.

"The evaluation of the gauge was compared to survey readings previously taken on September 14, 2013 by the RSO in conjunction with the required six month inventory requirements. Survey readings conducted this evening were done using a Ludlum Model 3 calibrated on December 20, 2013.

"There were no over exposures during this event due to the remote reading of the temperature and the quick evacuation of the area. Follow up surveys did note an area by the receiver of the damaged gauge (approximately 21 feet away) to be 0.4 mR which is higher than the previous reading in September of 0.1 mR. Crews were instructed to not enter the moat nor attempt to repair the receiver due to the inability to lock out the shutter at this time.

"All other areas noted in the vicinity of the gauge as well as above and below the gauge were the same as or below the September readings.

"The cause of the event as to the shell overheating will be further investigated tomorrow, January 3, 2014. The results of the investigation will be included in a letter within 30 days to [U.S.NRC] Region Ill."

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Power Reactor Event Number: 49702
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: RUSSELL LONG
HQ OPS Officer: GEROND GEORGE
Notification Date: 01/08/2014
Notification Time: 19:49 [ET]
Event Date: 01/08/2014
Event Time: 10:10 [PST]
Last Update Date: 01/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BOB HAGAR (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF ASSESSMENT CAPABILITY - NON-FUNCTIONAL AREA RADIATION MONITORS

"At [1010 PST] on 1/08/14, during performance of a surveillance the power supply for ten area radiation monitors in the Reactor Building was found with voltage out of specification. As a result, the affected area radiation monitors were declared non-functional. This condition represents a major loss of assessment capability and is being reported as such under 10 CFR 50.72 (b)(3)(xiii). As directed by station procedures, compensatory measures have been enacted until the power supply is restored.

"The Resident Inspector has been notified."

* * * UPDATE FROM JASON LOVEGREN TO JIM DRAKE ON 01/10/2014 AT 0214 EST* * *

"The power supply voltage has been restored to specification per applicable station procedures. All affected area radiation monitors have been declared functional. Compensatory measures have been suspended."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49707
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE FIELDS
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 01/09/2014
Notification Time: 18:56 [ET]
Event Date: 01/09/2014
Event Time: 18:03 [EST]
Last Update Date: 01/10/2014
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GEORGE HOPPER (R2DO)
JOHN LUBINSKI (NRR)
WILLIAM GOTT (IRD)

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

UNUSUAL EVENT DECLARED DUE TO SEVERE RAIN STORM

"On January 9, 2014 St. Lucie Unit 1 declared an Unusual Event based on a severe rain storm, a natural occurrence affecting the Protected Area. Specifically, visual sightings by station personnel that water levels are approaching storm drain system capacity. Countermeasures are being deployed and are currently operating satisfactorily. Both units continue to operate at full power. All safety systems remain available.

The licensee has notified the NRC Resident Inspector, state, and other local authorities.

Notified R2DO (Hopper), NRR EO (Lubinski) and IRD.

Notified DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, and Nuclear SSA via email.

* * * UPDATE FROM RACHEL SMITH TO GEROND GEORGE ON 01/10/2014 AT 0043 EST * * *

"On January 10, 2014 at 0001 EST, St. Lucie Unit 1 terminated an Unusual Event. Site storm drain system functioning as required. Severe weather has passed, site water levels have returned to normal."

Notified R2DO (Hopper), NRR EO (Lubinski) and IRD.

Notified DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, and Nuclear SSA via email.

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Power Reactor Event Number: 49708
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: JOHN MCDONALD
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 01/10/2014
Notification Time: 00:27 [ET]
Event Date: 01/09/2014
Event Time: 22:34 [EST]
Last Update Date: 01/10/2014
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):
GEORGE HOPPER (R2DO)

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

Event Text

AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP

"At 2234 hours EST on 01/09/2014, with the unit in Mode 1 at 100% power, an automatic reactor trip occurred. At the time of the event, Steam Generator Water level Protection Channel Testing was in progress. While testing was in progress with the 'C' Steam Generator Channel 1 Water Level Protection channel in trip for testing, a Turbine Trip occurred. The cause of the Turbine Trip is under investigation.

"The [Turbine Driven and Motor Driven] Auxiliary Feedwater System automatically actuated, as expected due to low steam generator water level, and provided feedwater to the steam generators. The pressurizer Power Operated Relief Valves (PORVs) and the Main Steam Safety Valves did not open during the event. All control rods indicated fully inserted following the reactor trip.

"Currently, the unit is stable in Hot Standby (Mode 3).

"This event is being reported as a 4 hour Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B) due to the valid Reactor Protection System Actuation.

"This event is being reported as an 8 hour Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A) due to the valid actuation of Auxiliary Feedwater System.

"At no time during this occurrence was the public or plant staff at risk as a result of this event.

"The NRC Resident Inspector has been notified. State and local authorities will be notified. Estimated restart date is 1/12/2014"

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Power Reactor Event Number: 49709
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: JASON LOVEGREN
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/10/2014
Notification Time: 02:14 [ET]
Event Date: 01/09/2014
Event Time: 17:43 [PST]
Last Update Date: 01/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BOB HAGAR (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE

"Reactor Building (Secondary Containment) pressure increased to above the Technical Specification Surveillance requirement of 0.25 inches vacuum water gauge briefly (two minutes or less) on two occasions. This is reportable as an event that could have prevented fulfillment of a safety function needed to control the release of radiation and mitigate the consequences of an accident. Reactor Building pressure has been restored to normal (greater than 0.25 inches vacuum water gauge) returning Secondary Containment to operable status. The cause of the event is under investigation.

"There were no radiological releases associated with the event.

"No safety system actuations or isolations occurred."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 49710
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/10/2014
Notification Time: 06:39 [ET]
Event Date: 01/09/2014
Event Time: 23:17 [CST]
Last Update Date: 01/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
WAYNE WALKER (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Standby 0 Hot Shutdown

Event Text

DEGRADED FITTINGS CONNECTED TO CONTAINMENT PENETRATION

"During an engineering walk down inside containment a minor leak from a pipe fitting was discovered on the primary sampling piping connected to penetration M-45. There was previously identified minor leakage from a fitting on this same penetration outside of containment in the auxiliary building. The containment isolation valves are currently tagged closed."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 49712
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: ANDREW TEREZAKIS
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 01/10/2014
Notification Time: 13:27 [ET]
Event Date: 01/10/2014
Event Time: 12:14 [EST]
Last Update Date: 01/10/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
GEORGE HOPPER (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 93 Power Operation 93 Power Operation

Event Text

OFFSITE NOTIFICATION DUE TO TEMPORARY BYPASS OF NORMAL OUTFALL DURING SEVERE WEATHER

"On January 10, 2014, Florida Power and Light reported to the Florida Department of Environmental Protection that the St. Lucie Nuclear Plant temporarily bypassed the normal storm collection outfall path at 17:45 EST on January 9, 2014. The bypassed flow of water was a result of severe rainfall at the station and a blockage in the normal outfall path.

"This non-emergency notification is being made pursuant to 10CFR50.72(b)(2)(xi) due to the notification of the Florida Department of Environmental Protection."

The licensee originally made the offsite notification to the State of Florida agency associated with the emergency declaration and severe weather event on January 9, 2014 (see Event Notification 49707).

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49713
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JUSTIN EASTMAN
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 01/10/2014
Notification Time: 20:11 [ET]
Event Date: 01/10/2014
Event Time: 19:48 [EST]
Last Update Date: 01/10/2014
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GEORGE HOPPER (R2DO)
JOHN LUBINSKI (NRR)
VICTOR MCREE (R2RA)
ERIC LEEDS (NRR)
WILLIAM GOTT (IRD)

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

UNUSUAL EVENT DECLARED DUE TO EXPLOSION WITHIN PROTECTED AREA BOUNDARY

The licensee declared a Notice of an Unusual Event per EAL HU2.2 "Explosion with Protected Area Boundary" following an apparent fault and explosion on the M29 transformer (a non-safety related transformer). This resulted in a loss of one electrical bus at the ocean discharge station; however, no safety-related electrical loads were effected and both units remained at 100 percent electrical power. Station personnel reported that there was no smoke in the area of the M29 transformer and the event may have been a flashover explosion in the area of the transformer. All safety systems remain available. Licensee is investigating the cause of the explosion, and no offsite assistance was required.

The licensee has notified the NRC Resident Inspector, the State of North Carolina, and other local authorities.

Notified DHS SWO, FEMA Operations Center, NICC Watch Officer, and NuclearSSA via e-mail.

* * * UPDATE ON 01/10/14 AT 2343 EST FROM MIKE MORRIS TO RYAN ALEXANDER * * *

"Notification of an Unusual Event is being terminated [at 2320 EST] because the condition no longer exists. The source of the apparent explosion was a failed insulator on a breaker and is known to present no danger to public health and safety. Both Units are stable and a recovery organization is in place."

The licensee has notified the NRC Resident Inspector regarding the termination of the event.

Notified R2DO (Hopper), NRR EO (Lubinski), IRD Manager (Gott), DHS SWO, FEMA Operations Center, NICC Watch Officer, and Nuclear SSA via e-mail.

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Power Reactor Event Number: 49714
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MICHAEL STIDMON
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/11/2014
Notification Time: 03:33 [ET]
Event Date: 01/11/2014
Event Time: 01:00 [CST]
Last Update Date: 01/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
CHRISTINE LIPA (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 91 Power Operation 60 Power Operation

Event Text

OFFSITE NOTIFICATION DUE TO DECREASING DISCHARGE TEMPERATURE

"At 0205 CST [on 1/11/14], Xcel Energy Environmental Services made a report to the State of Minnesota due to cooling water return to the Mississippi River via the plants discharge canal dropping by more than 5 degrees F in an hour. The cause of the temperature drop was due to an emergent reduction in reactor power and generator load in response to a degrading condenser vacuum.

"This notification is being made under 10 CFR 50.72(b)(2)(xi) based on a notification to another Government Agency.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 49715
Facility: FARLEY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN ANDREWS
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 01/11/2014
Notification Time: 13:24 [ET]
Event Date: 01/11/2014
Event Time: 11:00 [CST]
Last Update Date: 01/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
GEORGE HOPPER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 51 Power Operation

Event Text

PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS

"On January 10, 2014, at 0919 CST, the plant voluntarily entered multiple required action statements in Technical Specifications 3.3.1 Reactor Trip System Instrumentation and 3.3.2 Engineered Safety Feature Actuation System to conduct surveillance testing of the B-train Solid State Protection System (SSPS). During testing, abnormal indications were received. As a result of the abnormal indications, the SSPS has not been returned to operable status within the required completion time of 24 hours. At 1100 CST on January 11, 2014, Unit 2 commenced a plant shutdown required by technical specifications and will be in Mode 3 by 1519. Therefore, this is reportable under 10 CFR 50.72(b)(2)(i), plant shutdown required by technical specifications.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 49716
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: SHAWN SNOOK
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/11/2014
Notification Time: 22:25 [ET]
Event Date: 01/11/2014
Event Time: 16:05 [EST]
Last Update Date: 01/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WAYNE SCHMIDT (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

DIGITAL RADIATION MONITORING SYSTEM COMMUNICATION FAILURE

"At 1605 EST on January 11, 2014, Beaver Valley Power Station (BVPS) Unit 2 determined that the Digital Radiation Monitoring System (DRMS) had a communication loop failure resulting in a loss of control room radiation monitor indication and alarm capability. BVPS Unit 2 DRMS was declared nonfunctional. Repair efforts were initiated and compensatory measures were established.

"At 2040 EST on January 11, 2014, BVPS Unit 2 DRMS was returned to service and declared functional.

"The failure of the BVPS Unit 2 DRMS communication loop resulted in a loss of emergency assessment capability and is reportable per 10 CFR 50.72(b)(3)(xiii).

"The NRC Resident Inspector has been notified."

The licensee notified Pennsylvania, West Virginia and Ohio emergency management agencies as well as local authorities of this notification.

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Power Reactor Event Number: 49717
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 01/12/2014
Notification Time: 06:44 [ET]
Event Date: 01/12/2014
Event Time: 03:23 [CST]
Last Update Date: 01/12/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
WAYNE WALKER (R4DO)

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

Event Text

MANUAL REACTOR TRIP FOLLOWING CONTROL ROD POSITION DEVIATION

"After achieving criticality a deviation between control rods was observed by plant personnel. When attempting to level the control rods, one rod could not insert to the level of the rest of the group. A manual reactor trip was initiated by the operating crew. All tripable control rods fully inserted into the core."

The trip was uncomplicated and the licensee is investigating the cause of the control rod position deviation.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49718
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BENNIE WHITE
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/13/2014
Notification Time: 03:28 [ET]
Event Date: 01/13/2014
Event Time: 04:00 [EST]
Last Update Date: 01/13/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GEORGE HOPPER (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

LOSS OF TECHNICAL SUPPORT CENTER DUE TO PLANNED MAINTENANCE

"A condition Is being reported per TRM 13.13.1 Emergency Response Facilities Action 8.2. The Functionality of the Technical Support Center (TSC) has been lost due to planned maintenance activities performed on TSC Support Systems. Alternate facilities are available to provide emergency response functions and actions are proceeding to return the TSC to functional status with high priority. A 10CFR50.54(q) evaluation has been performed for this planned maintenance activity. The NRC resident Inspector has been notified."

Page Last Reviewed/Updated Monday, January 13, 2014
Monday, January 13, 2014