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Event Notification Report for January 10, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/09/2014 - 01/10/2014

** EVENT NUMBERS **


49569 49689 49702 49703 49704 49705 49706 49707 49708 49709 49710

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Part 21 Event Number: 49569
Rep Org: COLUMBIANA HI TECH, LLC
Licensee: COLUMBIANA HI TECH, LLC
Region: 1
City: GREENSBORO State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: LARRY WALKER
HQ OPS Officer: JEFF ROTTON
Notification Date: 11/21/2013
Notification Time: 16:23 [ET]
Event Date: 11/14/2013
Event Time: [EST]
Last Update Date: 01/09/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
FRANK EHRHARDT (R2DO)
PART 21 GROUP (EMAI)
MERAJ RAHIMI (NMSS)

Event Text

PART 21 REPORT REGARDING IDENTIFIED DISCREPANCY WITH INDIVIDUAL NDT LEVEL II CERTIFICATION

Received the following information was obtained via fax:

"Columbiana HI Tech, LLC is performing an evaluation to determine a potentially reportable condition per 10 CFR Part 21 requirements. Description of Noncompliance: A review of NDE certifications revealed discrepant training and work experience records from previous employment provided by a Columbiana HI Tech, LLC employee at the time of certification. This condition was first discovered on 11/14/13. The employee was certified under the Columbiana HI Tech, LLC Qualification & Certification of Nondestructive Examination Personnel Procedure passing all written and practical examinations required for Visual (VT) and Liquid Penetrant (PT) Inspection methods. The discrepant experience and training records from a previous employer were used to help fulfill the training and experience requirements for certification.

"Items affected: Columbiana Hi Tech, LLC Licensed components: Package USA/9196/B(U)F-96; certification number 9196 Rev. 26 UX-30 Overpack. A list of units affected will be compiled.

"Columbiana HI Tech, LLC CUSTOMER components: A list of components manufactured and inspected during the effected time is being reviewed to allow CUSTOMER Notification. Full disclosure will be made to all effected customers as soon as identified and within the reporting requirements of 10 CFR Part 21."


* * * RETRACTION - FROM LARRY WALKER TO GEROND GEORGE AT 1812 EST ON 01/09/2014 * * *

"Columbiana Hi Tech, LLC has concluded that the extent of the issue associated with this inspector is limited to his certification and did not negatively impact his competency for performance of Nondestructive Examination.

"Columbiana Hi Tech has determined this is not a reportable condition per 10 [CFR] Part 21."

Notified R2DO(Hopper), Part 21 Group, and NMSS EO(Silva) via 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: 49703
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: 01/09/2014
Notification Time: 06:42 [ET]
Event Date: 01/09/2014
Event Time: 03:15 [CST]
Last Update Date: 01/09/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
BOB HAGAR (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 96 Power Operation

Event Text

INTAKE STRUCTURE SLUICE GATE INOPERABLE

" At 2230 CST on 1/8/14 during operator rounds it was self identified there was a block of ice formed on the shaft and top of one of the intake structure sluice gates. This has bent the sluice gate operating shaft. At 0315 CST on 1/9/14 it was verified this gate could not be closed.

"There are six intake sluice gates that are required to be able to close to act as flood barriers. The other 5 sluice gates are not affected by this condition."

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 49704
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: 01/09/2014
Notification Time: 06:42 [ET]
Event Date: 01/09/2014
Event Time: 05:18 [CST]
Last Update Date: 01/09/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
BOB HAGAR (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 0 Hot Shutdown

Event Text

TECH SPEC REQUIRED SHUTDOWN DUE TO INOPERABLE RAW WATER PUMPS.

"At 0315 CST T.S. 2.0.1 was entered for all four Raw Water pumps being declared inoperable. The pumps were declared inoperable due to inability to close one of the sluice gates. There are six sluice gates and one is not functional.

"At 0518 the technical specification required shutdown commenced."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM AMY BURKHART TO NESTOR MAKRIS ON 01/09/14 AT 1915 EST * * *

"At 0900 CST 1/9/14 Fort Calhoun Station Unit 1 was manually tripped and entered Mode 3. Reactor Coolant System (RCS) cooldown to less than 300 deg F was commenced at time 1030 CST 1/9/14. The RCS temperature was less than 300 deg F at time 1433 CST. A press release has been issued."

The licensee informed the NRC Resident Inspector.

Notified R4DO [Hagar]

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Power Reactor Event Number: 49705
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAN PIPKIN
HQ OPS Officer: NESTOR MAKRIS
Notification Date: 01/09/2014
Notification Time: 15:29 [ET]
Event Date: 01/09/2014
Event Time: [CST]
Last Update Date: 01/09/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
BOB HAGAR (R4DO)

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

UNANALYZED CONDITION IDENTIFIED FROM OPERATING EXPERIENCE REVIEW

"A review of industry operating experience regarding the impact of unfused [safety-related] direct current ammeter circuits in the main control room has determined the described condition [having the ammeters installed] to be applicable to River Bend Station, resulting in a potentially unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. River Bend Station does have unfused ammeter leads. This normally is not a concern, since two failures are required to cause the problem described in the document referenced above; an ammeter lead must short to ground, and another lead of the opposite polarity must also short to ground. Either of these events by itself will set an alarm, but not cause equipment damage. This allows for locating and repairing the problem before the second failure occurs. However, during a fire, there is a greater chance that these two failures could happen simultaneously, or before a single failure can be repaired.

"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures have been implemented."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 49706
Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL MARVEL
HQ OPS Officer: GEROND GEORGE
Notification Date: 01/09/2014
Notification Time: 15:21 [ET]
Event Date: 01/09/2014
Event Time: 11:35 [EST]
Last Update Date: 01/09/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
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

ENTRY INTO & EXIT FROM TECHNICAL SPECIFICATION 3.6.5.1.1 DUE TO OPEN AIR LOCK DOORS

"Station Personnel simultaneously opened the inner and outer air lock doors from Unit 2 (U2) Reactor Enclosure to the Refuel Floor. Reactor Enclosure Secondary Containment Integrity was declared Inoperable per U2 TS 3.6.5.1.1, due to failure to meet surveillance requirement U2 TS 4.6.5.1.1.b.2, due to the report of both containment airlock doors on 352' momentarily open at the same time. Reactor Enclosure D/P[differential pressure] remained steady at 0.35 inches vacuum water gauge.

"Reactor Enclosure Secondary Containment Integrity was declared Operable following verification that at least one air lock door to each access of secondary containment was closed per U2 TS 4.6.5.1.1.b.2. Total [Limiting Condition for Operation] time was approximately 5 seconds."

The NRC Resident Inspector has been informed.

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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.

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