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Event Notification Report for April 15, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/12/2013 - 04/15/2013

** EVENT NUMBERS **


48628 48888 48889 48914 48918 48919 48920 48921 48922 48923

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Power Reactor Event Number: 48628
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: MICHAEL PEAK
HQ OPS Officer: PETE SNYDER
Notification Date: 12/27/2012
Notification Time: 15:46 [ET]
Event Date: 12/27/2012
Event Time: 14:45 [CST]
Last Update Date: 04/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HEATHER GEPFORD (R4DO)

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

Event Text

SCHEDULED OPERATIONS SUPPORT CENTER (OSC) OUTAGE FOR EQUIPMENT UPGRADE

"Fort Calhoun Station (FCS) will be implementing a scheduled modification to renovate and upgrade the interior configuration of the site's Operational Support Center (OSC). The OSC is located within the Technical Support Center (TSC). The TSC will remain fully operable. Due to the construction, beginning on December 27, 2012 with a planned completion date of February 27, 2013, the OSC will be inoperable. An alternate OSC has been established on-site and is fully operable."

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 0900 EST ON 03/08/13 FROM MICHAEL PEAK TO S. SANDIN * * *

"This is an update to Event Notification 48628, dated December 27, 2012.

"On March 8th, 2013, Fort Calhoun Station (FCS) will be entering a new phase of scheduled modifications to renovate and alter the interior configuration of its Technical Support Center (TSC). The TSC ventilation system will not be functional during this phase of modification. Combined with renovations, the primary TSC and OSC will be inoperable. An alternate OSC and TSC have been established. If the Emergency Response Organization is activated the alternate emergency facilities will be available for emergency responders per existing Emergency Plan procedures.

"The project is scheduled to be completed April 12, 2013. An update to this report will be provided when the TSC renovation is complete."

The licensee informed the NRC Resident Inspector. Notified R4DO (Werner).

* * * UPDATE AT 1020 EDT ON 04/12/13 FROM DAVID ORTIZ TO P. SNYDER * * *

"This is an update to Event Notification 48628, dated December 27, 2012.

"As of April 12th, 2013 Fort Calhoun Station has completed modifications to the Technical Support Center (TSC) and Operations Support Center (OSC). The TSC ventilation system has been proved functional through required testing. The primary TSC/OSC is now fully operational."

The licensee notified the NRC Resident Inspector. Notified R4DO (Deese).

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Agreement State Event Number: 48888
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: PEKINS ELMER
Region: 4
City: RICHLAND State: WA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KRISTEN SCHWAB
HQ OPS Officer: VINCE KLCO
Notification Date: 04/04/2013
Notification Time: 16:08 [ET]
Event Date: 03/18/2013
Event Time: [PDT]
Last Update Date: 04/04/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
FSME RESOURCES (EMAI)

Event Text

AGREEMENT STATE REPORT - SHIPMENT EXCEEDED SURFACE CONTAMINATION LIMITS

The following information was received from the Washington State Division of Radiation Protection by email:

"PermaFix Northwest received a shipment from Perkin Elmer, Inc. that consisted of 32 packages, 4 plastic drums and 28 metal drums, and was shipped as an exclusive use shipment. Upon receipt, the drums were surveyed and 2 plastic drums were found to exceed the 49 CFR 173.443 non-removable contamination limit of 2,200 dpm/cm2 for an exclusive use shipment. The drum survey results were reported as 44,391 dpm/100 cm2 H-3 and 18,080 dpm/100 cm2 C-14; 20,127 dpm/100 cm2 H-3 and 18,508 dpm/100 cm2 C-14, and 13,323 dpm/100 cm2 H-3 and 10,019 dpm/100 cm2 C-14. This most contaminated drum was manifested with only H-3 and C-14, the other 2 drums were manifested with only C-14."

Washington Incident Number: WA-13-021

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Agreement State Event Number: 48889
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: JACOBSEN CONSULTING
Region: 4
City: MODESTO State: CA
County:
License #: 6370-39
Agreement: Y
Docket:
NRC Notified By: KAMANI HEWADIKARAM
HQ OPS Officer: VINCE KLCO
Notification Date: 04/04/2013
Notification Time: 17:43 [ET]
Event Date: 04/03/2013
Event Time: [PDT]
Last Update Date: 04/04/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
FSME RESOURCES (EMAI)
MEXICO (EMAI)
ILTAB (EMAI)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST MOISTURE GAUGE

The following information was from the State of California via email:

"On 04/04/13, [the licensee] RSO, called RHB [California Radiologic Health Branch] to report a lost gauge. The gauge is a Model 503 DR CPN moisture gauge (S/N H33064926) containing 50 mCi (max) of Americium 241:Be. [The RSO] stated that he placed the gauge in the back of his truck next to the tailgate, then got distracted by a telephone call and started driving from 4181 Brew Master Dr, Suite 4, Ceres, CA, on Crows Landing, Hwy N 99 and then onto Hwy 88 without securing the gauge. He discovered the gauge missing [at 1600 PDT] on 04/03/13, upon arrival at a jobsite. The Ceres Police Department was notified of the lost gauge (case # 213-001653). Licensee was advised to place an advertisement in a local paper/craigslist offering a reward of $4000.00 for the safe return of the gauge. RHB will be investigating the incident and licensee will be cited for the items of non compliance associated with this incident."

California Report: #040413

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Power Reactor Event Number: 48914
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JAMES KURAS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/11/2013
Notification Time: 16:47 [ET]
Event Date: 04/11/2013
Event Time: 15:10 [CDT]
Last Update Date: 04/12/2013
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
RICK DEESE (R4DO)
JANE MARSHALL (IRD)
ART HOWELL (RA)
DAN DORMAN (NRR)
JOHN MONNINGER (NRR)

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

Event Text

UNUSUAL EVENT FOR A FIRE LASTING GREATER THAN 15 MINUTES

"The fire started at 1455 CDT in the turbine building southeast stairwell and on the auxiliary boiler room roof. Fire fighting efforts continue as fire exists inside the wall between the turbine building and the auxiliary boiler room.

The licensee notified the NRC Resident Inspector, state, and local governments.

Notified DHS, FEMA, and the NICC.

* * * UPDATE FROM WARREN BRANDT TO PETE SNYDER AT 0100 EDT ON 4/12/13 * * *

"Wolf Creek declared a NOUE at 15:10 CDT on 4/11/13 due to a fire that started at 14:55 [CDT] in the Turbine Building SE stairwell and on the Auxiliary Boiler room roof. The fire was extinguished at 15:19 [CDT], and cool to the touch at 16:48 [CDT]. No offsite fire response support was required. The fire did not impact any safety related equipment.

"The NOUE was terminated at 17:03 CDT 4/11/13. The cause of the fire is under investigation."

Notified R4DO (Deese), NRR EO (Monninger), IRD (Marshall), DHS, FEMA and NICC (via email).

* * * UPDATE FROM PIERCE MOORE TO JOHN SHOEMAKER AT 1400 EDT ON 4/12/13 * * *

"Update to Termination of NOUE due to Fire on roof of Auxiliary Boiler.

"Wolf Creek declared a NOUE at 15:10 CDT on 4/11/13 due to a fire that started at 14:55 [CDT] in the Turbine Building SE stairwell and on the Auxiliary Boiler room roof. The fire was extinguished at 15:19 [CDT], and cool to the touch at 16:48 [CDT]. The Offsite Fire Department was called and responded but their support in fire suppression was not required, they did assist in clean up and fire investigation efforts. The fire did not impact any safety related equipment.

"The NOUE was terminated at 17:03 CDT 4/11/13. The cause of the fire is under investigation."

Notified R4DO (Deese), NRR EO (Monninger), IRD (Marshall) via email.

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Power Reactor Event Number: 48918
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: DALE BISAILLON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/12/2013
Notification Time: 14:45 [ET]
Event Date: 04/12/2013
Event Time: 10:10 [EDT]
Last Update Date: 04/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
HAROLD GRAY (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

UNANALYZED CONDITION - MISSING BACKFLOW PREVENTER

"On 4/12/2013 at 1010 EDT, it was determined that a floor drain line between the Turbine Building and Intermediate Building did not have a backflow preventer as expected. Backflow protection is provided to prevent the possible spread of a fire via the drain system. The Turbine Building and the Intermediate Building are considered two different fire areas within the scope of the fire protection program. The discovery of this condition is being reported as an unanalyzed condition as defined by 10CFR50.72(b)(3)(ii)(B).

"In accordance with the Technical Requirements Manual, an hourly fire watch inspection and fire detector operability verification have been established until an equivalent level of protection is provided or until permanent corrective actions can be implemented.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 48919
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MATTHEW QUICK
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/13/2013
Notification Time: 03:18 [ET]
Event Date: 04/12/2013
Event Time: 22:00 [CDT]
Last Update Date: 04/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DAVE PASSEHL (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Defueled 0 Defueled

Event Text

UNANALYZED CONDITION DUE TO ISOLATED DIFFERENTIAL PRESSURE SWITCH ON SAFETY RELIEF VALVE TAILPIPE

"On April 12th, 2013 at 2200 CDT, investigation into the inability to complete a Safety/Relief Valve (S/RV) discharge line excess flow check valve test determined that a relief valve discharge monitoring instrument valve had been inappropriately closed since late June, 2011. The closed valve isolated two differential pressure switches that impact the operation of 'E' Low-Low Set (LLS) valve. The LLS logic and instrumentation were affected by the loss of two 'E' S/RV tailpipe discharge pressure switches which indicate S/RV open status and start two inhibit timers which prevent plant operators or the LLS S/RV logic from immediately re-opening the valve to allow the water leg in the S/RV discharge line to recede. The LLS logic and instrumentation is designed to mitigate the effects of postulated thrust loads on the S/RV discharge lines by preventing subsequent actuations with an elevated water leg in the S/RV discharge line. It also mitigates the effects of postulated pressure loads on the torus shell or suppression pool by preventing multiple actuations in rapid succession of the S/RVs subsequent to their initial actuation. The valve found closed has been returned to its normal open position. This condition resulted in the 'E' S/RV LLS function being aligned contrary to its design configuration and as such is being reported as an unanalyzed condition as defined by 10 CFR 50.72(b)(3)(ii)(B)."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48920
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: GEORGE LESTER
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/13/2013
Notification Time: 18:21 [ET]
Event Date: 04/13/2013
Event Time: 11:09 [CDT]
Last Update Date: 04/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVE PASSEHL (R3DO)

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

SERVICE WATER SYSTEM EFFLUENT LINE NON-FUNCTIONAL

"At 1109 CDT on 4/13/13, R-20, Service Water System Effluent Line (Auxiliary Building Service Water Header) was declared non-functional due to low SW [Service Water] sampling flow. R-20 is used for Emergency Action Level (EAL) classifications of an unplanned release of liquid radioactivity to the environment that exceeds the requirements of the Offsite Dose Calculation Manual for an Unusual Event and an Alert, and is therefore, being conservatively reported under 10 CFR 50.72(b)(3)(xiii) as a loss of emergency assessment capability."

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 48921
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: KARL COSSEY
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/14/2013
Notification Time: 13:24 [ET]
Event Date: 04/14/2013
Event Time: 06:20 [CDT]
Last Update Date: 04/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVE PASSEHL (R3DO)

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

Event Text

CONTAINMENT SPRAY CHEMICAL ADDITION FLOW PATH ISOLATED

"At 0620 CDT on 4/14/13, the Unit 1 Sodium Hydroxide Tank outlet valve was found to be shut. This valve isolated the flow path for both trains of containment spray chemical addition and resulted in LCO 3.6.7 (Spray Additive System) not being met, which resulted in a condition reportable pursuant to 10 CFR 50.72(b)(3)(v)(D).

"At 0651 CDT on 4/14/13, the Unit 1 Sodium Hydroxide Tank outlet valve was restored to its required locked open position and TSAC [Technical Specification Action Conditions] 3.6.7.8 was exited."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48922
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RANDY ROSE
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/14/2013
Notification Time: 13:47 [ET]
Event Date: 04/14/2013
Event Time: 14:00 [EDT]
Last Update Date: 04/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVE PASSEHL (R3DO)

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

Event Text

UNAVAILABILITY OF TSC VENTILATION SYSTEM DUE TO SCHEDULED MAINTENANCE

"At 1400 EDT on Sunday, April 14, 2013, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.

"Under certain accident conditions, the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.

"TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 1400 EDT on Wednesday, April 17, 2013.

"The licensee has notified the NRC Resident Inspector.

"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the loss of an emergency response facility."

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Power Reactor Event Number: 48923
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN WHALLEY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/15/2013
Notification Time: 02:01 [ET]
Event Date: 04/14/2013
Event Time: 22:17 [EDT]
Last Update Date: 04/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
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 N 0 Startup 0 Hot Shutdown

Event Text

SPECIFIED SYSTEM ACTUATIONS WHILE SHUTTING DOWN

"On Sunday, April 14, 2013 at 2217 hours, with the Pilgrim Nuclear Power Station (PNPS) Reactor Mode Select Switch (RMSS) in Start-up, the turbine generator previously removed from service, and the reactor sub-critical on Intermediate Range Monitors Range 2 and lowering, a manual reactor scram was inserted due to reactor pressure lowering beyond established control bands. At the time of the manual reactor scram PNPS was conducting a planned reactor shutdown to commence refueling outage (RFO) -19. All control rods fully inserted and Primary Containment Isolation System Group II (Reactor Building) and Group VI (Reactor Water Cleanup System) actuations occurred as designed due to the expected reactor water level shrink associated with the scram signal. All plant systems responded as designed. Off-site power was unaffected and was supplied by the start-up transformer (normal power supply for refuel and reactor shutdown operations).

"The Main Steam Isolation Valves (MSIV) were manually closed to terminate the reactor pressure reduction and the High Pressure Coolant Injection (HPCI) system was manually started in the reactor pressure control mode. The Reactor Protection System (RPS) was reset as were the reactor building and reactor water clean-up system isolation signals. Currently, the plant cooldown is continuing with the HPCI system in pressure control and reactor water level being maintained within normal bands with the condensate and feedwater system. The cause of the lowering reactor pressure has not been determined and remains under review.

"This event had no impact on the health and/or safety of the public.

"This 8-hour notification is being made in accordance with 10 CFR 50.72 (b)(3)(iv)(A)."

The NRC Senior Resident Inspector has been notified. The licensee will also be notifying state authorities.

Page Last Reviewed/Updated Monday, April 15, 2013
Monday, April 15, 2013