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Event Notification Report for September 13, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/10/2010 - 09/13/2010

** EVENT NUMBERS **


46210 46240 46241 46242 46243 46244 46246

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General Information or Other Event Number: 46210
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: MULTIPLE
Region: 1
City: NEW CASTLE State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID J. ALLARD
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/27/2010
Notification Time: 17:33 [ET]
Event Date: 08/27/2010
Event Time: [EDT]
Last Update Date: 09/11/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
PAMELA HENDERSON (R1DO)
PAUL MICHALAK (FSME)

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

Event Text

AGREEMENT STATE REPORT INVOLVING ORPHANED / MISSING GENERAL LICENSE SOURCES

The following information was received from the State of Pennsylvania via fax:

"Event Report ID No: PA100020

"License No: PA-G0241, PA-G0029, PA-G0141

"Licensee(s): New Castle Rolling Mills, Sharon Strip Steel and/or Cedar Mills

"Event date and time: Unknown

"Event location: 902 North Cedar Street, New Castle, PA 16102

"Event type: Five (5) missing [licensed material] GL sources and shutter function failure

"Notifications: July 2010 PA DEP Southwest Regional Office Inspection

"Event Description: Since becoming an Agreement State in March 2008, DEP has transitioned hundreds of NRC specific and general licenses (GL) to PA state control. Recently, working from an NRC spreadsheet, DEP has been issuing GL certificates of registration for certain category GLs, and tracking unresponsive GL owners. The original information we had from the NRC indicated 11 sources had been distributed to the above location over time. The current facility owner is not a steel manufacturer, and was unaware these GL sources were on their property.

"An inspection in July 2010 noted 6 of potentially 11 'C-frame' thickness gauge GL sources could be accounted for, with 4 onsite and 2 recently transferred back to a gauge manufacturer. Each of the 11 GL gauges contained a one (1) curie americium-241 sealed source. Since there is no NRC data on possible return or transfer of GL sources, and two manufacturers are no longer in business, the tracking of 5 GL sources appears to be impossible. The event location noted above has had three different owners / GL licensees over the years, two of which are known out of business. A third firm may still be in business, and will be pursued regarding the 5 unaccounted for sources. Lastly, 1 of the 4 GL sources was found to have an open shutter. All 4 'orphan' sources have been registered with the DOE/LANL OSRP [Off-Site Source Recovery Project] program for transfer.

"Due to the unaccountability of the five 1 Ci Am-241 GL sources, DEP believes this to be reportable under 20.2201 (a)(1)(i). And, since one of the six sources that were accounted for had an open shutter, DEP finds this to be reportable under 30.50(b)(2)(i).

"CAUSE OF THE EVENT: Improper transfer of GL sources and ineffective regulatory control.

"ACTIONS: Two of the devices have been returned to a manufacturer. Four of the sources remain at the facility in New Castle, PA in a secured location. More investigation is being done to track the five unaccountable GL devices.

"Media attention: None at this time"

* * * UPDATE FROM DAVID ALLARD TO VINCE KLCO ON 9/11/2010 AT 2131* * *

The following information was received by facsimile:

"After a PaDEP [Pennsylvania Department] teleconference with the NRC on August 31,2010, it was determined that all gauges associated with this event are accounted for, and this update is needed to retract the notification of five (5) missing one (1) curie Am-241 GL sources. Apparently a duplication of data error occurred on the NRC's GL spreadsheet, resulting in the miscalculation of eleven (11) total gauges, when in fact only six (6) gauges were transferred to this site over the years.

"Two (2) gauges have been returned to a manufacturer while four (4) gauges remain at the location, securely stored, awaiting disposal or transfer. These sources are registered with the DOE/LANL OSRP program, and will soon be registered on the CRCPD's 'source exchange' program for possible reuse or recycle.

"However, due to the fact that one of the four GL sources was found to have an open shutter and this remains reportable under 10 CFR 30.50(b)(2)(i). The current property owner was instructed to contact a gauge service vendor to correct the open shutter, and inform the [Pennsylvania] Department when complete.

"CAUSE OF THE EVENT: Improper tracking of GL sources, and failure to control the GL sources on the part of the licensees.

"ACTIONS: Two of the devices have been returned to a manufacturer. Four of the sources remain at the facility in New Castle, PA in a secured location.

"Media attention: None at this time"

Notified R1DO(Cook) and FSME EO(Foster)

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

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source

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Power Reactor Event Number: 46240
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JAMIE WEIGANDT
HQ OPS Officer: VINCE KLCO
Notification Date: 09/09/2010
Notification Time: 20:25 [ET]
Event Date: 09/09/2010
Event Time: 15:20 [CDT]
Last Update Date: 09/12/2010
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 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

EMERGENCY SIRENS INADVERTENTLY ACTUATE

"At 1520 [CDT], Point Beach was notified by Manitowoc County Sheriff's Department (MCSD) and citizens of audible EP Siren actuation in the City of Two Rivers and the Town of Two Creeks, WI. System troubleshooting was in progress at the time of actuation.

"Alert and Notification System Siren configuration was restored to normal at approximately 1630 [CDT]. All required ANS sirens were 'Poll tested' and are fully functional.

"Further reviews indicated that Sirens P-001 through P-013 (13 sirens) had each simultaneously received a 180 second activation. At this time the cause of the activation signal is unknown. All troubleshooting and testing are currently suspended; event investigation has commenced."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM RIVAS TO KLCO ON 9/12/10 AT 1156 * * *

"This notification is an update to ENS notification #46240 made by Point Beach.

"Notification #46240 was submitted September 9 at 2025 EDT regarding Point Beach notification by Manitowoc County Sheriff's Department (MCSD) and citizens of audible EP Siren actuation in the City of Two Rivers and the town of Two Creeks, WI. System troubleshooting was in progress at the time of actuation.

"This notification is to inform [the NRC] of the planned press release to inform the citizens of the affected communities of the event.

"At 0834 CDT 9/12/2010 Point Beach issued a letter to the Editor of Manitowoc Times Herald Times Reporter Newspaper regarding inadvertent Siren Activation.

"Corrective actions have been taken in the [Point Beach] EP siren maintenance program to avoid a recurrence and the Site Resident NRC Inspector has been notified."

Notified the R3DO (Lipa).

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Power Reactor Event Number: 46241
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DON DEWEY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/10/2010
Notification Time: 00:29 [ET]
Event Date: 09/09/2010
Event Time: 21:29 [EDT]
Last Update Date: 09/10/2010
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):
WILLIAM COOK (R1DO)

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

Event Text

MANUAL REACTOR TRIP DUE TO SERVICE WATER LEAK IN THE MAIN GENERATOR EXCITER HOUSING

"On September 9, 2010, at approximately 2129 hours [EDT], Indian Point 3 manually tripped the reactor from the control room following indications of a service water leak in the Main Generator Exciter housing. Unit 3 is currently stable in mode 3. All automatic actions occurred as required. All control rods fully inserted. No primary or steam generator safety relief valves lifted. The motor driven auxiliary feedwater pumps automatically started on low steam generator level as designed. Decay heat removal is via the steam generators to the main condenser. Offsite power is available and supplying all safeguards busses.

"Unit 2 is unaffected and remains in Mode 5 in a forced outage for 21 RCP [Reactor Coolant Pump] repair.

"During the Fast Bus Transfer [the] 34 Reactor Coolant Pump tripped. The cause is being investigated.

"There was an inadvertent release of CO2 to 31 Main Boiler Feed Pump. The cause was due to the suction relief valve lifting which has subsequently reseated.

"The NRC Sr. Resident Inspector and New York State Public Service Commission have been notified."

The reactor is currently being maintained at normal operating temperature and pressure.

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Power Reactor Event Number: 46242
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: BRAD GAUGER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/10/2010
Notification Time: 13:47 [ET]
Event Date: 09/09/2010
Event Time: 15:20 [CDT]
Last Update Date: 09/10/2010
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 100 Power Operation 100 Power Operation

Event Text

EMERGENCY SIRENS INADVERTENTLY ACTUATE

"Spurious siren activation at Point Beach affects associated sirens (P001 - P010) at Kewaunee Power station. A separate 50.72 notification is to be made for Kewaunee per procedure GWP-11.08.04.

"At 1216 CDT, 09/10/10 station EP personnel notified the control room staff that an inadvertent activation of EP sirens occurred for the Point Beach Station at 1520, 09/09/10. This information was relayed to the EP personnel via Manitowoc County EP personnel, who had received the information from Point Beach personnel previously. Below is the information from the Point Beach notification:

"At 1520 CDT, Point Beach was notified by Manitowoc County Sherriff's Department (MCSD) and citizens of audible EP siren actuation in the city of Two Rivers and the town of Two Creeks, WI. System troubleshooting was in progress at the time of actuation.

"Alert and Notification System siren configuration was restored to normal at approximately 1630 CST, 09/09/10. All required ANS sirens were 'poll tested' and are fully functional.

"Further reviews indicated that sirens P-001 through P-013 (13 sirens) had each simultaneously received a 180 second activation. At this time the cause of the activation signal is unknown. All troubleshooting and testing are currently suspended; event investigation has commenced."

The licensee notified the NRC Resident Inspector.

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Fuel Cycle Facility Event Number: 46243
Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
                   LEU FABRICATION
                   LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: SCOTT MURRAY
HQ OPS Officer: VINCE KLCO
Notification Date: 09/10/2010
Notification Time: 14:00 [ET]
Event Date: 09/09/2010
Event Time: 14:30 [EDT]
Last Update Date: 09/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
Person (Organization):
ROBERT HAAG (R2DO)
SHEENA WHALEY (NMSS)

Event Text

ACCIDENT EVALUATION IMPROPERLY ANALYZED IN THE INTEGRATED SAFETY ANALYSIS

"During a GNF-A [Global Nuclear Fuel-Americas] review of the Fuel Manufacturing Operation (FMO) Integrated Safety Analysis (ISA), it was determined at [1430 EDT] on September 9, 2010 that the accident evaluation associated with hydrogen containment in the Dry Conversion Process was improperly analyzed in the ISA. A loss of hydrogen containment was analyzed in the ISA, however appropriate Items Relied on for Safety (IROFS) to prevent or mitigate a hydrogen explosion, resulting in a loss of UF6 or HF containment, were not identified in the ISA.

"The affected equipment was promptly shut down on September 9, 2010. Existing hydrogen detection systems were augmented to assure controls are available and reliable to perform their intended safety functions as interim compensatory measures. These controls were functionally verified prior to restart of the affected operations at 2230 [EDT] on September 9, 2010. The interim controls will be designated as IROFS upon completion of the ISA documentation update currently underway.

"This event is being reported pursuant to the reporting requirements of 10CFR70 Appendix A(b)(1) within 24 hours of discovery."

The licensee considers this discovery to be of low safety significance because the discovery did not result in an unsafe condition. The required IROFS have been identified and are in place.

The licensee notified the NRC Region 2 Office, the North Carolina Radiation Protection Section and the New Hanover County Emergency Preparedness Organization.

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Fuel Cycle Facility Event Number: 46244
Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
                   LEU FABRICATION
                   LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: SCOTT MURRAY
HQ OPS Officer: VINCE KLCO
Notification Date: 09/10/2010
Notification Time: 17:00 [ET]
Event Date: 09/10/2010
Event Time: 10:00 [EDT]
Last Update Date: 09/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(2) - LOSS OR DEGRADED SAFETY ITEMS
Person (Organization):
ROBERT HAAG (R2DO)
SHEENA WHALEY (NMSS)

Event Text

DEGRADATION OF SAFETY EQUIPMENT

"At approximately 1000 [EDT] on September 10, 2010 during normal operation of a Gad slugger feed hood in the Fuel Manufacturing Building, a connection between the powder hopper and the vibrating feeder was observed as being not properly secured. After starting the vibrating feeder a small amount of powder leaked from the vibrating feeder into the hood. The base of the hood is equipped with a photo-sensor that detected the powder accumulation and automatically shut down the vibrating feeder to stop the leak. A total of 2.2 kg of powder was removed from the hood. An investigation determined that a clamp on the feed tube had not been properly reinstalled following an equipment cleanout.

"The two controlled parameters for criticality safety of this equipment are moderation and geometry and Items Relied on for Safety (IROFS) are established for both. With the clamp improperly installed, the geometry-related IROFS was in a degraded state. Additional IROFS on moderation remained available to perform their intended safety functions and were not challenged. Geometry control was maintained by the photo-sensor interlock; however this IROFS is not credited for this accident sequence in the ISA.

"Although, this event did not result in an unsafe condition and double contingency was maintained, the performance requirements could not be met when taking no credit for the degraded IROFS. As a result, this report is conservatively being made per 10CFR70 Appendix A (b)(2).

"The Gad slugger and similar equipment have been shutdown pending implementation of additional corrective actions."

The licensee will notify the NRC Region 2 Office, the North Carolina Radiation Protection Section and the New Hanover County Emergency Preparedness Organization.

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Power Reactor Event Number: 46246
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: MIKE COEN
HQ OPS Officer: VINCE KLCO
Notification Date: 09/10/2010
Notification Time: 19:46 [ET]
Event Date: 09/09/2010
Event Time: 15:34 [EDT]
Last Update Date: 09/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ROBERT HAAG (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
4 M/R N 0 Hot Standby 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DURING STARTUP DUE TO A CONTROL BANK STEP COUNTER FAILURE

"During a Unit 4 reactor startup on 9/9/2010 while the reactor was subcritical in Mode 3, the Control Bank C Group 1 Step Counter failed [due to a battery failure]. The reactor trip breakers were opened in accordance with procedures as required by the Action of Technical Specification 3.1.3.3. All rods fully inserted. The unit remained in Mode 3. This was a manual actuation of the reactor protection system.

"This report is made in accordance with 10 CFR 50.72(b)(3)(iv)(A) - Valid actuation of the Reactor Protection System. This is a late report. Reportability was not recognized at the time of the event as a result of misleading guidance in 0-ADM-115 'Notification of Plant Events' [site specific] procedure. A condition report is being initiated [by the licensee] to evaluate procedure changes to avoid further occurrences."

The licensee notified the NRC Resident Inspector.

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