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Event Notification Report for July 22, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/21/2010 - 07/22/2010

** EVENT NUMBERS **


46100 46101 46102 46113 46114 46115

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General Information or Other Event Number: 46100
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: TECUMSEH POULTRY LLC
Region: 4
City: TECUMSEH State: NE
County:
License #: GL0103
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: JOHN KNOKE
Notification Date: 07/16/2010
Notification Time: 14:16 [ET]
Event Date: 07/16/2010
Event Time: [CDT]
Last Update Date: 07/16/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHUCK CAIN (R4DO)
GLENDA VILLAMAR (FSME)
DARYL JOHNSON email (ILTA)

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

Event Text

AGREEMENT STATE REORT - THIRTEEN TRITIUM EXIT SIGNS LOST

The following was received via fax from the NE Division of Radioactive Materials:

"Six Isolite model 2040-01-12 Tritium exit signs were shipped to Campbell Soup Company at 333 South 3rd Street in Tecumseh, NE in 1993 with 10 Curies of tritium per sign. Six Evenlite model 201 Tritium exit signs were shipped in 1995 with 12.5 Curies of Tritium per sign. One additional sign from Brandhurst, Inc was shipped in 1986. Isolite, Evenlite and Brandhurst did not provide Nebraska with the serial numbers. MBA Poultry bought the facility from Campbell Soup Company in 1998. MBA Poultry sold it to Tecumseh Poultry in 2000. Tecumseh Poultry does not know where the 13 tritium exit signs went."

Manufacturer Activity Model Manufacturer Activity Model
1) Isolite 10.0 Ci 2040 7) Evenlite 12.5 Ci 201
2) Isolite 10.0 Ci 2040 8) Evenlite 13.5 Ci 201
3) Isolite 10.0 Ci 2040 9) Evenlite 12.5 Ci 201
4) Isolite 10.0 Ci 2040 10) Evenlite 12.5 Ci 201
5) Isolite 10.0 Ci 2040 11) Evenlite 12.5 Ci 201
6) Isolite 10.0 Ci 2040 12) Evenlite 12.5 Ci 201
13) Brandhurst unknown 201
Nebraska Report No: NE100001


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

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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General Information or Other Event Number: 46101
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: UNIVERSITY OF PENNSYLVANIA
Region: 1
City: PHILADELPHIA State: PA
County:
License #: PA-0131
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: JOHN KNOKE
Notification Date: 07/16/2010
Notification Time: 15:44 [ET]
Event Date: 07/07/2010
Event Time: [EDT]
Last Update Date: 07/16/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JUDY JOUSTRA (R1DO)
GLENDA VILLAMAR (FSME)

Event Text

AGREEMENT STATE REPORT - DELIVERED DOSE DIFFERED FROM THE PRESCRIBED DOSE BY GREATER THAN 50%

The following was received via fax from the Pennsylvania Department of Environmental Protection:

"On July 7, 2010 a patient was beginning the first of three vaginal treatment fractions with an Ir-192 HDR. It was discovered on July 14, 2010 that the end of the treatment tube was placed 3.5 cm short of its intended location. When the patient returned for the second treatment, she was imaged again, and staff noticed the treatment tube was in a different location from the previous treatment. Licensee estimates that, for the first fraction, the intended treatment volume received only about 10% of the intended dose for that fraction. Per 10CFR35.3045(a)(1)(iii), it is required for the licensee to report any event in which the fractionated dose delivered differs from the prescribed dose, for a single fraction, by 50% or more.

"It is believed the medical staff mis-identified the treatment location and the end of the treatment tube was placed 3.5cm short of its intended location. The licensee is considering making up this dose by adding a fourth treatment fraction. There is no anticipated adverse effect to the patient.

"There is a PaDEP/BRP reactive inspection scheduled to investigate this ME at U Penn. The patient and the referring physician were notified. A follow-up written report from the licensee is expected."

PA Report # PA100015

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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General Information or Other Event Number: 46102
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: AMC HOFFMAN CENTER 22
Region: 1
City: ALEXANDRIA State: VA
County: FAIRFAX
License #: GL-1722
Agreement: Y
Docket:
NRC Notified By: MICHAEL WELLING
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/16/2010
Notification Time: 15:53 [ET]
Event Date: 07/02/2010
Event Time: [EDT]
Last Update Date: 07/16/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JUDY JOUSTRA (R1DO)
KEVIN HSUEH (FSME)
ILTAB (E-MAIL) (ILTA)

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

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGN

"On July 2, 2010 it was discovered during the morning walk-through that one exit sign containing 7.5 curies of H-3 [tritium] was stolen. The licensee searched the trash cans and talked with janitorial staff. The sign was not found. A police report was filed with the Alexandria Police Department."

Virginia Event Number: VA-10-06

The sign was manufactured by Isolite, model 2040-50B. The sign contained 7.5 Ci at the time of manufacture however, the date of manufacture and thus the current sign activity is not known.

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

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: 46113
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: BEN COOK
HQ OPS Officer: HOWIE CROUCH
Notification Date: 07/21/2010
Notification Time: 11:39 [ET]
Event Date: 07/21/2010
Event Time: 08:16 [CDT]
Last Update Date: 07/21/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ANN MARIE STONE (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

INADVERTENT MANUAL INITIATION OF EMERGENCY ALERT SIRENS

"At 0816 [CDT] on 7/21/2010, the Monticello Nuclear Power Generating Plant (MNGP) received a report from the Sherburne County Sheriff Dispatcher that there had been an inadvertent manual initiation of Emergency Preparedness sirens in the county while performing siren testing. All plant conditions/parameters are normal. A total of 48 emergency sirens were on for approximately 1 minute before being secured. The inadvertent initiation of the sirens was determined to be reportable under 10 CFR 50.72(b)(2)(xi), 'News Release or Notification of Other Government Agency.'

"Sherburne County, the State of Minnesota, and the site NRC Resident Inspector have been notified."

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Power Reactor Event Number: 46114
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD ELLIOT
HQ OPS Officer: PETE SNYDER
Notification Date: 07/21/2010
Notification Time: 19:48 [ET]
Event Date: 07/21/2010
Event Time: 17:30 [EDT]
Last Update Date: 07/21/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JONATHAN BARTLEY (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

NOTIFICATION OF NORTH CAROLINA WILDLIFE RESOURCES DUE TO STRIPED BASS MORTALITY

"Duke Energy Scientific Services group notified the NC [North Carolina] Wildlife Resources Commission that we (McGuire Nuclear Station) were experiencing some Striper mortalities in and around the Cowan's Ford Dam.

"Since Monday (7/19/2010) of this week we have collected approximately 100 dead stripers. Some appear to have died from fishing related activities (catch and release) but some were also noted to be stressed from oxygen deprivation.

"[The Duke Energy Scientific Services group representative] also notified the NC Wildlife Resources Commission the McGuire Nuclear Station was operating their Low Level Intake [LLI] Pumps to support maintenance of their NPDES Permit 99 degree Fahrenheit average monthly temperature limit.

"July has been unusually hot and plant management has felt the need to run the LLI approximately 6 days to achieve compliance with our temperature limit. During the operation of the LLI pumps, Duke Energy's Scientific Services group is monitoring water quality and fish in the lake via the following activities:

"1) Daily hydroacoustic surveys of the Cowans Ford Dam forebay both immediate to the dam and also an approximately 2 mile run up the Catawba River channel.

"2) Around-the-clock monitoring of fish behavior in the immediate vicinity of the LLI. A DIDSON camera sits atop the LLI (25 meter deep) and is automated to record hourly video of areas both above the LLI and in front of the LLI using motorized rotators. These videos are monitored by [personnel] throughout the day and night.

"3) Every other day water quality monitoring including dissolved oxygen and temperature profiles at every meter to the bottom of the lake. These profiles occur in the forebay and at multiple locations up the channel.

"4) Daily surveys for dead striped bass by boat up the major tributaries of the lake. We will record lengths and condition of both dead and dying stripers before disposing of them.

"5) Hourly MNS discharge temperature monitoring.

"These activates will continue to be exercised until the pumps are turned off."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46115
Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: FRANK G. GORLEY
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/22/2010
Notification Time: 08:32 [ET]
Event Date: 05/29/2010
Event Time: 08:49 [EDT]
Last Update Date: 07/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JONATHAN BARTLEY (R2DO)

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

INVALID ACTUATION OF PRIMARY CONTAINMENT ISOLATION VALVES DUE TO A FAULTY TRANSISTOR

"This report is being made under 10CFR50.73(a)(2)(iv)(A). On May 29,2010, at 0849 EDST Unit 2 received a trip of the 'B' RPS alternate supply. This trip was due to a faulty transistor on the internal circuit board for the voltage regulator. The transistor was replaced, the voltage regulator tested and replaced in the system. The trip of the "B" RPS alternate supply resulted in isolation of Primary Containment Isolation Valves in more than one system. The systems that were isolated due to this event were Reactor Water Clean-up and Fission Products Monitoring. Except for critical scrams, invalid actuations are not reportable by telephone under 50.72. NUREG 1022 defines by examples given that actuation of the reactor protection system constitutes actuation of RPS full scram signal when the reactor is critical. In the condition that occurred during day shift on Saturday, May 29, 2010 only one channel of RPS actuated on failure of the Unit 2 'B' RPS alternate supply. That being the case there was not sufficient logic made up to result in a reactor scram or RPS actuation. An RPS actuation would be considered a reportable event; however, the trip of only the 'B' alternate RPS supply would not be considered an RPS actuation. This condition did involve the initiation of some containment isolation signals resulting in containment isolation valves in more than one system since RWCU and fission product monitor isolation valves closing as a result of the loss of the 'B' RPS system. Valid signals are those signals that are initiated in response to actual plant conditions or parameters satisfying the requirements for initiation of the safety function of the system. In this case the isolation signal was caused by the loss of power to the affected instrumentation rather than response to required conditions or parameters which makes this an 'invalid' isolation signal. For this event, Plant Hatch has chosen to make this telephone notification to the NRC Operations Center within 60 days after discovery of the event instead of submitting a written LER.

"All actuations above were complete.

"No system actuations resulted from the trip of the 'B' RPS alternate supply."

The licensee has notified the NRC Resident Inspector.

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