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Event Notification Report for August 6, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/05/2009 - 08/06/2009

** EVENT NUMBERS **


45239 45240 45245 45247

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General Information or Other Event Number: 45239
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: LONGVIEW FIBRE
Region: 4
City: LONGVIEW State: WA
County:
License #: WN-I090-1
Agreement: Y
Docket:
NRC Notified By: ANINE GRUMBLES
HQ OPS Officer: VINCE KLCO
Notification Date: 08/03/2009
Notification Time: 13:15 [ET]
Event Date: 07/30/2009
Event Time: [PDT]
Last Update Date: 08/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE - DAMAGED GAUGE

"On 11 Dec 2008 a generally-licensed fixed gauge (serial M3465, containing 80 millicuries Cs-137 as of 2nd quarter 1989; decayed to 50.4 millicuries in July 2009) was removed by the manufacturer from its installed location and placed in storage pending disposal. On 30 July 2009, a WA [Washington] Department of Health (DOH) materials inspector visited the fixed gauge licensee (also specific license WN-I090-1) to conduct a reciprocity inspection of the manufacturer's on-site activities. The manufacturer's representative was there to remove and package a total of 14 decommissioned gauges for disposal.

"Several of the gauges showed varying degrees of corrosion. The fixed gauge, serial M3465, showed significant corrosion and was missing a cover plate. The manufacturer's representative reported no unusual radiation measurements prior to packaging activities on 30 July 2009. During packaging, the fixed gauge was rolled over at which time the DOH materials inspector measured the dose rate at the opening as 500 milliRoentgen per hour. Immediate action was taken to control exposure.

"The manufacturer's representative adequately secured and shielded the gauge prior to shipping. Apparently the shutter and lead shielding that blocks the radiation beam was either broken or misaligned and failed to function as designed. There was no significant exposure to personnel. The WA DOH investigation continues."

The State of Washington incident number is: WA-09-055.

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General Information or Other Event Number: 45240
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: MEDIPHYSICS, INC DBA G.E. HEALTH CARE
Region: 3
City: Chicago State: IL
County:
License #: IL-01109-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: DONALD NORWOOD
Notification Date: 08/03/2009
Notification Time: 17:15 [ET]
Event Date: 07/27/2009
Event Time: [CDT]
Last Update Date: 08/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN GIESSNER (R3DO)
CHRISTEPHER MCKENNEY (FSME)

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

Event Text

AGREEMENT STATE REPORT - LOST (THEN RECOVERED) I-123 CAPSULES

"On July 29, 2009, The [Illinois Emergency Management] Agency received preliminary notification from the licensee's radiation safety officer that a package of radioactive material destined for a radiopharmacy in Arizona had not arrived as scheduled, but was subsequently located and forwarded after a day's delay. Subsequent conversations indicated that for a period of approximately 12 hours the package was secured in the possession of a member of the public until it was retrieved by the courier and forwarded to the licensed recipient. The package contained a total of 3 vials with 30 capsules of I-123 which are intended for medical diagnostic studies. Those capsules were 100 to 200 microCi of I-123 each for a total activity in the package of 20.5 milliCi at the time the package was prepared for shipment on July 26, 2009. The measured dose rate 3 feet from the package at the time of shipment was less than 0.1 milliR/h. Due to limited time spent handling and being near the package for the period in question, the dose to the member of the public was well below regulatory limits. When finally received by the pharmacy, the package was found to be intact, with no signs of damage, leakage or the contents having been previously opened or removed. The licensee is investigating corrective actions to take with regards to actions by the courier top prevent a recurrence. A formal report from the licensee concerning this matter is pending. Until that time, this item remains open and under investigation by the [Illinois Emergency Management] Agency."

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.

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: 45245
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: JOHN SLACK
HQ OPS Officer: DONALD NORWOOD
Notification Date: 08/05/2009
Notification Time: 12:00 [ET]
Event Date: 08/05/2009
Event Time: 07:50 [PDT]
Last Update Date: 08/05/2009
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
WAYNE WALKER (R4DO)
MARY JANE ROSS-LEE (NRR)
ELMO COLLINS (R4RA)
ERIC LEEDS ()
ANTHONY McMURTRAY (IRD)
MARYANN DOYLE (DHS)
DENNIS VIA (FEMA)

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

Event Text

UNUSUAL EVENT DECLARED DUE TO TOXIC GAS FROM A SWITCHGEAR FIRE IN THE TURBINE BUILDING

At 0750 PDT the licensee experienced a turbine trip and reactor scram. At approximately the same time, a fire was detected in the non-safety related 6.9 kV feed bus to switchgear SH-5 and SH-6 in the turbine building. The fire and associated fault to the switchgear feed bus caused a loss of power to both reactor recirculation pumps and the automatic reactor scram. The fire produced smoke and potentially toxic gases. Due to the presence of potentially toxic gas in the power plant, an Unusual Event was declared at 0812 PDT based on EAL 9.3.U.3. At the present time, the fire is out and the smoke is being cleared from the plant.

All rods fully inserted upon the reactor scram. Systems functioned as expected except for problems with the EHC system which resulted in the bypass valves remaining open which caused the reactor to depressurize to approximately 390 psi. MSIVs were manually shut to halt the reactor depressurization and cooldown. Decay heat is being removed via relief valves to the suppression pool with reactor pressure being maintained between 500 and 600 psi. Suppression pool cooling is via RHR. Makeup water to the reactor is via normal feed. Licensee is on natural circulation at the time of this report. Normal shutdown electrical alignment is established with the exception of Division II emergency switchgear which is aligned to the backup transformer.

A request for assistance was made to the Hanford fire department, however, the fire was out prior to their arrival on site.

The licensee has notified State, local agencies and the NRC Resident Inspector.


* * * UPDATE FROM JOHN SLACK TO DONALD NORWOOD AT 1332 ON 08/05/09 * * *

The Unusual Event has been terminated as of 1006 PDT. The licensee is taking the unit to cold shutdown.

The licensee will notify the NRC Resident Inspector.

Notified NRR EO (Ross-Lee), R4DO (Walker), DHS (Enzer), and FEMA (Eaches).

* * * UPDATE FROM NICK RULLMAN TO PETE SNYDER AT 1827 ON 08/05/09 * * *

"Following the reactor scram, with the turbine bypass valves failed fully open, the inboard main steam isolation valves had to be manually closed to prevent excessive cool down. The outboard main steam isolation valves automatically closed from the inability to maintain condenser vacuum. The inability to maintain condenser vacuum was due to limited equipment access in the Turbine Building from heavy smoke. This is reportable under Part 50.72(b)(3)(iv)(A) as a valid actuation of one of the systems listed in Part 50.72(b)(3)(iv)(B)(2)."

The licensee notified the NRC Resident Inspector.

Notified R4DO (Walker).

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Power Reactor Event Number: 45247
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: WILLIAM STANG
HQ OPS Officer: DONALD NORWOOD
Notification Date: 08/05/2009
Notification Time: 15:34 [ET]
Event Date: 08/06/2009
Event Time: 06:00 [CDT]
Last Update Date: 08/05/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN GIESSNER (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

PLANNED MAINTENANCE TO AFFECT TECHNICAL SUPPORT CENTER

"On 8/6/09 at 0600 hours CDT the Monticello Nuclear Generating Plant's Technical Support Center uninterruptable power supply will be isolated to perform a planned maintenance activity. The maintenance activity requires implementation of compensatory measures to maintain TSC functions during the activity. The compensatory measures include having the Emergency Director report to the Control Room and co-locating the remaining TSC staff at the EOF should an event be declared requiring ERO activation. The ERO has previously successfully demonstrated the ability to implement these compensatory measures. The maintenance activity is scheduled to be completed with the TSC returned to full functionality by the end of the dayshift on 8/6/09. The Site Emergency Response Organization has been notified of the maintenance activity and instructed on the planned compensatory measures to be implemented during the activity. MNGP will notify the NRC upon completion of the activity restoring full TSC operability. This event is considered reportable per 10CFR50.72(b)(3)(iii). The licensee has notified the NRC Resident Inspector."

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