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Event Notification Report for April 01, 2008

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
03/31/2008 - 04/01/2008

EVENT NUMBERS
44112441144411544378

Power Reactor
Event Number: 44112
Facility: SALEM
Region: 1     State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM BYYKKONEN
HQ OPS Officer: JASON KOZAL
Notification Date: 04/01/2008
Notification Time: 10:28 [ET]
Event Date: 04/01/2008
Event Time: 05:30 [EDT]
Last Update Date: 04/01/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
Person (Organization):
JOHN CARUSO (R1)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling
Event Text
POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED OFFSITE

"A potentially contaminated individual was transported to the Salem County Memorial Hospital by the on-site Fire Protection personnel due to a non-industrial medical emergency. The individual had been working in unit two containment as a Foreign Material Exclusion Area watch. The individual was surveyed en-route to the hospital and was determined to be not contaminated. The individual remains at the hospital and is undergoing testing and evaluation. Salem unit two remains defueled with spent fuel cooling in-service."

Licensee notified the NRC Resident Inspector.


Power Reactor
Event Number: 44114
Facility: NINE MILE POINT
Region: 1     State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MARK GREER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/01/2008
Notification Time: 11:16 [ET]
Event Date: 04/01/2008
Event Time: 07:10 [EDT]
Last Update Date: 04/01/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
Person (Organization):
JOHN CARUSO (R1)
GREG MORELL (FSME)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling
Event Text
CONTAMINATED INJURED WORKER TRANSPORTED OFFSITE

"Medical event requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment. Initial onsite survey for radioactive contamination was unable to be performed before transport of the person offsite for medical treatment. Ambulance left site at 08:02 EDT. Surveys completed at hospital found low levels of radioactive contamination on individual's clothing and skin. This is determined to be a level 1 contamination event (0 - 5000 counts per minute above background). Maximum reading of 600 counts per minute above background located on right hand. Remaining locations 20 to 100 counts per minute above background. Individual has been decontaminated with no remaining contamination above background. Radiation protection personnel have taken control of radioactive material and returned it to Nine Mile Point in accordance with D.O.T. guidelines."

Licensee Radiation Protection personnel surveyed the ambulance and the emergency room for contamination per plant procedures. No spread of contamination was found.

The licensee has notified the NRC Resident Inspector.


Power Reactor
Event Number: 44115
Facility: TURKEY POINT
Region: 2     State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: MARK JONES
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/01/2008
Notification Time: 14:51 [ET]
Event Date: 04/01/2008
Event Time: 11:26 [EDT]
Last Update Date: 04/01/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
CAROLYN EVANS (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation
Event Text
OFFSITE NOTIFICATION TO STATE OF FLORIDA DUE TO CHROMATE SPILL

"During a scheduled run of the 3A Emergency Diesel Generator for surveillance, an active engine coolant leak was discovered on the diesel engine radiator while pressurized. 3A Emergency Diesel Generator was shutdown to depressurize the radiator leakage path. The leak caused a spill of 55 gallons of chromated engine cooling water into the Emergency Diesel Generator building. The leakage rate has decreased to approximately 1 drop per minute after depressurization and is contained within a berm.

"There was no release to the environment and therefore there was no ground water intrusion.

"Notification to State of Florida Department of Environmental Resources Management was completed at 1350 on 4/1/2008.

"3A Emergency Diesel Generator remains inoperable at this time pending repairs to the radiator. Unit 3 is currently in a 72-hour Technical Specification Action Statement. This Technical Specification Action Statement is extendable to 14 days with proceduralized compensatory actions.

"Unit 4 is currently in Mode 5 for refueling. 4A and 4B Emergency Diesel Generators remain operable, and Unit 4 shutdown risk remains GREEN (acceptable levels of performance of key safe shutdown functions).

"This notification is being conducted in accordance with 10CFR50.72(b)(2)(xi)."

The licensee informed the State of Florida and the NRC Resident Inspector.


General Information or Other
Event Number: 44378
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: KAISER FOUNDATION HOSPITAL - SAN JOSE
Region: 4
City: SAN JOSE   State: CA
County:
License #: 2625-43
Agreement: Y
Docket:
NRC Notified By: MARK GOTTLIEB
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/31/2008
Notification Time: 18:11 [ET]
Event Date: 04/01/2008
Event Time: 00:00 [PDT]
Last Update Date: 07/31/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
NEIL O'KEEFE (R4)
KEVIN HSUEH (FSME)
ILTAB VIA E-MAIL
MEXICO VIA FAX
Event Text
AGREEMENT STATE REPORT - LOSS OF LESS THAN CAT 3 LEVEL Gd-153 SOURCES

"The licensee disposed of an ADAC camera in April 2008 and inadvertently failed to remove the 2 Gd-153 sources, isotope products serial numbers E2-886 and E2-890, which contained 250 mCi (9.25 GBq) each as of May 2007. The Gd sources were contained within lead shielding in the device. The sources in their shielding do not present a hazard. Currently, each of the unshielded sources would present a hazard with an exposure rate of about 124 mr/hr at one foot. Currently, the sources have decayed to around 67 mCi (134 mCi total). As of 7/31/2008, the licensee has not been successful in locating the sources.

"According to the licensee, Norcal, a company that performs installation and removal of medical devices, removed the ADAC Vantage camera, and disposed of it sometime in April 2008 to a Waste Transfer Station, Waste Management, in San Leandro.

"Waste Management was contacted and provided the names of the 2 metal recycling companies they would have used to recycle the metal. DC Metals and ALCO metals were both contacted and stated that they do not have any such device at their facility. They indicated if they had received it, the gamma camera would have been recycled to scrap metal very quickly.

"The RSO stated that she just learned of this incident after their consultant had asked them last week for information regarding the disposition of the two 250 mCi Gd- 153 sources. After checking, they learned the sources had not been removed and were missing. The licensee is investigating to try and determine the location of the missing two Gd-153 sources."

Per report, the discovery date of this event was 7/24/2008.

California Report #073008.

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