United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2009 > April 6

Event Notification Report for April 6, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/03/2009 - 04/06/2009

** EVENT NUMBERS **


44946 44949 44965 44966 44967 44968 44970

To top of page
General Information or Other Event Number: 44946
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: FLETCHER HOSPITAL
Region: 1
City: FLETCHER State: NC
County:
License #: 045-0370-1
Agreement: Y
Docket:
NRC Notified By: CLIFF HARRIS
HQ OPS Officer: JOE O'HARA
Notification Date: 03/31/2009
Notification Time: 14:41 [ET]
Event Date: 03/31/2009
Event Time: 08:30 [EDT]
Last Update Date: 03/31/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MEL GRAY (R1)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - CONTAMINATION FOUND ON NUCLEAR MEDICINE PACKAGING

The following was received from the state via e-mail:

"N.C. Radiation Protection Section was notified on March 31, 2009 by the hospital about a nuclear medicine package received from a nuclear pharmacy in excess of the loose contamination limits.

"The swipes performed on the package read 2890 dpm vs the limit of 2200 dpm. The package was placed in hot storage and will be stored for decay.

"Licensee notified the carrier and the pharmacy."

NC Event Report ID Number is NC-09-20.

To top of page
General Information or Other Event Number: 44949
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: MAYO CLINIC
Region: 1
City: JACKSONVILLE State: FL
County:
License #: 1812-3
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/01/2009
Notification Time: 08:48 [ET]
Event Date: 03/31/2009
Event Time: [EDT]
Last Update Date: 04/01/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MEL GRAY (R1)
ANGELA McINTOSH (FSME)
ILTAB (email) ()

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

Event Text

AGREEMENT STATE REPORT - LOST I-125 SEED

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

"Cardinal Health working under Mayo Clinic license lost one I-125 seed. Sterilization room and adjoining spaces and personnel were surveyed. It is speculated that the source entered the internal plumbing of the sterilizer. The pipes are of sufficient thickness to prevent external detection. It is surmised by Mayo RSO that Cardinal Health personnel did not follow procedure. RSO estimates that remaining activity as of 31 Mar 2009 is 150 micro Ci's [original activity 300 micro Ci's], with no increased exposure to Cardinal Health staff. Mayo Clinic will work with Cardinal Health staff to modify procedure to ensure source cannot escape vial or tray during sterilization. In addition, retraining will be conducted with all Cardinal health staff involved. Any further investigation is referred to Materials and Licensing. This office will take no further action on this incident."

The Florida Incident Number for this event is FL09-030.

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

To top of page
Power Reactor Event Number: 44965
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ELLIS VANN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/03/2009
Notification Time: 03:27 [ET]
Event Date: 04/03/2009
Event Time: 00:28 [CDT]
Last Update Date: 04/03/2009
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):
STEVE ORTH (R3)

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

Event Text

MANUAL REACTOR SCRAM DUE TO INCREASING REACTOR WATER LEVEL DURING CALIBRATION

"This report is being made under [10 CFR] 50.72(b)(2)(iv)(B) for inserting a manual reactor scram due to indicated reactor water level of 205 inches and rising. The exact cause of the reactor water level increase is not known at this time. However, STP [Surveillance Test Procedure] 3.3.3.2-09, 'Reactor Water Level and Pressure Instruments Calibration' was in progress at the time and is likely the cause of the level transient.

"In addition, this report is being made under [10 CFR] 50.72(b)(3)(iv)(A) due to PCIS [Primary Containment Isolation System] groups 2, 3 and 4 being received when reactor water level dropped below 170 inches following the reactor scram. All isolations went to completion. This level response is considered normal following a reactor scram from power and reactor water level is currently being controlled in the normal band. All PCIS group isolations were reset."

All rods fully inserted during the scram. The plant is in a normal shutdown electrical lineup with offsite sources powering the safety busses. No safety or relief valves lifted during the transient. Decay heat is being removed via the steam bypass to condenser valves.

The licensee has notified the NRC Resident Inspector.

To top of page
Other Nuclear Material Event Number: 44966
Rep Org: GAF MATERIALS CORPORATION
Licensee: GAF MATERIALS CORPORATION
Region: 1
City: WAYNE State: NJ
County:
License #: GL 705645-13
Agreement: N
Docket:
NRC Notified By: SEAN CONNOLLY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/03/2009
Notification Time: 09:55 [ET]
Event Date: 04/03/2009
Event Time: [EDT]
Last Update Date: 04/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
MEL GRAY (R1)
ANGELA MCINTOSH (FSME)
ILTAB via e-mail ()

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

Event Text

LOST NI-63 SOURCE

The licensee was performing their annual registration inventory when they discovered that a gas chromatograph detector was missing. A search of the premises was conducted and they were unable to locate the device thus it is considered lost.

The detector contained a Ni-63 source with an original source strength of 15 mCi (on 11/15/87). Its original use was in a Hewlett-Packard model 19233B Gas Chromatograph, serial number L-3031.

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

To top of page
Power Reactor Event Number: 44967
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: HARRY ANDERSON
HQ OPS Officer: JOE O'HARA
Notification Date: 04/03/2009
Notification Time: 13:40 [ET]
Event Date: 04/03/2009
Event Time: 11:36 [EDT]
Last Update Date: 04/03/2009
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):
MEL GRAY (R1)

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

Event Text

MANUAL REACTOR TRIP DUE TO LOSS OF 21 MBFP

"At 1136 hours on April 3, 2009 with the plant in mode 1, Indian Point Energy Center Unit 2 experienced a 21 Main Boiler Feed Pump (MBFP) trip. Following the MBFP trip the turbine runback circuit did not actuate as expected. The plant operators attempted to perform a manual main turbine runback and inserted a manual reactor trip based on the impending trip signal of Steam Generator low level. Auxiliary feedwater automatically started as expected. Troubleshooting of the cause of the transient is in progress. Unit 2 is stable in mode 3 with AFW in service. Heat removal is to the main condenser via the steam dumps. Offsite power is available and supplying all safeguards busses. Unit 3 is not affected and remains in mode 6 for 3R15.

"The [NRC] Resident Inspector has been notified."

To top of page
Power Reactor Event Number: 44968
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: DAVID DUNCAN
HQ OPS Officer: JOE O'HARA
Notification Date: 04/03/2009
Notification Time: 17:07 [ET]
Event Date: 04/03/2009
Event Time: 16:30 [EDT]
Last Update Date: 04/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
STEVE ORTH (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

PLANNED MAINTENANCE ON SPDS AND ERDS

"At 1630 hours on 04/03/2009, the SPDS and ERDS system was removed from service to support activities for a planned maintenance outage on the UPS vital bus power supply. The duration of work is expected to be approximately 24 hours. During this time, Control Room indications and alternate methods will be available. Since the SPDS computer system will be unavailable for greater than 8 hours, this is considered a Loss of Emergency Assessment Capability and reportable under 10CFR50.72(b)(3)(xiii)."

The licensee will notify the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 44970
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [ ] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: BRIAN FERGUSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/04/2009
Notification Time: 08:54 [ET]
Event Date: 04/03/2009
Event Time: 23:54 [MST]
Last Update Date: 04/04/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
RICK DEESE (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 M/R Y 29 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR SCRAM DUE TO HIGH VIBRATIONS IN THE TURBINE

"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.

"On April 3, 2009, at approximately 2345 Mountain Standard Time (MST), Palo Verde Unit 3 operators manually tripped the reactor from approximately 29% rated thermal power in response to increasing vibration on the main turbine. The unit was being shutdown from 100% power for a refueling outage at the time of the trip.

"Following the manual reactor trip, all CEAs fully inserted into the reactor core. This was an uncomplicated reactor trip. No emergency classification was required per the Emergency Plan. No automatic ESF actuations occurred and none were required. Safety related buses remained energized during and following the reactor trip. The Emergency Diesel Generators did not start and were not required. The offsite power grid is stable. No LCOs have been entered as a result of this event. No major equipment was inoperable prior to the event that contributed to the event."

No relief or safety valves lifted during the event. Decay heat is being removed via the steam dump to condenser valves. The licensee will continue to cool the plant down to support their planned refueling outage. There was no effect on Unit 1 or Unit 2.

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012