United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2005 > March 30

Event Notification Report for March 30, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/29/2005 - 03/30/2005

** EVENT NUMBERS **


41521 41529 41534 41540 41541 41543 41546 41547

To top of page
General Information or Other Event Number: 41521
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: G.E. HEALTHCARE
Region: 3
City: ARLINGTON HEIGHTS State: IL
County:
License #: IL-01109-01
Agreement: Y
Docket:
NRC Notified By: DARREN PERRERO
HQ OPS Officer: JOHN KNOKE
Notification Date: 03/24/2005
Notification Time: 11:48 [ET]
Event Date: 03/24/2005
Event Time: [CST]
Last Update Date: 03/25/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
LAURA KOZAK (R3)
TOM ESSIG (NMSS)
BENJAMIN SANDLER (TAS)

Event Text

MISSING SHIPMENT OF 105 BRACHYTHERAPY (I-125) SEEDS TOTALING 66 MILLICURIES

GE Healthcare, also known as Medi Physics, reported that a package of radioactive material had not been received as expected by Northwest Arkansas Medical Center in Springdale, Arkansas. The package, which contains 105 brachytherapy seeds, was to be delivered on Monday March 21, 2005. The seeds contain approximately 0.63 milliCi of activity each, with a total package activity of 66 milliCi. The maximum radiation level on the surface of the package is less than 0.5 milliR/hr.

The material was sent via FedEx on Friday March 18 and received at the FedEx facility in Tulsa, Oklahoma on March 19. No further information has been logged since. Medi Physics' customer service group has begun their investigation.

The Arkansas Division of Radiation Control has been advised of the situation.

IL report number: IL050022


*** UPDATE FROM STATE OF IL (G. VINSON) TO (J. KNOKE) AT 15:14 EST ON 3/25/05 ***

The State of IL, Division of Nuclear Safety, called to indicate the missing package containing 105 brachytherapy seeds was located in the Fed Express facility in Arkansas. The package, which was estimated to be found about 11:30 EST on 3/25/05, was intact and in its original condition. The licensee believes the missing package was in the possession of Fed Ex at all times, with no third party intervention. The brachytherapy seeds are being returned to G.E. Healthcare to determine that all seeds are accounted for and to further investigate how the package was lost within the Fed Ex system.

Notifications were given to R3 (Kozak), NMSS (Moore), and TAS (Sandler).

To top of page
General Information or Other Event Number: 41529
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: PERKIN ELMER LIFE SCIENCES
Region: 1
City: BOSTON State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BOB WALKER
HQ OPS Officer: BILL GOTT
Notification Date: 03/27/2005
Notification Time: 08:16 [ET]
Event Date: 03/26/2005
Event Time: 04:14 [EST]
Last Update Date: 03/27/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN ROGGE (R1)
DANIEL GILLEN (NMSS)
SUE GAGNER (PAO)
JACK CRLENJAK (IRD)

Event Text

AGREEMENT STATE REPORT - FIRE INVOLVING RADIOACTIVE MATERIAL

At 0414 on 03/26/05, a fire broke out in a laboratory of the Perkin Elmer Life Sciences in Boston, MA, that contained 8 Curies Carbon 14. The C-14 was stored in multiple locations. Local fire fighters and hazmat team responded. The fire was extinguished at approximately 0800. There was evidence of contamination inside the building and on the firefighters protective clothing. The levels were 3 - 4 times background. Two firefighters were treated at the hospital for smoke inhalation. The licensee has taken bioassay samples from the two individuals. Wipes outside the facility had no contamination. The cause of the fire is unknown.

To top of page
Power Reactor Event Number: 41534
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CRAIG INGOLD
HQ OPS Officer: JOHN KNOKE
Notification Date: 03/28/2005
Notification Time: 15:27 [ET]
Event Date: 03/28/2005
Event Time: 13:59 [CST]
Last Update Date: 03/29/2005
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
KENNETH RIEMER (R3)
HERB BERKOW (NRR)
JACK CRLENJAK (IRD)
FEMA ()
DHS ()

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

Event Text

UNUSUAL EVENT DECLARED DUE TO HYDROGEN LEAK

The licensee faxed the following information:

"Following the Unit 2 trip, (due to a malfunction of the generator protection circuitry), a hydrogen leak was identified on the Unit 2 main generator. The leakage was sufficient enough to cause a flammable gas release affecting normal plant operation. The Unusual Event was declared under HU6 - Hazards and Other Conditions. The State and local authorities were notified at 14:09 CST. There is NO fire, it is a hydrogen release only."

The licensee said the hydrogen totalizer, which indicated a flow rate of 100 cfm, may be a probable area of leakage. The hydrogen leaked directly into the turbine building. Air samples indicated personnel breathing apparatus was not required. The licensee expects to exit from the UE once the hydrogen system was purged with CO2. Estimated timeframe is 3-6 hours.

The licensee notified the NRC Resident Inspector.

*** UPDATE FROM D. BRAGLIA TO J. KNOKE AT 17:40 EST ON 3/28/05 ***

The licensee terminated their Unusual Event at 16:40 CST, and the plant status is 0% power / Mode 3. The hydrogen leak was determined to be from a bushing on the main generator. The hydrogen leakage is believed to have lasted only 5 minutes.

The licensee notified the State and NRC Resident Inspector.

Notified R3DO (Riemer), IRD Manager (Crlenjak), NRR EO (Berkow), FEMA and DHS.

*** UPDATE FROM J. GERRITY TO J. KNOKE AT 14:30 EST ON 3/29/05 ***

Received Event Summary Report from Braidwood station. Corrected Unusual Event termination time from 16:40 to 16:23 CST. Notified R3DO (Riemer) and NRR EO (Brenner)

To top of page
Power Reactor Event Number: 41540
Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PHIL CHASE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/28/2005
Notification Time: 23:56 [ET]
Event Date: 03/28/2005
Event Time: 17:38 [EST]
Last Update Date: 03/29/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMES TRAPP (R1)

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

HIGH PRESSURE COOLANT INJECTION TEMPORARILY INOPERABLE

The following information was obtained from the licensee via facsimile (licensee text in quotes):

"Unit 2 High Pressure Coolant Injection (HPCI) [was] declared inoperable due to a loose control power fuse clip associated with the HPCI Pump Suction from Suppression Pool Valve HV-055-212041. The loose clip resulted in loss of control power to this DC motor operated valve and therefore rendered the HPCI system inoperable. The fuse clip has been replaced and the HPCI system returned to an operable status. This report is being made pursuant to 10CFR 50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident."

The licensee will notify the NRC Resident Inspector.

To top of page
Other Nuclear Material Event Number: 41541
Rep Org: DEPT OF NAVY RADIATION SAFETY CMTE
Licensee: DEPT OF NAVY RADIATION SAFETY CMTE
Region: 1
City: Crystal City State: VA
County:
License #: 45-93645-01NA
Agreement: N
Docket:
NRC Notified By: COMMANDER FRAGOSA
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/29/2005
Notification Time: 09:54 [ET]
Event Date: 03/23/2005
Event Time: 12:00 [EST]
Last Update Date: 03/29/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
JAMES TRAPP (R1)
TOM ESSIG (NMSS)
TAS (VIA E-MAIL) ()

Event Text

CHEMICAL AGENT DETECTORS MISSING FROM DEPARTMENT OF NAVY INVENTORY

A representative for the Navy's master materials license reported a number of chemical agent detectors missing based on the two most recent inventory cycles. Specifically, 27 Chemical Agent Monitors (CAMs) that utilize a 10 milliCurie Nickel-63 plated source (SSND# NR-1129-D-103-S) are missing [270 millicuries of Ni-63 total]. In addition, 11 Automatic Chemical Agent Detector Alarms (ACADAs) with two 10 milliCurie Ni-63 plated sources in each detector (SSND# NR-1129-D-101-S) are missing [220 millicuries of Ni-63 total]. The majority of these detectors have been reported missing from Marine Core Logistics Base in Albany, GA. However, a number of these detectors have been distributed to Marine Expeditionary Units in the field. Details of the times, locations, and circumstances under which the detectors went missing are still under investigation by the Navy and will be reported in a followup 30-day written report.

The licensee has contacted the NRC Regional Inspector (Masnyk-Bailey) and HQ contact (Bhachu).

To top of page
Power Reactor Event Number: 41543
Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAMON RITTER
HQ OPS Officer: JOHN KNOKE
Notification Date: 03/29/2005
Notification Time: 15:24 [ET]
Event Date: 03/29/2005
Event Time: 14:00 [EST]
Last Update Date: 03/29/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
JAMES TRAPP (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 95 Power Operation 95 Power Operation

Event Text

24 - HR CONDITION OF LICENSE REPORT DUE TO T.S. NOT MET

The licensee provided the following information:

"On March 29, 2005, Seabrook determined that the requirements of T.S. 3.8.1.1 were not met when the Reserve Auxiliary Transformer (RAT), AC supply to the Bus E5, was removed from service on February 14, 2005. T.S. 3.8..1.1, Action a. requires that the operability of the remaining AC power source be verified within 1 hour, and at least once every 8 hours thereafter. This action requirement was not completed on February 14, 2005 when the RAT AC power supply to Bus E5 was removed from service. At the time of this event the unit Auxiliary Transformer AC power supply to Bus E5 and E6, and the RAT AC power supply to bus E6, were in service. This event is reportable pursuant to Seabrook Station license, Condition 2.G., as a violation of the Technical Specifications.

The licensee notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 41546
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: J. MILLIGAN
HQ OPS Officer: JOHN KNOKE
Notification Date: 03/29/2005
Notification Time: 19:07 [ET]
Event Date: 03/29/2005
Event Time: 10:57 [CST]
Last Update Date: 03/29/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GREG PICK (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Standby 0 Hot Standby

Event Text

ACTUATION OF THE REACTOR PROTECTION SYSTEM AND AUXILIARY FEEDWATER SYSTEM WHILE ESTABLISHING INITIAL CONDITIONS FOR LEAK TEST IN MODE 3.

The licensee faxed the following information:

"On 3/29/05, with the Callaway plant at 0 % power in Mode 3, Steam Generator (S/G) levels were being maintained using 'B' Condensate Pump. Reactor Coolant System (RCS) temperature was being controlled using Condenser Steam Dumps. Preparation was in progress for performance of a leak test on Main Feedwater Isolation Valve AEFV0041. As part of the leak test, condensate flow was temporarily isolated to 'C' S/G and the Auxiliary Feedwater System was aligned to provide water to the 'C' S/G. When low was initiated to 'C' S/G using auxiliary Feedwater, level initially increased due to the injection of a small volume of warm water contained within the Feedwater piping at the S/G, then proceeded to rapidly decrease due to S/G shrink caused by the injection of Auxiliary Feedwater with a temperature of approximately 70 degree F. Level in 'C' S/G decreased until S/G Lo Lo Level reactor trip and Auxiliary Feedwater Actuation signals were generated. Performance of the leak test was terminated and RCS temperature and S/G levels were stabilized at normal parameters for Mode 3."

The licensee informed the NRC Resident Inspector.

To top of page
General Information or Other Event Number: 41547
Rep Org: GENERAL ELECTRIC NUCLEAR ENERGY
Licensee: GENERAL ELECTRIC NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JASON S. POST
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/29/2005
Notification Time: 19:17 [ET]
Event Date: 01/28/2005
Event Time: [EST]
Last Update Date: 03/29/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
JAMES TRAPP (R1)
MALCOLM WIDMANN (R2)
KENNETH RIEMER (R3)
GREG PICK (R4)
OMID TABATABAI (NRR)

Event Text

PART 21 REPORT INVOLVING POTENTIAL TO EXCEED LOW PRESSURE TECHNICAL SPECIFICATION SAFETY LIMIT

The following is a portion of a facsimile submitted by GE Energy-Nuclear:

"The defect is a calculation of an anticipated operational occurrence (AOO), which predicts that the Pressure Regulator Failure Maximum Demand (Open) (PRFO) transient will be terminated by a high water level trip as a result of level swell in the reactor. An improved (and approved) model predicts that MSIV closure will occur when steam line pressure reaches the low-pressure isolation setpoint (LPIS), rather than terminate due to a high water level trip. Depending upon the plant-specific response to a PRFO, including the value of the LPIS, reactor steam dome pressure could decrease to below 785 psig while thermal power exceeds 25% of rated, which would be a violation of SL 2.1.1.1. This constitutes a Defect as defined in 10 CFR 21.3, even though there is no safety hazard created. SL 2.1.1.1 was intended to protect fuel cladding integrity during startup conditions without the need to perform a Critical Power Ratio (CPR) calculation. The AOO of concern is a transient from normal operating conditions that causes CPR to increase, so the event produces additional margin to the Minimum Critical Power Ratio Safety Limit (SLMCPR) and does not threaten fuel cladding integrity. The LPIS should not be considered as a Limiting Safety System Setting (LSSS) for SL 2.1.1.1 since it does not provide a 'significant safety function' with regard to protecting fuel cladding integrity. This indicates that SL 2.1.1.1 is overly conservative because an event that causes CPR to increase and does not threaten fuel cladding integrity, may result in exceeding a reactor core SL."

Notified Plants:

AFFECTED: Nine Mile Point 2, Fermi 2, Pilgrim, Vermont Yankee, Limerick 1 & 2, Peach Bottom 2 & 3, Perry 1, and Hope Creek.

POTENTIALLY AFFECTED: Clinton, Oyster Creek, Brunswick 1 & 2, Nine Mile Point 1, FitzPatrick, Grand Gulf, River Bend, Dresden 2 & 3, LaSalle 1 & 2, Quad Cities 1 & 2, Cooper, Duane Arnold, Monticello, Hatch 1 & 2, Browns Ferry 1, 2 & 3.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012