United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2008 > January 30

Event Notification Report for January 30, 2008

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/29/2008 - 01/30/2008

** EVENT NUMBERS **


43930 43934 43937 43940 43941 43942

To top of page
General Information or Other Event Number: 43930
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: SOUTHERN BAPTIST HOSPITAL OF FLORIDA
Region: 1
City: JACKSONVILLE State: FL
County: DUVAL
License #: 2213-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/24/2008
Notification Time: 15:29 [ET]
Event Date: 01/24/2008
Event Time: [EST]
Last Update Date: 01/24/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
TODD JACKSON (R1)
GREG MORELL (FSME)

Event Text

AGREEMENT STATE REPORT - WRONG ISOTOPE ADMINISTERED

"On January 14, [2008], a physician gave a verbal order for a I-123 [Iodine-123] uptake scan. But instead, the patient was given a I-131 uptake scan. On January 16, the physician reviewed the results and realized the wrong isotope had been used. The patient has been notified. No adverse health effects are expected. Florida is investigating."

The amount of I-131 delivered to the patient was 4.7 milliCuries.

This event was assigned Incident Number FL08-012 by the State of Florida.

A 'medical event' indicates potential problems in a medical facility's use of radioactive materials. It does not result in harm to the patient.

To top of page
Fuel Cycle Facility Event Number: 43934
Facility: BWX TECHNOLOGIES, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: BARRY COLE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/25/2008
Notification Time: 17:23 [ET]
Event Date: 01/25/2008
Event Time: 17:00 [EST]
Last Update Date: 01/25/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL
Person (Organization):
BINOY DESAI (R2)
JOSEPH HOLONICH (FSME)
MICHAEL TSCHILTZ (NMSS)
FUELS OUO (EMAIL) ()

Event Text

STATEMENT FOR INQUIRIES BY MEDIA CONCERNING IMPOSED CIVIL PENALTY

BWX Technologies, Inc. will issue the following statement for media inquiries into the NRC imposed civil penalties for an event that occurred at the facility in July, 2007:

"On July 26, 2007, BWXT in Lynchburg, Va., reported an unusual event at its Mount Athos plant to the Nuclear Regulatory Commission (NRC). A vacuum cleaner containing uranium-bearing wastewater tipped over while being moved from one location to another. Fewer than 22 liters of wastewater spilled from the container; a negligible amount of uranium was present in the wastewater.

"The incident did not result in a release of radioactive material to employees or the environment, and there was no possibility of a criticality due to the small amount of material being transported. Additionally, no employees were injured as a result of the incident, and manufacturing operations at the facility were not impacted. In accordance with its operating license, BWXT immediately notified the NRC following the incident.

"As a result of the event, the NRC imposed a civil penalty in the amount of $32,500 on the facility. The NRC has given BWXT 30 days to pay the fine or protest its imposition. Following the incident, BWXT implemented corrective actions related to the process."

The licensee has notified the NRC Resident Inspector of this notification.

To top of page
Fuel Cycle Facility Event Number: 43937
Facility: NUCLEAR FUEL SERVICES INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
                   NAVAL REACTOR FUEL CYCLE
                   LEU SCRAP RECOVERY
Region: 2
City: ERWIN State: TN
County: UNICOI
License #: SNM-124
Agreement: Y
Docket: 07000143
NRC Notified By: RANDY SHAKELFORD
HQ OPS Officer: PETE SNYDER
Notification Date: 01/28/2008
Notification Time: 15:15 [ET]
Event Date: 01/15/2008
Event Time: 16:21 [EST]
Last Update Date: 01/28/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
Person (Organization):
BINOY DESAI (R2)
MIKE TSCHILTZ (NMSS)
FUELS OUO GROUP (E-MA)

Event Text

INADEQUATE INSPECTIONS ON THRU-WALL PIPING PENETRATION SLEEVES

"The issue is associated with sleeved line penetrations thru walls [in the 300 Complex]. The documented periodic inspection was not adequate to verify the continued reliability and availability of the sleeve. In addition, the discussion in the supporting safety analysis was insufficient.

"During the two (2) year review of the safely-related equipment (SRE) test, it was determined that the test could not be performed as written and that the test did not verify the continued reliability and availability of the sleeve. In addition, after a review of the discussion in the supporting safety analysis, the discussion was determined to be insufficient.

"There were no actual safety consequences to workers, the public, or the environment. Although determined to be extremely remote because of the nature of the pipe and sleeve, the potential criticality consequences include a leak of uranium-bearing solution from the pipe and sleeve and into the wall.

"The safety significance is determined to be low due to the following:
- the solution lines and sleeves are compatible with the associated uranium-bearing solutions (stainless steel);
- the sections of lines and sleeves thru the walls are straight pipe with no connections; and,
- leaks have not been observed in straight pipe and sleeve sections.

"Additional actions taken in response to the event:

"The number and locations of the sleeved line penetrations are being investigated. The grout/caulk may be removed to facilitate inspections of the sleeves. Safety-related equipment (SRE) tests and safety analyses are being revised to better describe the accident sequence/barriers and periodic inspections."

The licensee notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 43940
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RICKY GIVENS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 01/29/2008
Notification Time: 00:51 [ET]
Event Date: 01/28/2008
Event Time: 18:43 [CST]
Last Update Date: 01/29/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BINOY DESAI (R2)

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

HIGH PRESSURE CORE INJECTION (HPCI) INOPERABLE

"On 1/28/08 at 1843 CST, Browns Ferry Unit 1 was performing 1-SR-3.3.5.1.3(D) HPCI System Condensate Header Low Level Switch Calibration and Functional Test when 1-LS-73-56A failed to actuate. Per TS 3.3.5.1, 1-LS-73-56A is inoperable. 1-SR-3.3.5.1.3(D) defeats the logic relay normally actuated by 73-56A & B. This causes HPCI to be inoperable per TS 3.3.5.1.D if the relay is defeated for greater than 1 hour. Failure of the 73-56A switch prevented restoration of the relay within the 1 hour time frame.

"This event is reportable under 10CFR 50.72(b)(3)(v)(B) 'any event or condition that at the time of discovery could have prevented the fulfillment of the Safety Function of structures or systems that are needed to: Remove Residual Heat' and 10CFR 50.72(b)(3)(v)(D) 'any event or condition that at the time of discovery could have prevented the fulfillment of the Safety Function of structures or systems that are needed to: mitigate the consequences of an accident.'

"This event also requires a 60 day written report in accordance with 10CFR 50.73(a)(2)(v)(B) and 10CFR 50.73(a)(2)(v)(D).

"The defeated relay was restored to normal and the HPCI system returned to operable status at 2330 CST on 1/28/08."

The licensee notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 43941
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: ALAN HALL
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/29/2008
Notification Time: 06:30 [ET]
Event Date: 01/29/2008
Event Time: 05:31 [EST]
Last Update Date: 01/29/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
BINOY DESAI (R2)
MARY JANE ROSS-LEE (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 25 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP TO REPAIR RCP "2B1" SEAL PACKAGE

"St Lucie Plant, Unit 2, manually tripped the reactor at 0531 hrs. EST, as part of a controlled reactor plant shutdown, in response to an RCS leak rate of 0.28 gpm, indicated to be associated with the 2B1 Reactor Coolant Pump seal package. All systems functioned as expected, satisfactorily. All CEAs fully inserted. Decay Heat removal is with Steam Generators and Main Feedwater. This report is made pursuant to 10 CFR
50.72(b)(2)(iv)(B)."

Unit 2 will cooldown to Mode 5 for repairs.

The licensee informed the NRC Resident Inspector.

* * * UPDATE FROM ALAN HALL TO HOWIE CROUCH @ 1218 EST ON 1/28/08 * * *

"St. Lucie Plant, Unit 2, reported their manual reactor trip of 0531 hrs. EST, at 0630 hrs. EST, for an unidentified leak associated with the 2B1 RCP seal package (EN 43941). Subsequent investigation, reported to the STA [Shift Technical Advisor] at 1015 hrs. EST, determined that this leak constitutes an RCS Pressure Boundary Leak. This leak is at a pipe-to-flange weld on the outboard side of the first flanged coupling of the 2B1 RCP Upper Cavity Seal pressure sensing line. Investigation is in progress to determine the detailed configuration at the leak and root cause. There were NO ESFAS signals or actuations. Decay Heat Removal continues on Steam Generators, with MFW [Main Feedwater] and SBCS [Steam Bypass Control System]; Off-Site power continues [to be] available and stable; Unit 1 at 100% power with operations and conditions normal. This report is made pursuant to 10 CFR 50.72(b)(3)(ii)(A)."

The licensee informed the NRC Resident Inspector of this update. Notified R2DO (Bonser).

To top of page
Power Reactor Event Number: 43942
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DANIEL SEMETER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/29/2008
Notification Time: 21:50 [ET]
Event Date: 01/29/2008
Event Time: 14:41 [EST]
Last Update Date: 01/29/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
HAROLD GRAY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 98 Power Operation 98 Power Operation

Event Text

HIGH PRESSURE COOLANT INJECTION SYSTEM NOT AVAILABLE FOR SAFE SHUTDOWN CAPABILITY

"The D/C power supply for the Unit 1 High Pressure Coolant Injection (HPCI) system instrumentation has failed resulting in the inability of HPCI to meet its requirement to support safely shutting down the reactor during a Station Blackout (Complete Loss of A/C Power) situation. The Emergency Core Cooling System (ECCS) function of HPCI is still available with the alternate A/C power supply."

The licensee is actively troubleshooting the power supply. The HPCI unavailability places the licensee in a 14-day Limiting Condition for Operation action statement.

The licensee has notified the NRC Resident Inspector.

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