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Event Notification Report for November 13, 2003

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/12/2003 - 11/13/2003

** EVENT NUMBERS **


40304 40307 40312 40315 40316 40317 40318

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General Information or Other Event Number: 40304
Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: CHEMSYN SCIENCE LABS
Region: 4
City: LENEXA State: KS
County:
License #: 25-B561-01
Agreement: Y
Docket: KS030013
NRC Notified By: TOM CONLEY
HQ OPS Officer: BILL GOTT
Notification Date: 11/07/2003
Notification Time: 17:44 [ET]
Event Date: 10/28/2003
Event Time: [CST]
Last Update Date: 11/07/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARK SHAFFER (R4)
LARRY CAMPER (NMSS)

Event Text

AGREEMENT STATE - PERSONNEL OVEREXPOSURE

"Licensee reported via phone call of potential overexposure of two employees to carbon-14. The licensee indicated initial calculations showed approximately 2.5 Rem exposure.

"Licensee followed up the phone call on November 7, 2003, after receiving urinalysis results. The initial calculations indicated internal whole body exposure to carbon-14 of 7976 milli Rem and 8976 milli Rem for two employees.

"The 252 milliCuries carbon-14 was in a mixture of 221 micro liter benzene in a flame sealed glass ampoule which was being readied for shipment to a customer. The ampoule was wiped for contamination and placed on a counter outside of the fume hood for approximately 2 hours. Initially the ampoule was thought to be in the fume hood.

"The ampoule was found to be leaking and 59 milliCuries of carbon-14 remained in the ampoule. The resultant loss into the lab was 193 milliCuries of carbon-14."

This is a preliminary report to be updated as information is received.

Person 1 received 7.976 Rem internal (CEDE) occupational.
Person 2 received 8.976 Rem internal (CEDE) occupational.

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General Information or Other Event Number: 40307
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SOUTHWEST RESEARCH INSTITUTE
Region: 4
City: SAN ANTONIO State: TX
County:
License #: L00775-000
Agreement: Y
Docket:
NRC Notified By: JIM OGDEN
HQ OPS Officer: ARLON COSTA
Notification Date: 11/10/2003
Notification Time: 09:32 [ET]
Event Date: 11/10/2003
Event Time: [CST]
Last Update Date: 11/10/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARK SHAFFER (R4)
DOUG BROADDUS (NMSS)
CNSNS (Via Fax) ()

Event Text

AGREEMENT STATE REPORT FOR LOST/STOLEN SOURCE

"On October 30, 2003, during a routine inventory of sources, it was discovered that a Nickel-63 electron capture source that had been in storage since January 23, 1996, was missing. An exhaustive search of source storage areas did not locate the source. However, upon questioning employees that had access to the source storage area, one employee recalled that the source in question had been picked up by a Health Physics Technician from the manufacturer, it was believed during the year 1998. The manufacturer denies having the source picked. A search of paperwork is ongoing to locate a transfer document, if one exists."

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General Information or Other Event Number: 40312
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CONSTRUCTION TESTING & ENGINEERING , INC.
Region: 4
City: SACRAMENTO State: CA
County:
License #: 5927-34
Agreement: Y
Docket:
NRC Notified By: BARBARA HAMRICK
HQ OPS Officer: MIKE RIPLEY
Notification Date: 11/10/2003
Notification Time: 17:51 [ET]
Event Date: 11/10/2003
Event Time: [PST]
Last Update Date: 11/10/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WILLIAM JONES (R4)
LARRY CAMPER (NMSS)

Event Text

AGREEMENT STATE REPORT - STOLEN AND RECOVERED TROXLER MOISTURE DENSITY GAUGE

The State of California was informed at 1900, November 9, 2003 that Construction Testing & Engineering had reported the theft of one of their Troxler gauges (Model 3440, S/N 24168). The theft occurred on Friday November 7, 2003, and was reported to Sacramento County Sheriff. The sheriff detectives indicated that they would be questioning the operator who had possession of the gauge at the time it was stolen. An onsite inspection/investigation will be conducted.

The licensee RSO indicated that the theft had been on the local television news Monday morning along with photographs of the stolen device, and a reward for its recovery.

Subsequent to the initial report, the gauge was reported by an unknown party to be in a ditch in an area north of Sacramento. Sheriffs, Hazmat, and other agencies responded and the gauge was recovered without incident.

California Incident Report # 111003.

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Power Reactor Event Number: 40315
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DANIEL HARDIN
HQ OPS Officer: MIKE RIPLEY
Notification Date: 11/12/2003
Notification Time: 14:03 [ET]
Event Date: 11/12/2003
Event Time: 10:03 [EST]
Last Update Date: 11/12/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN PELCHAT (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 93 Power Operation 93 Power Operation
2 N Y 96 Power Operation 96 Power Operation

Event Text

EMERGENCY SIREN TEST FAILURE

"On November 12, 2003, at approximately 1003 hours, during an annual emergency preparedness siren test, the five sirens from New Hanover County, NC, did not respond to the signal sent by the New Hanover County Emergency Operations Center (EOC). The sirens were subsequently tested from the Brunswick Nuclear Plant (BNP) Emergency Offsite Facility (EOF) and responded as required. Maintenance activities are in progress to restore New Hanover County EOC siren initiation capability. Initiation capability will be maintained at the BNP EOF until the capability is restored to New Hanover County. Of the remaining 31 sirens tested, 30 successfully passed the annual test and are considered to be operable. The additional failed siren blew a control power fuse during the test and has since been repaired, tested, and returned to operable status. The resident inspector has been notified.

"The safety significance of this event is considered to be minimal. Both Units 1 and 2 are operating in Mode 1 under normal parameters. Compensatory measures are in place to ensure the affected sirens will initiate if required.

"Activities to restore siren initiation capability are in progress."

* * * * UPDATE FROM DANIEL HARDIN TO MIKE RIPLEY 1706 ET 11/12/03 * * * *

Repairs and retesting have been completed and, as of 1530 ET 11/12/03, New Hanover County EOC siren initiation capability has been restored.

Notified R2DO (J. Pelchat)

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Power Reactor Event Number: 40316
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: LAWRENCE BEAVERS
HQ OPS Officer: MIKE RIPLEY
Notification Date: 11/12/2003
Notification Time: 20:11 [ET]
Event Date: 11/12/2003
Event Time: 18:15 [EST]
Last Update Date: 11/12/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
KENNETH JENISON (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION OF EMERGENCY SIREN ACTIVATION


Calvert County, Maryland was notified that, while "silent" testing the new St. Mary's County sirens (not yet in service), the Calvert County sirens were inadvertently activated. The sirens sounded for approximately 15 seconds.

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 40317
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: GARY OLMSTEAD
HQ OPS Officer: MIKE RIPLEY
Notification Date: 11/12/2003
Notification Time: 21:01 [ET]
Event Date: 11/12/2003
Event Time: 14:21 [CST]
Last Update Date: 11/12/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
WILLIAM JONES (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 67 Power Operation

Event Text

INADVERTENT ACTUATION OF ESSENTIAL SERVICE WATER SYSTEM

"On 11/12/03, Callaway Plant was restoring normal electrical power to electrical bus PB122 in the Circulating and Service Water Pumphouse. While attempting to restore the normal electrical power source to bus PB122, a Reactor Operator operated an incorrect switch. As a result of the incorrect switch operation, two other electrical feeder breakers opened and de-energized electrical busses PB121 and PB122. This resulted in a loss of the normal service water system which supplies cooling water to both safety related and non-safety related loads during normal operation. At 1421, operators manually initiated operation of the Essential Service Water system to restore cooling water to safety related loads. As a result of the loss of normal cooling water to non-safety related loads, a turbine runback occurred and power was stabilized at 68% reactor power. Initial plans are to perform inspections of affected electrical breakers plus circulating water and service water pumps. These inspections will not prevent a return to normal power.

"Essential Service Water is an alternate source of emergency feedwater but in this instance, it was actuated to supply cooling water to safety related loads, not to supply emergency feedwater. This event is voluntarily being reported as an 8-hour ENS call for a valid actuation of an emergency feedwater system."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40318
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: P. DUBROUILLET
HQ OPS Officer: GERRY WAIG
Notification Date: 11/13/2003
Notification Time: 05:27 [ET]
Event Date: 11/12/2003
Event Time: 22:22 [EST]
Last Update Date: 11/13/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN PELCHAT (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 96 Power Operation 96 Power Operation

Event Text

HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION DURING TESTING

"During quarterly surveillance testing of the High Pressure Coolant Injection (HPCI) System the HPCI system isolated. The cause of the isolation is believed to be high turbine exhaust diaphragm pressure. HPCI is currently inoperable. The outboard steam line isolation valve closed automatically and the inboard steam line isolation valve was manually closed. The HPCI room carbon dioxide fire protection system actuated due to the high temperature spike. No fire was present. The Reactor Core Isolation Cooling (RCIC) System, Auto Depressurization System (ADS), Low Pressure Core Spray System and Low Pressure Coolant Injection System are operable.

"Initial Safety Evaluation - Low initial safety significance due to availability of alternate high and low pressure injection systems.

"Corrective Actions - HPCI will remain inoperable pending investigation. Determine and correct the cause of HPCI isolation. Determine if the inboard steam isolation valve should have automatically closed."

The licensee has notified the NRC Resident Inspector.

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