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Event Notification Report for April 1, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/31/2004 - 04/01/2004

** EVENT NUMBERS **


40611 40613 40630 40631 40632

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General Information or Other Event Number: 40611
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: SAINT FRANCIS HOSPITAL
Region: 1
City: MEMPHIS State: TN
County:
License #: R-79104
Agreement: Y
Docket:
NRC Notified By: DEBRA SHULTS
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/26/2004
Notification Time: 14:53 [ET]
Event Date: 03/25/2004
Event Time: 08:45 [EST]
Last Update Date: 03/26/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RONALD BELLAMY (R1)
ROBERTO TORRES (NMSS)

Event Text

AGREEMENT STATE REPORT INVOLVING A MISADMINSTRATION DURING EYE TREATMENT

"Event description: A pterygium patient was scheduled to receive a 42.5 second treatment utilizing a 100 millicurie Srontium-90 sealed source manufactured by 3M Company, model number 6D1A. The dosimetrist programmed the manual timer for 4 minutes and 25 seconds. During the treatment, the physician questioned the treatment time and it was terminated after 2 minutes and 30 seconds. The prescribed dose was 20 Gy. The patient received 70.59 Gy. The patient and the physician were notified of the misadministration. The licensee notified the Division the same day of the event. The licensee will submit a written report within 15 days. This incident is reportable under 1200-2-5-.32 (79) (e) (4) of 'State Regulations for Protection Against Radiation.'"

TN Event Report ID No.: TN-04-035

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General Information or Other Event Number: 40613
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GLOBAL GEO ENGINEERING
Region: 4
City: WEST COVINA State: CA
County:
License #: 6899-30
Agreement: Y
Docket:
NRC Notified By: BARBARA HAMRICK
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/27/2004
Notification Time: 19:00 [ET]
Event Date: 03/26/2004
Event Time: 22:00 [PST]
Last Update Date: 03/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID GRAVES (R4)
PATRICIA HOLAHAN (NMSS)
AARON DANIS (TAS)
VICTOR GONZALES (MEX)

Event Text

STATE LICENSEE, GLOBAL GEO ENGINEERING, REPORTED A TROXLER GAUGE WAS STOLEN FROM A TECHNICIAN'S TRUCK.

A Troxler moisture/density gauge, Model 3430, with nominal activity of 10 mCi Cs-137 and 30 mCi Am-241, was stolen from the back of a flat bed truck sometime after 10:00 pm on 3/26/04, and before 5:00 am 3/27/04. The truck was parked at the technician's residence in West Covina. The technician involved worked late last night, and took the gauge home and left it chained to the flat bed truck overnight. The licensee contacted the West Covina PD. The licensee will be offering a $500 reward for the return of the gauge.

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Power Reactor Event Number: 40630
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JIM WILSON
HQ OPS Officer: ARLON COSTA
Notification Date: 03/31/2004
Notification Time: 18:02 [ET]
Event Date: 03/31/2004
Event Time: 07:57 [CST]
Last Update Date: 03/31/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
OTHER UNSPEC REQMNT
Person (Organization):
MICHAEL PARKER (R3)
TERRY REIS (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 92 Power Operation 92 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

NON-LICENSED EMPLOYEE TESTED POSITIVE FOR ALCOHOL

A non-licensed supervisor tested positive for alcohol during a "for cause" test. A review of the employee's work concluded that the individual had not been engaged in safety-related activities. The individual has been denied access to Point Beach Nuclear Plant and to all other Nuclear Management Company, LLC (NMC) sites. Contact the Headquarters Operations Officer for additional details.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40631
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JEFF ABERNETHY
HQ OPS Officer: ARLON COSTA
Notification Date: 03/31/2004
Notification Time: 19:28 [ET]
Event Date: 03/31/2004
Event Time: 18:56 [EST]
Last Update Date: 03/31/2004
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
JOEL MUNDAY (R2)
MICHAEL JOHNSON (NRR)
SUSAN FRANT (DIRO)
GIL AGUIRRE (DHS)
MIKE EACHES (FEMA)

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

Event Text

UNUSUAL EVENT DECLARED DUE TO REACTOR COOLANT SYSTEM LEAKAGE GREATER THAN 10 GPM

On 3/31/04, Saint Lucie Unit 1 was in a refueling outage when it experienced a leak-by which appeared to be at a Volume Control Tank to Hold Up Tank divert valve off the Shutdown Purification System. The Reactor Coolant System (RCS) leakage was greater than ten gallons per minute as indicated in the Control Room. The Facility declared an Unusual Event at 1856 EST since the RCS leakage was greater than ten but less fifty gallons per minute. Refueling activities were stopped as a result of the incident. The RCS leakage was isolated and the Unusual Event was terminated at 1915.

The licensee has notified local, state and other government agencies through the ring down phone system. The NRC Resident Inspector will be notified.

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Power Reactor Event Number: 40632
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: ROBERT MURILLO
HQ OPS Officer: MIKE RIPLEY
Notification Date: 04/01/2004
Notification Time: 00:44 [ET]
Event Date: 03/31/2004
Event Time: 19:19 [CST]
Last Update Date: 04/01/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
OTHER UNSPEC REQMNT
Person (Organization):
DALE POWERS (R4)

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

NEW WORST CASE SINGLE FAILURE MAY EXCEED 10 CFR 46 ACCEPTANCE CRITERION FOR SBLOCA

"A new worst case single failure was identified on 03-31-04 for the small break LOCA analysis of record due to a postulated loss of a DC power bus. This condition may result in the analysis of record exceeding 10 CFR 50.46 acceptance criterion of 2200 F when a small break LOCA with this failure is postulated.

"The current small break LOCA analysis of record assumes a single failure of one Emergency Diesel Generator (EDG) and credits flow from one charging pump. The peak cladding temperature for the analysis of record is 1929 F compared to the acceptance criteria of less than or equal to 2200 F. Half of the flow from a charging pump is assumed to go to the RCS and half is assumed to flow out the break. It was identified on 03-31-04 that a single failure of a DC power bus would be more limiting than the currently assumed single failure of an EDG. The DC bus failure will result in the EDG failure to start and also cause a charging loop isolation valve to the RCS to fail closed on loss of DC power. The other charging flow path to the RCS is on the assumed broken RCS leg so it is assumed to be spilled to the containment resulting in no charging flow to the RCS. Therefore, no charging flow would be delivered to the RCS as assumed in the current small break LOCA analysis of record. This condition has not been analyzed.

"Engineering judgment indicates that in the event of a small break accident the 10 CFR 50.46 acceptance criterion of 2200 F may be exceeded if the charging flow is not credited in the analysis of record. Therefore, this condition is reportable pursuant to 10 CFR 50.46 and 10 CFR 50.72(b)(3)(ii)(B).

"The current conservatism in the analysis of record and previous Westinghouse SBLOCA non-design basis scoping analyses using the NOTRUMP code provide assurance the plant is operating in a safe manner and is operable. The NOTRUMP analyses included cases with no changing flow. The peak clad temperature for these analyses were significantly below the acceptance criteria of 2200 F by more than 200 F. Thus, if an analysis were performed for Waterford 3 with the NOTRUMP code there is reasonable assurance due to the large margins that acceptable results would be achieved without any charging flow.

"This report is based on conservative judgment and available information. This report may be retracted based on the results of further evaluation."

The licensee notified the NRC Resident Inspector.

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Friday, March 30, 2012