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Event Notification Report for August 12, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/11/2005 - 08/12/2005

** EVENT NUMBERS **


41903 41905 41911 41912 41913

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General Information or Other Event Number: 41903
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: PRECISION ENERGY SERVICES
Region: 4
City:  State: LA
County:
License #: LA-4413-L01
Agreement: Y
Docket:
NRC Notified By: MIKE HENRY
HQ OPS Officer: BILL GOTT
Notification Date: 08/08/2005
Notification Time: 15:22 [ET]
Event Date: 08/02/2005
Event Time: [CDT]
Last Update Date: 08/08/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RUSSELL BYWATER (R4)
SCOTT MOORE (NMSS)

Event Text

AGREEMENT STATE REPORT - STUCK WELL LOGGING SOURCE

The State provided the following information via facsimile:

"On August 2, 2005, Precision Energy Services had a 2 Curie source of Cs-137 and a 20 Curie source of Am/Be 241 get stuck down hole at a depth of 11,300 feet. The well depth is 12,000 feet. Precision Energy Services is trying to retrieve the well logging tool that has the two radioactive sources in it."

The well is offshore in Louisiana waters. State lease #18076, Well #1.

LA Event Report ID: LA050007

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General Information or Other Event Number: 41905
Rep Org: RI DEPT OF RADIOLOGICAL HEALTH
Licensee: RHODE ISLAND HOSPITAL
Region: 1
City: PROVIDENCE State: RI
County:
License #: 7A-051-02
Agreement: Y
Docket:
NRC Notified By: JACK FERRUOLO
HQ OPS Officer: BILL GOTT
Notification Date: 08/09/2005
Notification Time: 15:57 [ET]
Event Date: 07/18/2005
Event Time: [EDT]
Last Update Date: 08/09/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN CARUSO (R1)
JOHN HICKEY (NMSS)

Event Text

AGREEMENT STATE REPORT - MEDICAL EVENT

The State provided the following information via facsimile:

"Treatment delivered to two (2) of seven (7) lesions on a patient on 18 July 2005, were discovered to be 50 percent less dose than that prescribed. (15 Gy (Grey) per lesion prescribed; two lesions received only 7.5 Gy each) This was discovered [on 3 August 2005], during an internal audit of treatments, conducted by medical physicist not originally involved with treatment. To date the investigation does not identify a problem with the equipment or the dose programs involved in planning. Initial indicators point to a potential communication problem between the original medical physicist and oncologist. At this time the investigation is pending due to the unavailability of the medical physicist due to vacation. Resumption of the investigation is to commence on or about 9 August 2005 when persons involved have returned from vacation."

RI Event Report ID: RI-05-003

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Power Reactor Event Number: 41911
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JOONG KO
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/11/2005
Notification Time: 14:33 [ET]
Event Date: 08/11/2005
Event Time: 10:48 [EDT]
Last Update Date: 08/11/2005
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):
ROBERT HAAG (R2)
SUSAN FRANT (IRD)
IAN JUNG (NRR)

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 ON A CONDENSATE PUMP BUS LOCKOUT

"On 8/11/2005, a manual reactor trip was initiated due to lowering steam generator level caused by a partial loss of main Feedwater. The partial loss of feedwater was caused by the differential lock out of the non-vital 2A2 4160 V bus which resulted in loss of the 2A Condensate Pump that tripped the 2A Main Feedwater Pump. All rods inserted and no Steam Generator Safety Valves lifted. The differential lock out of the non-vital 2A2 4160 V [bus] deenergized the 2A3 vital 4160V bus, starting the 2A Emergency Diesel Generator and the 2A3 loads were sequenced on the Emergency Diesel Generator per design. Subsequently, the Auxiliary Feedwater System was automatically initiated due to lowering steam generator levels. All safe shutdown equipment operated as expected. The plant is stable in Mode 3, Hot Standby conditions, with decay heat removal being accomplished by steaming to the Main Condenser and Feedwater to the steam generators supplied by the Main Feedwater system. The Offsite power grid is available and stable. The '2C' Auxiliary Feedwater Pump was out of service for routine surveillance and it had no effect on the cause of the trip nor had any effect on the trip recovery. St. Lucie is investigating the cause of the lockout on the 2A2 4160V bus. Unit 1 was not affected by this event."

At the time of this report, the 2A Emergency Diesel Generator was still loaded while investigations were underway. Steam generator level is being maintained using main feed.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41912
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DANIEL HAUTALA
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/11/2005
Notification Time: 15:56 [ET]
Event Date: 08/11/2005
Event Time: 08:45 [MST]
Last Update Date: 08/11/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RUSSELL BYWATER (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 95 Power Operation 95 Power Operation
2 N Y 100 Power Operation 100 Power Operation
3 N Y 99 Power Operation 99 Power Operation

Event Text

ONE EMERGENCY PREPAREDNESS SIREN OUT OF SERVICE

"On August 11, 2005 at approximately 08:45 Mountain Standard Time (MST), the Palo Verde Emergency Preparedness Department identified an inoperable single siren (#15). While reviewing the siren monitoring computer log, an Information Services Technician received a 'no response' signal on siren #15. Upon investigation, siren #15 was found inoperable. The siren was vandalized by destroying the siren controller case and stealing the internal battery. The affected siren is estimated to impact approximately 496 members of population in the emergency planning zone (EPZ) beyond 5 miles but within 10 miles. Palo Verde's reporting criterion is a loss of capability to inform greater than 10% of the population beyond 5 miles but within 10 miles. This call is being placed due to the relatively large segment of the population affected and the uncertainty of the length of time that will be needed to restore the siren to operable condition. The Palo Verde Emergency Plan (section 6.6.2.1) has a contingency for dispatching Maricopa County Sheriff's Office (MCSO) vehicles with loud speakers to alert persons within the affected area(s) when sirens are inoperable.

"The County was informed at 09:05 MST to implement the MCSO notification if a need arises.

"There are no events in progress that require siren operation."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41913
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: BRAD EKLUND
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 08/12/2005
Notification Time: 03:26 [ET]
Event Date: 08/12/2005
Event Time: 00:19 [MST]
Last Update Date: 08/12/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
RUSSELL BYWATER (R4)
SUSAN FRANT (IRD)
CHRISTOPHER GRIMES (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 94 Power Operation 94 Power Operation

Event Text

PLANT ENTERED LCO ACTION STATEMENT 3.8.1 TO BE IN MODE 5 DUE TO UNIT 1 "B" DIESEL GEN. BEING DECLARED INOPERABLE

"On August 12. 2005, at approximately 00:19 hours Mountain Standard Time (MST), Palo Verde Nuclear Generating Station (PVNGS) Unit 1 commenced a reactor shutdown required by Technical Specification 3.8.1.

"Limiting Condition for Operability (LCO) 3.8.1 requires two diesel generators (DGs) each capable of supplying one train of the onsite Class 1E AC Electrical Power Distribution System be available. On August 9, 2005, at approximately 04:20 MST, Unit 1 Diesel Generator 'B' failed to maintain the proper steady state output voltage (4080-4300 VAC) during monthly operability surveillance testing per '40ST-9DG02'. Diesel Generator 'B' was declared inoperable and the Unit entered LCO 3.8.1 action 'B'. An engineering action plan was initiated in an attempt to identify the cause of the generator output voltage fluctuation and correct the problem. To date, troubleshooting efforts have unable to isolate the problem. On August 12 at 0420 MST the 72 hour Completion Time associated with LCO 3.8.1 Action 'B' will expire and at 00:19 MST Unit 1 commenced a reactor shutdown in compliance with LCO 3.8.1 Action 'H'.

"The event did not result in the release of radioactivity to the environment and did not adversely affect the safe operation of the plant or health and safety of the public. The required offsite power sources are operable and the electrical grid is stable."

The NRC Resident Inspector will be notified.

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