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> February 14
Event Notification Report for February 14, 2008
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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/13/2008 - 02/14/2008
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 43975 |
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CONAM INSPECTION & ENGINEERING SERVICES
Region: 4
City: SIGNAL HILL State: CA
County:
License #: 4832-19
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: STEVE SANDIN
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Notification Date: 02/09/2008
Notification Time: 22:23 [ET]
Event Date: 02/02/2008
Event Time: 09:00 [PST]
Last Update Date: 02/09/2008
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Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
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Person (Organization):
MICHAEL SHANNON (R4)
ANDREW PERSINKO (FSME)
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Event Text
AGREEMENT STATE REPORT INVOLVING FAILURE OF RADIOGRAPHY CAMERA TO LOCK SOURCE IN THE SHIELDED POSITION
The following information was received via email:
"On Saturday, February 2, 2008, at approximately 9:00 A.M., a CONAM radiographer was performing radiography at Conoco Phillips in Signal Hill, CA, when he found he was unable to lock the device after retracting the source to the fully shielded position. The source was fully shielded throughout the incident, and remained under the constant surveillance of the radiographer. The Assistant RSO arrived on site at approximately 10:00 am, determined there was dirt in the locking [pin] that prevented it from popping up. He cleaned the dirt, and the locking [pin] engaged, locking the source in place. The device was transported back to the licensee's laboratory, tagged as out of service, and will be sent to INC for inspection and maintenance. The device involved is an INC IR 100 camera (S/N 4160), containing 80 Ci of Ir-192. There were no significant exposures from this event. RHB will follow up with the licensee to determine the root cause of the event, and any necessary corrective actions." |
| Power Reactor |
Event Number: 43976 |
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MIKE REANDEAU
HQ OPS Officer: JEFF ROTTON
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Notification Date: 02/11/2008
Notification Time: 01:48 [ET]
Event Date: 02/10/2008
Event Time: 22:07 [CST]
Last Update Date: 02/13/2008
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
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Person (Organization):
THOMAS KOZAK (R3)
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| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
A/R |
Y |
97 |
Power Operation |
0 |
Hot Shutdown |
Event Text
MANUAL REACTOR SCRAM DUE TO INCREASING REACTOR VESSEL LEVEL
"On February 10, 2008, at approximately 2207 hours CST, the 'B' Reactor Recirculation pump tripped from fast speed to off. The resultant reactor pressure vessel level swell resulted in reactor pressure vessel level being greater than 48 inches and rising. Per Clinton Power Station operating procedures, the 'A' Reactor Operator placed the mode switch to the 'shutdown' position initiating a manual reactor scram. All control rods inserted [fully]. CPS is currently stable in Mode 3."
Decay heat is being removed to the main condenser via the turbine bypass valves. Reactor level is being maintained using the motor driven reactor feedpump. No SRVs lifted during the transient. Licensee is in progress of restoring the electrical plant to a normal shutdown lineup.
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 2226 ON 2/13/08 FROM M. EVANS TO P. SNYDER * * *
"After further analysis of the scram, it was determined that an automatic level 8, high reactor water level, scram occurred approximately one second prior to the reactor operator placing the mode switch to the 'shutdown' position."
The licensee notified the NRC Resident Inspector. |
| General Information or Other |
Event Number: 43979 |
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: ONCOLOGY SYSTEMS, INC.
Region: 4
City: ST. ROSE State: LA
County:
License #: LA-11598-L01
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: STEVE SANDIN
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Notification Date: 02/11/2008
Notification Time: 16:44 [ET]
Event Date: 02/09/2008
Event Time: 09:00 [CST]
Last Update Date: 02/11/2008
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Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
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Person (Organization):
DALE POWERS (R4)
ANDREW PERSINKO (FSME)
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Event Text
AGREEMENT STATE REPORT INVOLVING FAILURE OF HDR SOURCE TO RETRACT DURING TESTING
The following information was provided by the State of Louisiana via email:
"On February 9, 2008 at around 9:00 am, a Model Number AccuSource 1000, with a Model M-19 Iridium-192 High Dose Rate Brachytherapy Source failed to retract automatically while pre-operational acceptance testing was being performed at New York Radiation Oncology Associates, Queens, New York City, New York. The AccuSource 1000 is manufactured by Oncology Systems, Inc. Their license number is LA-11598-L01, amendment# - initial, with an expiration date of July 31, 2012. Agency Interest Number is 147139.
"Model M-19 Iridium-192 source SSD number is LA-0612-S-115-S. The sources maximum quantity is 12 curies of Iridium-192.
"Oncology Systems, Inc. according to their license condition number eight, states that 'The licensee shall report to the Department, immediately by phone and written notice with ten (10) days of occurrence of any irregularities pertaining to inability to retract the source to its fully shielded [position], and failure of any component or software (critical to safe operation of the device) to properly perform its intended function under the authority of this license.'
"This was reported by SPEC who is the manufacturer of the Model M-19 Iridium-192 source. Talking with SPEC, it does not seem that Oncology Systems, Inc. have any personnel located at the 119 Teal Street, St. Rose, LA 70087 location."
The source, which was extended approximately 10 cm when it stuck, was manually retracted. There was no reported personnel overexposures, however, the individual's film badges involved in returning the source to the shielded position have been sent out for processing. The City of NY Rad Health Department was notified by the State of Louisiana of this incident. |
| General Information or Other |
Event Number: 43982 |
Rep Org: AREVA NP, INC.
Licensee: AREVA NP, INC.
Region: 1
City: LYNCHBURG State: VA
County:
License #:
Agreement: N
Docket:
NRC Notified By: GAYLE ELLIOTT
HQ OPS Officer: STEVE SANDIN
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Notification Date: 02/13/2008
Notification Time: 15:26 [ET]
Event Date: 12/27/2007
Event Time: [EST]
Last Update Date: 02/13/2008
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Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
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Person (Organization):
GLENN DENTEL (R1)
EUGENE GUTHRIE (R2)
PART 21 COORD (NRR)
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Event Text
PART 21 INVOLVING POTENTIALLY DAMAGED FUEL ASSEMBLY SPACER SIDE PLATES
The following information was received via facsimile:
"Reportable Defect
"(i) Name and address tithe individual informing the Commission: Gayle Elliott, 3315 Old Forest Road, Lynchburg, VA 24501
"(ii) Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect: Susquehanna Steam Electric Station, Units 1 and 2, potentially may contain ATRIUM- fuel assemblies with damaged spacer side plates.
"(iii) Identification of the firm constructing the facility or supplying the basic component which falls to comply or contains a defect: AREVA NP Inc. (AREVA NP) supplied the ATRIUM-10 fuel assemblies to the Susquehanna units. The spacer side plates were damaged during recent re-channeling campaigns at the reactor site.
"(iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by such a defect or failure to comply: The damaged (missing) spacer side plates could impact the critical power performance of the fuel assemblies and the local power peaking distribution within the fuel assembly.
"(v) The date on which the information of such a defect or failure to comply was obtained: This issue was determined to be a deviation on December 27, 2007.
"(vi) In the case of a basic component which fails to comply, the number and the location of all such components in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations in this part: The known defect has occurred at Susquehanna Unit 1. Based on the number of spacer pieces found, four (4) fuel assemblies could be damaged.
"(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for this action; and the length of time that has been or will be taken to complete the action: AREVA NP recommended and PPL Implemented Operating Limit penalties for the potentially damaged fuel assemblies to protect the MCPR Safety Limit and LHGR SAFDL.
"(viii) Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees: See (vii) above." |
| Power Reactor |
Event Number: 43984 |
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: KEITH LEONARD
HQ OPS Officer: KARL DIEDERICH
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Notification Date: 02/13/2008
Notification Time: 17:28 [ET]
Event Date: 01/30/2008
Event Time: 05:13 [EST]
Last Update Date: 02/13/2008
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
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Person (Organization):
EUGENE GUTHRIE (R2)
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| 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
LOSS OF ALL 81 OFFSITE SIRENS FOR APPROXIMATELY 80 MINUTES
"On 1/30/08 at approximately 0617 Eastern Standard Time, while conducting a routine public warning siren interrogation test, the Harris Nuclear Plant (HNP) determined that the offsite emergency sirens were not capable of being activated. Initial investigations revealed that HNP lost power to the sirens due to a failure of the control module in the Uninterruptible Power Supply (UPS) of the siren system. At approximately 0644, an interrogation test of the system was completed and the sirens were verified to be operating normally. This event was initially viewed as not reportable. Subsequent investigation conducted between 1/31/08 and 2/13/08 revealed that other equipment supplied by the UPS was lost for between 70 and 80 minutes. As there is no direct monitoring capability for siren power supplies, it is reasonable to conclude that the sirens had been lost for a period of time between 70 and 80 minutes. This event should have been reported under 10 CFR 50.72(b)(3)(xiii) on 1/30/08. A completely new UPS system has been installed, and [the] siren systems are fully functional at this time."
The UPS was replaced on 2/7/08. Its loss on 1/30/08 affected all 81 sirens.
The NRC Resident Inspector will be notified. |
| Power Reactor |
Event Number: 43985 |
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JAMES KURAS
HQ OPS Officer: KARL DIEDERICH
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Notification Date: 02/13/2008
Notification Time: 22:24 [ET]
Event Date: 02/13/2008
Event Time: 18:50 [CST]
Last Update Date: 02/13/2008
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
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Person (Organization):
DALE POWERS (R4)
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| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
100 |
Power Operation |
88 |
Power Operation |
Event Text
TECHNICAL SPECIFICATION 3.0.3 REQUIRED SHUTDOWN
"With the 'B' Emergency Diesel Generator out of service for 7 day LCO, the 'A' [Centrifugal Charging Pump] (CCP) was declared inoperable due to associated room cooler tube leak. TS 3.0.3 was entered at 1820 hours with plant shutdown commencing at 1850 hours. At 1950 hours, the NRC granted a 19-hour Notice Of Enforcement Discretion (NOED) from the initial CCP 'A' inoperability time of 1420 hours until entry into TS 3.0.3 is required. Time when Wolf Creek will be required to enter TS 3.0.3 for the 'A' CCP inoperable due to room cooler leakage is now 0920 hours on 2/14/08. Power reduction was stopped at 1950 hours. Currently making preparations to return the unit to 100% power."
Repairs to the 'A' CCP are expected to be complete before 2400 CST 2/13/08.
The Licensee has notified the NRC Resident Inspector. |
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