| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/27/2008 - 06/30/2008 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 44311 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BRUCK
HQ OPS Officer: JOE O'HARA | Notification Date: 06/23/2008
Notification Time: 03:26 [ET]
Event Date: 06/23/2008
Event Time: 03:00 [EDT]
Last Update Date: 06/27/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL KUNOWSKI (R3)
|
| 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 LOSS OF EMERGENCY RESPONSE CAPABILITY - TSC IS UNAVAILABLE
"UNAVAILABILITY OF TSC CHARCOAL FILTER FOR SCHEDULED MAINTENANCE
"At 0300 on Monday, June 23,2008, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) ventilation system charcoal filter was removed from service for planned charcoal bed maintenance. The balance of the TSC ventilation is not affected by the charcoal bed maintenance and remains available.
"Under certain accident conditions the TSC may become unavailable due to the inability of the filtration system to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary based upon results of procedurally required monitoring of TSC radiological conditions.
"Charcoal filter maintenance is scheduled to complete at 1000 on Wednesday, June 25, 2008.
"The licensee has notified the NRC Senior Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the loss an emergency response facility."
* * * UPDATE AT 1455EDT ON 06/24/08 FROM SCOTT SCHNEIDER TO S. SANDIN * * *
At 0905 on Tuesday, June 24, 2008, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) ventilation system charcoal filter was removed from service for planned charcoal bed maintenance. The balance of the TSC ventilation is not affected by the charcoal bed maintenance and remains available. The charcoal filter was removed from service at 0300 on Monday, June 23, 2008 (as previously reported via EN # 44311), and subsequently restored to available status at 1614.
"Under certain accident conditions the TSC may become unavailable due to the inability of the filtration system to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary based upon results of procedurally required monitoring of TSC radiological conditions.
"Charcoal filter maintenance is scheduled to complete at 1300 on Wednesday, June 25, 2008.
"The licensee has notified the NRC Senior Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the loss an emergency response facility."
Notified R3DO (Lipa).
* * * UPDATE PROVIDED BY DEAN BRUCK TO JASON KOZAL AT 1846 ON 6/27/08 * * *
"The planned maintenance and testing was completed. The TSC Ventilation system was returned to service at 2045 EDT on 06/26/08.
"The licensee notified the NRC Senior Resident Inspector."
Notified R3DO (Lipa). |
| General Information or Other | Event Number: 44315 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: UNITED INSPECTION AND TESTING CO.
Region: 4
City: MORENO VALLEY State: CA
County:
License #: 4788-33
Agreement: Y
Docket:
NRC Notified By: BARBARA HAMRICK
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/24/2008
Notification Time: 13:12 [ET]
Event Date: 03/05/1993
Event Time: [PDT]
Last Update Date: 06/24/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4)
MICHELE BURGESS (FSME)
ILTAB (via email) ()
MEXICO (via fax) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT INVOLVING DISCOVERY OF A MISSING SOURCE AT A SCRAP YARD
The following information was received from the State of California via email:
"At approximately 1400 hours on Friday, June 20th, Adams Steel reported that a truck from Ecology Auto Parts had alarmed their gate radiation monitors. The truck read 2 millirem per hour at 5 feet away, and about 30 microrem per hour at 20 feet away. The South RM ICE office dispatched an inspector to identify the isotope and assist in isolating the source. The inspector identified the isotope as Cs-137 (nominally 8 mCi), in one of the shrink-wrapped pallets of recyclable metals. Upon removing the shrink wrap, the source rod, index rod, and handle of a moisture-density gauge was identified. The inspector placed the source end of the device in a lead pig, secured the pig in another container, and transferred the device to the radiation control program's southern radioactive materials storage area. Wipes of the other materials on the pallet showed no contamination, and a leak test of the source showed no leakage.
"The device is part of a Troxler 3430 moisture-density gauge. The americium source was not found. The serial number is 20007. The device originally belonged to United Testing and Inspection, who had reported it stolen March 5, 1993. At that time, the licensee offered a reward for the device, filed a police report, investigated the incident, and took corrective actions (review of all security procedures with employees, upgraded locks on storage area, and limited direct access to the storage area)."
CA 5010 Number (Date Notified) - 062008.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. |
| Power Reactor | Event Number: 44320 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: RON FELLOWS
HQ OPS Officer: JOE O'HARA | Notification Date: 06/27/2008
Notification Time: 10:34 [ET]
Event Date: 05/09/2008
Event Time: 21:32 [EDT]
Last Update Date: 06/27/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
HAROLD GRAY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 0 | Hot Standby | 0 | Hot Standby | Event Text INVALID AUXILIARY FEEDWATER SYSTEM ACTUATION
"This 60-day telephone notification is being made under reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1).
"On May 9, 2008, while in a refueling outage, an invalid actuation of the 'A' Auxiliary Feedwater train occurred while performing the Turbine Trip and Auxiliary Governor Solenoids Operability Check.
"The cause of the event was a failure of the 'A' Motor Driven Auxiliary Feedwater Pump (MDAFWP) bypass control relay, 63XT3-TDA. The relay failed to operate as designed under the system conditions and configuration specified by the procedure, resulting in an actuation signal. No actual plant condition existed which required an Auxiliary Feedwater actuation.
"The event resulted in the complete actuation of the 'A' Motor Driven Auxiliary Feedwater train. All equipment functioned as designed for the existing plant configuration. Relay 63XT3-TDA was replaced and retested per the appropriate R. E. Ginna work control processes."
The licensee notified the NRC Resident Inspection. |
| General Information or Other | Event Number: 44322 | Rep Org: FISHER CONTROLS INTERNATIONAL, LLC
Licensee: FISHER CONTROLS INTERNATIONAL, LLC
Region: 3
City: MARSHALLTOWN State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BILL FITZGERALD
HQ OPS Officer: JOHN KNOKE | Notification Date: 06/27/2008
Notification Time: 16:51 [ET]
Event Date: 06/27/2008
Event Time: [CDT]
Last Update Date: 06/27/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
CHRISTINE LIPA (R3)
KATHLEEN O'DONOHUE (R2)
VERN HODGE (NRR)
OMID TABATABAI (NRO)
MARK CUNNINGHAM (NRR)
| Event Text PART 21 NOTIFICATION - PERFORMANCE AFFECTED ON 3" CL150 FISHER V150 VALVE ASSEMBLIES
"Purpose:
The purpose of this Fisher Information Notice (FIN) is to alert FPL that as of 20 June, 2008, Fisher Controls International LLC became aware of the possibility of a situation which may affect the performance of the applicable equipment.
"Equipment Affected by This Information Notice:
Items provided to FPL - Turkey Point per Fisher Order Number 010-A001017058,Item 0001, (FPL Order 00108848, Rev. 3). This equipment included 3" CL150 Fisher V150 valve assemblies (quantity 2). The equipment is identified by Fisher Serial Numbers 18497294 and 18497295 (FPL Tag Number 04224971).
"Applicability:
This notice applies only to the subject equipment supplied by Fisher Controls International LLC, identified above, that was provided to FPL-Turkey Point. Fisher Controls has determined that the subject items did not meet the material requirements specified by the FPL Order 00108848, Rev. 3. Specifically the discrepancies are:
* TFE packing was provided instead of graphite packing.
* TCM seal rings were provided instead of HD metal seal rings.
The difference in these parts will also require that a different seal protector ring be provided." |
| Power Reactor | Event Number: 44323 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: DONNA GUINN
HQ OPS Officer: JOHN KNOKE | Notification Date: 06/27/2008
Notification Time: 16:53 [ET]
Event Date: 06/27/2008
Event Time: 14:30 [CDT]
Last Update Date: 06/27/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DAVID PROULX (R4)
|
| 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 GROUP PAGE VIA INTERACTIVE NOTIFICATION SYSTEM IS NOT OPERATIONAL
"On June 27, 2008 at 1430 CDT, Fort Calhoun Station (FCS) performed testing of the group paging system via the Interactive Notification System (INS) . The group page did not perform as designed. Further investigation and testing of the group page manually resulted in the same issue. It has been determined that the group page function is not operational.
"FCS has implemented backup manual callout process for the emergency response organization. Therefore emergency facility activation may take longer than normal. Troubleshooting efforts are ongoing."
Licensee has notified NRC Resident Inspector. |
| Power Reactor | Event Number: 44324 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES SHAW
HQ OPS Officer: JASON KOZAL | Notification Date: 06/27/2008
Notification Time: 18:46 [ET]
Event Date: 06/27/2008
Event Time: 15:00 [EDT]
Last Update Date: 06/27/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
CHRISTINE LIPA (R3)
|
| 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 PROCEDURE CHANGE INITIATED TO SUPPORT TSC HABITABILITY DOSE CALCULATION
"At 1500 on Friday, June 27, 2008, upon review of a calculation performed to demonstrate the TSC habitability requirements; a determination was made that a procedure change was required to support the assumptions in the calculation. The identified procedure change was effective at 1800 on June 27, 2008. Based on implementation of the procedure change, the TSC is now considered functional, but degraded.
"This issue has been entered into the Corrective Action Program.
"The licensee has notified the NRC Senior Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the loss an emergency response facility." |
| Power Reactor | Event Number: 44326 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MARIA GHARAKHANIAN
HQ OPS Officer: JEFF ROTTON | Notification Date: 06/28/2008
Notification Time: 12:54 [ET]
Event Date: 06/28/2008
Event Time: 11:46 [EDT]
Last Update Date: 06/28/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
HAROLD GRAY (R1)
|
| 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 DUE TO LOSS OF BOTH FEEDWATER PUMPS
At 1146, the reactor was manually tripped due to a feedwater transient that was caused by a loss of both feedwater pumps. The exact cause of the loss of both feedwater pumps is still being investigated. Prior to the reactor trip, the licensee was performing main turbine stop valve testing and during that testing received an isolation of extraction steam.
On the manual reactor trip, all control rods fully inserted. No RCS PORVs or reactor safety valves lifted. The steam generator atmospheric dump valves did lift and reseat. Decay heat is being removed to the condenser via the turbine dump valves. Auxiliary Feedwater (AFW) initiated and fed the steam generators after the loss of both main feedwater (MFW) pumps. MFW was restored and is controlling steam generator levels. AFW has been secured. The electric plant is in a normal shutdown lineup and the EDGs are available. There was no effect on Unit 3.
The licensee has notified the NRC Resident Inspector, Connecticut Department of Environmental Protection, and all local emergency response organizations. |
| Power Reactor | Event Number: 44327 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: FOREST LERO
HQ OPS Officer: JEFF ROTTON | Notification Date: 06/28/2008
Notification Time: 16:59 [ET]
Event Date: 06/28/2008
Event Time: 00:29 [CDT]
Last Update Date: 06/28/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
KATHLEEN O'DONOHUE (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text POSITIVE FOR CAUSE FITNESS FOR DUTY TEST
A non-licensed employee had a confirmed positive for alcohol during a for cause fitness-for-duty test. The employee's access to the plant has been placed on hold. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector. | |