| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/31/2008 - 11/03/2008 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 44470 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: GLEN MORROW
HQ OPS Officer: STEVE SANDIN | Notification Date: 09/07/2008
Notification Time: 14:45 [ET]
Event Date: 09/07/2008
Event Time: 08:05 [CDT]
Last Update Date: 10/31/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
RICHARD SKOKOWSKI (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 67 | Power Operation | 67 | Power Operation | Event Text ISOLATION CONDENSER DECLARED INOPERABLE FOLLOWING SURVEILLANCE TESTING
"Unit 2 Isolation Condenser did not meet acceptance criteria per DOS 1300-01 Isolation Condenser 5 year heat removal capability test. This is a single train system and cannot fulfill its safety function. The Isolation Condenser is a single train system. The function of the IC System is to respond to main steam SAFETY ANALYSES line isolation events by providing core cooling to the reactor. The IC System is an Engineered Safety Feature System, and credit is taken in the loss of feedwater transient analysis for IC System operation."
Unit 2 entered a 14-day TS LCO A/S 3.5.3 at 0249 CDT on 09/07/08 after declaring the IC System Inoperable. The Action Statement (A/S) requires restoration of the IC System to Operable status within 14 days or place the unit in hot shutdown within 12 hrs followed by entry into cold shutdown in the following 24 hrs. The licensee is performing maintenance to adjust the cooling flow valve stroke time in order to re-test and exit the LCO A/S.
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 1318 EDT ON 10/31/08 FROM SCOTT BRILEY TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"The purpose of this notification is to retract ENS notification 44470 made on September 7, 2008 for Dresden Nuclear Power Station. After further evaluation, Dresden has determined that the Isolation Condenser did successfully pass its 5-year heat removal test on September 7, 2008. The evaluation corrected the steam flow rate based on a more accurate instrument and calculated the heat removal rate by multiplying the mass flow rate through the Isolation Condenser times the difference in enthalpy between the steam going to the condenser and the condensate leaving the condenser. Therefore, the Isolation Condenser was capable of performing its safety function and the ENS report is being retracted."
The licensee informed the NRC Resident Inspector. Notified R3DO (Kozak). |
| Power Reactor | Event Number: 44606 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: FARA BURDICK
HQ OPS Officer: DONALD NORWOOD | Notification Date: 10/28/2008
Notification Time: 12:28 [ET]
Event Date: 10/28/2008
Event Time: 09:00 [MST]
Last Update Date: 10/31/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BLAIR SPITZBERG (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text MAINTENANCE ON PUBLIC PROMPT NOTIFICATION SYSTEM EMERGENCY SIRENS
"The following event description is based on information currently available. If through subsequent reviews of the event, additional information is identified that is pertinent to this event or alters the information being provided at the time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"From October 28, 2008 until October 31, 2008, Palo Verde personnel will be performing maintenance on public prompt notification system sirens. One siren at a time will be removed from service, and will be restored prior to continuing to the next siren.
"Siren #42 provides notification to approximately 558 members of the public within 5 miles of Palo Verde.
"Siren #44 provides notification to approximately 210 members of the public within 5 miles of Palo Verde.
"Siren #25 provides notification to approximately 302 members of the public within 5 miles of Palo Verde.
"Siren #23 provides notification to approximately 498 members of the public within 5 miles of Palo Verde.
"Siren #22 provides notification to approximately 855 members of the public within 5 miles of Palo Verde.
"Siren #18 provides notification to approximately 396 members of the public within 5 miles of Palo Verde
"Siren #17 provides notification to approximately 1106 members of the public within 5 miles of Palo Verde.
"Siren #36 provides notification to approximately 301 members of the public within 5 miles of Palo Verde.
"Siren #15 provides notification to approximately 940 members of the public within 5 to 10 miles of Palo Verde.
"Each of these are considered by Palo Verde to be a 'large segment of the population.'
"The Palo Verde Emergency Plan has a contingency for dispatching Maricopa County Sheriff's Office (MCSO) vehicles, during an actual event, with loud speakers to alert persons within the affected area when sirens are inoperable.
"There are no events in progress that require siren operation. A follow-up call will be placed when the affected sirens are returned to service.
"The NRC Resident Inspector has been notified of the siren maintenance and this ENS call."
These sirens are utility owned.
* * * UPDATE AT 1335 EDT ON 10/31/08 FROM FARA BURDICK TO S. SANDIN * * *
The following information was received as an update to this report:
"This is an update of ENS call # 44606. At this time, maintenance on the Palo Verde public prompt notification for sirens identified in ENS #44606, has been completed, siren testing was successful and the sirens are operable and in service at this time.
"The NRC Resident Inspector has been notified of the siren maintenance and this ENS call."
Notified R4DO (Spitzberg). |
| General Information or Other | Event Number: 44607 | Rep Org: OK DEQ RAD MANAGEMENT
Licensee: WAL-MART
Region: 4
City: MUSKOGEE State: OK
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MIKE BRODERICK
HQ OPS Officer: JASON KOZAL | Notification Date: 10/28/2008
Notification Time: 11:48 [ET]
Event Date: 10/21/2008
Event Time: [CDT]
Last Update Date: 10/28/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4)
MICHELE BURGESS (FSME)
ILTAB (VIA EMAIL) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text MISSING TRITIUM EXIT SIGNS
The state provided the following via e-mail:
"On October 21, 2008 the Oklahoma Department of Environmental Quality was notified of missing GL radioactive material by the environmental services manager for Wal-Mart. The devices are Tritium exit sign (TES) light modules. The last known location for these TES were in Wal-Mart stores identified below. The Corporation had inventoried TES in Wal-Mart stores several weeks earlier. When company employees prepared to remove the TES's for disposal, they were unable to locate three of the TES. Information concerning the TES follows.
"Store # 00130, 1000 West Shawnee St., Muskogee, OK 30316, Serial# - Unknown, Manufacturer -Unknown, Curie Content - Unknown
"Store # 03295, 6310 South Elm Place, Broken Arrow, OK 74011, Serial# - Unknown, Manufacturer -Unknown, Curie Content - Unknown
"Store # 03295, 6310 South Elm Place, Broken Arrow, OK 74011, Serial# - 277852, Manufacturer -Isolite, Curie Content - 20"
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. |
| General Information or Other | Event Number: 44609 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: DELEK REFINING LIMITED
Region: 4
City: TYLER State: TX
County:
License #: L02289
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOE O'HARA | Notification Date: 10/28/2008
Notification Time: 17:09 [ET]
Event Date: 10/28/2008
Event Time: 09:00 [CDT]
Last Update Date: 10/30/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4)
CHRISTIAN EINBERG (FSME)
| Event Text CS-137 SOURCE DISCONNECTED FROM LEVEL DETECTOR OPERATING ROD
"At 1515 on 10/28/08, the Agency was notified by the licensee of an event involving a Thermo Measure Tech Model 5191 level measurement gauge. The licensee had noted that the gauge was no longer reading properly and sent a maintenance crew to the area to perform repairs. While conducting repairs, an individual from the safety group came by to perform radiation surveys. The survey indicated elevated levels of radiation so the safety representative had the area evacuated and roped off. The licensee contacted the manufacturer who sent technicians to the facility to investigate. They found that radiation levels were in fact elevated and determined that the source had separated from the operating rod. The source is still located in the gauge housing, but is not currently shielded. The source is a 260 milliCurie (calculated based on decay) Cesium (Cs) -137 source. The licensee has started their investigation including time and distance studies with workers who were in the area. The gauge is located in an area of the plant not frequented by workers. The manufacturer is scheduled to remove the gauge from the vessel and send it to their facilities for further inspection on 10/29/08."
* * * UPDATE FROM ART TUCKER TO PETE SNYDER ON 10/30/08 AT 0833 EDT * * *
The Agreement State of Texas provided the following information via e-mail:
"The licensee contacted the [Texas Department of State Health Services (TDSHS)] on October 29, 2008, and informed them that the gauge had been removed from the tank it was mounted on by the manufacturer. The Cs-137 source was found in the gauge housing. The gauge and source were packaged for transportation back to the manufacturer's facility for inspection and repair. The [TDSHS] will be provided the results of the inspection when it is completed."
Texas Event Number: I - 8576.
Notified R4DO (Spitzberg), FSME (Burgess). |
| Power Reactor | Event Number: 44618 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL RICHARDSON
HQ OPS Officer: JOHN KNOKE | Notification Date: 10/31/2008
Notification Time: 13:45 [ET]
Event Date: 10/31/2008
Event Time: 12:52 [EDT]
Last Update Date: 10/31/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
DEBORAH SEYMOUR (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | N | 0 | Hot Standby | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO ROD CONTROL MALFUNCTION
"Initial conditions: Low Power Physics Testing after outage. Performing Dynamic Rod Worth measurements. Single dropped rod (K-2) on Control Bank B occurred after movement disagreement between rod groups. Entered AP-14, 'Rod Control Malfunction'. Performed a manual reactor trip and manual start of Auxiliary Feedwater as directed by Normal Operating Procedures for unit shutdown. Feedwater isolation occurred due to Low T-Ave concurrent with reactor trip."
All control rods were fully inserted.
Licensee has notified NRC Resident Inspector. |
| Fuel Cycle Facility | Event Number: 44621 | Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: KEVIN BEASLEY
HQ OPS Officer: JOHN KNOKE | Notification Date: 11/01/2008
Notification Time: 14:36 [ET]
Event Date: 11/01/2008
Event Time: 08:37 [CDT]
Last Update Date: 11/01/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
DEBORAH SEYMOUR (R2)
PATTI SILVA (NMSS)
| Event Text PROCESS GAS LEAK DETECTION SYSTEM NOT FUNCTIONING CORRECTLY
"At 0837 CDT, on 11-01-08 the Plant Shift Superintendent (PSS) was notified that the Process Gas Leak Detection (PGLD) system for C-333 Unit 5 Cell 3 was not functioning as required. An operator was preparing to test fire the system as required by TSR SR 2.4.4.1-1 when it was discovered that the Ready light was not illuminated. This PGLD system contains detectors that cover C-333 Unit 5 Cell 3 and Section 1 and 2 of the cell bypass piping. At the time of this failure, Unit 5 Cell 3 and some areas of Sections 1 and 2 of the cell bypass were operating above atmospheric pressure. TSR 2.4.4.1 requires that at least the minimum number of detector heads in the cell and in each defined section of the cell bypass are operable during steady state operations above atmospheric pressure. With the Unit 5 Cell 3 PGLD system inoperable, none of the required cell heads and only 2 of the required 3 heads in Sections 1 and 2 of the cell bypass were operable. This PGLD System was declared inoperable, TSR LCO 2.4.4.1.B.1 and 2.4.4.1.C.1 were entered and a continuous smoke watch was put in place within one hour. Engineering has determined that the system would not have been able to perform its intended safely function with the Ready light not illuminated.
"This event is reportable as a 24 hour event in accordance with 10CFR 76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when:
a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident;
b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and
c.) no redundant equipment is available and operable to perform the required safety function.
"The NRC Resident Inspector has been notified of this event."
PGDP Assessment and Tracking Report No. ATR.08-3142; PGDP Event Report No. PAD-2008.034; |
| Power Reactor | Event Number: 44622 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JIM CASE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/02/2008
Notification Time: 08:16 [ET]
Event Date: 11/02/2008
Event Time: 08:30 [EST]
Last Update Date: 11/02/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
LAURA KOZAK (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 | Event Text EMERGENCY RESPONSE DATA SYSTEM (ERDS) OUT OF SERVICE FOR PLANNED MAINTENANCE
"The Perry Nuclear Power Plant will be taking the Plant Computer out of service for scheduled maintenance which will take ERDS out of service. From 0830 hours EST, on November 2, 2008, for approximately 6 hours, personnel will be resetting computer time from EDT to EST and [will] troubleshoot the Plant Computer. During this planned maintenance, the Safety Parameter Display System (SPDS) and the automatic mode calculation of the Computer Aided Dose Assessment Program (CADAP) [will] be unavailable.
"In the event of an emergency, plant parameter data will be orally transmitted to the facilities through the Status Board Ring Down circuit with back-up by the Plant Branch Exchange, the Off Premise Exchange, and various redundant infra-facility circuits throughout the emergency facilities. The dose assessment function will be maintained during the out of service time period by manual input of data into CADAP and, if required, by manual
calculation. The ability to open and maintain an 'open line' using the Emergency Notification System will not be affected and will be the primary means of transferring plant data to the NRC as a contingency until the ERDS can be returned to service during the period of unavailability.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(xiii), as a condition that results in a major loss of offsite communications capability. A follow-up notification will be made when the activities are completed and the equipment is restored. The [NRC] Resident Inspector has been notified."
* * * UPDATE FROM JIM CASE TO JOHN KNOKE AT 1530 EST ON 11/02/08 * * *
The Plant Computer was put back in operation at 1525 EST. Notified R3DO (Kozak) |
| Power Reactor | Event Number: 44623 | Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: STEVE SANDIN | Notification Date: 11/02/2008
Notification Time: 20:33 [ET]
Event Date: 11/02/2008
Event Time: 15:50 [EST]
Last Update Date: 11/02/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
EUGENE COBEY (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 | Event Text HPCI SYSTEM DECLARED INOPERABLE DUE TO CONTROLLER FAILURE
"The Unit 1 MCR [Main Control Room] HPCI [High Pressure Coolant Injection] flow indicator was observed oscillating just above zero gpm with periodic spikes to approximately 50% of scale (3000 gpm) with a concurrent drop in flow controller output signal while in standby. There were no activities in progress on or near the HPCI system when the oscillation and instrument spikes occurred. Walkdown of the instrument rack and HPCI room equipment found no abnormalities. The HPCI system was declared inoperable at 1550 hours 11/2/2008 (14 day Shutdown LCO). Troubleshooting is in progress to determine the cause of the flow oscillations.
"The HPCI system is considered available as there are no indications of controller failure that would impact operation in manual flow control mode.
"Unit 1 RCIC, and all other ECCS systems remain OPERABLE."
The licensee will inform the NRC Resident Inspector. |
| Power Reactor | Event Number: 44624 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC BLOUGH
HQ OPS Officer: JOE O'HARA | Notification Date: 11/03/2008
Notification Time: 04:35 [ET]
Event Date: 11/03/2008
Event Time: 02:07 [EST]
Last Update Date: 11/03/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
DEBORAH SEYMOUR (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text MANUALLY OPENED REACTOR TRIP CIRCUIT BREAKERS TO INSERT CONTROL BANK "B"
"Manually opened reactor trip breakers in Mode 5 to insert control bank 'B' due to blown fuse in rod control cabinet."
Licensee was moving control rod bank "B" following I & C work, and the control rod bank failed to move as expected. All other control rod banks were inserted into the core at the time of the event. EDG's and offsite power sources are OPERABLE, and there is no increase in plant risk.
The licensee will inform the NRC Resident Inspector. | |