Event Notification Report for October 12, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/11/2009 - 10/12/2009
EVENT NUMBERS
45426454274542845431
Power Reactor
Event Number: 45426
Facility: LASALLE
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: DAN COVEYOU
HQ OPS Officer: DONG HWA PARK
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: DAN COVEYOU
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/12/2009
Notification Time: 05:33 [ET]
Event Date: 10/12/2009
Event Time: 03:33 [CDT]
Last Update Date: 10/12/2009
Notification Time: 05:33 [ET]
Event Date: 10/12/2009
Event Time: 03:33 [CDT]
Last Update Date: 10/12/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JULIO LARA (R3DO)
JULIO LARA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 70 | Power Operation |
TECHNICAL SPECIFICATION SHUTDOWN DUE TO UNIDENTIFIED LEAKAGE FROM RCS
"This notification is being provided in accordance with 10CFR50.72(b)(2)(i), plant shutdown required by Technical Specifications.
"At 0300 [CDT] on 10/12/09, LaSalle Unit 2 commenced a plant shutdown. At 2333 [CDT] on 10/11/09, LaSalle Unit 2 exceeded the 2 gpm increase in unidentified leakage within the previous 24 hour period of Technical Specification [TS] LCO 3.4.5.d. per required action B.1, unidentified leakage increase was required to be restored to within limits within 4 hours. At 0333 [CDT] on 10/12/09, TS 3.4.5 required action 8.1 was declared not met, and TS 3.4.5 condition C was entered which requires the unit to be in mode 3 within 12 hours and mode 4 within 36 hours. TS LCO 3.4.5, RCS operational leakage requires the plant to be in mode 3 by 10/12/09 at 1533 [CDT] and mode 4 by 10/13/09 at 1533 [CDT].
"The unidentified leakage is currently at 2.3 gpm. Although not physically verified, the source of the leakage is suspected to be from the 2B21-F016, Inboard Main Steam Line drain valve packing. Other primary containment parameters - Drywell Air Temperature, Drywell and Suppression Chamber Pressure, Suppression Pool Average Temperature - remain within TS limits."
The licensee expects to enter mode 3 by 1200 CDT on 10/12/09 and mode 4 by 0000 on 10/13/09. The licensee suspects the leakage to be from the Inboard Main Steam Line Drain Valve packing due to an earlier maintenance requiring cycling of that valve. All safety-related systems required for plant shutdown and cooldown are operable.
The licensee has notified the NRC Resident Inspector.
"This notification is being provided in accordance with 10CFR50.72(b)(2)(i), plant shutdown required by Technical Specifications.
"At 0300 [CDT] on 10/12/09, LaSalle Unit 2 commenced a plant shutdown. At 2333 [CDT] on 10/11/09, LaSalle Unit 2 exceeded the 2 gpm increase in unidentified leakage within the previous 24 hour period of Technical Specification [TS] LCO 3.4.5.d. per required action B.1, unidentified leakage increase was required to be restored to within limits within 4 hours. At 0333 [CDT] on 10/12/09, TS 3.4.5 required action 8.1 was declared not met, and TS 3.4.5 condition C was entered which requires the unit to be in mode 3 within 12 hours and mode 4 within 36 hours. TS LCO 3.4.5, RCS operational leakage requires the plant to be in mode 3 by 10/12/09 at 1533 [CDT] and mode 4 by 10/13/09 at 1533 [CDT].
"The unidentified leakage is currently at 2.3 gpm. Although not physically verified, the source of the leakage is suspected to be from the 2B21-F016, Inboard Main Steam Line drain valve packing. Other primary containment parameters - Drywell Air Temperature, Drywell and Suppression Chamber Pressure, Suppression Pool Average Temperature - remain within TS limits."
The licensee expects to enter mode 3 by 1200 CDT on 10/12/09 and mode 4 by 0000 on 10/13/09. The licensee suspects the leakage to be from the Inboard Main Steam Line Drain Valve packing due to an earlier maintenance requiring cycling of that valve. All safety-related systems required for plant shutdown and cooldown are operable.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 45427
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: STEVE SAMPLE
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: STEVE SAMPLE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/12/2009
Notification Time: 12:00 [ET]
Event Date: 10/12/2009
Event Time: 04:00 [CDT]
Last Update Date: 10/12/2009
Notification Time: 12:00 [ET]
Event Date: 10/12/2009
Event Time: 04:00 [CDT]
Last Update Date: 10/12/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
VIVIAN CAMPBELL (R4DO)
VIVIAN CAMPBELL (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
EMERGENCY OPERATIONS FACILITY INOPERABLE DUE TO LOSS OF VENTILATION
"Loss of ventilation to an emergency response facility: Emergency Operations Facility (EOF).
"During performance of the EOF diesel generator operability test, the EOF ventilation system was placed in filtration mode. The air conditioning unit and air return fan did not run. Emergency Preparedness personnel evaluated the habitability of the EOF and determined that the filtration mode of the ventilation system was not functional. Because of the loss of the ventilation function for the EOF, the facility was not functional.
"The EOF is available for emergency response purposes unless the temperature could not be maintained or a release is in progress. The backup EOF is available for use if needed. Repair of the EOF's ventilation system is in progress. This is reported per 10CFR50.72(b)(3)(xiii)."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE FROM STEVE SAMPLE TO DONALD NORWOOD AT 1620 10/12/09 * * *
The EOF was restored to operable status at 1247 CDT.
The licensee notified the NRC Resident Inspector. Notified R4DO (Campbell).
"Loss of ventilation to an emergency response facility: Emergency Operations Facility (EOF).
"During performance of the EOF diesel generator operability test, the EOF ventilation system was placed in filtration mode. The air conditioning unit and air return fan did not run. Emergency Preparedness personnel evaluated the habitability of the EOF and determined that the filtration mode of the ventilation system was not functional. Because of the loss of the ventilation function for the EOF, the facility was not functional.
"The EOF is available for emergency response purposes unless the temperature could not be maintained or a release is in progress. The backup EOF is available for use if needed. Repair of the EOF's ventilation system is in progress. This is reported per 10CFR50.72(b)(3)(xiii)."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE FROM STEVE SAMPLE TO DONALD NORWOOD AT 1620 10/12/09 * * *
The EOF was restored to operable status at 1247 CDT.
The licensee notified the NRC Resident Inspector. Notified R4DO (Campbell).
Power Reactor
Event Number: 45428
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: PHILLIP MARTIN
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: PHILLIP MARTIN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/12/2009
Notification Time: 17:22 [ET]
Event Date: 10/12/2009
Event Time: 16:03 [CDT]
Last Update Date: 10/12/2009
Notification Time: 17:22 [ET]
Event Date: 10/12/2009
Event Time: 16:03 [CDT]
Last Update Date: 10/12/2009
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
VIVIAN CAMPBELL (R4DO)
BILL GOTT (IRD)
ERIC LEEDS (NRR)
ELMO COLLINS (R4RA)
PATRICK HILAND (NRR)
VIVIAN CAMPBELL (R4DO)
BILL GOTT (IRD)
ERIC LEEDS (NRR)
ELMO COLLINS (R4RA)
PATRICK HILAND (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
NOTIFICATION OF UNUSUAL EVENT DUE TO SMALL FIRE LASTING GREATER THAN 10 MINUTES
"At 1551, [the control room] received a 911 notification of a fire in the Condenser area. Entered abnormal procedure 5.1 Incident [and the] fire brigade was dispatched. Follow-up reports indicated that the fire was in the Heater Bay area in the vicinity of B2/B3 heaters.
'At 1556, the Control Room received a report via the Work Control Center from a qualified fire watch on the scene that the fire had been extinguished.
"At 1603 the Emergency Director declared a NOUE, on EAL 5.1.1, due to a fire in the Protected Area that takes longer than 10 minutes to extinguish. At the time of the declaration, a six sided search had not yet been conducted in accordance with procedural requirements.
"At 1613, the Fire Brigade Leader reported a six sided search of the Heater Bay area was complete, and the fire was declared OUT.
"At 1619 the 'all clear' alarm sounded.
"At 1638, the Emergency Director terminated the NOUE.
"The actual location of the fire was in a pipe chase between B-4 and B-3 Heaters and was caused by hot ceramic pellets from a heating blanket that was above the area of the location of the fire. The heating blankets were being used to pre-heat the piping in preparation for welding. A pigtail that feeds the blanket failed and some of the hot ceramic pellets from inside the blanket dropped down on to the plastic protecting the area below from foreign materials. The hot ceramic pellets on the plastic caused a small (approx. 3 inch diameter) fire. The active fire only lasted for approximately five minutes.
"All required notification were completed in a timely manner."
The licensee notified the NRC Resident Inspector.
"At 1551, [the control room] received a 911 notification of a fire in the Condenser area. Entered abnormal procedure 5.1 Incident [and the] fire brigade was dispatched. Follow-up reports indicated that the fire was in the Heater Bay area in the vicinity of B2/B3 heaters.
'At 1556, the Control Room received a report via the Work Control Center from a qualified fire watch on the scene that the fire had been extinguished.
"At 1603 the Emergency Director declared a NOUE, on EAL 5.1.1, due to a fire in the Protected Area that takes longer than 10 minutes to extinguish. At the time of the declaration, a six sided search had not yet been conducted in accordance with procedural requirements.
"At 1613, the Fire Brigade Leader reported a six sided search of the Heater Bay area was complete, and the fire was declared OUT.
"At 1619 the 'all clear' alarm sounded.
"At 1638, the Emergency Director terminated the NOUE.
"The actual location of the fire was in a pipe chase between B-4 and B-3 Heaters and was caused by hot ceramic pellets from a heating blanket that was above the area of the location of the fire. The heating blankets were being used to pre-heat the piping in preparation for welding. A pigtail that feeds the blanket failed and some of the hot ceramic pellets from inside the blanket dropped down on to the plastic protecting the area below from foreign materials. The hot ceramic pellets on the plastic caused a small (approx. 3 inch diameter) fire. The active fire only lasted for approximately five minutes.
"All required notification were completed in a timely manner."
The licensee notified the NRC Resident Inspector.
Other Nuclear Material
Event Number: 45431
Rep Org: OHIO DEPARTMENT OF HEALTH
Licensee: PRODUCERS SERVICE CORPORATION
Region: 3
City: ZANESVILLE State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MICHAEL SNEE
HQ OPS Officer: DONG HWA PARK
Licensee: PRODUCERS SERVICE CORPORATION
Region: 3
City: ZANESVILLE State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MICHAEL SNEE
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/14/2009
Notification Time: 09:12 [ET]
Event Date: 10/12/2009
Event Time: 00:00 [EDT]
Last Update Date: 10/14/2009
Notification Time: 09:12 [ET]
Event Date: 10/12/2009
Event Time: 00:00 [EDT]
Last Update Date: 10/14/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ERIC DUNCAN (R3DO)
ANGELA MCINTOSH (FSME)
ERIC DUNCAN (R3DO)
ANGELA MCINTOSH (FSME)
AGREEMENT STATE REPORT - LOST GAUGE FOUND WITH SHUTTER STUCK OPEN
The following event was received from the state via e-mail:
"A radiation alarm was tripped at PSC Metals from a load of scrap metal coming from Polk Metal and Iron located in Zanesville, Ohio. The load of scrap metal was returned to Polk Metal and Iron. The BRP [Bureau of Radiation Protection] was informed on October 12 and dispatched an inspector to Polk Metal and Iron on October 13. Based on the information on the device [Texas Nuclear model # 5190 SN B5283 containing 200 mCi of Cs-137] the BRP contacted the manufacturer and learned that the device was initially distributed to Producers Service Corporation, also located in Zanesville.
"The Producers Service Corporation was contacted and sent a representative to meet the BRP inspector at the Polk site to retrieve the gauge. The inspector surveyed the gauge and found that the shutter was stuck open with an in-beam dose rate of 200 mR/hr at six inches. The shutter mechanism was freed and verified closed by the inspector. The device was transported less than a mile to the Producers Service Corp facility and is now secured in a vacant office in a secured building. The inspector wipe tested the device and found it to be free of contamination. Producers Service Corporation is in the process of contacting the device manufacturer to make disposal arrangements. The device was a generally licensed device distributed on September 9, 1986.
"The inspector determined that the device was inadvertently sent to the scrap yard and that Producers Service Corporation was not attempting to illegally dispose of the device.
"Device Name: Fixed Gauge
Manufacturer: Texas Nuclear
Model Number: 5190
Serial Number: B5283"
Ohio Report No. OH09-031
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Although IAEA categorization of this event is typically based on device type, the staff has been made aware of the actual activity of the source, and after calculation determines that it is a Less than Cat 3 event.
Note: the value assigned by device type "Category 3" is different than the calculated value "Less than Cat 3"
The following event was received from the state via e-mail:
"A radiation alarm was tripped at PSC Metals from a load of scrap metal coming from Polk Metal and Iron located in Zanesville, Ohio. The load of scrap metal was returned to Polk Metal and Iron. The BRP [Bureau of Radiation Protection] was informed on October 12 and dispatched an inspector to Polk Metal and Iron on October 13. Based on the information on the device [Texas Nuclear model # 5190 SN B5283 containing 200 mCi of Cs-137] the BRP contacted the manufacturer and learned that the device was initially distributed to Producers Service Corporation, also located in Zanesville.
"The Producers Service Corporation was contacted and sent a representative to meet the BRP inspector at the Polk site to retrieve the gauge. The inspector surveyed the gauge and found that the shutter was stuck open with an in-beam dose rate of 200 mR/hr at six inches. The shutter mechanism was freed and verified closed by the inspector. The device was transported less than a mile to the Producers Service Corp facility and is now secured in a vacant office in a secured building. The inspector wipe tested the device and found it to be free of contamination. Producers Service Corporation is in the process of contacting the device manufacturer to make disposal arrangements. The device was a generally licensed device distributed on September 9, 1986.
"The inspector determined that the device was inadvertently sent to the scrap yard and that Producers Service Corporation was not attempting to illegally dispose of the device.
"Device Name: Fixed Gauge
Manufacturer: Texas Nuclear
Model Number: 5190
Serial Number: B5283"
Ohio Report No. OH09-031
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Although IAEA categorization of this event is typically based on device type, the staff has been made aware of the actual activity of the source, and after calculation determines that it is a Less than Cat 3 event.
Note: the value assigned by device type "Category 3" is different than the calculated value "Less than Cat 3"