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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/15/2008 - 02/19/2008
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 43980 |
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: WASTE MANAGEMENT
Region: 4
City: SULPHUR State: LA
County:
License #: LA-4187-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: BILL HUFFMAN |
Notification Date: 02/12/2008
Notification Time: 16:15 [ET]
Event Date: 02/06/2008
Event Time: [CST]
Last Update Date: 02/12/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
DALE POWERS (R4)
ROBERT LEWIS (FSME) |
Event Text
AGREEMENT STATE REPORT - LOUISIANA - LEAKING CHECK SOURCE
The State provided the following information via facsimile:
"On February 8, 2008, Waste Management reported a leaking source. On February 7, 2008, an e-mail from Suntrac was opened. This e-mail contained information on two leak tests that were performed on two sealed radioactive check sources. One of the sealed sources had removable activity that was above 0.005 uCi. A 5 mCi source of Cs-137 had a removable activity of 0.0084 uCi. This source has been taken out of service. Waste Management will contact Suntrac for disposal of the source. The source was identified as 'Orange #2' and a serial number was not known."
LA Report ID LA080003 |
| Fuel Cycle Facility |
Event Number: 43983 |
Facility: BWX TECHNOLOGIES, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: CHERYL GOFF
HQ OPS Officer: BILL HUFFMAN |
Notification Date: 02/13/2008
Notification Time: 17:01 [ET]
Event Date: 02/13/2008
Event Time: 09:30 [EST]
Last Update Date: 02/13/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION |
Person (Organization):
EUGENE GUTHRIE (R2)
ABY MOHSENI (NMSS)
FUELS OUO VIA EMAIL () |
Event Text
24 HOUR REPORT CONCERNING IMPROPERLY ANALYZED CONDITION RELATED TO INTEGRATED SAFETY ANALYSIS
"During a routine internal audit of the Uranium Recovery 3-inch Extraction System on February 13 at 0930, a Nuclear Criticality Safety (NCS) engineer observed several inconsistencies between the documented limits and controls in the Integrated Safety Analysis summary and those derived in the associated NCS evaluations. These anomalies were non-conservative in nature and included items such as the inside diameters of the columns, column wall thickness, and limits on the number of stainless steel columns in the system. In addition, the most recent NCS evaluation of the system employed a different analytical methodology than earlier evaluations. The evaluation employed the solid angle methodology, which had not been previously utilized to evaluate the 3-inch Extraction System. In past evaluations, the system was modeled using the law of substitution as a 7 x 2 array of 4-inch columns, mirrored in the x and y faces to form an infinite planar array. This change in methodology was incorrect. Based on these uncertainties in the safety basis, the engineer was unable to determine if double contingency was maintained.
"An evaluation is currently being performed.
"BWXT is making this 24-hour report in accordance with 10 CFR 70.61, Appendix A, (b)(1) - Any event or condition that results in the facility being in a state that was not analyzed, was improperly analyzed, or is different from that analyzed in the Integrated Safety Analysis, and which results in failure to meet the performance requirements of § 70.61.
"The operation was immediately shutdown by Nuclear Criticality Safety pending further investigation."
The licensee notified the NRC Resident Inspector. |
| General Information or Other |
Event Number: 43988 |
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: COVANTA ENERGY
Region: 4
City: CROWES LANDING State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: K. PRENDERGAST
HQ OPS Officer: JOHN KNOKE |
Notification Date: 02/14/2008
Notification Time: 15:36 [ET]
Event Date: 02/14/2008
Event Time: [PST]
Last Update Date: 02/14/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
DALE POWERS (R4)
ROBERT LEWIS (FSME) |
Event Text
AGREEMENT STATE REPORT - TRACTOR TRAILER SET OFF RADIATION ALARM
"On 2/13/08 RHB was notified of a tractor trailer from the Turlock transfer station (municipal trash) that set off the radiation alarms at Covanta Energy. The truck was returned to the Turlock transfer station and arrangements were made to survey the vehicle to determine the reason for the alarm. On 2/14/08 an RHB inspector visited the transfer station to survey the truck to determine the radionuclide and quantity. Readings on the truck were stated to be 5 mr/hr at surface. Cesium 137 was identified. The cesium source measured 260 mr/hr using an Ion Chamber at about a foot. This would be approximately 85 mCi. The source was located and placed in properly shielded lead pig. The source will be stored at Thomas Gray and Associates and will be examined for serial numbers and to accurately determine the activity at a later date. The source appeared rusty and was very small and was similar to a brachytherapy source. Following the examination additional information will be provided." |
| Power Reactor |
Event Number: 43990 |
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CHRIS SKINNER
HQ OPS Officer: JASON KOZAL |
Notification Date: 02/16/2008
Notification Time: 02:45 [ET]
Event Date: 02/15/2008
Event Time: 19:02 [EST]
Last Update Date: 02/16/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(B) - POT RHR INOP |
Person (Organization):
GLENN DENTEL (R1) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
POTENTIAL INOPERABILITY OF EMERGENCY CORE COOLING SYSTEMS DUE TO AN UNALALYZED CONDITION
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(ii) which states in part Any event or condition that results in (A) the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded; or (B) the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety and 10 CFR 50.72(b)(3)(v) which states in part... Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (A) Shut down the reactor and maintain it in a safe shutdown condition; (B) Remove residual heat; (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident. This notification describes a licensee identification of a condition where the low pressure emergency core cooling systems (ECCS) may not have been able to perform their safety functions of removing residual heat and significantly degrades plant safety. The condition has been corrected.
"At 2152 on 15 February 2008, while operating at 100% power, Nine Mile Point Unit 2 completed evaluating a 10 CFR 21 communication from General Electric on ECCS suction strainers, and concluded that the calculation on debris head loss was non conservative. The original design basis net positive suction head calculations assumed a suppression pool water level of 199.5 feet. Based upon the General Electric notification, at this suppression pool water level, the low pressure core spray and all three residual heat removal systems might not have been able to perform their safety functions. Further engineering evaluation determined that if the suppression pool level was [greater than or equal to] 200.3 feet then the suction strainers debris head loss could be met and the low pressure ECCS would be able to perform their safety functions.
"At 1902 the control room operators took action to raise suppression pool water level while engineering completed their evaluation based on the expectation that suppression pool water would have to be raised. At 1910 on 15 February 2008, suppression pool water level was raised to 200.3 feet, which resulted in the low pressure core spray and residual heat removal systems being able to perform their safety function."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor |
Event Number: 43991 |
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: NED DENNIN
HQ OPS Officer: MARK ABRAMOVITZ |
Notification Date: 02/17/2008
Notification Time: 08:31 [ET]
Event Date: 02/17/2008
Event Time: 09:00 [EST]
Last Update Date: 02/17/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
GLENN DENTEL (R1) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
94 |
Power Operation |
94 |
Power Operation |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
PLANNED PHONE OUTAGE
"The Emergency Notification System (ENS), Health Physics Network (HPN), site commercial telephone lines and Emergency Response Data System (ERDS) have been taken out of service for a planned maintenance outage. The outage is scheduled for a duration of six hours. The plant radio system, plant page system, and Prelude phone system are unaffected by the maintenance."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1534 ON 2/17/08 FROM NED DENNIN TO JEFF ROTTON * * *
All phones are back in service and operable.
The licensee will notify the NRC Resident Inspector.
Notified R1DO (Dentel). |
| Power Reactor |
Event Number: 43992 |
Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: EDWIN URQHART
HQ OPS Officer: JASON KOZAL |
Notification Date: 02/18/2008
Notification Time: 05:08 [ET]
Event Date: 02/18/2008
Event Time: 01:20 [EST]
Last Update Date: 02/18/2008 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION |
Person (Organization):
EUGENE GUTHRIE (R2) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
Y |
89 |
Power Operation |
89 |
Power Operation |
Event Text
UNANALYZED CONDITION DUE TO #2 TURBINE BYPASS VALVE FAILURE
"Unit two reduced power to 90% to perform monthly turbine testing surveillance on 2/18/08. All tests were completed satisfactorily with the exception of the main turbine #2 Bypass Valve (BPV). At 0120 hours, the #2 BPV stroked fully open per procedure, but the last 10% of travel to full open did not yield the expected response of BPV fast open from 90% to 100%. The fast acting solenoid did indicate expected state change to 'energized' at 90% valve open, but the BPV did not indicate fast open. Therefore the Main Turbine Bypass System has been declared inoperable and associated actions of Tech Spec 3.7.7 have been invoked. This spec requires compliance with LCO 3 .2.2 MINIMUM CRITICAL POWER RATIO (MCPR) limits for an inoperable main turbine bypass system as specified in the COLR (Core Operating Limit Report), are made applicable (within 2 hours) or reduce THERMAL POWER to <24% RTP within the following 4 hours. The MCPR limits were calculated by reactor engineering and installed in the process computer at 0347 hours. A decrease in reactor power was not required once the MCPR limit was installed.
"The COLR (ref.: TRM Appendix A) states Unit Two can be operated with EITHER the End- of- Cycle Recirc Pump Trips (EOC-RPTs) out of service OR the Turbine Bypass Valves inoperable, but not both. The EOC-RPTs were already out of service as allowed for current conditions of the operating cycle. Upon discovery of the inoperable Bypass Valve, it was recognized that this placed Unit Two in an unanalyzed condition for fuel thermal limit. The shift crew took immediate actions to confirm the surveillance was current for EOC-RPTs and placed them in service per approved plant procedures. This was accomplished at 0315 hours, which returned the unit to an analyzed condition."
The licensee notified the NRC Resident Inspector. |
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