Event Notification Report for February 13, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/12/2008 - 02/13/2008
Fuel Cycle Facility
Event Number: 43983
Facility: BWX TECHNOLOGIES, INC.
Region: 2 State: VA
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
NRC Notified By: CHERYL GOFF
HQ OPS Officer: BILL HUFFMAN
Region: 2 State: VA
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
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
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
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
Person (Organization):
EUGENE GUTHRIE (R2)
ABY MOHSENI (NMSS)
FUELS OUO VIA EMAIL
EUGENE GUTHRIE (R2)
ABY MOHSENI (NMSS)
FUELS OUO VIA EMAIL
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.
"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.
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
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JAMES KURAS
HQ OPS Officer: KARL DIEDERICH
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
Notification Time: 22:24 [ET]
Event Date: 02/13/2008
Event Time: 18:50 [CST]
Last Update Date: 02/13/2008
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):
DALE POWERS (R4)
DALE POWERS (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 88 | Power Operation |
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.
"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.