Event Notification Report for May 24, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/23/2004 - 05/24/2004
Research Reactor
Event Number: 40776
Rep Org: IDAHO STATE UNIVERSITY
Licensee: IDAHO STATE UNIVERSITY
Region: 4
City: POCATELLO State: ID
County: BANNOCK
License #: R-110
Agreement: Y
Docket: 05000284
NRC Notified By: JOHN BENNION
HQ OPS Officer: JEFF ROTTON
Licensee: IDAHO STATE UNIVERSITY
Region: 4
City: POCATELLO State: ID
County: BANNOCK
License #: R-110
Agreement: Y
Docket: 05000284
NRC Notified By: JOHN BENNION
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/26/2004
Notification Time: 09:38 [ET]
Event Date: 05/24/2004
Event Time: 09:00 [MDT]
Last Update Date: 05/26/2004
Notification Time: 09:38 [ET]
Event Date: 05/24/2004
Event Time: 09:00 [MDT]
Last Update Date: 05/26/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MIKE RUNYAN (R4)
TERRY REIS (NRR)
MIKE RUNYAN (R4)
TERRY REIS (NRR)
BREACH OF PRIMARY FISSION PRODUCT BARRIER
During routine annual maintenance, a fueled control rod was determined to have a cladding failure. The control rod end cap weld was broken and the fuel in the fueled control rod had been exposed. A preliminary radiological assessment was performed and showed negligible release. There was minimum surface contamination isolated to the area of the breach. Radiation readings on contact were less than 20 millirem/hour. All air sample concentrations were well below 10CFR20 Derived Air Concentration (DAC) limits.
Licensee notified the NRC Program Manager for Non Power Reactors and the Region 4 RA.
During routine annual maintenance, a fueled control rod was determined to have a cladding failure. The control rod end cap weld was broken and the fuel in the fueled control rod had been exposed. A preliminary radiological assessment was performed and showed negligible release. There was minimum surface contamination isolated to the area of the breach. Radiation readings on contact were less than 20 millirem/hour. All air sample concentrations were well below 10CFR20 Derived Air Concentration (DAC) limits.
Licensee notified the NRC Program Manager for Non Power Reactors and the Region 4 RA.
Power Reactor
Event Number: 40774
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JIM CASE
HQ OPS Officer: BILL GOTT
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JIM CASE
HQ OPS Officer: BILL GOTT
Notification Date: 05/24/2004
Notification Time: 17:12 [ET]
Event Date: 05/24/2004
Event Time: 15:00 [EDT]
Last Update Date: 05/24/2004
Notification Time: 17:12 [ET]
Event Date: 05/24/2004
Event Time: 15:00 [EDT]
Last Update Date: 05/24/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION 50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION 50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
SONIA BURGESS (R3)
SONIA BURGESS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
DEGRADED CONDITION DUE TO EMERGENCY SERVICE WATER FAILURE
"Emergency Service Water "A" (ESW ) Pump failure resulted in inoperability of all Div 1 ECCS systems at 0150 on 05/21/04 [See event notification 40767]. A plant shutdown was initiated with mode 4 [cold shutdown] achieved at 0619 on 05/23/04. During the disassembly and inspection of ESW A pump, a failed coupling on the pump shaft was found to be the cause of the failure. An Operability Determination [OD] was requested on ESW B at 1330 on 05/24/04 since both pumps had the identical coupling design and the pumps had similar run times. At 1500, the Design Engineering Manager informed the control room that engineering could not return a completed OD within the allotted time that could justify continued ESW B operability. The control room Shift Manager than declared the ESW B pump inoperable. This results in a condition that could have prevented the fulfillment of a safety function, specifically the removal of residual heat."
The licensee notified the NRC Resident Inspector.
"Emergency Service Water "A" (ESW ) Pump failure resulted in inoperability of all Div 1 ECCS systems at 0150 on 05/21/04 [See event notification 40767]. A plant shutdown was initiated with mode 4 [cold shutdown] achieved at 0619 on 05/23/04. During the disassembly and inspection of ESW A pump, a failed coupling on the pump shaft was found to be the cause of the failure. An Operability Determination [OD] was requested on ESW B at 1330 on 05/24/04 since both pumps had the identical coupling design and the pumps had similar run times. At 1500, the Design Engineering Manager informed the control room that engineering could not return a completed OD within the allotted time that could justify continued ESW B operability. The control room Shift Manager than declared the ESW B pump inoperable. This results in a condition that could have prevented the fulfillment of a safety function, specifically the removal of residual heat."
The licensee notified the NRC Resident Inspector.
Other Nuclear Material
Event Number: 40838
Rep Org: AGILENT TECHNOLOGIES
Licensee: AGILENT TECHNOLOGIES
Region: 1
City: Wilmington State: DE
County: Newcastle
License #: 07-28762-02G
Agreement: N
Docket:
NRC Notified By: DAVID BENNETT
HQ OPS Officer: HOWIE CROUCH
Licensee: AGILENT TECHNOLOGIES
Region: 1
City: Wilmington State: DE
County: Newcastle
License #: 07-28762-02G
Agreement: N
Docket:
NRC Notified By: DAVID BENNETT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/24/2004
Notification Time: 12:13 [ET]
Event Date: 05/24/2004
Event Time: 00:00 [EDT]
Last Update Date: 06/24/2004
Notification Time: 12:13 [ET]
Event Date: 05/24/2004
Event Time: 00:00 [EDT]
Last Update Date: 06/24/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
JAMES NOGGLE (R1)
M. WAYNE HODGES (NMSS)
JAMES NOGGLE (R1)
M. WAYNE HODGES (NMSS)
LOSS OF NICKEL-63 SOURCE
On March 18, 2004, Agilent Technologies of Wilmington, DE shipped a 15 milliCurie Nickel-63 (Ni-63) source to their Germany distribution center for shipment to the end-user, AVT McCormick in Cochin, India. The package was shipped out of the Germany distribution center via Air Express on April 12, 2004. When the package was received by the end-user, the source could not be found in the package. According to the end-user, the package received did not have any damage or indication of being opened previously.
The sealed source was for an electron capture detector. Nickel-63 is a beta emitter.
The licensee has notified Region 1 (Modes).
On March 18, 2004, Agilent Technologies of Wilmington, DE shipped a 15 milliCurie Nickel-63 (Ni-63) source to their Germany distribution center for shipment to the end-user, AVT McCormick in Cochin, India. The package was shipped out of the Germany distribution center via Air Express on April 12, 2004. When the package was received by the end-user, the source could not be found in the package. According to the end-user, the package received did not have any damage or indication of being opened previously.
The sealed source was for an electron capture detector. Nickel-63 is a beta emitter.
The licensee has notified Region 1 (Modes).