| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/08/2005 - 07/11/2005 ** EVENT NUMBERS ** |
 | Other Nuclear Material | Event Number: 41767 | Rep Org: U.S. ARMY
Licensee: U.S. ARMY
Region: 3
City: ROCK ISLAND State: IL
County:
License #: 12-000712-06
Agreement: Y
Docket:
NRC Notified By: JEFF HACENNER
HQ OPS Officer: BILL GOTT | Notification Date: 06/13/2005
Notification Time: 09:39 [ET]
Event Date: 06/10/2005
Event Time: [CDT]
Last Update Date: 07/08/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
TODD JACKSON (R1)
PATRICK LOUDEN (R3)
TOM ESSIG (NMSS)
TAS (email) ()
| Event Text STOLEN M-22 AUTOMATIC CHEMICAL DETECTORS
Five M-22 Automatic Chemical Detectors were stolen from the NBC Room (locked secure storage) at Fort Campbell, KY. The theft was discovered on June 10, 2005. Each device contains 20 milliCuries of Nickel - 63. The Army Criminal Investigative Service and the Fort Campbell Military police are conducting an investigation. The Device serial number/source serial numbers are: Y14M0989/Y14C0989, Y14M08283/Y14D08283, Y14M08429/Y14D08429, Y14M08075/Y14D08075, Y14M08548/Y14D08548.
The licensee notified R3 (D. Wiedeman)
* * * UPDATE AT 10:00 AM ON 7/8/05 FROM T. GIZICKI TO P. SNYDER * * *
U. S. Army TACOM Command Rock Island, IL called to update the event. It was discovered that the detectors reported as stolen on 10 June 2005 were not stolen but inappropriately removed from a storage room. The Army found the material in another room on 20 June 2005.
Notified R3 (L. Kozak), R1 (G. Bowman), and NMSS EO (J. Hickey) |
| Power Reactor | Event Number: 41828 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: COOPER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 07/08/2005
Notification Time: 16:20 [ET]
Event Date: 07/08/2005
Event Time: 09:15 [CDT]
Last Update Date: 07/08/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
THOMAS FARNHOLTZ (R4)
GARY JANOSKO (NMSS)
GREG BOWMAN (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 OFFSITE NOTIFICATION RELATED TO IMPROPERLY PACKAGED RADIOACTIVE WASTE MATERIAL SHIPMENT
"At 09:15 CDT Cooper Nuclear Station was notified by Chem Nuclear Limited Liability Company (LLC) of Barnwell South Carolina waste disposal site, of a condition discovered during the off loading of the first Trans Nuclear Radioactive Material (TN RAM) shipping cask (#05-10). This shipping cask was utilized for the shipment of the first TN RAM liner from the current fuel pool cleanup project. Per conversation with the Chem Nuclear LLC representative a small 1/4" by 1/4" piece of metal debris was discovered between the outer wall of the inner TN RAM liner and the interior wall of the TN RAM cask. This was discovered after the inner liner was off loaded into the disposal trench. The radiation level of this debris was 70 R/hr contact. The debris was removed from the TN RAM cask interior and placed in a 30 gal drum for temporary storage. Barnwell has requested a decision from NPPD on the disposal of this item. There were no violations of the DOT limits specified for the external dose rates of the TN RAM cask during the CNS Shipment.
"Cooper Nuclear Station representatives are being sent to Barnwell, South Carolina to assist in the determination of the cause and appropriate corrective actions.
"This is a potential violation of the Department of Health and Environmental Controls (DHEC) of the State of South Carolina acceptance criteria for unpackaged material outside of a disposal liner. This was also a potential violation of the Certificate of Compliance for the NRC Certified Type B TN RAM Cask.
"This is being reported per 10 CFR 50.72(b)(2)(xi) since Chem Nuclear LLC has notified DHEC of the State of South Carolina."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41829 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: MICHAEL MURPHY
HQ OPS Officer: BILL HUFFMAN | Notification Date: 07/08/2005
Notification Time: 22:49 [ET]
Event Date: 07/08/2005
Event Time: 19:15 [EDT]
Last Update Date: 07/08/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
| Person (Organization):
STEPHEN CAHILL (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | | 4 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text STARTUP TRANSFORMERS DECLARED INOPERABLE BASED ON POTENTIAL UNDERVOLTAGE CONDITION
"PTN (Turkey Point) received a notification from System Operations that switchyard voltage limits (based upon System Operations Contingency Analysis) was forecasted to exceed switchyard voltage limits if Unit 3 had tripped. This condition existed from 1434 to 1448 on July 8, 2005.
"At 1915 on July 8, 2005, PTN determined that both Unit 3 and 4 Startup Transformers were inoperable at 1434 on July 8, 2005, and entered Technical Specification 3.8.1.1 action e. This action was to notify the NRC within 4 hours; and to restore at least one of the inoperable Startup Transformers to OPERABLE status within 24 hours. At 1448 on July 8, 2005, both Startup Transformers were declared OPERABLE and PTN exited Technical Specification 3.8.1.1 action e."
The licensee stated that the potential for low grid voltage at the Turkey Point Nuclear Plant was based on offsite conditions and was a postulated condition. Low voltage conditions did not actually occur.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41831 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: LANCE LANE
HQ OPS Officer: JOHN KNOKE | Notification Date: 07/10/2005
Notification Time: 01:20 [ET]
Event Date: 07/09/2005
Event Time: 22:54 [CDT]
Last Update Date: 07/10/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
THOMAS FARNHOLTZ (R4)
|
| 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 LOSS OF EMERGENCY ASSESSMENT CAPABILITY DUE TO INOPERABLE EP SIRENS
"At 2154 hours on July 9, 2005, power was lost to the #11, Otter Creek and #12, Jacob's Creek Emergency Plan Sirens. At 2254 hours on July 9, 2005, the #11 and #12 sirens are still without power. Siren #4, WC Lake South, was previously determined to be inoperable at 1210 hours on July 6, 2005, due to being struck by lightning. With 3 of the 11 Emergency Plan sirens out of service for greater than 1 hour a major loss of emergency assessment capability exists.
"Lyon Coffey Electric is currently working to restore power to the #11 and #12 Emergency Plan sirens.
"The NRC Senior Resident Inspector has been notified.
"At 2359 hours power has been restored to the #11 and #12 sirens restoring emergency assessment capability."
The licensee contacted the dispatcher at the LLEO as an informational call. |
| Power Reactor | Event Number: 41832 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [ ] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: ALAN RAUSH
HQ OPS Officer: JOHN KNOKE | Notification Date: 07/10/2005
Notification Time: 06:42 [ET]
Event Date: 07/10/2005
Event Time: 03:18 [EDT]
Last Update Date: 07/10/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
GREG BOWMAN (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text TURBINE TRIP RESULTING IN RPS ACTUATION AND AUTOMATIC REACTOR SCRAM
"This non-emergency 4-hour and 8-hour report is pursuant to 10CFR50.72(b)(2) and 10CFR50.72(b)(3). On 7/10/05 at 0318 hours, Unit 2 experienced a turbine trip and subsequent reactor scram. An RPS actuation occurred, as expected, following the turbine trip. RPS responded normally and reactor power is 0%. Reactor water level went below 1 inch, as expected, following a reactor scram from 100% power. At a reactor level of less than 1 inch, PCIS Group 2 and 3 isolations occurred. Reactor water level has been restored above 1 inch to the normal level using the normal reactor feedwater system. All safety systems responded as designed.
"An investigation is in progress to determine the cause of the turbine trip and to initiate appropriate corrective actions."
During the scram the RCS experienced a high pressure condition which caused both recirculation pumps to trip and 3 SRVs to lift and reseat. The licensee is presently depressurizing primary system in order to restart one of the recirculation pumps. Current RCS parameters: Pressure - 320 psig; Temperature - 428 F; and Level - +23 inches. All rods fully inserted.
Prior to the turbine trip the licensee was conducting a routine weekly "Mechanical Trip Valve Test."
The licensee notified the NRC Resident Inspector. | |