Event Notification Report for September 25, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/24/2006 - 09/25/2006
Other Nuclear Material
Event Number: 42861
Rep Org: WEAVER BOOS CONSULTANTS
Licensee: WEAVER BOOS CONSULTANTS
Region: 3
City: GRIFITH State: IN
County:
License #: 13-26305-01
Agreement: N
Docket:
NRC Notified By: DON WARD
HQ OPS Officer: JOHN MacKINNON
Licensee: WEAVER BOOS CONSULTANTS
Region: 3
City: GRIFITH State: IN
County:
License #: 13-26305-01
Agreement: N
Docket:
NRC Notified By: DON WARD
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/25/2006
Notification Time: 15:08 [ET]
Event Date: 09/25/2006
Event Time: 13:00 [CST]
Last Update Date: 09/25/2006
Notification Time: 15:08 [ET]
Event Date: 09/25/2006
Event Time: 13:00 [CST]
Last Update Date: 09/25/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
SONIA BURGESS (R3)
GREG MORELL (NMSS)
ILTAB (E-MAILED) (NSIR)
SONIA BURGESS (R3)
GREG MORELL (NMSS)
ILTAB (E-MAILED) (NSIR)
TROXLER MOISTURE DENSITY GAUGE LOST DURING SHIPMENT
On 09/20/06 Troxler Naperville, IL office sent a Troxler Model # 3430 to Weaver Boos Consultant office located at 5677 DTC Blvd, Suite 102, Greenwood Village, CO. The gauge was to have arrived at the Weaver Boos Consultant, Greenwood Village, CO office on 09/22/06. Licensee contacted the shipper, FedEx. FedEx is looking for the gauge. The gauge contains 8 millicuries of Cesium-137 and 40 millicuries of Am-241/Be. The serial number of the gauge is 29815. The licensee reported this incident to NRC Region III office.
*** UPDATE FROM WARD TO KNOKE AT 10:25 ON 09/27/06 ***
Notified by licensee that FedEx has located the missing Troxler gauge, Model # 3430, and has delivered it to the licensee's office in Greenwood Village, CO. Notified R3DO (Burgess), NMSS (Wastler) and Emailed ILTAB.
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.
On 09/20/06 Troxler Naperville, IL office sent a Troxler Model # 3430 to Weaver Boos Consultant office located at 5677 DTC Blvd, Suite 102, Greenwood Village, CO. The gauge was to have arrived at the Weaver Boos Consultant, Greenwood Village, CO office on 09/22/06. Licensee contacted the shipper, FedEx. FedEx is looking for the gauge. The gauge contains 8 millicuries of Cesium-137 and 40 millicuries of Am-241/Be. The serial number of the gauge is 29815. The licensee reported this incident to NRC Region III office.
*** UPDATE FROM WARD TO KNOKE AT 10:25 ON 09/27/06 ***
Notified by licensee that FedEx has located the missing Troxler gauge, Model # 3430, and has delivered it to the licensee's office in Greenwood Village, CO. Notified R3DO (Burgess), NMSS (Wastler) and Emailed ILTAB.
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.
Power Reactor
Event Number: 42969
Facility: COOK
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DALE TURINETTI
HQ OPS Officer: BILL GOTT
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DALE TURINETTI
HQ OPS Officer: BILL GOTT
Notification Date: 11/07/2006
Notification Time: 13:16 [ET]
Event Date: 09/25/2006
Event Time: 10:34 [EDT]
Last Update Date: 11/07/2006
Notification Time: 13:16 [ET]
Event Date: 09/25/2006
Event Time: 10:34 [EDT]
Last Update Date: 11/07/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JAMNES CAMERON (R3)
JAMNES CAMERON (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
INVALID SYSTEM ACTUATION - PARTIAL PHASE A CONTAINMENT ISOLATION
"This 60-day telephone notification is being made under the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) to describe an invalid actuation partial containment Phase A isolation affecting more than one system.
"On 09/25/2006 at approximately 1034 hours, while in MODE 6, 'Refueling Operations' with no core alterations in progress, a partial Containment Phase 'A' Isolation occurred without a valid initiating signal from the Train 'A' Solid State Protection System. All components responded as designed and Operations verified stable conditions in accordance with plant operating procedures.
"The following components were actuated:
1-XCR-100, Containment Air Supply Header No. 2 Containment Isolation Valve,
1-XCR-102, Control Air Supply Header No. 1 Containment Isolation Valve,
1-VCR-11, Glycol to Air Handling Units,
1-VCR-21, Glycol from Air Handling Units,
1-DCR-600, Containment Sumps to Dirty Waste Hold-up Tank Containment Isolation Valve,
1-DCR-610, Ice Condenser Fans Cooler Units Drain to WDS Containment Isolation Valve,
1-CCR-455, CCW to Reactor Support Coolers Containment Isolation Valve,
1-QCR-919, Demin Water to Containment Isolation Valve,
1-QRV-51, Pressurizer Auxiliary Spray Line from CVCS Isolation Valve,
1-QRV-61, Alternate Charging Line to Cold Leg 1 Isolation Valve,
1-QRV-62, Normal Charging Line to Cold Leg 4 Isolation Valve.
"All components responded as expected. The remaining Phase 'A' components did not actuate because they had been previously removed from service.
"This event was caused by an intermittent electrical connection at Universal Logic Card A313 receptacle and a failed A213 card. The inadequate receptacle spring tension on the A313 card has been corrected, and the failed A213 card has been replaced. There were no safety consequences or impacts on the health and safety of the public. The event has been entered into the Donald C. Cook Nuclear Plant's corrective action program. The NRC Senior Resident was notified of this report, time 1220, 11/7/06."
"This 60-day telephone notification is being made under the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) to describe an invalid actuation partial containment Phase A isolation affecting more than one system.
"On 09/25/2006 at approximately 1034 hours, while in MODE 6, 'Refueling Operations' with no core alterations in progress, a partial Containment Phase 'A' Isolation occurred without a valid initiating signal from the Train 'A' Solid State Protection System. All components responded as designed and Operations verified stable conditions in accordance with plant operating procedures.
"The following components were actuated:
1-XCR-100, Containment Air Supply Header No. 2 Containment Isolation Valve,
1-XCR-102, Control Air Supply Header No. 1 Containment Isolation Valve,
1-VCR-11, Glycol to Air Handling Units,
1-VCR-21, Glycol from Air Handling Units,
1-DCR-600, Containment Sumps to Dirty Waste Hold-up Tank Containment Isolation Valve,
1-DCR-610, Ice Condenser Fans Cooler Units Drain to WDS Containment Isolation Valve,
1-CCR-455, CCW to Reactor Support Coolers Containment Isolation Valve,
1-QCR-919, Demin Water to Containment Isolation Valve,
1-QRV-51, Pressurizer Auxiliary Spray Line from CVCS Isolation Valve,
1-QRV-61, Alternate Charging Line to Cold Leg 1 Isolation Valve,
1-QRV-62, Normal Charging Line to Cold Leg 4 Isolation Valve.
"All components responded as expected. The remaining Phase 'A' components did not actuate because they had been previously removed from service.
"This event was caused by an intermittent electrical connection at Universal Logic Card A313 receptacle and a failed A213 card. The inadequate receptacle spring tension on the A313 card has been corrected, and the failed A213 card has been replaced. There were no safety consequences or impacts on the health and safety of the public. The event has been entered into the Donald C. Cook Nuclear Plant's corrective action program. The NRC Senior Resident was notified of this report, time 1220, 11/7/06."