| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/21/2009 - 08/24/2009 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45271 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: MACTEC ENGINEERING & CONSULTING, INC.
Region: 1
City: CHANTILLY State: VA
County:
License #: 107-133-1
Agreement: Y
Docket:
NRC Notified By: MICHAEL WELLING
HQ OPS Officer: BILL HUFFMAN | Notification Date: 08/18/2009
Notification Time: 10:10 [ET]
Event Date: 08/14/2009
Event Time: 08:00 [EDT]
Last Update Date: 08/18/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RICHARD CONTE (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - TROXLER GAUGE RUN OVER BY CONSTRUCTION EQUIPMENT
The following information was received from the State via facsimile:
"The Virginia Radioactive Materials Program received a telephone message on Monday, August 17, 2009 (message was left at 6:30 PM on Friday, August 14, 2009) concerning the licensee's Troxler gauge. The gauge had been run over by a roller while in operation. The Radioactive Materials Program returned the call to the licensee's RSO at 7:45 AM on Monday, August 17. The accident occurred at 8AM on Friday, August 14. The guide rod and source rod were broken off the gauge, but the instrument's case was otherwise intact. The operator of the gauge placed it into the shipping container, placed the shipping container in the locked box on the back of the pickup truck, and transported the gauge back to the shop. The licensee's RSO surveyed the gauge and took wipe samples. Two radiation safety specialists from the Radioactive Materials Program visited the licensee, arriving at 12:00 noon on Monday, August 17. The radiation safety specialists visually inspected the gauge, took survey measurements with a maximum level of 100 mR/hr at the surface and 4 mR/hr at one meter from the shipping container, and also took wipe samples. When the gauge was run over, it was operating in "backscatter" mode, so the Cs-137 source was within the case of the gauge. The accident did damage the shutter mechanism for the Cs-137 source so that it could not be closed. The gauge in its shipping container was placed in a locked storage cabinet in the shop pending disposal. The local Troxler vendor had been contacted by the licensee's RSO. The licensee was advised to give the vendor the current radiation survey of the package and to obtain the results of the wipe tests prior to allowing the vendor to transport the gauge. The radiation safety specialists also visited the site of the accident, where they surveyed the ground at the site of the accident, the roller that ran over the gauge, and the pickup truck that transported the gauge. All surveyed areas at the accident location were at background."
VA Event Report ID No.: VA-2009-03 |
| General Information or Other | Event Number: 45272 | Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: TTM TECHNOLOGIES
Region: 4
City: REDMOND State: WA
County:
License #: R0012
Agreement: Y
Docket:
NRC Notified By: BRANDIN KETTER
HQ OPS Officer: JOHN KNOKE | Notification Date: 08/18/2009
Notification Time: 12:33 [ET]
Event Date: 08/06/2009
Event Time: [PDT]
Last Update Date: 08/18/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM JONES (R4DO)
ANGELA MCINTOSH (FSME)
EMAIL ONLY (ILTA)
CANADA VIA FAX ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - NINE MISSING PO-210 AND PM-147 SEALED SOURCES
"On 19 June 2009, TTM Technologies in Redmond was contacted as part of a routine check of their inventory of generally licensed devices. It was discovered at this time that the facility was closing and that the gauges and static eliminators had been sent to TTM Technologies facilities in other states. TTM Technologies has since tracked down as many of the missing devices as possible. Those facilities that have received sources have been informed of the reporting requirements and regulations surrounding those generally licensed devices. NRD, Inc. was contacted to see if any of the remaining unaccounted for sources had been returned to them. They have not been. The remaining missing sources are being reported as lost.
"This report lists eight devices/sources. A ninth device/source (exactly the same as number 8 except for the serial number) is being included here instead. This device/source is serial number A2CK423. Seven of the nine devices/sources are Po-210 static eliminators and have gone through more than ten half-lives. The other two devices are sources of Pm-147 in beta backscatter gauges and have gone through approximately 8 half-lives. It is therefore concluded that the missing sources are of little threat to human health and safety.
"Source of Radiation:
Source Number: 1
Form of Radioactive Material: SEALED SOURCE
Radionuclide: PM-147
Source Use: OTHER
Activity:0.9E-3 Ci 0.0333 GBq
Manufacturer: OXFORD INSTRUMENT
Model Number: GM-1
Serial Number: 75125P
"Source Number: 2
Form of Radioactive Material: SEALED SOURCE
Radionuclide: PM-147
Source Use: OTHER
Activity:0.6E-3 Ci 0.0222 GBq
Manufacturer: OXFORD INSTRUMENT
Model Number: GM-1
Serial Number: 65986P
"Source Number: 3
Form of Radioactive Material: SEALED SOURCE
Radionuclide: PO-210
Source Use: STATIC ELIMINATOR
Activity:0.05513 Ci 2.03981 GBq
Manufacturer: NRD, INC
Model Number: P-2001
Serial Number: A2EA910
"Source Number: 4
Form of Radioactive Material: SEALED SOURCE
Radionuclide: PO-210
Source Use: STATIC ELIMINATOR
Activity:0.05513 Ci 2.03981 GBq
Manufacturer: NRD, INC
Model Number: P-2001
Serial Number: A2BM653
"Source Number: 5
Form of Radioactive Material: SEALED SOURCE
Radionuclide: PO-210
Source Use: STATIC ELIMINATOR
Activity:0.05513 Ci 2.03981 GBq
Manufacturer: NRD, INC
Model Number: P-2021
Serial Number: A2DY847
"Source Number: 6
Form of Radioactive Material: SEALED SOURCE
Radionuclide: PO-210
Source Use: STATIC ELIMINATOR
Activity:0.010 Ci 0.37 GBq
Manufacturer: NRD, INC
Model Number: P-2021
Serial Number: A2CE789
"Source Number: 7
Form of Radioactive Material: SEALED SOURCE
Radionuclide: PO-210
Source Use: STATIC ELIMINATOR
Activity:0.010 Ci 0.37 GBq
Manufacturer: NRD, INC
Model Number: P-2021
Serial Number: A2BM653
"Source Number: 8
Form of Radioactive Material: SEALED SOURCE
Radionuclide: PO-210
Source Use: STATIC ELIMINATOR
Activity:0.010 Ci 0.37 GBq
Manufacturer: NRD, INC
Model Number: P-2021
Serial Number: A2CK423
"Corrective Actions: 1 Personnel received additional training."
Washington state reporting requirement WAC 246-221-240
Washington Report No: WA090061
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: 45278 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAVE DEES
HQ OPS Officer: JOHN KNOKE | Notification Date: 08/19/2009
Notification Time: 20:38 [ET]
Event Date: 08/19/2009
Event Time: 15:49 [CDT]
Last Update Date: 08/21/2009 | 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):
WILLIAM JONES (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP CAUSED BY TURBINE TRIP
"Wolf Creek experienced a reactor trip at 1549 CDT. The first out annunciator was TURBINE TRIP and P9 Reactor TRIP. At approximately the same time the unit experienced a momentary loss of offsite power.
"The emergency diesel generators started [and loaded] as expected to supply power to the safety busses due to the loss of offsite power. Auxiliary Feedwater and Feedwater Isolation actuations occurred as expected. All control rods inserted into the core during the trip. All Reactor Coolant Pumps tripped due to the loss of offsite power. Decay heat was initially being removed by the Steam Generator Atmospheric Relief Valves.
"Presently the plant is stable in Mode 3. The 'D' Reactor Coolant Pump has been restarted. The licensee is continuing to investigate the cause of the trip."
The atmospheric relief valves lifted for approximately 10 minutes, however there was no primary to secondary leakage. Both A & B EDG's loaded for about 2 minutes. At the present time the electrical lineup is normal and the EDG's are shutdown. Plant is at Normal Operating Pressure and just below Normal Operating Temperature. Decay heat and S/G levels are being maintained with the Auxiliary Feedwater pumps.
The licensee has notified the NRC Resident Inspector. The Licensee may issue a press release on this event.
* * * UPDATE FROM DAVE DEES TO VINCE KLCO AT 1135 EDT ON 8/21/2009 * * *
The atmospheric relief valves lifted for approximately 2 minutes, not 10 minutes as stated above. Also the A & B EDG's did not load for only 2 minutes. Actually "the B Safety Bus was paralleled to its normal off site source and the B Emergency Diesel was realigned for auto-start at 1740. The A Safety Bus was paralleled to its normal off site source and the A Emergency Diesel was realigned for auto-start at 1844."
Notified the R4DO (Jones). |
| Power Reactor | Event Number: 45281 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAVE DEES
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/21/2009
Notification Time: 11:22 [ET]
Event Date: 08/21/2009
Event Time: 06:48 [CDT]
Last Update Date: 08/21/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
WILLIAM JONES (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text FEED WATER ISOLATION DUE TO HIGH STEAM GENERATOR WATER LEVEL
"Turbine trip and Feed [Water] Isolation Signal generated as result of high level in 'A' Steam Generator. At approximately 0648 CDT a turbine trip and Feed Water Isolation Signal was generated when the level in the 'A' Steam Generator exceeded the initiation set point of 78%. Steam Generator level returned below the initiation setpoint at approximately 0656 CDT.
"The turbine was already in the tripped condition and Feed Water Isolation Valves closed due to the plant trip that occurred at 1549 CDT on 8/19/2009 (Reference EN# 45278).
"Steam Generators are being fed with the motor driven Auxiliary Feed Water Pumps. Decay heat removal is via the Steam Generator Atmospheric Relief Valves. The plant is in Mode 3 with Reactor Coolant System pressure at approximately 2235 psig and temperature at approximately 561 F.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 45282 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WILLIAM BAKER
HQ OPS Officer: JOHN KNOKE | Notification Date: 08/21/2009
Notification Time: 15:02 [ET]
Event Date: 08/21/2009
Event Time: 09:52 [CDT]
Last Update Date: 08/21/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
| Person (Organization):
SCOTT SHAEFFER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOGIC FOR COMMON ACCIDENT SIGNAL IS FLAWED FOR SAFE SHUTDOWN INSTRUCTION
"Safe Shutdown Instruction (SSI) 0-SSI-9 for an Appendix R fire event requires for a Unit 1 Safe Shutdown success path that 4kV Shutdown Board A be supplied by Diesel Generator 3A via 4kV Shutdown Board 3EA. During a Unit 2 simulator exercise utilizing this SSI, reactor vessel water level lowered to Level 1 (-122 inches) causing a Common Accident Signal (CAS) trip of 4 Kv Shutdown Board 3EA inter-tie breaker (1844) that de-energized 4kV Shutdown Board A. This condition will not support the Unit 1 success path for alternate decay heat removal during an Appendix R fire. The 4 Kv Shutdown Board A must be re-energized by closing breaker 1844. For this SSI (0-SSI-9) the subsequent automatic start of the 2A RHR and Core Spray pumps in response to the CAS logic has not been considered in the development of the SSIs. In response to this condition, compensatory measures have been implemented to provide equivalent shutdown capability, documented on Fire Protection Impairment Permit (FPIP) 09-1920.
"This event is reportable within 8 hours under 10CFR50.72 (b)(3)(v)(A) - Any event or condition that results in the condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: Shut down the reactor and maintain it in a safe shutdown condition. This event is also a reportable within 60 days under 10CFR50.73(a)(2)(v)(A) - Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to: Shut down the reactor and maintain it in a safe shutdown condition.
"This condition has been documented in the BFN Corrective Action program as PER# 177130. Unit 1, 2 and 3 remain at 100% power and are not affected by this event. The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 45284 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MICHAEL STONES
HQ OPS Officer: JOHN KNOKE | Notification Date: 08/23/2009
Notification Time: 21:52 [ET]
Event Date: 08/23/2009
Event Time: 17:50 [EDT]
Last Update Date: 08/23/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RICHARD CONTE (R1DO)
|
| 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 UNPLANNED INOPERABILITY OF THE HIGH PRESSURE CORE SPRAY SYSTEM
"A momentary alarm for loss of HPCS system DC control power was received in the NMP2 control room. Troubleshooting has determined that a loose connection existed at a fuse block in the DC control power circuitry. The HPCS system was declared inoperable and Technical Specification 3.5.1, Condition B, was entered at 1715. In accordance with Condition B, the Reactor Core Isolation Cooling (RCIC) system was verified to be operable.
"Repairs were subsequently completed and the HPCS system has been declared operable as of 2046."
The licensee has notified the NRC Resident Inspector |
| Power Reactor | Event Number: 45285 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: MIKE MacLENNAN
HQ OPS Officer: VINCE KLCO | Notification Date: 08/24/2009
Notification Time: 04:06 [ET]
Event Date: 08/24/2009
Event Time: 02:40 [CDT]
Last Update Date: 08/24/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JOHN GIESSNER (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TSC AIR FILTRATION SYSTEM INOPERABLE DUE TO PLANNED MAINTENANCE
"Planned maintenance activities will commence today (August 24, 2009) on the Quad Cities Station Technical Support Center (TSC) ventilation air filtration system. The maintenance will be completed in approximately 36 hours, and is scheduled to be worked continuously to minimize out-of-service time.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing procedures; contingency plans are in place to expeditiously restore the TSC ventilation to an operable status. If TSC evacuation is warranted due to radiological conditions, the facility will be relocated in accordance with existing procedures.
"This event is reportable per 10CFR50.72(b)(3)(xiii) since the scheduled maintenance affects an emergency response facility.
"The NRC Resident Inspector has been notified." | |