| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/24/2007 - 05/25/2007 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 43262 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: WAYNE BENTLEY
HQ OPS Officer: JEFF ROTTON | Notification Date: 03/28/2007
Notification Time: 17:39 [ET]
Event Date: 03/28/2007
Event Time: 13:41 [CDT]
Last Update Date: 05/24/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JULIO LARA (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 98 | Power Operation | 98 | Power Operation | Event Text HPCI INOPERABLE DUE TO SURVEILLANCE TEST FAILURE
"During the running of the HPCI operability, STP 3.5.1-05, the discharge relief, PSV 2302, lifted and failed to reseat. The relief valve discharges to the Torus Area floor and was captured in the floor drain sump system. The STP was aborted and the HPCI system was declared inoperable.
The licensee notified the NRC Resident Inspector.
* * * RETRACTION ON 05/24/07 AT 1302 EDT BY ROBERT MURRELL TAKEN BY MACKINNON * * *
"The purpose of this notification is to retract a previous report made on 3/28/07 at 1739 (ET) (EN 43262). Notification of this issue to the NRC on 3/28/07 was initially made as a result of declaring HPCI inoperable during the running of the HPCI operability, Surveillance Test Procedure (STP) 3.5.1-05. HPCI was declared inoperable when the discharge relief, PSV 2302, lifted and failed to reseat. The relief valve discharges to the Torus Area floor and was capture in the floor drain sump system. The STP was aborted and HPCI system was declared inoperable.
"Since the initial report, Engineering had determined that the HPCI system was capable of performing its safety function.
"Engineering concluded that the stuck open HPCI discharge pressure relief valve would not have prevented HPCI from fulfilling its design function of providing adequate high pressure makeup to the reactor vessel. Existing operating procedure guidance would have ensured that HPCI injection would not have been terminated in the event it was needed under accident conditions, even with PSV2302 stuck open. Operating procedure guidance and Reactor Building floor drain sump pump capacity are adequate to prevent a flooding concern.
"This event is not considered a Safety System Functional Failure and is not reportable to the NRC as a Licensee Event Report (LER) per 10 CFR 50.73."
The NRC Resident Inspector was notified of this retraction by the licensee. R3DO (Richard Skokowski) notified. |
| General Information or Other | Event Number: 43377 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: LARGO MEDICAL CENTER
Region: 1
City: LARGO State: FL
County:
License #: 1284-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/21/2007
Notification Time: 14:40 [ET]
Event Date: 05/17/2007
Event Time: [EDT]
Last Update Date: 05/22/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
EUGENE COBEY (R1)
MICHELE BURGESS (FSME)
| Event Text AGREEMENT STATE REPORT - MEDICAL EVENT
"RSO contacted this office [Florida Bureau of Radiation Control] at 1335 hours 21-May-2007 to report a medical event. Patient has metastatic cancer and no thyroid. Doctor prescribed a whole body scan. Technologist gave patient a therapy dosage for the cancer, instead of the scan. Doctor and patient notified of misadministration. This incident referred to the radioactive materials office for investigation. No further action will be taken on this incident."
The therapy dosage administered was 26.8 mCuries of I-131 in liquid form.
Florida Incident number: FL07-081
* * * UPDATE BY E-MAIL AT 1547 EDT ON 5/22/2007 FROM C. FLANNERY TO JEFF ROTTON * * *
"This event has been reviewed and determined to be a reportable medical event."
A "Medical Event" may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| General Information or Other | Event Number: 43380 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CONVERSE CONSULTANTS
Region: 4
City: MONROVIA State: CA
County:
License #: 4507-19
Agreement: Y
Docket:
NRC Notified By: DONELLE KRAJEWSKI
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/22/2007
Notification Time: 12:07 [ET]
Event Date: 05/22/2007
Event Time: 05:15 [PDT]
Last Update Date: 05/22/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CLAUDE JOHNSON (R4)
GREG MORELL (FSME)
ILTAB via email ()
CNSNS (Mexico - fax) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text CALIFORNIA AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE
"At 0830 on 5-22-07, the radiation safety officer notified [California Radiological Health Branch] that a vehicle (Chevy Silverado with an attached camper shell) was stolen with a nuclear gauge locked in the camper shell (Troxler, model 3440, #18250 with 8 mCi Cs-137 & 40 mCi Am-241:Be). The gauge was locked inside a transport case, the transport case was chained, blocked, & braced in the camper shell. The gauge user does not remember if the door to the camper shell was locked. The gauge user had not secured and locked the club to the steering wheel and he does not think the handle of the gauge was locked. The driver discovered the theft around 0515 this morning when he returned to his vehicle after being in a donut shop for approximately 10 minutes. The donut shop is located in Bellflower on the corner of Alondra and Eucalyptus. The Lakewood Police Department were notified and they took the report of the theft. The RSO was asked to notify [California Radiological Health Branch] immediately if the gauge was recovered. The licensee will be cited for failing to properly secure the gauge. Corrective actions: The licensee will counsel the gauge user, will provide refresher training to all gauge users on the required security of the gauge while in transit, and will perform unannounced inspections of each gauge user's vehicle to ensure they are following the company's established policies and procedures regarding the security of gauges while in transit."
Lakewood Police Report #: 607-14202-1337-093
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.
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source. |
| Power Reactor | Event Number: 43381 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TIM BOLAND
HQ OPS Officer: BILL HUFFMAN | Notification Date: 05/24/2007
Notification Time: 04:42 [ET]
Event Date: 05/24/2007
Event Time: 02:11 [CDT]
Last Update Date: 05/24/2007 | 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):
BRIAN BONSER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 3 | Startup | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO ELECTRO-HYDRAULIC CONTROL (EHC) SYSTEM LEAK
"On 05/24/2007 at 0211 CDT Browns Ferry Unit 1 initiated a Manual reactor SCRAM due to an Electro-Hydraulic Control (EHC) System pressure lowering and reservoir level lowering due to an EHC system leak. The leak was from #6 Main Turbine Combined Intermediate Valve (CIV). All Systems responded as required to the manual SCRAM signal. No Emergency Core Cooling System (ECCS) initiations occurred as a result of the manual SCRAM signal. Reactor water level was maintained in the normal band during the SCRAM. There were no Primary Containment Isolation signals received during the SCRAM. The EHC leak was stopped due to reservoir level depletion and EHC pumps being secured. There were no indications of main steam relief valves (MSRVs) opening. Reactor pressure is being controlled using Main Steam Line Drains. Reactor Level is being maintained in band using Control Rod Drive pumps. Repair of the EHC leak is in progress."
The Scram was characterized as uncomplicated. All rods fully inserted. The only significant equipment out of service at the time was RCIC. When the leak was initially discovered, it was about 60 drops per minute. When repairs were attempted, the piping separated and approximately 600 gallons of EHC fluid was discharged out the break onto the turbine building floor. Cleanup of the EHC fluid is in progress and environmental monitoring is in place to assure no offsite release of the spill.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43382 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KEN McKUNE
HQ OPS Officer: STEVE SANDIN | Notification Date: 05/24/2007
Notification Time: 05:11 [ET]
Event Date: 05/24/2007
Event Time: 02:32 [EDT]
Last Update Date: 05/24/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
EUGENE COBEY (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 Standby | Event Text AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL
"This 4-hour notification is being made to report that Salem Unit 2 automatically tripped on low steam generator water level. The automatic trip was preceded by lowering steam generator feed pump suction pressure, followed by the trip of both steam generator feed pumps on low suction pressure. The cause of the low suction pressure was due to a condensate system breach that occurred in the Condensate Polisher building. The condensate polishing system has been isolated and condensate pressure has stabilized.
"Salem Unit 2 is currently in mode 3 with reactor coolant system temperature at 547 degrees with pressure at 2235 psig. 21, 22, and 23 auxiliary feedwater pumps started automatically, as expected, due to the low steam generator level. Decay heat removal is via the steam dumps to the main condenser. All equipment functioned as designed. There were no personnel injuries.
"A 15 minute notification was made to the State of New Jersey due to hydrazine laden water exiting the Condensate Polisher building and entering the storm drainage system."
All control rods fully inserted following the reactor trip. Emergency Diesel Generator are available, if needed. The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 43384 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: BRUCE SHICK
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/24/2007
Notification Time: 12:23 [ET]
Event Date: 05/24/2007
Event Time: 11:00 [EDT]
Last Update Date: 05/24/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
EUGENE COBEY (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMERGENCY OPERATIONS FACILITY OUT OF SERVICE FOR PLANNED MAINTENANCE
"EOF resources OOS due to planned maintenance of electrical supply transfer switch. No power available to EOF."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 13:39 ON 5/24/07 FROM BRUCE SHICK TO MARK ABRAMOVITZ * * *
Power was restored to the EOF at 13:30 on 5/24/07. |
| Fuel Cycle Facility | Event Number: 43385 | Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: TONY HUDSON
HQ OPS Officer: JOHN MacKINNON | Notification Date: 05/24/2007
Notification Time: 12:26 [ET]
Event Date: 05/24/2007
Event Time: 08:15 [CDT]
Last Update Date: 05/24/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
BRIAN BONSER (R2)
GREG MORELL (FSME)
| Event Text OFFSITE NOTIFICATION MADE TO ANOTHER GOVERNMENT AGENCY
"A required 24-hour notification was made by Paducah Regulatory Affairs to EPA Region IV in Atlanta, GA at 0815, 5-24-2007. The notification was made concerning a PCB spill of greater than the agreed upon action level of 10 pounds of PCBs confined within a building.
"The approximate 3 gallon PCB oil spill was from an electrical capacitor located inside the C-333 Process Building. The oil spilled onto a concrete floor and was contained to the immediate area. The area was flagged and posted as a PCB spill area and clean up is in progress.
"This event is reportable as a 4 hour event as required by the NRC NUREG 1022, a specific report made to a government agency. PGDP Assessment and Tracking Report No. ATR-07-1362; PGDP Event Report No. PAD-2007-06; Worksheet No. 43385."
The NRC Resident Inspector was notified of this event by the licensee. |
| Power Reactor | Event Number: 43387 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ROBERT MURRELL
HQ OPS Officer: JOHN MacKINNON | Notification Date: 05/24/2007
Notification Time: 12:54 [ET]
Event Date: 04/01/2007
Event Time: 02:49 [CDT]
Last Update Date: 05/24/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
RICHARD SKOKOWSKI (R3)
|
| 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 INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) ACTUATION DUE TO A FAILED RELAY COIL
"This 60-day telephone notification is being made under reporting requirements specified by 10CFR50.73 (a)(2)(iv)(A) to describe an invalid actuation of a containment isolation signal affecting more than one system.
"At 0249 on April 1, 2007, with the Duane Arnold Energy Center (DAEC) operating at 100% power, an invalid Group 3 isolation on the 'B' side of PCIS occurred. Group 3 isolation signals were generated for Primary Containment Isolation Valves for Drywell and Torus Ventilation, and Purge, Containment Nitrogen Compressor Suction and Discharge; Recirculation Pump Seals, and Post Accident Sample System.
"This event was caused by a failed (open) relay coil in a Potter Brumfield model KH4690 24VDC relay in the 'B' Fuel Pool Exhaust Radiation Monitor logic.
"All equipment responded in accordance with the plant design. Specifically, all actuations were complete and successful.
"There were no safety consequences or impacts on the health and safety of the public. The event was entered into DAEC's corrective action program for resolution.
"The licensee notified the NRC Resident Inspector." | |