| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/07/2010 - 06/08/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45972 | Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: SHAW ENVIRONMENTAL, INC.
Region: 3
City: COLUMBUS State: OH
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/02/2010
Notification Time: 15:00 [ET]
Event Date: 05/27/2010
Event Time: [EDT]
Last Update Date: 06/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PATTY PELKE (R3DO)
ANGELA MCINTOSH (FSME)
ILTAB (via email) (ILTA)
CANADA (via fax) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text OHIO AGREEMENT STATE REPORT - THREE TRITIUM EXIT SIGNS MISSING
The following information was obtained from the State of Ohio via email:
"A contractor installed tritium self-illuminating exit signs between March 2004 and October 2005 at various locations as part of a US Army Corps of Engineers contract to renovate military recruiting centers. The contractor recently conducted an inventory of the signs it had installed and discovered that some signs were not located where the installation records indicated that they had been installed.
"The signs in question are SRB Technologies, Model BetaLux-E, containing 10 Ci of H-3. Three (3) signs identified as missing in Ohio are: S/N 004222, installation address 1300 State Street, Alliance, Ohio, 44601 and S/Ns 009242 and 009243, installation address 2531 Franks Way, Columbus, Ohio, 43232.
"The signs were not located during a physical inspection of the properties. Interviews with personnel currently occupying the sites provided no information as to the disposition of the signs. The contractor is currently replacing the H-3 signs with electric signs and is returning the H-3 signs to the manufacturer for proper disposal.
"Contractor: Shaw Environmental, Inc. of Stoughton, MA."
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
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 |
| Hospital | Event Number: 45973 | Rep Org: BRISTOL HOSPITAL
Licensee: BRISTOL HOSPITAL
Region: 1
City: BRISTOL State: CT
County:
License #: 06-02057-01
Agreement: N
Docket:
NRC Notified By: BERNARD PERCARPIO
HQ OPS Officer: BILL HUFFMAN | Notification Date: 06/02/2010
Notification Time: 15:46 [ET]
Event Date: 01/12/2010
Event Time: [EDT]
Last Update Date: 06/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
GLENN DENTEL (R1DO)
LARRY CAMPER (FSME)
| Event Text DOSE LESS THAN PRESCRIBED DOSE IN TWO SEPARATE BRACHYTHERAPY TREATEMENTS
"[Patient #1], with localized prostate cancer, had an ultrasound directed transperineal implant with 60 I-125 seeds on 1/12/2010. The total activity implanted was 20.4 mCi. Final dosimetry was based on a CT scan performed on 2/16/2010. This revealed a D90 of 8400 cGy which was lower than the prescribed dose of 14500 cGy. The patient and referring physician were notified and the patient then received supplemental external beam irradiation of the prostate with 3000 cGy delivered between 3/11/2010 and 4/08/2010. The patient is currently doing well with minimal treatment related symptoms.
"[Patient #2], with localized prostate cancer, had an ultrasound directed transperineal implant with 66 Cs-131 seeds on 1/12/2010. The total activity implanted was 186 mCi. Final dosimetry was based on a CT scan performed on 2/16/2010. This revealed a D90 of 6500 cGy which was lower than the prescribed dose of 11000 cGy. All seeds were accounted for in the final review. However, careful review of the isodose lines revealed adequate coverage of the involved areas of the prostate. The patient and referring physician were notified and the prescribing physician indicated that additional treatment was not necessary.
"[Both] events occurred due to unexpected displacement of the seeds in an inferior (caudal) direction.
"[The licensee] continues to use preplanning for all prostate brachytherapy patients with careful direct supervision of needle and seed placement. Six (6) patients have been treated with brachytherapy at Bristol Hospital since January 2010 and the final dosimetry has been acceptable for all."
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: 45974 | Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: HINKLE CONTRACTING CORPORATION
Region: 1
City: STANTON State: KY
County:
License #: 201-472-51
Agreement: Y
Docket:
NRC Notified By: MARISSA VEGA VELEZ
HQ OPS Officer: JOE O'HARA | Notification Date: 06/02/2010
Notification Time: 16:16 [ET]
Event Date: 05/25/2010
Event Time: 11:35 [CDT]
Last Update Date: 06/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GLENN DENTEL (R1DO)
LARRY CAMPER (FSME)
| Event Text AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE
"Kentucky Department for Public Health Protection and Safety was notified on May 25, 2010, by the RSO for Hinkle Contracting Corporation that a radiological incident involving an accidental crushing of a density gauge occurred at Georgetown Municipal Airport 6206 Paris Pike, Georgetown, KY. Gauge was identified by [the RSO] as a Troxler 4640B Thin Layer Density Gauge. Troxler Gauge containing 9 milliCuries of Cs-137 had been crushed when an asphalt roller struck it. Based upon exposure rate measurements, visual verification, and review of Troxler 4640B specification data, it was determined by the [State of Kentucky] Radiation Health Branch that the radiation source had not been compromised." |
| Power Reactor | Event Number: 45979 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: RUSSELL WARD
HQ OPS Officer: DONG HWA PARK | Notification Date: 06/06/2010
Notification Time: 03:10 [ET]
Event Date: 06/06/2010
Event Time: 02:38 [EDT]
Last Update Date: 06/07/2010 | Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
PATTY PELKE (R3DO)
MELANIE GALLOWAY (NRR)
SCOTT MORRIS (IRD)
JACK GROBE (NRR)
MARK SATORIUS (R3)
MARY ANN DOYLE (DHS)
DWIGHT FULLER (FEMA)
|
| 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 AUTOMATIC REACTOR SCRAM DUE TO PARTIAL LOSS OF OFFSITE POWER
"Reactor shutdown. All control rods inserted. Maintaining reactor vessel level with reactor core isolation cooling. Maintaining reactor vessel pressure with reactor core isolation cooling. [Automatic] Reactor scram due to loss of division 2 offsite power. Classification code: Unusual Event (HU1) Natural Destruction Phenomena Affecting the Protected Area."
The licensee declared a Notification of Unusual Event at 0253 EDT. All rods fully inserted and decay heat is being removed by the main condensers. Division 1 buses are being powered by 1 of 3 offsite feeds and division 2 buses are being powered by the Emergency Diesel Generators.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM JEFF GROFF TO DONG PARK AT 0425 EDT ON 6/6/2010 * * *
"Division 2 power provided by Emergency Diesel Generators number 13 and 14. Classification Alert Code: (HA1) Natural Destruction Phenomena Affecting the Plant Vital Area. Main condenser is the heat sink."
The licensee declared an Alert at 0417 EDT. The reactor remains stable in Mode 3. Physical damage to the auxiliary and the turbine buildings were noticed after an initial inspection.
The licensee has notified the NRC Resident Inspector. Notified R3RA (Satorius), NRR (Grobe), IRD (Morris), R3DO (Pelke), NRR EO (Galloway), DHS (Doyle), FEMA (Guy), DOE(Morrone), USDA (Ussery), HHS (Standifer), and CNSC (Gdesnryxrs).
* * * UPDATE FROM JEFF GROFF TO DONG PARK AT 0603 EDT ON 6/6/2010 * * *
"At 0238 [EDT], severe weather caused a loss of 345KV [switchyard power]. Reactor scrammed from a turbine trip. Plant is stabilized with RPV [Reactor Pressure Vessel] water level in normal band and RPV pressure at 820 psig. RPV Pressure is being controlled on turbine BPV [By Pass Valve]. Division 2 EDG's [Emergency Diesel Generator] are supplying power to division 2 buses. Plant is currently in Alert due to physical damage to plant due to severe weather."
The NRC Senior Resident Inspector is on-site. Notified IRD (Morris), R3DO (Pelke), NRR EO (Galloway).
* * * UPDATE FROM ED KOKOSKY TO DONG PARK AT 0247 EDT ON 6/7/2010 * * *
"There is no release of radiological materials. No further potential exists for uncontrolled release of radioactive materials to the environment. The Reactor is shut down. Reactor pressure and temperature are within normal bands. Offsite electrical feeds to the site have been restored. An overall damage assessment has been prepared and reviewed to ensure no conditions exist that would create an entry condition to the Emergency Plan. Plant repairs will be accomplished through site processes."
At 0220 EDT on 6/7/10, the licensee has terminated from the Alert classification.
The licensee has notified the NRC Resident Inspector. Notified R3RA (Satorius), NRR (Grobe), IRD (Grant), R3DO (Pelke), NRR EO (Galloway), DHS (Doyle), FEMA (Blankenship), DOE(Bailey), USDA (Ussery), HHS (Peagler), and CNSC (Gdesnryxrs). |
| Power Reactor | Event Number: 45981 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BILL DUVALL
HQ OPS Officer: DONG HWA PARK | Notification Date: 06/07/2010
Notification Time: 11:03 [ET]
Event Date: 04/16/2010
Event Time: 19:15 [EDT]
Last Update Date: 06/07/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
STEVEN VIAS (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 86 | Power Operation | Event Text INVALID SPECIFIED SYSTEM ACTUATION
"Invalid actuation of ECCS for boiling water reactors (BWRs) including: high-pressure and low-pressure core spray systems; high pressure coolant injection system; low pressure injection function of the residual heat removal system.
"The following information is provided as a 60 day telephone notification to NRC under 10 CFR 50.73(a)(1) in lieu of submitting a written LER to report a condition that resulted in an invalid actuation of the 10CFR50.73(a)(2)(iv)(B) system checked above. NUREG1022 Revision 2 identifies the information that needs to be reported as discussed below.
"This report is being made under 10CFR50.73(a)(2)(iv)(A). On April 16, 2010, at 1717 EDT, Unit 1 received a false ECCS (Emergency Core Cooling System) Loss Of Cooling Accident (LOCA) signal on high drywell pressure. Based on plant data, all plant conditions were normal prior to event. Investigation identified an ATTS Slave Card failed in one of the Card File Racks. The Card File Rack contains ten (10) cards with two (2) being Master Trip Units (MTUs) that actuate on high drywell pressure. For initiation of an ECCS LOCA signal, both of the MTUs in the card file rack would have had to actuate. Cause of the event appears to be a momentary drop in supply voltage on the card file rack due to the failed slave card that lowered the set point of the MTUs to a point where they tripped. The set point is an internal voltage setting within the MTU. The failed ATTS cards have been replaced.
"Actuations: Core Spray A and B pumps started; Residual Heat Removal A, B, C, D pumps started; Diesel Generator 1A, 1B, and 1C started; Standby Plant Service Water Pump started; Plant Service Water 1A pump started (it had been in standby); Plant Service Water Valves 1P41-F310A, B, C, D closed (These are the Turbine Building isolation valves); Turbine Building Chiller B tripped; Main Control Room Environmental Control trains A and B started; HPCI Started but was secured prior to injection; Cooling Tower fans on towers A, B, C tripped.
"Reactor Water Level was normal at +37 inches and the highest Drywell Pressure indicated was 1.25 psig."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45982 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: RONALD CARPINO
HQ OPS Officer: BILL HUFFMAN | Notification Date: 06/07/2010
Notification Time: 13:47 [ET]
Event Date: 06/07/2010
Event Time: 10:20 [EDT]
Last Update Date: 06/07/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
PAMELA HENDERSON (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text NOTIFICATION OF FATALITY
"At approximately 0918 EDT a contract diver entered the Indian Point discharge canal for scheduled work on the outfall structure. At approximately 0928 hours the diver was unresponsive to communications and was pulled from the water. An Emergency Medical Technician (EMT) stationed at the job site performed emergency medical assistance and an ambulance was requested. The diver was transported to a local hospital where the diver was pronounced dead at 1020 EDT. An investigation of the event is in progress."
The licensee has notified State and local authorities. The licensee will also be notifying OSHA and plans to issue a press release. |
| Power Reactor | Event Number: 45985 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/07/2010
Notification Time: 22:13 [ET]
Event Date: 06/07/2010
Event Time: 18:44 [CDT]
Last Update Date: 06/07/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
DALE POWERS (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 80 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO VOIDING IN THE COMPONENT COOLING WATER SYSTEM
"[The licensee] commenced Tech Spec required shutdown at 1844 [CDT] on 6/7/10. Shutdown was commenced due to entry into [Technical Specification] 3.0.3 at 1828 hrs. on 6/7/10 due to voids in Component Cooling Water (CCW) Train causing both trains to be inoperable.
"While operating in Mode 1 at 100% rated thermal power, voids were found in the 'B' CCW train that was above the acceptable volume. 'B' CCW train was declared inoperable at 1828 hrs.. 'A' CCW train was already inoperable due to voids. Both trains inoperable required entry into Tech Spec 3.0.3. Shutdown was commenced at 1844 hrs. All system functioned normally. [The NRC] Senior Resident Inspector has been contacted."
During the shutdown, the licensee determined that voiding in the "B" train didn't reach the level required to render the "B" train inoperable and stopped the shutdown at 80% power. The licensee intends to begin a power ascension after re-verifying the voiding in the "B" train. | |