Event Notification Report for August 27, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/26/2009 - 08/27/2009
EVENT NUMBERS
4530445305453064530745308
Other Nuclear Material
Event Number: 45304
Rep Org: BANDMILL COAL CORPORATION
Licensee: BANDMILL COAL CORPORATION
Region: 1
City: YOLYN State: WV
County:
License #: GL-700079-13
Agreement: N
Docket:
NRC Notified By: WILLIAM NEWSOME
HQ OPS Officer: JASON KOZAL
Licensee: BANDMILL COAL CORPORATION
Region: 1
City: YOLYN State: WV
County:
License #: GL-700079-13
Agreement: N
Docket:
NRC Notified By: WILLIAM NEWSOME
HQ OPS Officer: JASON KOZAL
Notification Date: 08/27/2009
Notification Time: 12:51 [ET]
Event Date: 08/27/2009
Event Time: 05:00 [EDT]
Last Update Date: 08/27/2009
Notification Time: 12:51 [ET]
Event Date: 08/27/2009
Event Time: 05:00 [EDT]
Last Update Date: 08/27/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(4) - FIRE/EXPLOSION
10 CFR Section:
30.50(b)(4) - FIRE/EXPLOSION
Person (Organization):
JOHN WHITE (R1DO)
ANGELA MCINTOSH (FSME)
ANTHONY McMURTRAY (IRD)
JOHN WHITE (R1DO)
ANGELA MCINTOSH (FSME)
ANTHONY McMURTRAY (IRD)
FIRE INVOLVING RADIOACTIVE MATERIALS
The licensee facility experienced a large fire on 08/27/09 starting at approximately 0500. The facility involved houses 4 devices containing radioactive materials. These devices are used for process control. Three (3) of the devices contain 200 milliCuries of Cs-137 (Texas Nuclear Model #5202) and one device contains 100 milliCuries of Cs-137 (Texas Nuclear Model #7062BP). Currently the floors that contain the devices are believed to be intact. This however may change as the condition of the building degrades. The Mine Safety and Health Administration (MSHA) is currently not allowing anyone into the facility due to the treacherous conditions. It is not known when the licensee will be able to determine the integrity of the sources.
The Logan County, West Virginia Fire Department is responding to the fire, are aware of the sources, and are wearing appropriate personnel protective equipment. The firefighters have been using a Geiger counter to ensure radiological safety. Initial surveys of firefighters that entered the building were negative.
The source of the fire is still under investigation, but the licensee does not believe the fire to be suspicious in nature.
The licensee facility experienced a large fire on 08/27/09 starting at approximately 0500. The facility involved houses 4 devices containing radioactive materials. These devices are used for process control. Three (3) of the devices contain 200 milliCuries of Cs-137 (Texas Nuclear Model #5202) and one device contains 100 milliCuries of Cs-137 (Texas Nuclear Model #7062BP). Currently the floors that contain the devices are believed to be intact. This however may change as the condition of the building degrades. The Mine Safety and Health Administration (MSHA) is currently not allowing anyone into the facility due to the treacherous conditions. It is not known when the licensee will be able to determine the integrity of the sources.
The Logan County, West Virginia Fire Department is responding to the fire, are aware of the sources, and are wearing appropriate personnel protective equipment. The firefighters have been using a Geiger counter to ensure radiological safety. Initial surveys of firefighters that entered the building were negative.
The source of the fire is still under investigation, but the licensee does not believe the fire to be suspicious in nature.
Power Reactor
Event Number: 45305
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DANIEL HAUTALA
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DANIEL HAUTALA
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/27/2009
Notification Time: 18:20 [ET]
Event Date: 08/27/2009
Event Time: 09:20 [MST]
Last Update Date: 08/27/2009
Notification Time: 18:20 [ET]
Event Date: 08/27/2009
Event Time: 09:20 [MST]
Last Update Date: 08/27/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
GEOFFREY MILLER (R4DO)
GEOFFREY MILLER (R4DO)
| 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 |
CONFIRMED POSITIVE FITNESS FOR DUTY TEST BY NON-LICENSED SUPERVISOR
A non-licensed employee supervisor had a confirmed positive for illegal drugs during a random fitness for duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
A non-licensed employee supervisor had a confirmed positive for illegal drugs during a random fitness for duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
Power Reactor
Event Number: 45306
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JAMES READY
HQ OPS Officer: JASON KOZAL
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JAMES READY
HQ OPS Officer: JASON KOZAL
Notification Date: 08/27/2009
Notification Time: 21:40 [ET]
Event Date: 08/27/2009
Event Time: 19:45 [EDT]
Last Update Date: 08/27/2009
Notification Time: 21:40 [ET]
Event Date: 08/27/2009
Event Time: 19:45 [EDT]
Last Update Date: 08/27/2009
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JOHN WHITE (R1DO)
JOHN WHITE (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP
"At 1945 on 8/27/09 Indian Point Unit #3 automatically tripped due to a turbine trip signal. The cause for this automatic trip is under investigation. All auxiliary feedwater pumps started as expected. All control rods inserted as expected. Currently, Indian Point #3 is in Mode 3. The reactor coolant system is at Normal Operating Temperature, Pressure and Level. Offsite power is available and supplying all safeguards busses. Heat removal is to the main condenser via the steam dumps. Indian Point Unit 2 is unaffected and remains in Mode 1 at 100% power. The [NRC] Resident Inspector has been notified."
"At 1945 on 8/27/09 Indian Point Unit #3 automatically tripped due to a turbine trip signal. The cause for this automatic trip is under investigation. All auxiliary feedwater pumps started as expected. All control rods inserted as expected. Currently, Indian Point #3 is in Mode 3. The reactor coolant system is at Normal Operating Temperature, Pressure and Level. Offsite power is available and supplying all safeguards busses. Heat removal is to the main condenser via the steam dumps. Indian Point Unit 2 is unaffected and remains in Mode 1 at 100% power. The [NRC] Resident Inspector has been notified."
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 45307
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: PETE SNYDER
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: PETE SNYDER
Notification Date: 08/28/2009
Notification Time: 01:13 [ET]
Event Date: 08/27/2009
Event Time: 23:10 [EDT]
Last Update Date: 10/20/2009
Notification Time: 01:13 [ET]
Event Date: 08/27/2009
Event Time: 23:10 [EDT]
Last Update Date: 10/20/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
JOHN WHITE (R1DO)
JOHN WHITE (R1DO)
| 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 |
NON-CONSERVATIVE TECHNICAL SPECIFICATION SETPOINTS DISCOVERED
"Non-conservative Tech Spec setpoints were discovered that affected Steam Leak Detection for Unit 1 and Unit 2 [High Pressure Coolant Injection] HPCI room high differential temperatures. During a steam leak detection system design basis leak, the present temperature setpoint would not isolate the HPCI steam supply piping.
"A calculation has been performed by engineering which demonstrates that, with both room coolers secured, a design basis steam leak will result in the room ventilation differential temperature exceeding the present Tech Spec setpoints. At this time, the room unit coolers have been secured and HPCI and the associated steam leak detection system remain operable. Calculations are in-progress by engineering for changes to the high differential temperature steam leak detection setpoint."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM J. BROILET TO P. SNYDER ON 10/20/09 AT 1154 EDT * * *
"This is a retraction of the event notification made on 8/28/09 at 0113 EDT. This event (#45307) was initially reported as a condition that could have prevented fulfillment of a safety function under the requirement of 10 CFR 50.72 (b)(3)(v)(c).
"A follow-up review of the HPCI equipment room steam leak detection system calculations determined that other HPCI equipment room ambient high temperature instruments would have automatically actuated a HPCI steam line isolation during a 25 gpm design basis HPCI steam line leak event.
"Therefore, a condition did not exist at the time of discovery that could have prevented the fulfillment of the HPCI steam line isolation safety function."
The licensee notified the NRC Resident Inspector. Notified R1DO (Doerflein).
"Non-conservative Tech Spec setpoints were discovered that affected Steam Leak Detection for Unit 1 and Unit 2 [High Pressure Coolant Injection] HPCI room high differential temperatures. During a steam leak detection system design basis leak, the present temperature setpoint would not isolate the HPCI steam supply piping.
"A calculation has been performed by engineering which demonstrates that, with both room coolers secured, a design basis steam leak will result in the room ventilation differential temperature exceeding the present Tech Spec setpoints. At this time, the room unit coolers have been secured and HPCI and the associated steam leak detection system remain operable. Calculations are in-progress by engineering for changes to the high differential temperature steam leak detection setpoint."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM J. BROILET TO P. SNYDER ON 10/20/09 AT 1154 EDT * * *
"This is a retraction of the event notification made on 8/28/09 at 0113 EDT. This event (#45307) was initially reported as a condition that could have prevented fulfillment of a safety function under the requirement of 10 CFR 50.72 (b)(3)(v)(c).
"A follow-up review of the HPCI equipment room steam leak detection system calculations determined that other HPCI equipment room ambient high temperature instruments would have automatically actuated a HPCI steam line isolation during a 25 gpm design basis HPCI steam line leak event.
"Therefore, a condition did not exist at the time of discovery that could have prevented the fulfillment of the HPCI steam line isolation safety function."
The licensee notified the NRC Resident Inspector. Notified R1DO (Doerflein).
General Information or Other
Event Number: 45308
Rep Org: KARMANOS CANCER CENTER
Licensee: KARMANOS CANCER CENTER
Region: 3
City: DETROIT State: MI
County:
License #: 21-04127-06
Agreement: N
Docket:
NRC Notified By: JOE RAKOWSKI
HQ OPS Officer: HOWIE CROUCH
Licensee: KARMANOS CANCER CENTER
Region: 3
City: DETROIT State: MI
County:
License #: 21-04127-06
Agreement: N
Docket:
NRC Notified By: JOE RAKOWSKI
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/28/2009
Notification Time: 17:05 [ET]
Event Date: 08/27/2009
Event Time: 18:00 [EDT]
Last Update Date: 08/28/2009
Notification Time: 17:05 [ET]
Event Date: 08/27/2009
Event Time: 18:00 [EDT]
Last Update Date: 08/28/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
STEVE ORTH (R3DO)
GREG SUBER (FSME)
STEVE ORTH (R3DO)
GREG SUBER (FSME)
MEDICAL EVENT - PATIENT RECEIVED 60% LESS DOSE THAN PRESCRIBED
The licensee was performing reviews on past procedures when they discovered the following reportable event:
On March 3, 2009, a patient received a permanent prostate implant with a prescribed D90 dose of 144 Gy. The implant used fifty-eight I-125 seeds.
On April 3, 2009, the patient returned to the facility for a post-implant CT/dose reconstruction and it was determined that the D90 dose received by the patient was 85 Gy which is 60% of the prescribed dose.
The patient and prescribing physician were notified and the patient underwent an external radiation treatment to compensate.
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.
The licensee was performing reviews on past procedures when they discovered the following reportable event:
On March 3, 2009, a patient received a permanent prostate implant with a prescribed D90 dose of 144 Gy. The implant used fifty-eight I-125 seeds.
On April 3, 2009, the patient returned to the facility for a post-implant CT/dose reconstruction and it was determined that the D90 dose received by the patient was 85 Gy which is 60% of the prescribed dose.
The patient and prescribing physician were notified and the patient underwent an external radiation treatment to compensate.
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.