Event Notification Report for October 02, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/01/2003 - 10/02/2003
EVENT NUMBERS
402144021540216402174021840219
Power Reactor
Event Number: 40214
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: WILLIAM GILBERT
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: WILLIAM GILBERT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/02/2003
Notification Time: 11:45 [ET]
Event Date: 10/02/2003
Event Time: 09:10 [CDT]
Last Update Date: 10/02/2003
Notification Time: 11:45 [ET]
Event Date: 10/02/2003
Event Time: 09:10 [CDT]
Last Update Date: 10/02/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
CHUCK CAIN (R4)
CHUCK CAIN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 90 | Power Operation | 90 | Power Operation |
OFFSITE NOTIFICATION TO U.S. FISH AND WILDLIFE SERVICE AND NEBRASKA GAME AND PARKS COMMISSION
The following information was received from the licensee via facsimile:
"At 0910 [CDT] on 10/02/2003, the US Fish and Wildlife Service and the Nebraska Game and Parks Commission were contacted to inform them of an injured Raptor (owl). The owl is caught in the razor wire located along the top of the fence surrounding the Elevated Release Point. Current plan is to remove the owl and turn it over to Nebraska Game and Parks Commission."
The Licensee has informed the NRC Resident Inspector.
The following information was received from the licensee via facsimile:
"At 0910 [CDT] on 10/02/2003, the US Fish and Wildlife Service and the Nebraska Game and Parks Commission were contacted to inform them of an injured Raptor (owl). The owl is caught in the razor wire located along the top of the fence surrounding the Elevated Release Point. Current plan is to remove the owl and turn it over to Nebraska Game and Parks Commission."
The Licensee has informed the NRC Resident Inspector.
Power Reactor
Event Number: 40215
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: DAVID COSEO
HQ OPS Officer: JEFF ROTTON
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: DAVID COSEO
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/02/2003
Notification Time: 16:48 [ET]
Event Date: 10/02/2003
Event Time: 15:00 [EDT]
Last Update Date: 10/02/2003
Notification Time: 16:48 [ET]
Event Date: 10/02/2003
Event Time: 15:00 [EDT]
Last Update Date: 10/02/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
JULIO LARA (R3)
JULIO LARA (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF SAFE SHUTDOWN CAPABILITY DUE TO ALL OPRM CHANNELS BEING DECLARED INOPERABLE.
"On October 2, 2003, Detroit Edison received verbal confirmation from General Electric of a potential Non-Conservative Analysis of OPRM Period Tolerance and Corner Frequency.
"All OPRM channels have been declared inoperable. Technical Specifications 3.3.1.1 Action J requires an alternate method of detecting and suppressing thermal-hydraulic instabilities to be implemented within 12 hours. Alternate methods have been established to monitor for instability when operating in the Stability Awareness region, thus we are in compliance with the Technical Specifications.
"This report is being made in accordance with 10CFR50.72(b)(3)(v), Any event or condition that could have prevented the fulfillment of the safety function of a system needed to shut down the reactor and maintain it in a safe shutdown condition."
The Licensee will inform the NRC Resident Inspector.
"On October 2, 2003, Detroit Edison received verbal confirmation from General Electric of a potential Non-Conservative Analysis of OPRM Period Tolerance and Corner Frequency.
"All OPRM channels have been declared inoperable. Technical Specifications 3.3.1.1 Action J requires an alternate method of detecting and suppressing thermal-hydraulic instabilities to be implemented within 12 hours. Alternate methods have been established to monitor for instability when operating in the Stability Awareness region, thus we are in compliance with the Technical Specifications.
"This report is being made in accordance with 10CFR50.72(b)(3)(v), Any event or condition that could have prevented the fulfillment of the safety function of a system needed to shut down the reactor and maintain it in a safe shutdown condition."
The Licensee will inform the NRC Resident Inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 40216
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: CHUCK OLSON
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: CHUCK OLSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/02/2003
Notification Time: 20:32 [ET]
Event Date: 10/02/2003
Event Time: 17:15 [CDT]
Last Update Date: 12/01/2003
Notification Time: 20:32 [ET]
Event Date: 10/02/2003
Event Time: 17:15 [CDT]
Last Update Date: 12/01/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
CHUCK CAIN (R4)
CHUCK CAIN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
RCS BOUNDARY LEAKAGE DUE TO SMALL CRACK ON DRAIN LINE WELDED CAP
"Safety injection tank (SIT) isolation valve (2CV-5043-2) has a drain pipe under the valve body with a welded cap. The welded cap has a small crack with boric acid residue. The welded cap does not have any threads and is considered RCS boundary leakage. There is a check valve between the reactor coolant system (RCS) and the SIT Outlet valve. The crack will be repair welded prior to coming out of the 2R16 outage."
The Licensee has notified the NRC Resident Inspector.
* * * RETRACTED EVENT AT 1432 EST ON 12/01/03 FROM SCHEIDE TO ROTTON * * *
"This report is being made to retract a notification made at 1715 CDT on 10/02/03 (EN# 40216.)
"The notification documented the identification of a small amount of boric acid residue on a drain line attached to a Safety Injection Tank isolation valve (2CV-5034-2). The report stated that the indication was within the Reactor Coolant System boundary. However, subsequent review of the condition determined that the indication was not within the Reactor Coolant System boundary since it was isolated from the Reactor Coolant System by an operable check valve. Therefore, the condition did not represent a serious degradation of a principal safety barrier.
"Note; The drain line is 3/4 inch diameter stainless steel."
The licensee notified the NRC Resident Inspector. Notified Claude Johnson - R4DO.
"Safety injection tank (SIT) isolation valve (2CV-5043-2) has a drain pipe under the valve body with a welded cap. The welded cap has a small crack with boric acid residue. The welded cap does not have any threads and is considered RCS boundary leakage. There is a check valve between the reactor coolant system (RCS) and the SIT Outlet valve. The crack will be repair welded prior to coming out of the 2R16 outage."
The Licensee has notified the NRC Resident Inspector.
* * * RETRACTED EVENT AT 1432 EST ON 12/01/03 FROM SCHEIDE TO ROTTON * * *
"This report is being made to retract a notification made at 1715 CDT on 10/02/03 (EN# 40216.)
"The notification documented the identification of a small amount of boric acid residue on a drain line attached to a Safety Injection Tank isolation valve (2CV-5034-2). The report stated that the indication was within the Reactor Coolant System boundary. However, subsequent review of the condition determined that the indication was not within the Reactor Coolant System boundary since it was isolated from the Reactor Coolant System by an operable check valve. Therefore, the condition did not represent a serious degradation of a principal safety barrier.
"Note; The drain line is 3/4 inch diameter stainless steel."
The licensee notified the NRC Resident Inspector. Notified Claude Johnson - R4DO.
Power Reactor
Event Number: 40217
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: ELI DRAGOMER
HQ OPS Officer: GERRY WAIG
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: ELI DRAGOMER
HQ OPS Officer: GERRY WAIG
Notification Date: 10/03/2003
Notification Time: 02:05 [ET]
Event Date: 10/02/2003
Event Time: 21:00 [EDT]
Last Update Date: 10/03/2003
Notification Time: 02:05 [ET]
Event Date: 10/02/2003
Event Time: 21:00 [EDT]
Last Update Date: 10/03/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
EUGENE COBEY (R1)
EUGENE COBEY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF SAFE SHUTDOWN CAPABILITY DUE TO ALL OPRM CHANNELS BEING DECLARED INOPERABLE.
"According to information provided by Nuclear Fuels, Reactor Engineering and G. E. Nuclear Energy, a condition exists in the Oscillation Power Range Monitors (OPRM's) that could contribute to exceeding a Safety Limit. This condition involves excessive confirmation count resets attributed to both the conditioning filter cutoff frequency and period tolerance values. G.E. Nuclear Energy can not confirm that performance of the OPRM's with the conditioning filter cutoff frequency and period tolerance settings currently in use would prevent a condition whereby a Safety Limit MCPR could be violated during an anticipated instability event. The OPRM conditioning filter cutoff frequency and period tolerance are currently set as allowed by licensing documentation, and are calculated as specified in NEDO-32465-A, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications. As a result, all OPRM's at Nine-Mile Point Unit 2 are considered inoperable. This INOPERABILITY determination is based on information received from G.E. Nuclear Energy which evaluated the Nine Mile Point OPRM performance on July 24, 2003."
The licensee has taken action to address this condition in accordance with Technical Specification 3.3.1.1, Reactor Protection System Instrumentation. The licensee has a procedure providing guidance for alternate methods to detect and suppress thermal hydraulic instability.
The licensee has notified the NRC Resident Inspector.
"According to information provided by Nuclear Fuels, Reactor Engineering and G. E. Nuclear Energy, a condition exists in the Oscillation Power Range Monitors (OPRM's) that could contribute to exceeding a Safety Limit. This condition involves excessive confirmation count resets attributed to both the conditioning filter cutoff frequency and period tolerance values. G.E. Nuclear Energy can not confirm that performance of the OPRM's with the conditioning filter cutoff frequency and period tolerance settings currently in use would prevent a condition whereby a Safety Limit MCPR could be violated during an anticipated instability event. The OPRM conditioning filter cutoff frequency and period tolerance are currently set as allowed by licensing documentation, and are calculated as specified in NEDO-32465-A, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications. As a result, all OPRM's at Nine-Mile Point Unit 2 are considered inoperable. This INOPERABILITY determination is based on information received from G.E. Nuclear Energy which evaluated the Nine Mile Point OPRM performance on July 24, 2003."
The licensee has taken action to address this condition in accordance with Technical Specification 3.3.1.1, Reactor Protection System Instrumentation. The licensee has a procedure providing guidance for alternate methods to detect and suppress thermal hydraulic instability.
The licensee has notified the NRC Resident Inspector.
General Information or Other
Event Number: 40218
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: SINAI HOSPITAL
Region: 1
City: BALTIMORE State: MD
County: BALTIMORE
License #: MD-07-011-01
Agreement: Y
Docket:
NRC Notified By: NATHANIEL OWRUTSKY
HQ OPS Officer: JEFF ROTTON
Licensee: SINAI HOSPITAL
Region: 1
City: BALTIMORE State: MD
County: BALTIMORE
License #: MD-07-011-01
Agreement: Y
Docket:
NRC Notified By: NATHANIEL OWRUTSKY
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/03/2003
Notification Time: 13:45 [ET]
Event Date: 10/02/2003
Event Time: 00:00 [EDT]
Last Update Date: 10/03/2003
Notification Time: 13:45 [ET]
Event Date: 10/02/2003
Event Time: 00:00 [EDT]
Last Update Date: 10/03/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
EUGENE COBEY (R1)
FRED BROWN (NMSS)
EUGENE COBEY (R1)
FRED BROWN (NMSS)
MARYLAND AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION
On 10/02/03, a patient with suspected hyperthyroidism was undergoing treatment at Sinai Hospital in Baltimore, MD. During administration of an uptake diagnostic test, the patient was given a dose of 80 microcuries of I-131 versus the prescribed dose of 8 microcuries. Preliminary investigation indicates that hospital policy is to have technician dose measurement verified by another technician and approved by supervision until the technician shows proficiency at this task. It is unclear at this time whether the technician followed this protocol.
The prescribing physician has been notified and has notified the patient. Follow-up tests will be performed on the patient, but no increase in physiological effect on the patient is expected..
Maryland Department of Radiation Health is planning to contact the Hospital Radiation Safety Officer.
On 10/02/03, a patient with suspected hyperthyroidism was undergoing treatment at Sinai Hospital in Baltimore, MD. During administration of an uptake diagnostic test, the patient was given a dose of 80 microcuries of I-131 versus the prescribed dose of 8 microcuries. Preliminary investigation indicates that hospital policy is to have technician dose measurement verified by another technician and approved by supervision until the technician shows proficiency at this task. It is unclear at this time whether the technician followed this protocol.
The prescribing physician has been notified and has notified the patient. Follow-up tests will be performed on the patient, but no increase in physiological effect on the patient is expected..
Maryland Department of Radiation Health is planning to contact the Hospital Radiation Safety Officer.
General Information or Other
Event Number: 40219
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: NODARSE
Region: 1
City: TAMPA State: FL
County:
License #: 3166-1
Agreement: Y
Docket:
NRC Notified By: JEAROLD EAKINS
HQ OPS Officer: JEFF ROTTON
Licensee: NODARSE
Region: 1
City: TAMPA State: FL
County:
License #: 3166-1
Agreement: Y
Docket:
NRC Notified By: JEAROLD EAKINS
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/03/2003
Notification Time: 15:29 [ET]
Event Date: 10/02/2003
Event Time: 00:00 [EDT]
Last Update Date: 10/08/2003
Notification Time: 15:29 [ET]
Event Date: 10/02/2003
Event Time: 00:00 [EDT]
Last Update Date: 10/08/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
EUGENE COBEY (R1)
TRISH HOLAHAN (NMSS)
EUGENE COBEY (R1)
TRISH HOLAHAN (NMSS)
FLORIDA AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
Troxler moisture density gauge, model #3430, serial #32804 was stolen from the rear of licensee employee's truck parked at residence in Tampa, FL between the hours of 11 PM EDT 10/02/03 and 11 AM 10/03/03. The locked chain securing gauge box was broken. The gauge contained 40 [milliCuries] of Am-241/Be and 8 [milliCuries] of Cs-137. Tampa Police, Florida Department of Emergency Management and the NRC Region 2 have been informed. The licensee posted a notice offering a reward in the Tampa newspaper.
Florida Incident # FL 03-181
* * * UPDATE VIA E-MAIL FROM ADAMS TO CROUCH @ 1550 HRS ON 10/8/03 * * *
Troxler was notified by a pawn shop owner in Tampa on 8 October that they had bought the gauge. Troxler notified the State of Florida. The owner and police were notified and the gauge was retrieved. It was undamaged. The police have a good lead on the thieves. Licensee will be forwarding a copy of the police report to the State of Florida.
Notified R1DO (Bellamy) and NMSS EO (Hickey).
Troxler moisture density gauge, model #3430, serial #32804 was stolen from the rear of licensee employee's truck parked at residence in Tampa, FL between the hours of 11 PM EDT 10/02/03 and 11 AM 10/03/03. The locked chain securing gauge box was broken. The gauge contained 40 [milliCuries] of Am-241/Be and 8 [milliCuries] of Cs-137. Tampa Police, Florida Department of Emergency Management and the NRC Region 2 have been informed. The licensee posted a notice offering a reward in the Tampa newspaper.
Florida Incident # FL 03-181
* * * UPDATE VIA E-MAIL FROM ADAMS TO CROUCH @ 1550 HRS ON 10/8/03 * * *
Troxler was notified by a pawn shop owner in Tampa on 8 October that they had bought the gauge. Troxler notified the State of Florida. The owner and police were notified and the gauge was retrieved. It was undamaged. The police have a good lead on the thieves. Licensee will be forwarding a copy of the police report to the State of Florida.
Notified R1DO (Bellamy) and NMSS EO (Hickey).