Event Notification Report for November 17, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/16/2011 - 11/17/2011
EVENT NUMBERS
4745247453474544745847463
Power Reactor
Event Number: 47452
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: LEE GOLDSTEIN
HQ OPS Officer: JOE O'HARA
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: LEE GOLDSTEIN
HQ OPS Officer: JOE O'HARA
Notification Date: 11/17/2011
Notification Time: 16:58 [ET]
Event Date: 11/17/2011
Event Time: 13:45 [EST]
Last Update Date: 11/17/2011
Notification Time: 16:58 [ET]
Event Date: 11/17/2011
Event Time: 13:45 [EST]
Last Update Date: 11/17/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
STEVEN VIAS (R2DO)
STEVEN VIAS (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Refueling |
UNANALYZED CONDITION ON STARTUP FOLLOWING MAINTENANCE OUTAGE
"On November 17, 2011, at 1345 Eastern Standard Time (EST), it was determined that an unanalyzed condition that significantly degraded plant safety existed on Unit 2 following a mid-cycle maintenance outage which required reactor vessel disassembly. Unit 2 had reached Mode 2 (i.e., Startup) during the power ascension, when elevated drywell leakage was identified and the plant was shutdown (see EN#47444). Unit 2 was subsequently operating in Mode 4 (i.e., Cold Shutdown) to allow for drywell entry. During leak investigation activities, it was determined that the reactor pressure vessel (RPV) head was not fully tensioned. This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B) as a condition of the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.
"The safety significance of this event was minimal. Unit 2 was in power ascension operating at a maximum of approximately 7% of rated thermal power. Control Room Operators took appropriate action to shutdown the Unit when elevated drywell leakage was identified.
"The NRC Senior Resident Inspector has been notified."
"On November 17, 2011, at 1345 Eastern Standard Time (EST), it was determined that an unanalyzed condition that significantly degraded plant safety existed on Unit 2 following a mid-cycle maintenance outage which required reactor vessel disassembly. Unit 2 had reached Mode 2 (i.e., Startup) during the power ascension, when elevated drywell leakage was identified and the plant was shutdown (see EN#47444). Unit 2 was subsequently operating in Mode 4 (i.e., Cold Shutdown) to allow for drywell entry. During leak investigation activities, it was determined that the reactor pressure vessel (RPV) head was not fully tensioned. This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B) as a condition of the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.
"The safety significance of this event was minimal. Unit 2 was in power ascension operating at a maximum of approximately 7% of rated thermal power. Control Room Operators took appropriate action to shutdown the Unit when elevated drywell leakage was identified.
"The NRC Senior Resident Inspector has been notified."
Power Reactor
Event Number: 47453
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: WARREN BRANDT
HQ OPS Officer: JOE O'HARA
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: WARREN BRANDT
HQ OPS Officer: JOE O'HARA
Notification Date: 11/17/2011
Notification Time: 17:17 [ET]
Event Date: 11/17/2011
Event Time: 14:20 [CST]
Last Update Date: 11/17/2011
Notification Time: 17:17 [ET]
Event Date: 11/17/2011
Event Time: 14:20 [CST]
Last Update Date: 11/17/2011
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):
BLAIR SPITZBERG (R4DO)
BLAIR SPITZBERG (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 |
OFFSITE NOTIFICATION DUE TO DIESEL FUEL OIL SPILL
"A notification was made to the National Response Center and the Kansas Department of Health and Environment of a 7-10 gallon release of diesel fuel oil to the environment. The leak originated from a temporary diesel fueled heater in place for freeze protection for a temporary fire pump. The fuel oil was not released to surface water, and has been isolated."
The NRC Resident Inspector has been notified.
"A notification was made to the National Response Center and the Kansas Department of Health and Environment of a 7-10 gallon release of diesel fuel oil to the environment. The leak originated from a temporary diesel fueled heater in place for freeze protection for a temporary fire pump. The fuel oil was not released to surface water, and has been isolated."
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 47454
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MERT PROBASCO
HQ OPS Officer: JOE O'HARA
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MERT PROBASCO
HQ OPS Officer: JOE O'HARA
Notification Date: 11/17/2011
Notification Time: 18:00 [ET]
Event Date: 11/17/2011
Event Time: 15:15 [EST]
Last Update Date: 11/17/2011
Notification Time: 18:00 [ET]
Event Date: 11/17/2011
Event Time: 15:15 [EST]
Last Update Date: 11/17/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JOHN CARUSO (R1DO)
JOHN CARUSO (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 50 | Power Operation | 50 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABLE FEEDWATER CHECK VALVE
"On Thursday, November 17, 2011, at 1515 hours, with the reactor at approximately 50% core thermal power, the station entered a 24 hour cold shutdown action statement due to the inability to provide a manual isolation for a main feedwater line check valve that had been declared inoperable due to a leak. As background, the reactor was at reduced power in order to perform a planned main condenser thermal backwash. While at reduced power an inspection of the main steam tunnel (a normally locked closed high radiation area) was performed as part of a scheduled system inspection. The inspection identified a leak on the feedwater line 'B' outboard check valve (6-CK-62B). The feedwater check valve was declared inoperable and the Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.7.A.2.a.5 was entered. Because there is no ability to manually isolate the primary containment penetration the station is required to be in cold shutdown within 24 hours per TS 3.7.A.5.
"Currently, preparations are being completed to conduct the reactor shutdown and to initiate check valve repairs.
"This event had no impact on the health and safety of the public. The USNRC Senior Resident Inspector was onsite and has been notified."
The electrical lineup is normal and all safety related equipment required for shutdown and cooldown are operable.
"On Thursday, November 17, 2011, at 1515 hours, with the reactor at approximately 50% core thermal power, the station entered a 24 hour cold shutdown action statement due to the inability to provide a manual isolation for a main feedwater line check valve that had been declared inoperable due to a leak. As background, the reactor was at reduced power in order to perform a planned main condenser thermal backwash. While at reduced power an inspection of the main steam tunnel (a normally locked closed high radiation area) was performed as part of a scheduled system inspection. The inspection identified a leak on the feedwater line 'B' outboard check valve (6-CK-62B). The feedwater check valve was declared inoperable and the Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.7.A.2.a.5 was entered. Because there is no ability to manually isolate the primary containment penetration the station is required to be in cold shutdown within 24 hours per TS 3.7.A.5.
"Currently, preparations are being completed to conduct the reactor shutdown and to initiate check valve repairs.
"This event had no impact on the health and safety of the public. The USNRC Senior Resident Inspector was onsite and has been notified."
The electrical lineup is normal and all safety related equipment required for shutdown and cooldown are operable.
Agreement State
Event Number: 47458
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: SOUTH JERSEY HEALTHCARE REGIONAL MEDICAL CENTER
Region: 1
City: VINELAND State: NJ
County:
License #: 450632
Agreement: Y
Docket:
NRC Notified By: BILL CSASZAR
HQ OPS Officer: JOE O'HARA
Licensee: SOUTH JERSEY HEALTHCARE REGIONAL MEDICAL CENTER
Region: 1
City: VINELAND State: NJ
County:
License #: 450632
Agreement: Y
Docket:
NRC Notified By: BILL CSASZAR
HQ OPS Officer: JOE O'HARA
Notification Date: 11/18/2011
Notification Time: 15:45 [ET]
Event Date: 11/17/2011
Event Time: 15:48 [EST]
Last Update Date: 11/18/2011
Notification Time: 15:45 [ET]
Event Date: 11/17/2011
Event Time: 15:48 [EST]
Last Update Date: 11/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN CARUSO (R1DO)
BILL VON TILL (FSME)
JOHN CARUSO (R1DO)
BILL VON TILL (FSME)
AGREEMENT STATE REPORT - PATIENT RECEIVED GREATER THAN THE PRESCRIBED DOSE
A patient had a mass surgically removed from both sides of the nose and was undergoing a topical treatment for microscopic disease using a Nucletron HDR containing 8.52 curies of Ir-192 with a Valencia Model H3 skin applicator containing a platinum filter.
The planned administration was 7 fractions of 600 centigrays each on both the left and right side of the nose. During the initial planning for the treatment, an error was made in calculating the dwell time for each location and this incorrect data was entered into the HDR system. As a result of the error, the patient received 54% during each fraction (treatment) during two of the seven fractions on each side of the nose. Prior to the third fraction, the medical team is required per procedure to check calculations and caught the error before the third fraction (treatment) was performed.
The patient and prescribing physician have been informed, and there is no long range medical concern for disease as a result of this error. The total dose treatment has not been exceeded.
The state's licensee is revising procedures in order to prevent recurrence, and the state will be submitting an NMED report.
New Jersey Incident Number: #410674
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.
A patient had a mass surgically removed from both sides of the nose and was undergoing a topical treatment for microscopic disease using a Nucletron HDR containing 8.52 curies of Ir-192 with a Valencia Model H3 skin applicator containing a platinum filter.
The planned administration was 7 fractions of 600 centigrays each on both the left and right side of the nose. During the initial planning for the treatment, an error was made in calculating the dwell time for each location and this incorrect data was entered into the HDR system. As a result of the error, the patient received 54% during each fraction (treatment) during two of the seven fractions on each side of the nose. Prior to the third fraction, the medical team is required per procedure to check calculations and caught the error before the third fraction (treatment) was performed.
The patient and prescribing physician have been informed, and there is no long range medical concern for disease as a result of this error. The total dose treatment has not been exceeded.
The state's licensee is revising procedures in order to prevent recurrence, and the state will be submitting an NMED report.
New Jersey Incident Number: #410674
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.
Agreement State
Event Number: 47463
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: UNIVERSITY OF TEXAS MD ANDERSON CANCER CENTER
Region: 4
City: HOUSTON State: TX
County:
License #: 00466
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: HOWIE CROUCH
Licensee: UNIVERSITY OF TEXAS MD ANDERSON CANCER CENTER
Region: 4
City: HOUSTON State: TX
County:
License #: 00466
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/21/2011
Notification Time: 15:23 [ET]
Event Date: 11/17/2011
Event Time: 07:00 [CST]
Last Update Date: 11/21/2011
Notification Time: 15:23 [ET]
Event Date: 11/17/2011
Event Time: 07:00 [CST]
Last Update Date: 11/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAY AZUA (R4DO)
BILL VON TILL (FSME)
RAY AZUA (R4DO)
BILL VON TILL (FSME)
TEXAS AGREEMENT STATE REPORT - MEDICAL EVENT INVOLVING Y-90 MICROSPHERES
The following information was obtained from the State of Texas via email:
"On November 21, 2011, the Agency [Texas Department of State Health Services] was notified by one of its licensees that it had determined that a therapy event had occurred on November 17, 2011, during an administration of Yttrium-90 microspheres. The patient was prescribed a dose of 135 gray to the target tissue. Surveys of the administration equipment following the procedure indicated readings that were higher than expected if the full dose had injected into the patient. Initial estimates by the licensee are that a dose of 95.8 gray was administered to the target tissue, approximately a 29% variation from the prescribed dose. The licensee will confirm the dose administered and investigate to determine the cause of the event. Information on this event will be updated as it becomes available."
Texas Incident #: I-8904
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 following information was obtained from the State of Texas via email:
"On November 21, 2011, the Agency [Texas Department of State Health Services] was notified by one of its licensees that it had determined that a therapy event had occurred on November 17, 2011, during an administration of Yttrium-90 microspheres. The patient was prescribed a dose of 135 gray to the target tissue. Surveys of the administration equipment following the procedure indicated readings that were higher than expected if the full dose had injected into the patient. Initial estimates by the licensee are that a dose of 95.8 gray was administered to the target tissue, approximately a 29% variation from the prescribed dose. The licensee will confirm the dose administered and investigate to determine the cause of the event. Information on this event will be updated as it becomes available."
Texas Incident #: I-8904
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.