Event Notification Report for May 29, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/28/2007 - 05/29/2007
Hospital
Event Number: 43400
Rep Org: WASHINGTON UNIVERSITY
Licensee: WASHINGTON UNIVERSITY
Region: 3
City: ST. LOUIS State: MO
County:
License #: 24-00167-11
Agreement: N
Docket:
NRC Notified By: SUSAN LANGHORST
HQ OPS Officer: PETE SNYDER
Licensee: WASHINGTON UNIVERSITY
Region: 3
City: ST. LOUIS State: MO
County:
License #: 24-00167-11
Agreement: N
Docket:
NRC Notified By: SUSAN LANGHORST
HQ OPS Officer: PETE SNYDER
Notification Date: 06/01/2007
Notification Time: 15:56 [ET]
Event Date: 05/29/2007
Event Time: 10:15 [CDT]
Last Update Date: 06/14/2007
Notification Time: 15:56 [ET]
Event Date: 05/29/2007
Event Time: 10:15 [CDT]
Last Update Date: 06/14/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3047(a) - EMBRYO/FETUS DOSE > 50 mSv
10 CFR Section:
35.3047(a) - EMBRYO/FETUS DOSE > 50 mSv
Person (Organization):
KENNETH O'BRIEN (R3)
CYNTHIA FLANNERY (FSME)
KENNETH O'BRIEN (R3)
CYNTHIA FLANNERY (FSME)
CANCER TREATMENT OF RADIOACTIVE IODINE RESULTS IN A DOSE TO FETUS
A patient was seen by the prescribing physician on May 22, 2007 about a cancer treatment with Iodine 131. The hospital conducted a pregnancy test on the patient. The result was negative. The individual was advised not to get pregnant prior to the treatment.
On May 29, 2007, the treatment was conducted at Barnes Jewish Hospital Radiation Oncology. The prescribed dose was for 125 millicuries of I-131. 125.5 millicuries of I-131 was the actual administered dose.
On May 30, 2007 the patient called the hospital to report that she conducted a home pregnancy test with positive results. The patient was asked to come in to the hospital on May 30, 2007 for another test. The hospital radiation safety officer received the results of the test on May 31, 2007. The results were positive. The staff at the hospital calculated a dose to the adult uterus as an approximation for the dose received by the fetus. The dose was estimated to be 25 to 34 rem.
The risk to the fetus is still being determined by the hospital. The possible effects on the fetus will be discussed with the patient at a future date.
A patient was seen by the prescribing physician on May 22, 2007 about a cancer treatment with Iodine 131. The hospital conducted a pregnancy test on the patient. The result was negative. The individual was advised not to get pregnant prior to the treatment.
On May 29, 2007, the treatment was conducted at Barnes Jewish Hospital Radiation Oncology. The prescribed dose was for 125 millicuries of I-131. 125.5 millicuries of I-131 was the actual administered dose.
On May 30, 2007 the patient called the hospital to report that she conducted a home pregnancy test with positive results. The patient was asked to come in to the hospital on May 30, 2007 for another test. The hospital radiation safety officer received the results of the test on May 31, 2007. The results were positive. The staff at the hospital calculated a dose to the adult uterus as an approximation for the dose received by the fetus. The dose was estimated to be 25 to 34 rem.
The risk to the fetus is still being determined by the hospital. The possible effects on the fetus will be discussed with the patient at a future date.
Power Reactor
Event Number: 43394
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: LANCE LANE
HQ OPS Officer: JOE O'HARA
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: LANCE LANE
HQ OPS Officer: JOE O'HARA
Notification Date: 05/29/2007
Notification Time: 10:09 [ET]
Event Date: 05/29/2007
Event Time: 08:08 [CDT]
Last Update Date: 06/13/2007
Notification Time: 10:09 [ET]
Event Date: 05/29/2007
Event Time: 08:08 [CDT]
Last Update Date: 06/13/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
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 | 100 | Power Operation | 100 | Power Operation |
SAFETY PARAMETER DISPLAY SYSTEM (SPDS) REMOVED FROM SERVICE FOR COMPUTER UPGRADE
"On 05/29/2007 at 08:08 am CDT, the Wolf Creek Nuclear Plant Information System (NPIS) was removed from service for a planned computer system upgrade. The system upgrade will result in the SPDS and Emergency Response Data System (ERDS) being inoperable for approximately three weeks.
"Wolf Creek Nuclear Operating Corporation is making this ENS notification pursuant to the criteria of 10 CFR 50.72(b)(3)(xiii). There is no other loss of emergency assessment capability concurrent with the removal of the NPIS from service. Plant personnel entered the appropriate Off-Normal procedure and will obtain local readings for the equipment that is normally monitored by SPDS and NPIS during the plant computer upgrade.
"The Senior NRC Resident has been briefed on this evolution and the planned return to service of the system."
* * * UPDATE FROM LANE TO SNYDER AT 1802 EDT ON 6/11/07 * * *
"On 06/09/07 at 18:46 CDT, the Wolf Creek Nuclear Plant Information System (NPIS) was returned to service following the computer upgrade. This restored the Safety Parameter Display System (SPDS) to OPERABLE and made the Emergency Response Data System (ERDS) available for use. The ERDS system will not be considered OPERABLE until testing has been performed with the NRC to confirm proper data transmissions.
"Some data points and processes are still being tested prior to being returned to service."
The licensee notified the NRC Resident Inspector. Notified R4DO (M. Hay).
* * * UPDATE FROM JIM KURAS TO JOE O'HARA AT 1633 EDT ON 6/13/07 * * *
"On 6/13/07 at 14:57 CDT (ERDS) testing with the NRC completed satisfactory to confirm proper data transmission."
The licensee notified the NRC Resident Inspector. Notified R4DO(Hay).
"On 05/29/2007 at 08:08 am CDT, the Wolf Creek Nuclear Plant Information System (NPIS) was removed from service for a planned computer system upgrade. The system upgrade will result in the SPDS and Emergency Response Data System (ERDS) being inoperable for approximately three weeks.
"Wolf Creek Nuclear Operating Corporation is making this ENS notification pursuant to the criteria of 10 CFR 50.72(b)(3)(xiii). There is no other loss of emergency assessment capability concurrent with the removal of the NPIS from service. Plant personnel entered the appropriate Off-Normal procedure and will obtain local readings for the equipment that is normally monitored by SPDS and NPIS during the plant computer upgrade.
"The Senior NRC Resident has been briefed on this evolution and the planned return to service of the system."
* * * UPDATE FROM LANE TO SNYDER AT 1802 EDT ON 6/11/07 * * *
"On 06/09/07 at 18:46 CDT, the Wolf Creek Nuclear Plant Information System (NPIS) was returned to service following the computer upgrade. This restored the Safety Parameter Display System (SPDS) to OPERABLE and made the Emergency Response Data System (ERDS) available for use. The ERDS system will not be considered OPERABLE until testing has been performed with the NRC to confirm proper data transmissions.
"Some data points and processes are still being tested prior to being returned to service."
The licensee notified the NRC Resident Inspector. Notified R4DO (M. Hay).
* * * UPDATE FROM JIM KURAS TO JOE O'HARA AT 1633 EDT ON 6/13/07 * * *
"On 6/13/07 at 14:57 CDT (ERDS) testing with the NRC completed satisfactory to confirm proper data transmission."
The licensee notified the NRC Resident Inspector. Notified R4DO(Hay).
Power Reactor
Event Number: 43395
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARK SHAFFER
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARK SHAFFER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 05/29/2007
Notification Time: 11:22 [ET]
Event Date: 05/29/2007
Event Time: 08:35 [EDT]
Last Update Date: 05/29/2007
Notification Time: 11:22 [ET]
Event Date: 05/29/2007
Event Time: 08:35 [EDT]
Last Update Date: 05/29/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
PAMELA HENDERSON (R1)
PAMELA HENDERSON (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO LOSS OF FEED PUMPS AFTER ELECTRICAL TRANSIENT
"On 5/28/07 with Hope Creek in Operating Condition 1 at 100% Reactor power, an electrical transient and loss of 'A' and 'B' reactor feed pumps resulted in lowering reactor water level. Operators inserted a manual reactor scram at 0835 in response to the lowering reactor water level. Reactor water level lowered to (-) 38 inches subsequent to the manual scram, resulting in initiation of High Pressure Coolant Injection (HPCl) and injection to the reactor vessel. The Reactor Core Isolation Cooling (RCIC) system also initiated but tripped. Investigation of the cause of the electrical transient, loss of the 'A' and 'B' RFP's, and trip of the RCIC system are currently in progress.
"Initial review of the event indicates that all other systems operated as expected. Current plant conditions as of 1100 are: Hope Creek is in mode 3 at 715 psig with heat removal to the main condenser via the Main Turbine Bypass valves. All control nods fully inserted on the scram.
"This report also documents a 4 hour report under 10CFR50.72(b)(2)(iv)(A) for valid ECCS initiation and injection to the reactor vessel (RAL 11.3.1)."
The reactor is stable with the water level currently at 17 inches and feedwater being supplied by the 'C' feed pump. No Safeties lifted during the transient. All systems functioned as required except for the trip of the RCIC. The licensee was not in any major technical specification LCO at the time of the trip.
The licensee notified the NRC Resident Inspector. The licensee will also notify the States of NJ and Delaware, and Lower Alloways Creek Township.
"On 5/28/07 with Hope Creek in Operating Condition 1 at 100% Reactor power, an electrical transient and loss of 'A' and 'B' reactor feed pumps resulted in lowering reactor water level. Operators inserted a manual reactor scram at 0835 in response to the lowering reactor water level. Reactor water level lowered to (-) 38 inches subsequent to the manual scram, resulting in initiation of High Pressure Coolant Injection (HPCl) and injection to the reactor vessel. The Reactor Core Isolation Cooling (RCIC) system also initiated but tripped. Investigation of the cause of the electrical transient, loss of the 'A' and 'B' RFP's, and trip of the RCIC system are currently in progress.
"Initial review of the event indicates that all other systems operated as expected. Current plant conditions as of 1100 are: Hope Creek is in mode 3 at 715 psig with heat removal to the main condenser via the Main Turbine Bypass valves. All control nods fully inserted on the scram.
"This report also documents a 4 hour report under 10CFR50.72(b)(2)(iv)(A) for valid ECCS initiation and injection to the reactor vessel (RAL 11.3.1)."
The reactor is stable with the water level currently at 17 inches and feedwater being supplied by the 'C' feed pump. No Safeties lifted during the transient. All systems functioned as required except for the trip of the RCIC. The licensee was not in any major technical specification LCO at the time of the trip.
The licensee notified the NRC Resident Inspector. The licensee will also notify the States of NJ and Delaware, and Lower Alloways Creek Township.