Event Notification Report for December 28, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/27/2007 - 12/28/2007
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 43871
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: ALAN HALL
HQ OPS Officer: JOHN KNOKE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: ALAN HALL
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/28/2007
Notification Time: 06:46 [ET]
Event Date: 12/28/2007
Event Time: 04:50 [EST]
Last Update Date: 03/26/2008
Notification Time: 06:46 [ET]
Event Date: 12/28/2007
Event Time: 04:50 [EST]
Last Update Date: 03/26/2008
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):
SCOTT SHAEFFER (R2)
SCOTT SHAEFFER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Startup | 0 | Hot Standby |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN - DROPPED CEA
"At 0347 on 12/28/07, during plant start up from a refueling outage while In Mode 2, one control element assembly (CEA) dropped to the bottom of the core from the upper electrical limit. The reactor was not critical at the time. Technical Specification LCO 3.1.3.1 action (e) was initiated to proceed to Mode 3 at 0450 while actions are taken to repair and retrieve the CEA. This four hour non-emergency report is being made pursuant to 10 CFR 50.72(b)(2)(i), the 'Initiation of any nuclear plant shutdown required by Technical Specifications'."
The licensee notified the NRC Resident Inspector.
* * * RETRACTED ON 03/26/2008 AT 1433 EDT BY JACK BREEN TO DAN LIVERMORE * * *
The licensee is retracting this report based on the following:
"At 03:47 on 12/28/07, during plant start up from a refueling outage while in Mode 2, one control element assembly (CEA) dropped to the bottom of the core from the upper electrical limit. The reactor was not critical at the time. Technical Specification LCO 3.1.3.1 [Action E] was initiated to proceed to Mode 3 at 0450 while actions were taken to repair and retrieve the CEA. This event was reported as a four hour non-emergency report pursuant to 10CFR 50.72(b)(2)(i), 'The initiation of any nuclear plant shutdown required by Technical Specifications.' Upon further review of the event, and since the Unit was not critical in mode 2 at the time of the event, this event is not considered reportable in accordance with the guidance provide in NUREG-1022, Rev. 2, 'Event Reporting Guidelines 10CFR50.72 and 50.73,' in which 'The initiation of any plant shutdown' does not include mode changes required by TS if initiated after the plant is already in a shutdown condition. As such this notification is being retracted. The Site Resident has been notified of this retraction."
"At 0347 on 12/28/07, during plant start up from a refueling outage while In Mode 2, one control element assembly (CEA) dropped to the bottom of the core from the upper electrical limit. The reactor was not critical at the time. Technical Specification LCO 3.1.3.1 action (e) was initiated to proceed to Mode 3 at 0450 while actions are taken to repair and retrieve the CEA. This four hour non-emergency report is being made pursuant to 10 CFR 50.72(b)(2)(i), the 'Initiation of any nuclear plant shutdown required by Technical Specifications'."
The licensee notified the NRC Resident Inspector.
* * * RETRACTED ON 03/26/2008 AT 1433 EDT BY JACK BREEN TO DAN LIVERMORE * * *
The licensee is retracting this report based on the following:
"At 03:47 on 12/28/07, during plant start up from a refueling outage while in Mode 2, one control element assembly (CEA) dropped to the bottom of the core from the upper electrical limit. The reactor was not critical at the time. Technical Specification LCO 3.1.3.1 [Action E] was initiated to proceed to Mode 3 at 0450 while actions were taken to repair and retrieve the CEA. This event was reported as a four hour non-emergency report pursuant to 10CFR 50.72(b)(2)(i), 'The initiation of any nuclear plant shutdown required by Technical Specifications.' Upon further review of the event, and since the Unit was not critical in mode 2 at the time of the event, this event is not considered reportable in accordance with the guidance provide in NUREG-1022, Rev. 2, 'Event Reporting Guidelines 10CFR50.72 and 50.73,' in which 'The initiation of any plant shutdown' does not include mode changes required by TS if initiated after the plant is already in a shutdown condition. As such this notification is being retracted. The Site Resident has been notified of this retraction."
General Information or Other
Event Number: 43872
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: SOUTHWEST VOLUSIA HEALTHCARE CORP
Region: 1
City: ORANGE CITY State: FL
County:
License #: 2467-1
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: JOHN KNOKE
Licensee: SOUTHWEST VOLUSIA HEALTHCARE CORP
Region: 1
City: ORANGE CITY State: FL
County:
License #: 2467-1
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/28/2007
Notification Time: 11:34 [ET]
Event Date: 12/28/2007
Event Time: 00:00 [EST]
Last Update Date: 12/28/2007
Notification Time: 11:34 [ET]
Event Date: 12/28/2007
Event Time: 00:00 [EST]
Last Update Date: 12/28/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
NEIL PERRY (R1)
SANDRA WASTLER (FSME)
NEIL PERRY (R1)
SANDRA WASTLER (FSME)
MEDICAL EVENT - INCORRECT ISOTOPE ADMINISTERED
"Doctor ordered iodine (didn't specify isotope) thyroid uptake & scan for a patient. This licensee uses I-123 for this purpose. Patient was incorrectly scheduled for a I-131 (2.2mCi) whole body scan and that was done on 12/17/07. Error was discovered 12/25. Patient & doctor have been notified and no adverse health effects are expected. Licensee will submit a written report. Scheduling personnel will be re-educated to verify an order before scheduling patients for a procedure. The tech will be re-educated to read the script before dosing a patient. Any further action on this incident is referred to Radioactive Materials."
Incident Number FL07-205
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.
"Doctor ordered iodine (didn't specify isotope) thyroid uptake & scan for a patient. This licensee uses I-123 for this purpose. Patient was incorrectly scheduled for a I-131 (2.2mCi) whole body scan and that was done on 12/17/07. Error was discovered 12/25. Patient & doctor have been notified and no adverse health effects are expected. Licensee will submit a written report. Scheduling personnel will be re-educated to verify an order before scheduling patients for a procedure. The tech will be re-educated to read the script before dosing a patient. Any further action on this incident is referred to Radioactive Materials."
Incident Number FL07-205
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.
Power Reactor
Event Number: 43873
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC POWELL
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC POWELL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/28/2007
Notification Time: 19:58 [ET]
Event Date: 12/28/2007
Event Time: 17:54 [EST]
Last Update Date: 12/28/2007
Notification Time: 19:58 [ET]
Event Date: 12/28/2007
Event Time: 17:54 [EST]
Last Update Date: 12/28/2007
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):
NEIL PERRY (R1)
NEIL PERRY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC TRIP ON FAILURE OF STATION POWER TRANSFORMER
"This 4 hour notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) to report that Salem Unit 1 has experienced an automatic reactor trip. The trip was initiated by failure of 12 Station Power Transformer (SPT). The cause of the trip was the loss of two Reactor Coolant Pumps (RCP) (13 and 14). These RCPs were powered from 'F' and 'G' group busses (non safeguards), which were powered by 12 SPT.
"Post trip the following occurred: 11, 12 & 13 Auxiliary Feed Water (AFW) Pumps [automatically] started after the trip due to valid steam generator low levels (14%) as expected. The automatic start of the Auxiliary Feedwater System due to a valid steam generator low level is an ESF actuation and is an 8 hour report in accordance with 10 CFR 50.72 (b)(3)(iv)(B). 13 AFW pump was tripped [in accordance with] the Emergency Operating Procedure and will be returned to an operable condition following recovery of steam generator levels.
"All control rods fully inserted following the trip. No ECCS actuation occurred. There was no major equipment out of service prior to the event. No injuries resulted from this event.
"Salem Unit 1 is currently in Mode 3. Reactor Coolant System pressure is at 2235 PSIG and temperature is at 547 degrees with decay heat removal via the Main Steam Dump System. Unit 1 has no active shutdown [Technical Specification] action statements in effect.
"The NRC Resident Inspector has been notified."
"This 4 hour notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) to report that Salem Unit 1 has experienced an automatic reactor trip. The trip was initiated by failure of 12 Station Power Transformer (SPT). The cause of the trip was the loss of two Reactor Coolant Pumps (RCP) (13 and 14). These RCPs were powered from 'F' and 'G' group busses (non safeguards), which were powered by 12 SPT.
"Post trip the following occurred: 11, 12 & 13 Auxiliary Feed Water (AFW) Pumps [automatically] started after the trip due to valid steam generator low levels (14%) as expected. The automatic start of the Auxiliary Feedwater System due to a valid steam generator low level is an ESF actuation and is an 8 hour report in accordance with 10 CFR 50.72 (b)(3)(iv)(B). 13 AFW pump was tripped [in accordance with] the Emergency Operating Procedure and will be returned to an operable condition following recovery of steam generator levels.
"All control rods fully inserted following the trip. No ECCS actuation occurred. There was no major equipment out of service prior to the event. No injuries resulted from this event.
"Salem Unit 1 is currently in Mode 3. Reactor Coolant System pressure is at 2235 PSIG and temperature is at 547 degrees with decay heat removal via the Main Steam Dump System. Unit 1 has no active shutdown [Technical Specification] action statements in effect.
"The NRC Resident Inspector has been notified."