Event Notification Report for August 18, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/17/2003 - 08/18/2003
Power Reactor
Event Number: 40086
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: R. HUBBARD
HQ OPS Officer: JOHN MacKINNON
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: R. HUBBARD
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/18/2003
Notification Time: 18:36 [ET]
Event Date: 08/18/2003
Event Time: 15:54 [CDT]
Last Update Date: 08/18/2003
Notification Time: 18:36 [ET]
Event Date: 08/18/2003
Event Time: 15:54 [CDT]
Last Update Date: 08/18/2003
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):
BLAIR SPITZBERG (R4)
BLAIR SPITZBERG (R4)
| 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 REACTOR TRIP DUE LOW LOW "B" STEAM GENERATOR WATER LEVEL
"At 1554 CDT on 08/18/2003 all four Steam Generators alarmed with Steam Flow/Feed Flow Mismatch followed by indication that there was no feedwater flow to the "B" Steam Generator. The reactor tripped approximately 20 seconds later on Steam Generator Low-Low Level, 23.5% Narrow Range, as required. A review of the plant computer information shows that event-initiating cause may be the unexplained closure of the "B" Feedwater Isolation Valve.
"All plant safety related systems operated as required. The Steam Dumps, which function to remove excess heat as the secondary systems shutdown, exhibited control problems when they were shifted from temperature control mode to steam pressure mode, as required by the emergency operating procedures. The Steam Dumps are currently operating and controlling in manual mode. When the reactor tripped all four Steam Generator Atmospheric Relief Valves opened, a normal response for a trip from full power. The "A" Steam Generator Atmospheric Relief Valve was slow to close in automatic. The valve was closed in manual and returned to automatic and is controlling properly.
"The plant is currently stable in Mode 3 at NOP and NOT while plant personnel investigate the causes of the trip and formulate the repair/restart plan."
All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed. The electrical grid is stable.
The NRC Resident Inspector is in the Control Room.
"At 1554 CDT on 08/18/2003 all four Steam Generators alarmed with Steam Flow/Feed Flow Mismatch followed by indication that there was no feedwater flow to the "B" Steam Generator. The reactor tripped approximately 20 seconds later on Steam Generator Low-Low Level, 23.5% Narrow Range, as required. A review of the plant computer information shows that event-initiating cause may be the unexplained closure of the "B" Feedwater Isolation Valve.
"All plant safety related systems operated as required. The Steam Dumps, which function to remove excess heat as the secondary systems shutdown, exhibited control problems when they were shifted from temperature control mode to steam pressure mode, as required by the emergency operating procedures. The Steam Dumps are currently operating and controlling in manual mode. When the reactor tripped all four Steam Generator Atmospheric Relief Valves opened, a normal response for a trip from full power. The "A" Steam Generator Atmospheric Relief Valve was slow to close in automatic. The valve was closed in manual and returned to automatic and is controlling properly.
"The plant is currently stable in Mode 3 at NOP and NOT while plant personnel investigate the causes of the trip and formulate the repair/restart plan."
All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed. The electrical grid is stable.
The NRC Resident Inspector is in the Control Room.
General Information or Other
Event Number: 40088
Rep Org: ILLINOIS DEPT OF NUCLEAR SAFETY
Licensee: RUSH NORTH MEDICAL CENTER
Region: 3
City: SKOKIE State: IL
County:
License #: IL-01578-01
Agreement: Y
Docket:
NRC Notified By: JOE KLINGER
HQ OPS Officer: JOHN MacKINNON
Licensee: RUSH NORTH MEDICAL CENTER
Region: 3
City: SKOKIE State: IL
County:
License #: IL-01578-01
Agreement: Y
Docket:
NRC Notified By: JOE KLINGER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/19/2003
Notification Time: 18:44 [ET]
Event Date: 08/18/2003
Event Time: 11:00 [CDT]
Last Update Date: 08/19/2003
Notification Time: 18:44 [ET]
Event Date: 08/18/2003
Event Time: 11:00 [CDT]
Last Update Date: 08/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
THOMAS KOZAK (R3)
E. WILLIAM BRACH (NMSS)
THOMAS KOZAK (R3)
E. WILLIAM BRACH (NMSS)
PATIENT EXCEEDED PRESCRIBED DOSE.
A patient was undergoing an intravascular brachytherapy procedure using a Novoste 40 mm. Sr-90 system with a prescribed dose of 23 gray. Due to difficulties retracting the source train to its shielded position, the exposure time was 5.09 minutes (one minute longer than the planned 4.09 minutes). Preliminary estimates indicate that the delivered dose exceeded the prescribed dose by approximately 25 percent. Novoste was notified and a Novoste representative went to the medical facility to investigate. The Novoste system will be sent to Novoste in Georgia for analysis. The licensee continues to investigate and refine the dose calculations and will submit the required written report as soon as possible.
Illinois assigned event number: IL030064.
A patient was undergoing an intravascular brachytherapy procedure using a Novoste 40 mm. Sr-90 system with a prescribed dose of 23 gray. Due to difficulties retracting the source train to its shielded position, the exposure time was 5.09 minutes (one minute longer than the planned 4.09 minutes). Preliminary estimates indicate that the delivered dose exceeded the prescribed dose by approximately 25 percent. Novoste was notified and a Novoste representative went to the medical facility to investigate. The Novoste system will be sent to Novoste in Georgia for analysis. The licensee continues to investigate and refine the dose calculations and will submit the required written report as soon as possible.
Illinois assigned event number: IL030064.