Event Notification Report for August 19, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/18/2009 - 08/19/2009
EVENT NUMBERS
45278452764527745274
Power Reactor
Event Number: 45278
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVE DEES
HQ OPS Officer: JOHN KNOKE
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVE DEES
HQ OPS Officer: JOHN KNOKE
Notification Date: 08/19/2009
Notification Time: 20:38 [ET]
Event Date: 08/19/2009
Event Time: 15:49 [CDT]
Last Update Date: 08/25/2009
Notification Time: 20:38 [ET]
Event Date: 08/19/2009
Event Time: 15:49 [CDT]
Last Update Date: 08/25/2009
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):
WILLIAM JONES (R4DO)
WILLIAM JONES (R4DO)
| 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 CAUSED BY TURBINE TRIP
"Wolf Creek experienced a reactor trip at 1549 CDT. The first out annunciator was TURBINE TRIP and P9 Reactor TRIP. At approximately the same time the unit experienced a momentary loss of offsite power.
"The emergency diesel generators started [and loaded] as expected to supply power to the safety busses due to the loss of offsite power. Auxiliary Feedwater and Feedwater Isolation actuations occurred as expected. All control rods inserted into the core during the trip. All Reactor Coolant Pumps tripped due to the loss of offsite power. Decay heat was initially being removed by the Steam Generator Atmospheric Relief Valves.
"Presently the plant is stable in Mode 3. The 'D' Reactor Coolant Pump has been restarted. The licensee is continuing to investigate the cause of the trip."
The atmospheric relief valves lifted for approximately 10 minutes, however there was no primary to secondary leakage. Both A & B EDG's loaded for about 2 minutes. At the present time the electrical lineup is normal and the EDG's are shutdown. Plant is at Normal Operating Pressure and just below Normal Operating Temperature. Decay heat and S/G levels are being maintained with the Auxiliary Feedwater pumps.
The licensee has notified the NRC Resident Inspector. The Licensee may issue a press release on this event.
* * * UPDATE FROM DAVE DEES TO VINCE KLCO AT 1135 EDT ON 8/21/2009 * * *
The atmospheric relief valves lifted for approximately 2 minutes, not 10 minutes as stated above. Also the A & B EDG's did not load for only 2 minutes. Actually "the B Safety Bus was paralleled to its normal off site source and the B Emergency Diesel was realigned for auto-start at 1740. The A Safety Bus was paralleled to its normal off site source and the A Emergency Diesel was realigned for auto-start at 1844."
Notified the R4DO (Jones).
* * * UPDATE FROM DAVE DEES TO VINCE KLCO AT 1730 EDT ON 8/25/2009 * * *
"The initial report stated that there was no primary to secondary leakage. Actual primary to secondary leakage as measured on 8/14/2009 was a value of less than 0.722 gallons per day."
The licensee notified the NRC Resident Inspector.
Notified the R4DO (Miller)
"Wolf Creek experienced a reactor trip at 1549 CDT. The first out annunciator was TURBINE TRIP and P9 Reactor TRIP. At approximately the same time the unit experienced a momentary loss of offsite power.
"The emergency diesel generators started [and loaded] as expected to supply power to the safety busses due to the loss of offsite power. Auxiliary Feedwater and Feedwater Isolation actuations occurred as expected. All control rods inserted into the core during the trip. All Reactor Coolant Pumps tripped due to the loss of offsite power. Decay heat was initially being removed by the Steam Generator Atmospheric Relief Valves.
"Presently the plant is stable in Mode 3. The 'D' Reactor Coolant Pump has been restarted. The licensee is continuing to investigate the cause of the trip."
The atmospheric relief valves lifted for approximately 10 minutes, however there was no primary to secondary leakage. Both A & B EDG's loaded for about 2 minutes. At the present time the electrical lineup is normal and the EDG's are shutdown. Plant is at Normal Operating Pressure and just below Normal Operating Temperature. Decay heat and S/G levels are being maintained with the Auxiliary Feedwater pumps.
The licensee has notified the NRC Resident Inspector. The Licensee may issue a press release on this event.
* * * UPDATE FROM DAVE DEES TO VINCE KLCO AT 1135 EDT ON 8/21/2009 * * *
The atmospheric relief valves lifted for approximately 2 minutes, not 10 minutes as stated above. Also the A & B EDG's did not load for only 2 minutes. Actually "the B Safety Bus was paralleled to its normal off site source and the B Emergency Diesel was realigned for auto-start at 1740. The A Safety Bus was paralleled to its normal off site source and the A Emergency Diesel was realigned for auto-start at 1844."
Notified the R4DO (Jones).
* * * UPDATE FROM DAVE DEES TO VINCE KLCO AT 1730 EDT ON 8/25/2009 * * *
"The initial report stated that there was no primary to secondary leakage. Actual primary to secondary leakage as measured on 8/14/2009 was a value of less than 0.722 gallons per day."
The licensee notified the NRC Resident Inspector.
Notified the R4DO (Miller)
General Information or Other
Event Number: 45276
Rep Org: COLORADO DEPT OF HEALTH
Licensee: SUNCOR ENERGY
Region: 4
City: DENVER State: CO
County: DENVER
License #: 615-02
Agreement: Y
Docket:
NRC Notified By: JAMES GRICE
HQ OPS Officer: KARL DIEDERICH
Licensee: SUNCOR ENERGY
Region: 4
City: DENVER State: CO
County: DENVER
License #: 615-02
Agreement: Y
Docket:
NRC Notified By: JAMES GRICE
HQ OPS Officer: KARL DIEDERICH
Notification Date: 08/19/2009
Notification Time: 15:43 [ET]
Event Date: 08/19/2009
Event Time: 00:00 [MDT]
Last Update Date: 08/19/2009
Notification Time: 15:43 [ET]
Event Date: 08/19/2009
Event Time: 00:00 [MDT]
Last Update Date: 08/19/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WILLIAM JONES (R4DO)
LARRY CAMPER (FSME)
WILLIAM JONES (R4DO)
LARRY CAMPER (FSME)
AGREEMENT STATE REPORT - FLOW GAUGE SHUTTER UNABLE TO CLOSE
The following report was received from the state via e-mail:
"A Colorado Specific licensee, Suncor Energy (USA) Inc. (License # 615-02), reported that a fixed nuclear gauge was having shutter problems. The shutter was unable to be returned to a closed position during a routine check. The gauge is an Ohmart Vega Model SH-F2 containing 250 mCi of Cs-137 (serial number M-7105). The licensee plans to have a Ohmart Vega Technician on site within the next few weeks to take a look at the gauge and determine whether or not the gauge can be fixed or [if] it needs to be replaced."
The gauge is a flow gauge on a pipe in an oil refinery, and the shutter is normally open during facility operation. The radiological control area is normally maintained in force during operations, and remains in force. No inadvertent exposures are expected to have occurred.
The following report was received from the state via e-mail:
"A Colorado Specific licensee, Suncor Energy (USA) Inc. (License # 615-02), reported that a fixed nuclear gauge was having shutter problems. The shutter was unable to be returned to a closed position during a routine check. The gauge is an Ohmart Vega Model SH-F2 containing 250 mCi of Cs-137 (serial number M-7105). The licensee plans to have a Ohmart Vega Technician on site within the next few weeks to take a look at the gauge and determine whether or not the gauge can be fixed or [if] it needs to be replaced."
The gauge is a flow gauge on a pipe in an oil refinery, and the shutter is normally open during facility operation. The radiological control area is normally maintained in force during operations, and remains in force. No inadvertent exposures are expected to have occurred.
Power Reactor
Event Number: 45277
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVE DEES
HQ OPS Officer: JOHN KNOKE
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVE DEES
HQ OPS Officer: JOHN KNOKE
Notification Date: 08/19/2009
Notification Time: 20:33 [ET]
Event Date: 08/19/2009
Event Time: 15:00 [CDT]
Last Update Date: 08/19/2009
Notification Time: 20:33 [ET]
Event Date: 08/19/2009
Event Time: 15:00 [CDT]
Last Update Date: 08/19/2009
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):
WILLIAM JONES (R4DO)
WILLIAM JONES (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 |
TIME TO ESTABLISH CHARGING FLOW EXCEEDED THERMAL HYDRAULIC ANALYSIS
"Valve BNHV8812A RWST to RHR Pump A Isolation is manually closed in OFN RP-017, Control Room Evacuation, in response to a control room fire. Simulated timing assumed approximately 1 minute to close the valve. Discussions with the MOV engineer revealed that the valve takes 600 turns to close. Operations Standing Order 1 limits the number of hand wheel turns to 60 per minute. At a closure rate of 60 turns per minute, it will take a minimum of 10 minutes to close the valve, rather than the assumed 1-minute. The additional 9 minutes necessary to close the valve will delay the completion of subsequent steps. Most significantly, the time to establish charging flow increases from 20 minutes to a minimum of 29 minutes. Thermal hydraulic analysis documented in SA-08-006 assumed the charging flow will be established within 28 minutes. Therefore the time to establish charging flow exceeds that assumed in the thermal hydraulic analysis by at least 1 minute. Compensatory actions have been put in place in order to accomplish this task within the time allowed by the thermal hydraulic analysis."
The licensee has notified the NRC Resident Inspector.
"Valve BNHV8812A RWST to RHR Pump A Isolation is manually closed in OFN RP-017, Control Room Evacuation, in response to a control room fire. Simulated timing assumed approximately 1 minute to close the valve. Discussions with the MOV engineer revealed that the valve takes 600 turns to close. Operations Standing Order 1 limits the number of hand wheel turns to 60 per minute. At a closure rate of 60 turns per minute, it will take a minimum of 10 minutes to close the valve, rather than the assumed 1-minute. The additional 9 minutes necessary to close the valve will delay the completion of subsequent steps. Most significantly, the time to establish charging flow increases from 20 minutes to a minimum of 29 minutes. Thermal hydraulic analysis documented in SA-08-006 assumed the charging flow will be established within 28 minutes. Therefore the time to establish charging flow exceeds that assumed in the thermal hydraulic analysis by at least 1 minute. Compensatory actions have been put in place in order to accomplish this task within the time allowed by the thermal hydraulic analysis."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 45274
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: DAVID AXLINE
HQ OPS Officer: KARL DIEDERICH
Region: 4 State: CA
Unit: [] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: DAVID AXLINE
HQ OPS Officer: KARL DIEDERICH
Notification Date: 08/19/2009
Notification Time: 16:19 [ET]
Event Date: 08/19/2009
Event Time: 11:50 [PDT]
Last Update Date: 08/19/2009
Notification Time: 16:19 [ET]
Event Date: 08/19/2009
Event Time: 11:50 [PDT]
Last Update Date: 08/19/2009
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):
WILLIAM JONES (R4DO)
WILLIAM JONES (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 99 | Power Operation | 99 | Power Operation |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION FOR INADVERTANT ACTUATION OF SIRENS FOR 10 SECONDS
During an exercise, sirens for the city of San Clemente (19 of 52 total sirens) were inadvertently actuated for approximately ten seconds. The licensee made off-site notifications to California FEMA, California Dept of Health, California State Parks, Camp Pendleton, and the cities of San Clemente, San Juan Capistrano, and Dana Point.
The licensee has notified the NRC Resident Inspector.
During an exercise, sirens for the city of San Clemente (19 of 52 total sirens) were inadvertently actuated for approximately ten seconds. The licensee made off-site notifications to California FEMA, California Dept of Health, California State Parks, Camp Pendleton, and the cities of San Clemente, San Juan Capistrano, and Dana Point.
The licensee has notified the NRC Resident Inspector.