Event Notification Report for November 16, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/15/2002 - 11/16/2002
Power Reactor
Event Number: 39378
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: E. HINSON
HQ OPS Officer: ARLON COSTA
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: E. HINSON
HQ OPS Officer: ARLON COSTA
Notification Date: 11/16/2002
Notification Time: 10:31 [ET]
Event Date: 11/16/2002
Event Time: 08:40 [CST]
Last Update Date: 11/16/2002
Notification Time: 10:31 [ET]
Event Date: 11/16/2002
Event Time: 08:40 [CST]
Last Update Date: 11/16/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
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 | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
SECURITY REPORT INVOLVING A LOST ACCESS BADGE
Immediate compensatory measures taken upon discovery. Licensee notified the NRC resident inspector. Contact the Headquarters Operations Officer for details.
Immediate compensatory measures taken upon discovery. Licensee notified the NRC resident inspector. Contact the Headquarters Operations Officer for details.
Power Reactor
Event Number: 39379
Facility: COOK
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD HACKMAN
HQ OPS Officer: STEVE SANDIN
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD HACKMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/16/2002
Notification Time: 13:18 [ET]
Event Date: 11/16/2002
Event Time: 09:20 [EST]
Last Update Date: 11/16/2002
Notification Time: 13:18 [ET]
Event Date: 11/16/2002
Event Time: 09:20 [EST]
Last Update Date: 11/16/2002
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):
BRUCE BURGESS (R3)
BRUCE BURGESS (R3)
| 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 SODIUM HYPOCHLORITE DISCHARGE TO LAKE MICHIGAN
"Notification was made on 11/16/02 at 1150 to the National Response Center and at 1205 to the Michigan Dept. of Environmental Quality of a Sodium Hypochlorite discharge to Lake Michigan that exceeded the permitted concentration. On 11/16/02 at 0920, a chemist discovered and isolated a leak from the Hypochlorite facility. Circulating Water discharge Total Residual Chlorine (TRC) was measured at that time to be 0.3ppm. The concentration dropped below the permit limit of 0.038ppm at 0930. A recorded rise in TRC indicated that the leakage started at 0015. The Unit 1 TRC High Alarm did not function. The recorded TRC concentration ranged between 0.26 and 0.4ppm during the 9 hour period. Hypochlorite tank level change indicates that approximately 1080 gallons of 12% sodium hypochlorite solution was discharged from the leak to the forebay and out of the Circulating Water discharge to Lake Michigan. No environmental impact is expected from the discharge based on the chlorine concentration and release duration."
The licensee notified the NRC resident inspector.
"Notification was made on 11/16/02 at 1150 to the National Response Center and at 1205 to the Michigan Dept. of Environmental Quality of a Sodium Hypochlorite discharge to Lake Michigan that exceeded the permitted concentration. On 11/16/02 at 0920, a chemist discovered and isolated a leak from the Hypochlorite facility. Circulating Water discharge Total Residual Chlorine (TRC) was measured at that time to be 0.3ppm. The concentration dropped below the permit limit of 0.038ppm at 0930. A recorded rise in TRC indicated that the leakage started at 0015. The Unit 1 TRC High Alarm did not function. The recorded TRC concentration ranged between 0.26 and 0.4ppm during the 9 hour period. Hypochlorite tank level change indicates that approximately 1080 gallons of 12% sodium hypochlorite solution was discharged from the leak to the forebay and out of the Circulating Water discharge to Lake Michigan. No environmental impact is expected from the discharge based on the chlorine concentration and release duration."
The licensee notified the NRC resident inspector.
Power Reactor
Event Number: 39380
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN PIERCE
HQ OPS Officer: STEVE SANDIN
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN PIERCE
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/16/2002
Notification Time: 22:49 [ET]
Event Date: 11/16/2002
Event Time: 20:42 [CST]
Last Update Date: 11/19/2002
Notification Time: 22:49 [ET]
Event Date: 11/16/2002
Event Time: 20:42 [CST]
Last Update Date: 11/19/2002
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):
CHUCK CAIN (R4)
ELLIS MERSCHOFF (R4)
ELMO COLLINS (R4)
CHUCK CAIN (R4)
ELLIS MERSCHOFF (R4)
ELMO COLLINS (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNIT 1 EXPERIENCED A MANUAL REACTOR TRIP DUE TO A LOSS OF OPEN LOOP COOLING WATER
"The South Texas Project makes the following 4 hour non-emergency report of a manual Reactor Protection System actuation per 10CFR50.72.b.2.ii.
"At 20:42 on 11/16/02 Unit 1 reactor was manually tripped due to a loss of open loop cooling water. Reports indicated flooding in the circulating water intake structure due to a problem with circulating water pump #11, which caused the loss of open loop cooling."
Operators received a loss of open loop cooling which supplies auxiliary cooling to the main generator. Per procedure, Unit 1 was manually tripped. Upon investigation, a 4-6 inch crack in circulating water pump #11 housing was discovered. A preliminary review indicates that water may have electrically shorted the three operating open loop cooling pumps which are also located in the intake structure.
Unit 1 is currently stable in mode 3 with all auxiliary feedwater pumps in service. Vacuum in the main condenser is presently 27 inches with both circulating water pumps 13 and 14 operating. All rods fully inserted. Normal offsite power is available and no electrical buses were lost as a result of the flooding although electrical maintenance is investigating several electrical ground alarms. The licensee reviewed their Emergency Plan and determined that the criteria for declaration of an NOUE was not satisfied. The licensee notified the NRC resident inspector and does not plan on a press release at this time.
* * * UPDATE ON 11/19/02 AT 1741 EST FROM GREG JANAK TO HOWIE CROUCH * * *
This is a supplemental notification to EVENT # 39380 which was for a 4 hour non-emergency report of a manual Reactor Protection System Actuation.
At 20:42 [CST] on 11/16/02 following the Unit 1 manual reactor trip, the Auxiliary Feedwater System actuated as expected on Steam Generator low-low water level. This is being reported under 10CFR50.72(b)(3)(iv)(A).
Licensee reported that lowest steam generator water level observed was 17% on one steam generator.
"The South Texas Project makes the following 4 hour non-emergency report of a manual Reactor Protection System actuation per 10CFR50.72.b.2.ii.
"At 20:42 on 11/16/02 Unit 1 reactor was manually tripped due to a loss of open loop cooling water. Reports indicated flooding in the circulating water intake structure due to a problem with circulating water pump #11, which caused the loss of open loop cooling."
Operators received a loss of open loop cooling which supplies auxiliary cooling to the main generator. Per procedure, Unit 1 was manually tripped. Upon investigation, a 4-6 inch crack in circulating water pump #11 housing was discovered. A preliminary review indicates that water may have electrically shorted the three operating open loop cooling pumps which are also located in the intake structure.
Unit 1 is currently stable in mode 3 with all auxiliary feedwater pumps in service. Vacuum in the main condenser is presently 27 inches with both circulating water pumps 13 and 14 operating. All rods fully inserted. Normal offsite power is available and no electrical buses were lost as a result of the flooding although electrical maintenance is investigating several electrical ground alarms. The licensee reviewed their Emergency Plan and determined that the criteria for declaration of an NOUE was not satisfied. The licensee notified the NRC resident inspector and does not plan on a press release at this time.
* * * UPDATE ON 11/19/02 AT 1741 EST FROM GREG JANAK TO HOWIE CROUCH * * *
This is a supplemental notification to EVENT # 39380 which was for a 4 hour non-emergency report of a manual Reactor Protection System Actuation.
At 20:42 [CST] on 11/16/02 following the Unit 1 manual reactor trip, the Auxiliary Feedwater System actuated as expected on Steam Generator low-low water level. This is being reported under 10CFR50.72(b)(3)(iv)(A).
Licensee reported that lowest steam generator water level observed was 17% on one steam generator.