Event Notification Report for June 17, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/16/2002 - 06/17/2002
EVENT NUMBERS
3899638997389983899939000
Power Reactor
Event Number: 38996
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: BILL BANDHAUER
HQ OPS Officer: STEVE SANDIN
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: BILL BANDHAUER
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/17/2002
Notification Time: 14:16 [ET]
Event Date: 06/17/2002
Event Time: 10:48 [EDT]
Last Update Date: 06/17/2002
Notification Time: 14:16 [ET]
Event Date: 06/17/2002
Event Time: 10:48 [EDT]
Last Update Date: 06/17/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
KERRY LANDIS (R2)
KERRY LANDIS (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
AUTOSTART OF THE "A" EDG DUE TO THE LOSS OF THE OFFSITE POWER TRANSFORMER DURING INCLEMENT WEATHER
"On June 17, 2002 at 1048, the 'A' Emergency Diesel generator automatically actuated and powered the 'A' 4160V Engineered Safeguards bus. This event is Reportable as an 8-Hour Notification per 10 CFR 50.72 (b) (3) (iv) (B) (8). The actuation occurred due to the loss of the Off Site Power Transformer. The cause of the transformer loss has not been identified but is suspected to be related to inclement weather."
The Off Site Power Transformer has been tagged out for inspection although there is no apparent damage. Operations is evaluating placing the Backup ES Transformer (BEST) in service. The 'A' 4160V ES bus remains energized with the 'A EDG in service at this time. Unit 3 is currently in a 72-hour LCO A/S 3.8.1 Condition A.
The licensee informed the NRC Resident Inspector.
"On June 17, 2002 at 1048, the 'A' Emergency Diesel generator automatically actuated and powered the 'A' 4160V Engineered Safeguards bus. This event is Reportable as an 8-Hour Notification per 10 CFR 50.72 (b) (3) (iv) (B) (8). The actuation occurred due to the loss of the Off Site Power Transformer. The cause of the transformer loss has not been identified but is suspected to be related to inclement weather."
The Off Site Power Transformer has been tagged out for inspection although there is no apparent damage. Operations is evaluating placing the Backup ES Transformer (BEST) in service. The 'A' 4160V ES bus remains energized with the 'A EDG in service at this time. Unit 3 is currently in a 72-hour LCO A/S 3.8.1 Condition A.
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 38997
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: BRUCE SHICK
HQ OPS Officer: FANGIE JONES
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: BRUCE SHICK
HQ OPS Officer: FANGIE JONES
Notification Date: 06/17/2002
Notification Time: 15:43 [ET]
Event Date: 06/17/2002
Event Time: 15:00 [EDT]
Last Update Date: 06/17/2002
Notification Time: 15:43 [ET]
Event Date: 06/17/2002
Event Time: 15:00 [EDT]
Last Update Date: 06/17/2002
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):
JAMES TRAPP (R1)
JAMES TRAPP (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Standby |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
17 SIRENS FAILED WEEKLY SILENT TEST
The licensee was conducting the weekly silent test for the offsite notification sirens. 17 of them failed the test in Calvert County. Technicians are troubleshooting the system and believe they will have them operational by tonight.
Alternate means of notification have been put in place.
The licensee has notified the NRC Resident Inspector.
The licensee was conducting the weekly silent test for the offsite notification sirens. 17 of them failed the test in Calvert County. Technicians are troubleshooting the system and believe they will have them operational by tonight.
Alternate means of notification have been put in place.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 38998
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: FANGIE JONES
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: FANGIE JONES
Notification Date: 06/17/2002
Notification Time: 16:54 [ET]
Event Date: 06/17/2002
Event Time: 13:00 [EDT]
Last Update Date: 06/17/2002
Notification Time: 16:54 [ET]
Event Date: 06/17/2002
Event Time: 13:00 [EDT]
Last Update Date: 06/17/2002
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):
JAMES TRAPP (R1)
JAMES TRAPP (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
PROMPT ALERT SYSTEM INOPERABLE
The licensee determined that the "Prompt Alert Notification System" was inoperable, believed to be caused by a failed siren. Troubleshooting is ongoing and repairs are expected to be completed today.
Alternate means of notification have been put in place.
The licensee intends to notify the NRC Resident Inspector and has notified the Local and State Agencies.
The licensee determined that the "Prompt Alert Notification System" was inoperable, believed to be caused by a failed siren. Troubleshooting is ongoing and repairs are expected to be completed today.
Alternate means of notification have been put in place.
The licensee intends to notify the NRC Resident Inspector and has notified the Local and State Agencies.
Other Nuclear Material
Event Number: 38999
Rep Org: MIDWEST ENGINEERING
Licensee: MIDWEST ENGINEERING
Region: 3
City: MUNSTER State: IN
County:
License #: 48-26074-01
Agreement: N
Docket:
NRC Notified By: JIM KURNIK
HQ OPS Officer: FANGIE JONES
Licensee: MIDWEST ENGINEERING
Region: 3
City: MUNSTER State: IN
County:
License #: 48-26074-01
Agreement: N
Docket:
NRC Notified By: JIM KURNIK
HQ OPS Officer: FANGIE JONES
Notification Date: 06/17/2002
Notification Time: 17:43 [ET]
Event Date: 06/17/2002
Event Time: 16:30 [CDT]
Last Update Date: 06/17/2002
Notification Time: 17:43 [ET]
Event Date: 06/17/2002
Event Time: 16:30 [CDT]
Last Update Date: 06/17/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
ROGER LANKSBURY (R3)
LARRY CAMPER (NMSS)
ROGER LANKSBURY (R3)
LARRY CAMPER (NMSS)
TROXLER MOISTURE DENSITY GAUGE STOLEN FROM WORKER'S TRUCK
A Troxler moisture density gauge (model 3430) containing 8 millicuries of Cs-137 and 40 millicuries of Am-241/Be was stolen from a worker's truck parked at his home located in Griffith, IN. The gauge was last seen on 6/16/02 in the evening when it was locked up in the back of the worker's truck. It was discover missing 6/17/02 at about 1630 CDT. Griffith police department will be notified, the first call was to the NRC Operations Center.
A Troxler moisture density gauge (model 3430) containing 8 millicuries of Cs-137 and 40 millicuries of Am-241/Be was stolen from a worker's truck parked at his home located in Griffith, IN. The gauge was last seen on 6/16/02 in the evening when it was locked up in the back of the worker's truck. It was discover missing 6/17/02 at about 1630 CDT. Griffith police department will be notified, the first call was to the NRC Operations Center.
Power Reactor
Event Number: 39000
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: M. N. BROWN
HQ OPS Officer: FANGIE JONES
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: M. N. BROWN
HQ OPS Officer: FANGIE JONES
Notification Date: 06/17/2002
Notification Time: 22:43 [ET]
Event Date: 06/17/2002
Event Time: 18:55 [EDT]
Last Update Date: 06/17/2002
Notification Time: 22:43 [ET]
Event Date: 06/17/2002
Event Time: 18:55 [EDT]
Last Update Date: 06/17/2002
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):
KERRY LANDIS (R2)
KERRY LANDIS (R2)
| 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 |
REACTOR TRIP ON LOW-LOW STEAM GENERATOR LEVEL
The plant was operating at 100% when the 'C' main feedwater pump tripped for an unknown reason, trouble shooting continues. The turbine load was being reduced to a power level the remaining feedwater pumps could sustain. The level in steam generator 'A' dropped to the low-low level trip setpoint before the load reduction could be completed. The reactor trip occurred at 1902 EDT. All systems functioned as expected except for the nuclear instrument intermediate range N35 which was very erratic with fluctuations of 6 decades.
The emergency feedwater system motor and turbine driven pumps started as expected on low-low steam generator level (ESF signal) and continue to provide feedwater flow to the steam generators. Excess heat is being removed via the steam dumps to the main condenser. The plant is stable in Mode 3.
The licensee notified the NRC Resident Inspector.
The plant was operating at 100% when the 'C' main feedwater pump tripped for an unknown reason, trouble shooting continues. The turbine load was being reduced to a power level the remaining feedwater pumps could sustain. The level in steam generator 'A' dropped to the low-low level trip setpoint before the load reduction could be completed. The reactor trip occurred at 1902 EDT. All systems functioned as expected except for the nuclear instrument intermediate range N35 which was very erratic with fluctuations of 6 decades.
The emergency feedwater system motor and turbine driven pumps started as expected on low-low steam generator level (ESF signal) and continue to provide feedwater flow to the steam generators. Excess heat is being removed via the steam dumps to the main condenser. The plant is stable in Mode 3.
The licensee notified the NRC Resident Inspector.