Event Notification Report for May 09, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/08/2001 - 05/09/2001
EVENT NUMBERS
379813798237976379773797837979
Power Reactor
Event Number: 37981
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: PATRICIA HARRISON
HQ OPS Officer: FANGIE JONES
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: PATRICIA HARRISON
HQ OPS Officer: FANGIE JONES
Notification Date: 05/10/2001
Notification Time: 13:43 [ET]
Event Date: 05/09/2001
Event Time: 15:00 [EDT]
Last Update Date: 05/10/2001
Notification Time: 13:43 [ET]
Event Date: 05/09/2001
Event Time: 15:00 [EDT]
Last Update Date: 05/10/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
WILLIAM COOK (R1)
WILLIAM COOK (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 |
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
INADVERTENT FAILURE TO INCLUDE INDIVIDUALS IN RANDOM DRUG SCREENING POOL
The licensee discovered that three individuals were inadvertently left out of the computerized list of individuals subject to random drug screening. Immediate compensatory actions have been taken.
The licensee intends to notify the NRC Resident Inspector.
The licensee discovered that three individuals were inadvertently left out of the computerized list of individuals subject to random drug screening. Immediate compensatory actions have been taken.
The licensee intends to notify the NRC Resident Inspector.
General Information or Other
Event Number: 37982
Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: PROFESSIONAL SERVICES INDUSTRIES
Region: 4
City: PORTLAND State: OR
County:
License #: ORE-90056
Agreement: Y
Docket:
NRC Notified By: TERRY LINDSEY
HQ OPS Officer: FANGIE JONES
Licensee: PROFESSIONAL SERVICES INDUSTRIES
Region: 4
City: PORTLAND State: OR
County:
License #: ORE-90056
Agreement: Y
Docket:
NRC Notified By: TERRY LINDSEY
HQ OPS Officer: FANGIE JONES
Notification Date: 05/10/2001
Notification Time: 14:57 [ET]
Event Date: 05/09/2001
Event Time: 14:00 [PDT]
Last Update Date: 05/10/2001
Notification Time: 14:57 [ET]
Event Date: 05/09/2001
Event Time: 14:00 [PDT]
Last Update Date: 05/10/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JEFF SHACKELFORD (R4)
FREDERICK STURZ (NMSS)
JEFF SHACKELFORD (R4)
FREDERICK STURZ (NMSS)
AGREEMENT STATE REPORT - IMPROPER RADIOGRAPHY OPERATION
The Oregon Department of Health Radiation Protection shut down a radiography operation in North Portland at 1400 PDT on 5/9/2001 by Professional Services Industries (PSI). There were no operating survey instruments, the operators did not have alarming dosimeters, and warning signs were not posted. There was a 2-mR line set up at 6 feet from the 80-curie source. There will be an enforcement conference at 1300 PDT on 5/11/2001.
The Oregon Department of Health Radiation Protection shut down a radiography operation in North Portland at 1400 PDT on 5/9/2001 by Professional Services Industries (PSI). There were no operating survey instruments, the operators did not have alarming dosimeters, and warning signs were not posted. There was a 2-mR line set up at 6 feet from the 80-curie source. There will be an enforcement conference at 1300 PDT on 5/11/2001.
Power Reactor
Event Number: 37976
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: CRAIG MOWREY
HQ OPS Officer: DOUG WEAVER
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: CRAIG MOWREY
HQ OPS Officer: DOUG WEAVER
Notification Date: 05/09/2001
Notification Time: 14:45 [ET]
Event Date: 05/09/2001
Event Time: 14:07 [EDT]
Last Update Date: 05/09/2001
Notification Time: 14:45 [ET]
Event Date: 05/09/2001
Event Time: 14:07 [EDT]
Last Update Date: 05/09/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
CHARLES R. OGLE (R2)
CHARLES R. OGLE (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 |
| 4 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNESCORTED ACCESS GRANTED INAPPROPRIATELY. IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY.
THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.
THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.
Power Reactor
Event Number: 37977
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVE VANDERKAMP
HQ OPS Officer: DOUG WEAVER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVE VANDERKAMP
HQ OPS Officer: DOUG WEAVER
Notification Date: 05/09/2001
Notification Time: 16:23 [ET]
Event Date: 05/09/2001
Event Time: 14:20 [CDT]
Last Update Date: 05/10/2001
Notification Time: 16:23 [ET]
Event Date: 05/09/2001
Event Time: 14:20 [CDT]
Last Update Date: 05/10/2001
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):
JEFF SHACKELFORD (R4)
JEFF SHACKELFORD (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
FIRE PROTECTION REQUIREMENTS NOT MET
It has been discovered that all necessary compensatory actions for inoperable fire barriers are not included in the stations operating procedures for conditions when the swing 125 VDC and 250 VDC battery chargers are in service supplying the 'B' DC Electrical subsystem. The required degree of separation per 10CFR50 Appendix R does not exist between divisions when either swing charger is connected to the 'B' DC Electrical subsystem. Use of the swing chargers is not a normal lineup but has occurred during the past three years. The uncompensated lack of an adequate fire barrier between divisions of safe shutdown equipment is considered an unanalyzed condition that significantly degrades plant safety.
The licensee notified the NRC resident inspector.
* * * UPDATED AT 2153 EDT ON 5/10/01 BY STEVE WHEELER TO FANGIE JONES * * *
"The purpose of this follow-up is to clarify statements made in the original report.
"The first statement in the report states that '....all necessary compensatory actions for inoperable fire barriers are not included in the station's operating procedures.' The only compensatory measures not included in procedures are those concerning providing a fire watch when the swing charger is in service.
"With respect to the statement regarding 'uncompensated lack of an adequate fire barrier between divisions of safe shutdown equipment is considered an unanalyzed condition,' the condition exists only when the swing charger is in service and a fire watch has not been established.
"The final statement concerning 'an unanalyzed condition that significantly degrades plant safety,' the District provides the following clarification. During the periods when no fire watch was established, no actual fire occurred in the fire area, no power was lost or interrupted and the batteries were functional."
The licensee notified the NRC Resident Inspector. The R4DO (Jeff Shackelford) was notified.
It has been discovered that all necessary compensatory actions for inoperable fire barriers are not included in the stations operating procedures for conditions when the swing 125 VDC and 250 VDC battery chargers are in service supplying the 'B' DC Electrical subsystem. The required degree of separation per 10CFR50 Appendix R does not exist between divisions when either swing charger is connected to the 'B' DC Electrical subsystem. Use of the swing chargers is not a normal lineup but has occurred during the past three years. The uncompensated lack of an adequate fire barrier between divisions of safe shutdown equipment is considered an unanalyzed condition that significantly degrades plant safety.
The licensee notified the NRC resident inspector.
* * * UPDATED AT 2153 EDT ON 5/10/01 BY STEVE WHEELER TO FANGIE JONES * * *
"The purpose of this follow-up is to clarify statements made in the original report.
"The first statement in the report states that '....all necessary compensatory actions for inoperable fire barriers are not included in the station's operating procedures.' The only compensatory measures not included in procedures are those concerning providing a fire watch when the swing charger is in service.
"With respect to the statement regarding 'uncompensated lack of an adequate fire barrier between divisions of safe shutdown equipment is considered an unanalyzed condition,' the condition exists only when the swing charger is in service and a fire watch has not been established.
"The final statement concerning 'an unanalyzed condition that significantly degrades plant safety,' the District provides the following clarification. During the periods when no fire watch was established, no actual fire occurred in the fire area, no power was lost or interrupted and the batteries were functional."
The licensee notified the NRC Resident Inspector. The R4DO (Jeff Shackelford) was notified.
Power Reactor
Event Number: 37978
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: ED HEINEMAN
HQ OPS Officer: DOUG WEAVER
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: ED HEINEMAN
HQ OPS Officer: DOUG WEAVER
Notification Date: 05/09/2001
Notification Time: 20:37 [ET]
Event Date: 05/09/2001
Event Time: 15:06 [CDT]
Last Update Date: 05/09/2001
Notification Time: 20:37 [ET]
Event Date: 05/09/2001
Event Time: 15:06 [CDT]
Last Update Date: 05/09/2001
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):
BRUCE JORGENSEN (R3)
BRUCE JORGENSEN (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 18 | Power Operation |
TECH SPEC REQUIRED SHUTDOWN
Initiation of a unit shutdown began at 1700 May 9, 2001, as required by T.S. 3.7.B because Unit 2 Diesel Generators D5 and D6 were declared inoperable at 1506. They were declared inoperable because it was determined that they may not be capable of long-term operation as assumed in the plant accident analyses. This determination is based on the discovery that the diesel fuel and lubricating fluids in the engines may be incompatible and may damage the engines based on a re-review of industry operating experience.
The plant will go to Mode 5 and remain their until corrective actions are complete.
The licensee notified the NRC resident inspector.
Initiation of a unit shutdown began at 1700 May 9, 2001, as required by T.S. 3.7.B because Unit 2 Diesel Generators D5 and D6 were declared inoperable at 1506. They were declared inoperable because it was determined that they may not be capable of long-term operation as assumed in the plant accident analyses. This determination is based on the discovery that the diesel fuel and lubricating fluids in the engines may be incompatible and may damage the engines based on a re-review of industry operating experience.
The plant will go to Mode 5 and remain their until corrective actions are complete.
The licensee notified the NRC resident inspector.
Power Reactor
Event Number: 37979
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: ED HEINEMAN
HQ OPS Officer: DOUG WEAVER
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: ED HEINEMAN
HQ OPS Officer: DOUG WEAVER
Notification Date: 05/09/2001
Notification Time: 21:53 [ET]
Event Date: 05/09/2001
Event Time: 20:05 [CDT]
Last Update Date: 05/09/2001
Notification Time: 21:53 [ET]
Event Date: 05/09/2001
Event Time: 20:05 [CDT]
Last Update Date: 05/09/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
BRUCE JORGENSEN (R3)
BRUCE JORGENSEN (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 12 | Power Operation | 0 | Hot Standby |
MANUAL TURBINE TRIP - AUTOMATIC REACTOR TRIP
Initiated manual turbine trip due to condenser vacuum differential pressure which resulted in an automatic reactor trip. Reactor power prior to the trip was 12.5%. The cause of the high condenser vacuum differential pressure is undetermined at this time.
All control rods fully inserted, reactor coolant pumps are running. The steam generators are being fed with auxiliary feed. Decay heat is being removed by dumping steam with the turbine bypass atmospheric dumps. There are no known S/G tube leaks.
The licensee notified the NRC resident inspector.
Initiated manual turbine trip due to condenser vacuum differential pressure which resulted in an automatic reactor trip. Reactor power prior to the trip was 12.5%. The cause of the high condenser vacuum differential pressure is undetermined at this time.
All control rods fully inserted, reactor coolant pumps are running. The steam generators are being fed with auxiliary feed. Decay heat is being removed by dumping steam with the turbine bypass atmospheric dumps. There are no known S/G tube leaks.
The licensee notified the NRC resident inspector.