Event Notification Report for May 01, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/30/2001 - 05/01/2001
Power Reactor
Event Number: 37960
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: ROBERT RAY
HQ OPS Officer: STEVE SANDIN
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: ROBERT RAY
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/02/2001
Notification Time: 14:50 [ET]
Event Date: 05/01/2001
Event Time: 15:31 [EDT]
Last Update Date: 05/02/2001
Notification Time: 14:50 [ET]
Event Date: 05/01/2001
Event Time: 15:31 [EDT]
Last Update Date: 05/02/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JAY HENSON (R2)
JAY HENSON (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
24-HOUR OPERATING LICENSE NPF-12, SECTION 2 REPORT DUE TO EXCEEDING LICENSED POWER LIMIT
"V. C. Summer Station experienced a plant transient as a result of a feedwater heater level transmitter failure. The transient resulted in core power exceeding licensed limit of 2900 megawatts thermal (MWT) at 1531 hours on May 1, 2001. Preparations were underway to reduce power when the feedwater heaters were reset and power stabilized at less than 2900 MWT. The duration of the transient was less than seven minutes.
"The loss of feedwater heater string resulted in a lowering of steam generator feedwater supply temperature and subsequent drop in reactor coolant system Tcold (cold leg temperature).
"Subsequent investigation by Engineering and Independent Safety analyses Group personnel indicated core power reached 102.7% of maximum power as indicated by core differential temperature (delta T). Core delta T was determined to be the most reliable indication of core power during this transient.
" The cause of the feedwater heater level transmitter failure is currently under investigation. No automatic load reduction or other safety actuation occurred."
The licensee informed the NRC resident inspector.
"V. C. Summer Station experienced a plant transient as a result of a feedwater heater level transmitter failure. The transient resulted in core power exceeding licensed limit of 2900 megawatts thermal (MWT) at 1531 hours on May 1, 2001. Preparations were underway to reduce power when the feedwater heaters were reset and power stabilized at less than 2900 MWT. The duration of the transient was less than seven minutes.
"The loss of feedwater heater string resulted in a lowering of steam generator feedwater supply temperature and subsequent drop in reactor coolant system Tcold (cold leg temperature).
"Subsequent investigation by Engineering and Independent Safety analyses Group personnel indicated core power reached 102.7% of maximum power as indicated by core differential temperature (delta T). Core delta T was determined to be the most reliable indication of core power during this transient.
" The cause of the feedwater heater level transmitter failure is currently under investigation. No automatic load reduction or other safety actuation occurred."
The licensee informed the NRC resident inspector.
Power Reactor
Event Number: 37957
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: GORDON PICKERING
HQ OPS Officer: STEVE SANDIN
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: GORDON PICKERING
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/01/2001
Notification Time: 20:22 [ET]
Event Date: 05/01/2001
Event Time: 17:00 [CDT]
Last Update Date: 05/01/2001
Notification Time: 20:22 [ET]
Event Date: 05/01/2001
Event Time: 17:00 [CDT]
Last Update Date: 05/01/2001
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):
GAIL GOOD (R4)
GAIL GOOD (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNANALYZED CONDITION DUE TO INADEQUATE FIRE PROTECTION INVOLVING POWER SUPPLIES FOR EDG FUEL OIL TRANSFER PUMPS
"During a review of the site Appendix R program, W3 [Waterford 3] Engineering personnel discovered that the power supplies to both of the Emergency Diesel Generator Fuel Oil Transfer Pumps were not protected in accordance with 10CFR 50 Appendix R. The 480V power cables for both trains were found unprotected in Fire Area RAB 27. A fire in this room could potentially damage both Emergency Diesel Generator Fuel Oil Transfer Pumps power supply cables and would then impact the amount of time the Emergency Diesel Generators could operate. Due to the fire barriers missing on the above equipment and not providing the required amount of separation of safe shutdown trains, this condition is considered an unanalyzed condition that significantly degrades plant safety. This condition is reportable under 10CFR50.72(b)(3)(ii)(B) as an unanalyzed condition that significantly degrades plant safety.
"As a compensatory action fire watches have been established for the affected area in accordance with the site Technical Requirements Manual."
The licensee informed the NRC resident inspector.
"During a review of the site Appendix R program, W3 [Waterford 3] Engineering personnel discovered that the power supplies to both of the Emergency Diesel Generator Fuel Oil Transfer Pumps were not protected in accordance with 10CFR 50 Appendix R. The 480V power cables for both trains were found unprotected in Fire Area RAB 27. A fire in this room could potentially damage both Emergency Diesel Generator Fuel Oil Transfer Pumps power supply cables and would then impact the amount of time the Emergency Diesel Generators could operate. Due to the fire barriers missing on the above equipment and not providing the required amount of separation of safe shutdown trains, this condition is considered an unanalyzed condition that significantly degrades plant safety. This condition is reportable under 10CFR50.72(b)(3)(ii)(B) as an unanalyzed condition that significantly degrades plant safety.
"As a compensatory action fire watches have been established for the affected area in accordance with the site Technical Requirements Manual."
The licensee informed the NRC resident inspector.
Other Nuclear Material
Event Number: 37970
Rep Org: NEB DIV OF RADIOACTIVE MATERIALS
Licensee: NEB PUBLIC POWER DISTRICT
Region: 4
City: SUTHERLAND State: NE
County:
License #: NE-10-03-03
Agreement: Y
Docket:
NRC Notified By: JOHN FASSELL
HQ OPS Officer: DOUG WEAVER
Licensee: NEB PUBLIC POWER DISTRICT
Region: 4
City: SUTHERLAND State: NE
County:
License #: NE-10-03-03
Agreement: Y
Docket:
NRC Notified By: JOHN FASSELL
HQ OPS Officer: DOUG WEAVER
Notification Date: 05/07/2001
Notification Time: 16:22 [ET]
Event Date: 05/01/2001
Event Time: 00:00 [CDT]
Last Update Date: 05/08/2001
Notification Time: 16:22 [ET]
Event Date: 05/01/2001
Event Time: 00:00 [CDT]
Last Update Date: 05/08/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JEFF SHACKELFORD (R4)
LARRY CAMPER (NMSS)
SUSAN FRANT (NMSS)
JEFF SHACKELFORD (R4)
LARRY CAMPER (NMSS)
SUSAN FRANT (NMSS)
AGREEMENT STATE REPORT
The event took place at a coal plant where a nuclear gauge is installed on a coal chute. Not following established maintenance procedures led to workers entering the chute with the source exposed. A field of approximately 450 mr/hr was created. Whole body exposure was calculated based on a five hour stay time resulting in an estimate of 2.25 Rem for the most exposed individual. Two other individuals were involved with lower total exposure.
The source involved is believed to be Cs-137 with an activity between 100 and 200 mCi.
* * * UPDATE ON 05/08/01 AT 1429 ET BY JOHN FASSELL TAKEN BY MACKINNON * * *
Four workers were exposed instead of three and all four of the workers were radiation workers for the Neb Public Power District. Calculated whole body radiation exposure to the four workers: 2250 mrem, 1361 mrem, 611 mrem, and 450 mrem. The whole body dose was based on total exposure time multiplied by the maximum measured rate at the beam port, 450 mrem/hr. The individuals were approximately one foot away from the beam port
The operations center informed the R4DO (Shackelford) and NMSS EO (Hickey).
* * * UPDATE AT 1300 EDT ON 5/11/01 BY JOHN FASSELL TO FANGIE JONES * * *
Three of the workers have been determined to be members of the public and only one of the workers is a radiation worker. Further evaluation of the doses has been done with consideration to time motion study, geometry, surveys, and shielding by a utility company CHP. The radiation worker who was reported at 1361 mrem is now at 182 mrem. The workers (considered members of the public) reported at 2250 mrem is now at 285 mrem, reported at 611 mrem is now 87 mrem, and reported at 450 mrem is now 57 mrem.
The R4DO (Jeff Shackelford) and NMSS (John Hickey).
The event took place at a coal plant where a nuclear gauge is installed on a coal chute. Not following established maintenance procedures led to workers entering the chute with the source exposed. A field of approximately 450 mr/hr was created. Whole body exposure was calculated based on a five hour stay time resulting in an estimate of 2.25 Rem for the most exposed individual. Two other individuals were involved with lower total exposure.
The source involved is believed to be Cs-137 with an activity between 100 and 200 mCi.
* * * UPDATE ON 05/08/01 AT 1429 ET BY JOHN FASSELL TAKEN BY MACKINNON * * *
Four workers were exposed instead of three and all four of the workers were radiation workers for the Neb Public Power District. Calculated whole body radiation exposure to the four workers: 2250 mrem, 1361 mrem, 611 mrem, and 450 mrem. The whole body dose was based on total exposure time multiplied by the maximum measured rate at the beam port, 450 mrem/hr. The individuals were approximately one foot away from the beam port
The operations center informed the R4DO (Shackelford) and NMSS EO (Hickey).
* * * UPDATE AT 1300 EDT ON 5/11/01 BY JOHN FASSELL TO FANGIE JONES * * *
Three of the workers have been determined to be members of the public and only one of the workers is a radiation worker. Further evaluation of the doses has been done with consideration to time motion study, geometry, surveys, and shielding by a utility company CHP. The radiation worker who was reported at 1361 mrem is now at 182 mrem. The workers (considered members of the public) reported at 2250 mrem is now at 285 mrem, reported at 611 mrem is now 87 mrem, and reported at 450 mrem is now 57 mrem.
The R4DO (Jeff Shackelford) and NMSS (John Hickey).