Event Notification Report for November 26, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/25/1999 - 11/26/1999
EVENT NUMBERS
36464364653646636467
Fuel Cycle Facility
Event Number: 36464
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: RON CRABTREE
HQ OPS Officer: LEIGH TROCINE
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: RON CRABTREE
HQ OPS Officer: LEIGH TROCINE
Notification Date: 11/26/1999
Notification Time: 06:46 [ET]
Event Date: 11/26/1999
Event Time: 03:00 [EST]
Last Update Date: 11/26/1999
Notification Time: 06:46 [ET]
Event Date: 11/26/1999
Event Time: 03:00 [EST]
Last Update Date: 11/26/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RONALD GARDNER (R3)
BRIAN SMITH (NMSS)
FRANK CONGEL (IRO)
RONALD GARDNER (R3)
BRIAN SMITH (NMSS)
FRANK CONGEL (IRO)
NRC BULLETIN 91-01 RESPONSE (4-HOUR REPORT) - LOSS OF SPACING AND MODERATION CONTROLS
The following text is a portion of a facsimile received from Portsmouth:
"On 11/26/99 at 0341 hours, the Plant Shift Superintendent (PSS) was notified that NCSA-PLANT062.A02 Nuclear Criticality Safety Approval (NCSA) requirements were not being met. A conical section of pipe removed during maintenance activities on cell 33-5-10 was staged less than 2 feet from other uranium-bearing piping in the cell housing. It was also identified that the flanged openings of the conical transition piece were not covered as required by NCSA-PLANT062.A02. [These issues were discovered at 0300 hours.]"
"This violated requirement #3 of NCSA-PLANT062.A02, which states in part: 'Both favorable and unfavorable types of uncomplicated handling (UH) equipment shall be spaced a minimum of 2 feet edge-to-edge from other uranium-bearing equipment.' Requirement #4, which states that openings/penetrations made during maintenance activities shall be covered to minimize the potential for moderator collection and moist air exposure when unattended, was also violated."
"This is reportable under NRC Bulletin 91-01, 4-hour criticality control."
"There was no loss of hazardous/radioactive material or radioactive/radiological contamination exposure as a result of this event."
Portsmouth personnel notified the NRC resident inspector and plan to notify the Department of Energy site representative.
The following text is a portion of a facsimile received from Portsmouth:
"On 11/26/99 at 0341 hours, the Plant Shift Superintendent (PSS) was notified that NCSA-PLANT062.A02 Nuclear Criticality Safety Approval (NCSA) requirements were not being met. A conical section of pipe removed during maintenance activities on cell 33-5-10 was staged less than 2 feet from other uranium-bearing piping in the cell housing. It was also identified that the flanged openings of the conical transition piece were not covered as required by NCSA-PLANT062.A02. [These issues were discovered at 0300 hours.]"
"This violated requirement #3 of NCSA-PLANT062.A02, which states in part: 'Both favorable and unfavorable types of uncomplicated handling (UH) equipment shall be spaced a minimum of 2 feet edge-to-edge from other uranium-bearing equipment.' Requirement #4, which states that openings/penetrations made during maintenance activities shall be covered to minimize the potential for moderator collection and moist air exposure when unattended, was also violated."
"This is reportable under NRC Bulletin 91-01, 4-hour criticality control."
"There was no loss of hazardous/radioactive material or radioactive/radiological contamination exposure as a result of this event."
Portsmouth personnel notified the NRC resident inspector and plan to notify the Department of Energy site representative.
Power Reactor
Event Number: 36465
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE WILLIAMS
HQ OPS Officer: LEIGH TROCINE
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE WILLIAMS
HQ OPS Officer: LEIGH TROCINE
Notification Date: 11/26/1999
Notification Time: 09:12 [ET]
Event Date: 11/26/1999
Event Time: 08:00 [EST]
Last Update Date: 11/26/1999
Notification Time: 09:12 [ET]
Event Date: 11/26/1999
Event Time: 08:00 [EST]
Last Update Date: 11/26/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
LEN WERT (R2)
LEN WERT (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION REGARDING A LIVE SEA TURTLE REMOVED FROM THE INTAKE CANAL BARRIER NET
The following text is a portion of a facsimile received from the licensee:
"At approximately 0730 on 11/26/99, a live juvenile loggerhead sea turtle was removed from the barrier net in the common plant intake canal. The Florida Department of Environmental Protection was notified at approximately 0800 for transfer to a rehabilitation facility."
The licensee notified the NRC resident inspector.
The following text is a portion of a facsimile received from the licensee:
"At approximately 0730 on 11/26/99, a live juvenile loggerhead sea turtle was removed from the barrier net in the common plant intake canal. The Florida Department of Environmental Protection was notified at approximately 0800 for transfer to a rehabilitation facility."
The licensee notified the NRC resident inspector.
Power Reactor
Event Number: 36466
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: GARY OLMSTEAD
HQ OPS Officer: STEVE SANDIN
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: GARY OLMSTEAD
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/26/1999
Notification Time: 17:16 [ET]
Event Date: 11/26/1999
Event Time: 12:27 [CST]
Last Update Date: 11/26/1999
Notification Time: 17:16 [ET]
Event Date: 11/26/1999
Event Time: 12:27 [CST]
Last Update Date: 11/26/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
Person (Organization):
BLAIR SPITZBERG (R4)
BLAIR SPITZBERG (R4)
| 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 |
Unit experienced an automatic reactor trip following a momentary loss of power to an I&C power supply that resulted in a low Steam Generator water level.
"This event is being reported in accordance with 10CFR50.72(b)(2)(ii) due to an automatic Reactor Trip and subsequent Aux Feedwater actuation and Feedwater isolation:
"On 11/26/99 at 1227 CST with Callaway plant at 100% reactor power, a Reactor Trip occurred on low Steam Generator 'A' level due to an apparent momentary loss of power in Control Cabinet [Relay Panel] RP043. At 1204, annunciator 93A 'Power Control System (PCS) Power Failure' alarmed due to a failed RP043 primary power supply. Initial investigation revealed a failed fuse in the RP043 primary power supply. The secondary power supply immediately picked up load without incident.
"Subsequent to the primary power supply failure, I&C technicians were sent to the RP043 cabinet and the Primary Equipment Operator was sent to RP043 supply breaker PG19GCR218 to investigate. During this investigation, Main Feedwater Regulating valve [MFRV] 'A' went shut and both Main Feedwater Pumps [MFPs] went to their low speed stops. Attempts by the Reactor Operator to take manual control of 'A' MFRV and the MFPs were unsuccessful resulting in the aforementioned Reactor Trip.
"Discussions with I&C personnel stationed at RP043 indicated the secondary power supplies appeared energized throughout the event. Discussions with the Primary EO indicated he checked PG19GCR218 in the closed position coincident with the trip. Plant personnel are currently investigating PG19GCR218 and the apparent momentary loss of power to RP043. The plant is currently stable in Mode 3 with RCS pressure at 2237 psig and RCS temperature at 557.8 F.
"Additional information: The NRC Senior Resident Inspector was contacted at 1310 and responded to the Control Room."
Auxiliary Feedwater is currently supplying the Steam Generators with steam flow to the Main Condenser for decay heat removal. All control rods fully inserted.
"This event is being reported in accordance with 10CFR50.72(b)(2)(ii) due to an automatic Reactor Trip and subsequent Aux Feedwater actuation and Feedwater isolation:
"On 11/26/99 at 1227 CST with Callaway plant at 100% reactor power, a Reactor Trip occurred on low Steam Generator 'A' level due to an apparent momentary loss of power in Control Cabinet [Relay Panel] RP043. At 1204, annunciator 93A 'Power Control System (PCS) Power Failure' alarmed due to a failed RP043 primary power supply. Initial investigation revealed a failed fuse in the RP043 primary power supply. The secondary power supply immediately picked up load without incident.
"Subsequent to the primary power supply failure, I&C technicians were sent to the RP043 cabinet and the Primary Equipment Operator was sent to RP043 supply breaker PG19GCR218 to investigate. During this investigation, Main Feedwater Regulating valve [MFRV] 'A' went shut and both Main Feedwater Pumps [MFPs] went to their low speed stops. Attempts by the Reactor Operator to take manual control of 'A' MFRV and the MFPs were unsuccessful resulting in the aforementioned Reactor Trip.
"Discussions with I&C personnel stationed at RP043 indicated the secondary power supplies appeared energized throughout the event. Discussions with the Primary EO indicated he checked PG19GCR218 in the closed position coincident with the trip. Plant personnel are currently investigating PG19GCR218 and the apparent momentary loss of power to RP043. The plant is currently stable in Mode 3 with RCS pressure at 2237 psig and RCS temperature at 557.8 F.
"Additional information: The NRC Senior Resident Inspector was contacted at 1310 and responded to the Control Room."
Auxiliary Feedwater is currently supplying the Steam Generators with steam flow to the Main Condenser for decay heat removal. All control rods fully inserted.
Power Reactor
Event Number: 36467
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE WILLIAMS
HQ OPS Officer: STEVE SANDIN
Region: 2 State: FL
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE WILLIAMS
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/26/1999
Notification Time: 17:34 [ET]
Event Date: 11/26/1999
Event Time: 17:12 [EST]
Last Update Date: 11/26/1999
Notification Time: 17:34 [ET]
Event Date: 11/26/1999
Event Time: 17:12 [EST]
Last Update Date: 11/26/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
LEN WERT (R2)
LEN WERT (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION TO STATE AGENCY REGARDING DEAD SEA TURTLE FOUND IN BARRIER NET OF THE INTAKE CANAL
"[A] NOTIFICATION [WAS] MADE TO [THE] FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP) REGARDING [THE] REMOVAL OF [A] DEAD SUB-ADULT LOGGERHEAD SEA TURTLE FROM THE BARRIER NET IN THE COMMON PLANT INTAKE CANAL. THE TURTLE WAS REMOVED AT APPROXIMATELY 1700 [HOURS] ON 11/26/99, AND THE FLORIDA DEP WAS NOTIFIED AT 1710 HOURS. [THE] ANIMAL WAS FOUND WITH MONOFILAMENT FISHING LINE AROUND [THE] FRONT FLIPPERS AND [THE] MORTALITY IS NOT BELIEVED TO BE CAUSALLY RELATED TO PLANT OPERATIONS. THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR."
"[A] NOTIFICATION [WAS] MADE TO [THE] FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP) REGARDING [THE] REMOVAL OF [A] DEAD SUB-ADULT LOGGERHEAD SEA TURTLE FROM THE BARRIER NET IN THE COMMON PLANT INTAKE CANAL. THE TURTLE WAS REMOVED AT APPROXIMATELY 1700 [HOURS] ON 11/26/99, AND THE FLORIDA DEP WAS NOTIFIED AT 1710 HOURS. [THE] ANIMAL WAS FOUND WITH MONOFILAMENT FISHING LINE AROUND [THE] FRONT FLIPPERS AND [THE] MORTALITY IS NOT BELIEVED TO BE CAUSALLY RELATED TO PLANT OPERATIONS. THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR."