Event Notification Report for December 02, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/01/2003 - 12/02/2003
Power Reactor
Event Number: 40367
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: JEFF ROTTON
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/02/2003
Notification Time: 15:55 [ET]
Event Date: 12/02/2003
Event Time: 14:15 [EST]
Last Update Date: 12/02/2003
Notification Time: 15:55 [ET]
Event Date: 12/02/2003
Event Time: 14:15 [EST]
Last Update Date: 12/02/2003
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):
RICHARD CONTE (R1)
EDWIN HACKETT (NRR)
HO NIEH (DIRO)
RICHARD CONTE (R1)
EDWIN HACKETT (NRR)
HO NIEH (DIRO)
| 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 DUE TO ONSITE FATALITY
"At 1230 hrs, with both units at 100% power the Control Room was notified of a Medical Emergency at the Access Processing Facility on the Owner Controlled Area outside of the Protected Area. The affected individual was a contract employee working for Site Access Services. An ambulance and paramedics arrived on site at 1242 hrs. First Aid and CPR were initiated at the scene. The individual was transported offsite at 1257 hrs to the local Hospital. At 1415 hrs the control room was notified that the individual had passed away. This constitutes an event of public significance and therefore reportable under 10CFR50.72(b)(2)(XI) as a 4 hour ENS notification."
The licensee notified the NRC Resident Inspector and Pennsylvania Emergency Management Agency.
"At 1230 hrs, with both units at 100% power the Control Room was notified of a Medical Emergency at the Access Processing Facility on the Owner Controlled Area outside of the Protected Area. The affected individual was a contract employee working for Site Access Services. An ambulance and paramedics arrived on site at 1242 hrs. First Aid and CPR were initiated at the scene. The individual was transported offsite at 1257 hrs to the local Hospital. At 1415 hrs the control room was notified that the individual had passed away. This constitutes an event of public significance and therefore reportable under 10CFR50.72(b)(2)(XI) as a 4 hour ENS notification."
The licensee notified the NRC Resident Inspector and Pennsylvania Emergency Management Agency.
Power Reactor
Event Number: 40368
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DOUG HUNTER
HQ OPS Officer: JEFF ROTTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DOUG HUNTER
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/02/2003
Notification Time: 19:37 [ET]
Event Date: 12/02/2003
Event Time: 16:58 [CST]
Last Update Date: 12/02/2003
Notification Time: 19:37 [ET]
Event Date: 12/02/2003
Event Time: 16:58 [CST]
Last Update Date: 12/02/2003
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):
BRUCE BURGESS (R3)
BRUCE BURGESS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 88 | Power Operation | 0 | Hot Shutdown |
MANUAL SCRAM DUE TO LOW REACTOR WATER FEED PUMP SUCTION PRESSURE
"On December 2, 2003, at 1658, a manual scram was inserted from 88% power, which is the maximum power due to the plant being in coastdown. The manual scram was inserted due to feedwater suction pressure being below the trip set point for the operation of the Turbine Driven Reactor Feed Pumps and Reactor Pressure Vessel water level trending down. The initiating event was the loss of the 480V Unit Sub 1I. All plant systems operated normally on the scram with the exception of those systems that lost power due to the tripping of 480V Unit Sub 1I.
"The plant is shutdown at 0% power in Mode 3, maintaining pressure between 800 and 1065 psig, and reactor water level between level 3 and 8. Troubleshooting is in progress on the cause of the loss of the 480V Unit Sub 1I."
Plant is identifying the loads lost during the loss of the 480V Unit Sub 1I and the cause of the low feedwater suction pressure. No additional specified system actuations occurred. No SRVs lifted and the electrical plant lineup is stable and in a normal lineup for plant conditions with the exception of the lost 480V bus.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 2245 ON 12/02/03 FROM CARSKY TO ROTTON * * *
"As a consequence of the manual reactor scram inserted at 1658 CST, reactor water lowered to Level 3. This level is a valid RPS actuation and containment isolation signal [Groups 2, 3 and 20]. These actuations are being reported consistent with 10CFR50.72(b)(3)(iv)(A). The Level 3 RPS actuation is expected during a high power reactor scram.
"Additionally, on December 2, 2003, at 1935 CST, a Level 3 RPS actuation reoccurred while transferring reactor coolant makeup from the Motor Driven Reactor Feed (MDRFP) to a Condensate/Condensate Booster Pump pair. Reactor pressure was being lowered to the discharge pressure of the Condensate/Condensate Booster pumps. This Level 3 is a valid RPS actuation and containment isolation signal. These actuations are being reported consistent with 10CFR50.72(b)(3)(iv)(A).
"The plant is shutdown at 0% power in Mode 3, maintaining pressure between 550 and 750 psig, and reactor water level between level 3 and 8. Troubleshooting is in progress on the cause of the loss of the 480V Unit Sub 1I.
"Both of these events will be reported as a single Licensee Event Report (LER)."
The plant continues to remove decay heat via the turbine bypass valves to the main condenser.
The licensee will notify the NRC Resident Inspector.
Notified R3DO Bruce Burgess.
"On December 2, 2003, at 1658, a manual scram was inserted from 88% power, which is the maximum power due to the plant being in coastdown. The manual scram was inserted due to feedwater suction pressure being below the trip set point for the operation of the Turbine Driven Reactor Feed Pumps and Reactor Pressure Vessel water level trending down. The initiating event was the loss of the 480V Unit Sub 1I. All plant systems operated normally on the scram with the exception of those systems that lost power due to the tripping of 480V Unit Sub 1I.
"The plant is shutdown at 0% power in Mode 3, maintaining pressure between 800 and 1065 psig, and reactor water level between level 3 and 8. Troubleshooting is in progress on the cause of the loss of the 480V Unit Sub 1I."
Plant is identifying the loads lost during the loss of the 480V Unit Sub 1I and the cause of the low feedwater suction pressure. No additional specified system actuations occurred. No SRVs lifted and the electrical plant lineup is stable and in a normal lineup for plant conditions with the exception of the lost 480V bus.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 2245 ON 12/02/03 FROM CARSKY TO ROTTON * * *
"As a consequence of the manual reactor scram inserted at 1658 CST, reactor water lowered to Level 3. This level is a valid RPS actuation and containment isolation signal [Groups 2, 3 and 20]. These actuations are being reported consistent with 10CFR50.72(b)(3)(iv)(A). The Level 3 RPS actuation is expected during a high power reactor scram.
"Additionally, on December 2, 2003, at 1935 CST, a Level 3 RPS actuation reoccurred while transferring reactor coolant makeup from the Motor Driven Reactor Feed (MDRFP) to a Condensate/Condensate Booster Pump pair. Reactor pressure was being lowered to the discharge pressure of the Condensate/Condensate Booster pumps. This Level 3 is a valid RPS actuation and containment isolation signal. These actuations are being reported consistent with 10CFR50.72(b)(3)(iv)(A).
"The plant is shutdown at 0% power in Mode 3, maintaining pressure between 550 and 750 psig, and reactor water level between level 3 and 8. Troubleshooting is in progress on the cause of the loss of the 480V Unit Sub 1I.
"Both of these events will be reported as a single Licensee Event Report (LER)."
The plant continues to remove decay heat via the turbine bypass valves to the main condenser.
The licensee will notify the NRC Resident Inspector.
Notified R3DO Bruce Burgess.
General Information or Other
Event Number: 40427
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: VULCAN CHEMICALS
Region: 4
City: GEISMAR State: LA
County:
License #: LA-2848-L01
Agreement: Y
Docket:
NRC Notified By: SCOTT BLACKWELL
HQ OPS Officer: JEFF ROTTON
Licensee: VULCAN CHEMICALS
Region: 4
City: GEISMAR State: LA
County:
License #: LA-2848-L01
Agreement: Y
Docket:
NRC Notified By: SCOTT BLACKWELL
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/06/2004
Notification Time: 11:40 [ET]
Event Date: 12/02/2003
Event Time: 00:00 [CST]
Last Update Date: 01/06/2004
Notification Time: 11:40 [ET]
Event Date: 12/02/2003
Event Time: 00:00 [CST]
Last Update Date: 01/06/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MIKE RUNYAN (R4)
DOUG BROADDUS (NMSS)
MIKE RUNYAN (R4)
DOUG BROADDUS (NMSS)
AGREEMENT STATE REPORT CONCERNING LOST GAUGE
"A Kay-Ray Model 7063P gauge with serial number 12349 and a 500 milliCurie source of Cs-137 was not accounted for during the last Radiation Source Survey. The device has been stored in a locked warehouse with limited access since 1984. It was stored in a secured wooden crate with proper labeling. A search was conducted and interviews performed. As of December 2, 2003 the device has not been found. An email from Thermo Electron Corporation states that the source has decayed to 316.366 milliCurie. Vulcan also notified all of its scrap metal contractors to be on alert for the device."
"A Kay-Ray Model 7063P gauge with serial number 12349 and a 500 milliCurie source of Cs-137 was not accounted for during the last Radiation Source Survey. The device has been stored in a locked warehouse with limited access since 1984. It was stored in a secured wooden crate with proper labeling. A search was conducted and interviews performed. As of December 2, 2003 the device has not been found. An email from Thermo Electron Corporation states that the source has decayed to 316.366 milliCurie. Vulcan also notified all of its scrap metal contractors to be on alert for the device."