Event Notification Report for March 09, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/08/2003 - 03/09/2003
Power Reactor
Event Number: 39648
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DON ROLAND
HQ OPS Officer: ARLON COSTA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DON ROLAND
HQ OPS Officer: ARLON COSTA
Notification Date: 03/09/2003
Notification Time: 04:08 [ET]
Event Date: 03/09/2003
Event Time: 03:12 [EST]
Last Update Date: 03/09/2003
Notification Time: 04:08 [ET]
Event Date: 03/09/2003
Event Time: 03:12 [EST]
Last Update Date: 03/09/2003
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):
MOHAMED SHANBAKY (R1)
MOHAMED SHANBAKY (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 |
OFFSITE NOTIFICATION
"On 3/9/03 at 0140 the Main Control Room was notified that an ambulance was requested at the site. A contract pipe fitter working in Primary Containment on unit 2 experienced heat stress. Site EMT's stabilized the individual and he was transported to a local hospital for treatment. The individual was not contaminated. The ambulance left site at 0216, and the Pennsylvania Emergency Management Agency was notified at 0312. Due to notification to another government agency, this event is reportable under 10CFR50.72(b)(2)(xi)."
The Licensee notified the State of Pennsylvania and will notify the NRC Resident Inspector.
"On 3/9/03 at 0140 the Main Control Room was notified that an ambulance was requested at the site. A contract pipe fitter working in Primary Containment on unit 2 experienced heat stress. Site EMT's stabilized the individual and he was transported to a local hospital for treatment. The individual was not contaminated. The ambulance left site at 0216, and the Pennsylvania Emergency Management Agency was notified at 0312. Due to notification to another government agency, this event is reportable under 10CFR50.72(b)(2)(xi)."
The Licensee notified the State of Pennsylvania and will notify the NRC Resident Inspector.
Power Reactor
Event Number: 39650
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JONATHAN PIERCE
HQ OPS Officer: ARLON COSTA
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JONATHAN PIERCE
HQ OPS Officer: ARLON COSTA
Notification Date: 03/10/2003
Notification Time: 00:46 [ET]
Event Date: 03/09/2003
Event Time: 20:47 [CST]
Last Update Date: 03/10/2003
Notification Time: 00:46 [ET]
Event Date: 03/09/2003
Event Time: 20:47 [CST]
Last Update Date: 03/10/2003
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):
DALE POWERS (R4)
DALE POWERS (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Standby | 0 | Hot Standby |
SAFETY INJECTION SYSTEM ACTUATION AND CAUSE UNDER INVESTIGATION
"At 20:47 on 3/9/03, Unit 2 experienced a Safety Injection while the plant was stable at NOP(2235 psig)/NOT
(567 degrees) in Mode 3. All systems actuated as designed. An operator was operating the 'B' S/G PORV shortly
before the event occurred. All MSIVs were closed for ongoing work on the main turbine. The Sequence of
events report showed all 3 channels of steam pressure spiking low on the 'B' Steam Generator as the cause of the event. Initial look at trends on the integrated computer system showed [that] steam pressure channels did not lower to a point to cause the safety injection. An Event Review Team is being formed to investigate this event.
"A Reactor Coolant System PORV opened due to high pressure when the Spray valves closed due to the Instrument Air isolation (due to phase 'A') with the Pressurizer Heaters in manual. The Pressurizer heaters were secured and Reactor coolant System pressure stabilized. All ESF systems actuated as designed. The following systems actuated: Auxiliary Feedwater, Safety Injection, Phase 'A', Control Room Envelope and Fuel Handling Building HVAC systems, Essential Cooling Water, Component Cooling Water, Emergency Diesel Generators and ESF sequencers."
There was no safety injection since pressure was maintained above 2199 psi during the transient (Hi Head is 1700 psi). Heat removal is being performed through S/G PORVs and Unit 2 is currently stable at Mode 3.
The Licensee notified the NRC Resident Inspector.
"At 20:47 on 3/9/03, Unit 2 experienced a Safety Injection while the plant was stable at NOP(2235 psig)/NOT
(567 degrees) in Mode 3. All systems actuated as designed. An operator was operating the 'B' S/G PORV shortly
before the event occurred. All MSIVs were closed for ongoing work on the main turbine. The Sequence of
events report showed all 3 channels of steam pressure spiking low on the 'B' Steam Generator as the cause of the event. Initial look at trends on the integrated computer system showed [that] steam pressure channels did not lower to a point to cause the safety injection. An Event Review Team is being formed to investigate this event.
"A Reactor Coolant System PORV opened due to high pressure when the Spray valves closed due to the Instrument Air isolation (due to phase 'A') with the Pressurizer Heaters in manual. The Pressurizer heaters were secured and Reactor coolant System pressure stabilized. All ESF systems actuated as designed. The following systems actuated: Auxiliary Feedwater, Safety Injection, Phase 'A', Control Room Envelope and Fuel Handling Building HVAC systems, Essential Cooling Water, Component Cooling Water, Emergency Diesel Generators and ESF sequencers."
There was no safety injection since pressure was maintained above 2199 psi during the transient (Hi Head is 1700 psi). Heat removal is being performed through S/G PORVs and Unit 2 is currently stable at Mode 3.
The Licensee notified the NRC Resident Inspector.