Event Notification Report for November 13, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/12/2003 - 11/13/2003
EVENT NUMBERS
40320403214032240319
Power Reactor
Event Number: 40320
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: KEN TIEFENTHAL
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: KEN TIEFENTHAL
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 11/13/2003
Notification Time: 13:48 [ET]
Event Date: 11/13/2003
Event Time: 11:35 [EST]
Last Update Date: 11/13/2003
Notification Time: 13:48 [ET]
Event Date: 11/13/2003
Event Time: 11:35 [EST]
Last Update Date: 11/13/2003
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):
KENNETH JENISON (R1)
KENNETH JENISON (R1)
| 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 |
AUTOMATIC REACTOR TRIP FROM 100% POWER WITH CAUSE BEING INVESTIGATED
"Unit 1 was at 100% power when an automatic reactor trip occurred. The Auxiliary Feedwater systems automatically started due to low post trip steam generator levels. This includes the steam driven Auxiliary feedwater pump. The steam discharge of this pump is considered to [be] a gaseous release due to trace amounts of tritium in the secondary system. These trace amounts are well below limits. The pump was shutdown after 31 minutes of operation, terminating the discharge. The Rad Waste & Effluents Section will assess the impact during the event response review.
The plant is currently stable in mode 3 with steam generator levels restored to post shutdown values. The steam dumps and main unit condenser are available for heat removal. All normal and emergency busses are energized from offsite power."
All rods fully inserted, no ECCS actuation and no primary or secondary relief valves lifted.
The NRC Resident Inspector was notified.
"Unit 1 was at 100% power when an automatic reactor trip occurred. The Auxiliary Feedwater systems automatically started due to low post trip steam generator levels. This includes the steam driven Auxiliary feedwater pump. The steam discharge of this pump is considered to [be] a gaseous release due to trace amounts of tritium in the secondary system. These trace amounts are well below limits. The pump was shutdown after 31 minutes of operation, terminating the discharge. The Rad Waste & Effluents Section will assess the impact during the event response review.
The plant is currently stable in mode 3 with steam generator levels restored to post shutdown values. The steam dumps and main unit condenser are available for heat removal. All normal and emergency busses are energized from offsite power."
All rods fully inserted, no ECCS actuation and no primary or secondary relief valves lifted.
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 40321
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: FRED NYGARD
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: FRED NYGARD
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 11/13/2003
Notification Time: 19:25 [ET]
Event Date: 11/13/2003
Event Time: 17:15 [EST]
Last Update Date: 11/13/2003
Notification Time: 19:25 [ET]
Event Date: 11/13/2003
Event Time: 17:15 [EST]
Last Update Date: 11/13/2003
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):
KENNETH JENISON (R1)
KENNETH JENISON (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
LICENSEE CALLED THE WATERFORD, CT. FIRE DEPARTMENT TO ASSIST IN EXTINGUSHING A FIRE OUTSIDE THE PROTECTED AREA
The licensee notified the Waterford, CT Fire Department to assist in extinguishing a fire affecting their offsite domestic water supply in the owner controlled area outside of the protected area. The fire caused damage to the offsite domestic water system limited to the heat tracing circuit for piping, an influent water filter and a trailer that provided shelter for the equipment. The fire, which was approximately 75-100 yards outside the protected area fence, was extinguished within 11 mins. The domestic water influent filter has been bypassed to allow normal domestic water supply capacity to the plant. The cause is being investigated.
The NRC Resident Inspector was notified.
The licensee notified the Waterford, CT Fire Department to assist in extinguishing a fire affecting their offsite domestic water supply in the owner controlled area outside of the protected area. The fire caused damage to the offsite domestic water system limited to the heat tracing circuit for piping, an influent water filter and a trailer that provided shelter for the equipment. The fire, which was approximately 75-100 yards outside the protected area fence, was extinguished within 11 mins. The domestic water influent filter has been bypassed to allow normal domestic water supply capacity to the plant. The cause is being investigated.
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 40322
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: LAURIE RAYLE
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: LAURIE RAYLE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/13/2003
Notification Time: 23:39 [ET]
Event Date: 11/13/2003
Event Time: 21:49 [EST]
Last Update Date: 11/13/2003
Notification Time: 23:39 [ET]
Event Date: 11/13/2003
Event Time: 21:49 [EST]
Last Update Date: 11/13/2003
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):
KENNETH JENISON (R1)
KENNETH JENISON (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 80 | Power Operation |
LOSS OF 115 KV LINE RESULTS IN EMERGENCY DIESEL GENERATOR AUTO-START
"Auto initiation of Emergency Diesel Generator (EDG) 103 and re-energizing of PB 103 from EDG due to loss of off-site 115 KV line #4. Line #4 was momentarily lost, then re-energized. The loss of power also resulted in a trip of Reactor Recirculating Pump 13. Power reduced to approximately 80% rated. Recovery operations are in progress."
All systems functioned as required and there was not anything unusual or not understood.
The NRC Resident Inspector was notified.
"Auto initiation of Emergency Diesel Generator (EDG) 103 and re-energizing of PB 103 from EDG due to loss of off-site 115 KV line #4. Line #4 was momentarily lost, then re-energized. The loss of power also resulted in a trip of Reactor Recirculating Pump 13. Power reduced to approximately 80% rated. Recovery operations are in progress."
All systems functioned as required and there was not anything unusual or not understood.
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 40319
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: MCCOY
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: MCCOY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 11/13/2003
Notification Time: 12:37 [ET]
Event Date: 11/13/2003
Event Time: 09:54 [EST]
Last Update Date: 11/13/2003
Notification Time: 12:37 [ET]
Event Date: 11/13/2003
Event Time: 09:54 [EST]
Last Update Date: 11/13/2003
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):
KENNETH JENISON (R1)
KENNETH JENISON (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 |
AUTO START AND LOADING OF THE "B" EMERGENCY DIESEL GENERATOR
While the plant was in "ER-SC.1", Adverse Weather Plan, due to high winds and offsite power in a 50/50 alternate lineup, a momentary loss of offsite power circuit "751" occurred. This resulted in an undervoltage condition on safeguard busses "16" and "17". The "B" emergency diesel Generator automatically started and energized buses "16" and "17" . Entry was made into AP.Elec.1, Loss of 12A and/or 12B busses. The offsite electrical lineup was changed to 100/0 on circuit "767". Safeguard busses were re-energized from offsite power and the "B" diesel generator was secured and returned to automatic. This sequence of events took 22 minutes.
The NRC Resident Inspector was notified.
While the plant was in "ER-SC.1", Adverse Weather Plan, due to high winds and offsite power in a 50/50 alternate lineup, a momentary loss of offsite power circuit "751" occurred. This resulted in an undervoltage condition on safeguard busses "16" and "17". The "B" emergency diesel Generator automatically started and energized buses "16" and "17" . Entry was made into AP.Elec.1, Loss of 12A and/or 12B busses. The offsite electrical lineup was changed to 100/0 on circuit "767". Safeguard busses were re-energized from offsite power and the "B" diesel generator was secured and returned to automatic. This sequence of events took 22 minutes.
The NRC Resident Inspector was notified.