Event Notification Report for March 17, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/16/2007 - 03/17/2007
Power Reactor
Event Number: 43245
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: JOHN MacKINNON
Notification Date: 03/17/2007
Notification Time: 21:11 [ET]
Event Date: 03/17/2007
Event Time: 16:58 [EDT]
Last Update Date: 03/17/2007
Notification Time: 21:11 [ET]
Event Date: 03/17/2007
Event Time: 16:58 [EDT]
Last Update Date: 03/17/2007
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):
CHRIS HOTT (R1)
CHRIS HOTT (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
GROUP ISOLATIONS FOLLOWING MANUAL REACTOR SCRAM
"On March 17 2007, at approximately 1658 EDT, Group 2 (Reactor Building Ventilation Isolation) and Group 6 (RWCU Isolation) automatic containment isolation signals were received due to low reactor water level following the insertion of a manual scram signal. The manual scram signal was inserted following the reaching of internal administrative limits on changes in unidentified drywell leakage. The receipt of these isolation signals is not unusual following the insertion of a scram signal.
"The reactor was manually shutdown due to reaching internal administrative limits on changes in unidentified drywell leakage. Prior to the manual shutdown, the leakage had not reached the applicable Technical Specification limits. Drywell leakage as of 1800 EDT was 1.3 GPM identified and 2.59 GPM unidentified with the unit in Hot Shutdown Mode.
"All safety systems responded as expected. The plant is in a stable condition. Investigation is continuing."
The licensee notified the NRC Resident Inspector.
"On March 17 2007, at approximately 1658 EDT, Group 2 (Reactor Building Ventilation Isolation) and Group 6 (RWCU Isolation) automatic containment isolation signals were received due to low reactor water level following the insertion of a manual scram signal. The manual scram signal was inserted following the reaching of internal administrative limits on changes in unidentified drywell leakage. The receipt of these isolation signals is not unusual following the insertion of a scram signal.
"The reactor was manually shutdown due to reaching internal administrative limits on changes in unidentified drywell leakage. Prior to the manual shutdown, the leakage had not reached the applicable Technical Specification limits. Drywell leakage as of 1800 EDT was 1.3 GPM identified and 2.59 GPM unidentified with the unit in Hot Shutdown Mode.
"All safety systems responded as expected. The plant is in a stable condition. Investigation is continuing."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 43246
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: JEFF ROTTON
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/18/2007
Notification Time: 04:41 [ET]
Event Date: 03/17/2007
Event Time: 23:46 [CDT]
Last Update Date: 03/18/2007
Notification Time: 04:41 [ET]
Event Date: 03/17/2007
Event Time: 23:46 [CDT]
Last Update Date: 03/18/2007
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):
RICHARD SKOKOWSKI (R3)
RICHARD SKOKOWSKI (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
RPS TRIP SIGNAL AND CONTAINMENT ISOLATIONS RECEIVED DURING MAINTENANCE
"With the plant in refueling outage with all rods in and in Mode 5, a RPS trip and a containment isolation was received at 2347, 03/17/07. This event occurred when Div #2 Bus 16 Bus Pot Drawer was opened during isolation of 1AR Transformer Metering under C/O-17605. The opening of this Pot Drawer caused Div #2 4KV Bus 16, Div #2 480V LC-104 and Div #2 480V MCC-141, 142, 143, and 144 to open. 'B' RPS tripped causing full RPS trip due to SRM shorting removed. The loss of power caused RBV [Reactor Building Ventilation] and Spent Fuel Pool Radiation Monitors to trip and cause containment isolation to occur. Investigation into C/O-17605, restoration of power, resetting of RPS and containment isolation in progress."
The containment valves that received an isolation signal were: Primary Containment Atmosphere Control, Post Accident H2/O2 Control system, Post Accident Sampling system, O2 analyzing and SCTMT isolation (H&V).
The licensee notified the NRC Resident Inspector.
"With the plant in refueling outage with all rods in and in Mode 5, a RPS trip and a containment isolation was received at 2347, 03/17/07. This event occurred when Div #2 Bus 16 Bus Pot Drawer was opened during isolation of 1AR Transformer Metering under C/O-17605. The opening of this Pot Drawer caused Div #2 4KV Bus 16, Div #2 480V LC-104 and Div #2 480V MCC-141, 142, 143, and 144 to open. 'B' RPS tripped causing full RPS trip due to SRM shorting removed. The loss of power caused RBV [Reactor Building Ventilation] and Spent Fuel Pool Radiation Monitors to trip and cause containment isolation to occur. Investigation into C/O-17605, restoration of power, resetting of RPS and containment isolation in progress."
The containment valves that received an isolation signal were: Primary Containment Atmosphere Control, Post Accident H2/O2 Control system, Post Accident Sampling system, O2 analyzing and SCTMT isolation (H&V).
The licensee notified the NRC Resident Inspector.